Text

Initial Exam 2009-302 Draft Administrative JPMs
	ML100670467
Person / Time
Site:	Turkey Point
Issue date:	12/11/2009
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	50-250/09-302, 50-251/09-302 50-250/09-302, 50-251/09-302
	Download: ML100670467 (105)
	v • d • e

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Appendix C Job Performance Measure Worksheet Form ES-C-1 'Facility: Turkey Point Task No: Calculate Number of Gallons of Primary Water Required to Raise Power from 60% to Task

Title:

100% JPM No: NRC-25-ADMIN-JPM-A 1.1 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel KIA

Reference:

depletion, etc. 4.1/4.3 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Classroom Simulated Performance Actual Performance Yes Classroom Yes Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:

1. Unit 4 Cycle:

24

2. Reactor Power:

60%

3. Rod Height:

D-176

4. Boron Concentration: 770 ppm

5. Core Burnup:

10,000 MWD/MTU Task Standard:

6. Unit 4 has been at 60% Power for 96 hours.

Desired Conditions after Power Increase:

1. Reactor Power:

2. Rod Height:

Task Standard: 100 D-228 Calculate Number of Gallons of Primary Water Required to Raise Power from 60%-100%. Final value must fall between 3410 gallons and 5571 gallons. Required Materials:

1. Unit 4 Cycle 24 Plant Curve Book

2. 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5 - REACTIVITY WORKSHEET General

References:

1. 4-GOP-305, HOT STANDBY TO COLD SHUTDOWN

2. Unit 4 Cycle 24 Plant Curve Book

3. 0-OP-046, CVCS - BORON CONCENTRATION CONTROL NUREG 1021 Rev 9 Appendix C Appendix C Job Performance Measure Worksheet Form ES-C-1

'Facility: Turkey Point Task No: Calculate Number of Gallons of Primary Water Required to Raise Power from 60% to Task

Title:

100% JPM No: NRC-25-ADMIN-JPM-A 1.1 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel KIA

Reference:

depletion, etc. 4.1/4.3 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Classroom ~~~~~--------------------------------------------------- Simulated Performance Actual Performance Yes

~~---------

Classroom Yes Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions:

1. Unit 4 Cycle:

24

2. Reactor Power:

60%

3. Rod Height:

D-176

4. Boron Concentration: 770 ppm

5. Core Burnup:

10,000 MWD/MTU Task Standard:

6. Unit 4 has been at 60% Power for 96 hours.

Desired Conditions after Power Increase:

1. Reactor Power:

2. Rod Height:

Task Standard: 100 D-228 Calculate Number of Gallons of Primary Water Required to Raise Power from 60%-100%. Final value must fall between 3410 gallons and 5571 gallons. Required Materials:

1. Unit 4 Cycle 24 Plant Curve Book

2. 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5 - REACTIVITY WORKSHEET General

References:

1. 4-GOP-305, HOT STANDBY TO COLD SHUTDOWN

2. Unit 4 Cycle 24 Plant Curve Book

3. 0-OP-046, CVCS - BORON CONCENTRATION CONTROL NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 12 Form ES-C-1 /NITIA TlNG CUE: You have been directed to calculate the number of gallons of primary water required to raise reactor power from 60 to 100% using 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5 - REACTIVITY WORKSHEET. Desired Conditions after Power Increase:

1. Reactor Power:

100%

2. Rod Height:

0-228 Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Form ES-C-1 /NITIA TlNG CUE: You have been directed to calculate the number of gallons of primary water required to raise reactor power from 60 to 100% using 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5 - REACTIVITY WORKSHEET. Desired Conditions after Power Increase:

1. Reactor Power:

100%

2. Rod Height:

0-228 Time Critical Task: No Validation Time: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC # N/A Load Lesson N/A Page 3 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 I NUREG 1021 Rev 9 Appendix C I Appendix C Reset to IC # N/A Load Lesson N/A Page 3 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark( I) Start Time STEP 1 Identifies and obtains materials and procedures necessary to perform SAT task. UNSAT Standard: Operator obtains copy of O-OP-046, Attachment 5 and U4 Cycle 24 Plant Curve Book Cue CUE: Provide a copy of O-OP-046, Attachment 5 and the U4 Cycle 24 Plant Curve Book Comment NOTE: Evaluator may require the candidate to obtain procedure as part of this JPM. NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark( I) Start Time STEP 1 Identifies and obtains materials and procedures necessary to perform SAT task. UNSAT Standard: Operator obtains copy of O-OP-046, Attachment 5 and U4 Cycle 24 Plant Curve Book Cue CUE: Provide a copy of O-OP-046, Attachment 5 and the U4 Cycle 24 Plant Curve Book Comment NOTE: Evaluator may require the candidate to obtain procedure as part of this JPM. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 12 Form ES-C-1 I STEP 2 Operator enters appropriate values for Rod Worth from U4 Cycle 24 SAT Plant Curve Book, Section 2, Figure 5 and performs computation. ,.j UNSAT From U4 Cycle 24 Plant Curve Book, Section 2, Figure 5 for 10,000 MWD/MTU Determines 60% value (0-176) is 170 pcm for HFP. Standard: Determines 100% value (0-229) is 0 pcm. Appropriate values entered and answer of +170 pcm obtained. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 12 Form ES-C-1 I STEP 2 Operator enters appropriate values for Rod Worth from U4 Cycle 24 SAT Plant Curve Book, Section 2, Figure 5 and performs computation. ,.j UNSAT From U4 Cycle 24 Plant Curve Book, Section 2, Figure 5 for 10,000 MWD/MTU Determines 60% value (0-176) is 170 pcm for HFP. Standard: Determines 100% value (0-229) is 0 pcm. Appropriate values entered and answer of +170 pcm obtained. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-1 STEP 3 Operator enters appropriate values for Power Defect from U4 Cycle 24 SAT Plant Curve Book, Section 2, Figure 6A and performs computation. ..j UNSAT From U4 Cycle 24 Plant Curve Book, Section 2, Figure 6A for 10,000 MWD/MTU Determines 60% value (770 ppm) equal to 1204 +/- 20 pem. Standard: Determines 100% value (700 ppm-770ppm) equal to 1948-1934 +/- 20 pem. Appropriate values entered and answer of (-730)-(-744) +/- 20 pem obtained. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 STEP 3 Operator enters appropriate values for Power Defect from U4 Cycle 24 SAT Plant Curve Book, Section 2, Figure 6A and performs computation. ..j UNSAT From U4 Cycle 24 Plant Curve Book, Section 2, Figure 6A for 10,000 MWD/MTU Determines 60% value (770 ppm) equal to 1204 +/- 20 pem. Standard: Determines 100% value (700 ppm-770ppm) equal to 1948-1934 +/- 20 pem. Appropriate values entered and answer of (-730)-(-744) +/- 20 pem obtained. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 12 Form ES-C-1 I STEP 4 Operator calculates the desired change. SAT ~ UNSAT Determines value based on f1 rod worth = +170 pcm and f1 power defect = (-730)-(-744) +/- 20 pcm Standard: Operator enters the appropriate values from the previous two computations to derive an answer in the range of -560 to - 574 +/- 20 pcm. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 I STEP 4 Operator calculates the desired change. SAT ~ UNSAT Determines value based on f1 rod worth = +170 pcm and f1 power defect = (-730)-(-744) +/- 20 pcm Standard: Operator enters the appropriate values from the previous two computations to derive an answer in the range of -560 to - 574 +/- 20 pcm. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 Form ES-C-1 STEP 5 Operator determines present boron worth from U4 Cycle 24 Plant SAT Curve Book, Section 2, Figure 7 A. .J UNSAT Operator correctly determines present boron worth from U4 Cycle 24 Standard: Plant Curve Book, Section 2, Figure 7 A for 10000 MWD/MTU as 7013 +/- 20 pcm. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 12 Form ES-C-1 STEP 5 Operator determines present boron worth from U4 Cycle 24 Plant SAT Curve Book, Section 2, Figure 7 A. .J UNSAT Operator correctly determines present boron worth from U4 Cycle 24 Standard: Plant Curve Book, Section 2, Figure 7 A for 10000 MWD/MTU as 7013 +/- 20 pcm. Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 12 Form ES-C-1 I STEP 6 Operator calculates desired boron worth and concentration. SAT ..J UNSAT Determines value based on subtracting combined rod worth/power defect in range of -560 to - 574 +/- 20 pcm from integral boron worth of - _7013 +/- 20 pcm to yield a desired integral boron worth in the range of - 6439 pcm to - 6453 +/- 20 pcm. Standard: Operator correctly calculates (by interpolating U4 Cycle 24 Plant Curve Book, Section 2, Figure 7A for 10,000 MWD/MTU) desired boron concentration. 700 ppm +/- 10 ppm (-6439 pcm) to 710 ppm +/- 10 ppm (-6453 pcm) Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C --~~---- I Appendix C Page 9 of 12 Form ES-C-1 I STEP 6 Operator calculates desired boron worth and concentration. SAT ..J UNSAT Determines value based on subtracting combined rod worth/power defect in range of -560 to - 574 +/- 20 pcm from integral boron worth of - _7013 +/- 20 pcm to yield a desired integral boron worth in the range of - 6439 pcm to - 6453 +/- 20 pcm. Standard: Operator correctly calculates (by interpolating U4 Cycle 24 Plant Curve Book, Section 2, Figure 7A for 10,000 MWD/MTU) desired boron concentration. 700 ppm +/- 10 ppm (-6439 pcm) to 710 ppm +/- 10 ppm (-6453 pcm) Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 12 Form ES-C-1 STEP 7 Operator determines if boration or dilution is required. SAT ..J UNSAT Operator determines that dilution is required. Standard: Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 12 Form ES-C-1 STEP 7 Operator determines if boration or dilution is required. SAT ..J UNSAT Operator determines that dilution is required. Standard: Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 11 of 12 Form ES-C-1 I STEP 8 Operator determines number of gallons required. SAT ..j UNSAT Determines value based on boron concentration in the range of _ ppm to_ppm. Operator determines number of gallons of primary water required in Standard: the range of: 50,790 x In (770 ppm 1690 ppm) = 5571 gallons and 50,790 x In (770 ppm I 720 ppm) = 3410 gallons Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. .----------,,-------------------------------------------------~----------~ Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time -------- NUREG 1021 Rev 9 Appendix C I Appendix C Page 11 of 12 Form ES-C-1 I STEP 8 Operator determines number of gallons required. SAT ..j UNSAT Determines value based on boron concentration in the range of _ ppm to_ppm. Operator determines number of gallons of primary water required in Standard: the range of: 50,790 x In (770 ppm 1690 ppm) = 5571 gallons and 50,790 x In (770 ppm I 720 ppm) = 3410 gallons Cue Comment NOTE: Candidate may use either Hard Copy or Computer version of U4 Cycle 24 Plant Curve Book. .-----------r--------------------------------------------,--------~ Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time ------ NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 12 Form ES-C-1 Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A 1.1 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _ NUREG 1021 Rev 9 Appendix C Appendix C Page 12 of 12 Form ES-C-1 Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A 1.1 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _ NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS:

1. Unit 4 Cycle:

24

2. Reactor Power:

60

3. Rod Height:

D-176

4. Boron Concentration: 770 ppm

5. Core Burnup:

10,000 MWD/MTU

6. Unit 4 has been at 60% Power for 96 hours.

Desired Conditions after Power Increase:

3. Reactor Power:

100

4. Rod Height:

D-228 INITIA TlNG CUE: You have been directed to calculate the number of gallons of primary water required to raise reactor power from 60 to 100% using 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5-REACTIVITY WORKSHEET. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS:

1. Unit 4 Cycle:

24

2. Reactor Power:

60

3. Rod Height:

D-176

4. Boron Concentration: 770 ppm

5. Core Burnup:

10,000 MWD/MTU

6. Unit 4 has been at 60% Power for 96 hours.

Desired Conditions after Power Increase:

3. Reactor Power:

100

4. Rod Height:

D-228 INITIA TlNG CUE: You have been directed to calculate the number of gallons of primary water required to raise reactor power from 60 to 100% using 0-OP-046, CVCS - BORON CONCENTRATION CONTROL, ATTACHMENT 5-REACTIVITY WORKSHEET. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C

Procedure No. Procedure

Title:

0-OP-046 CVCS - Boron Concentration Control I PART 1: Power Change Only I) Rod Worth (A) ATTACHMENTS (Page 1 of3) REACTIVITY WORKSHEET NOTE Boric Acid Thumb Rules are as follows: 10pcm = 1 ppm 10 gallons = 1 ppm 1 gallon = 1 pcm Plant Curve Book, Section 2, Figure 5 Withdrawal rods = plus (+) reactivity Insert rods = minus (-) reactivity Calculate change in rod worth as follows: [~peml 0 pem] (+1_)+/70 pem Present Rod Worth Desired Rod Worth = (+1-) (A) Performed by Verified by

2)

Power Defect (B) Plant Curve Book, Section 2, Figure 6A Raise Power = minus (-) reactivity Lower Power = plus (+) reactivity Calculate change in power defect as follows: / :2oLj.:t::;2.o /7'# ~ 7. -737.:f 7-1 [ __ pem] [ pem] = (+1-) pem Present Pwr Defect Desired Pwr Defect = (+1-) (8) Performed by Verified by

3)

Calculate the Desired Change in pcrn (C) /7/ -13?:tZ7 -..)s?:t 2-7 [(+I-l..:LLfI pem ] + [(+1-) __ pem J = (+1-) pem (A) (8) (C) Performed by Verified by W2003:TNM/ln/ln/ln Page: 137 Approval Date: 6/27/08 I I Procedure No. Procedure

Title:

0-OP-046 CVCS - Boron Concentration Control I PART 1: Power Change Only I) Rod Worth (A) ATTACHMENTS (Page 1 of3) REACTIVITY WORKSHEET NOTE Boric Acid Thumb Rules are as follows: 10pcm = 1 ppm 10 gallons = 1 ppm 1 gallon = 1 pcm Plant Curve Book, Section 2, Figure 5 Withdrawal rods = plus (+) reactivity Insert rods = minus (-) reactivity Calculate change in rod worth as follows: [~peml 0 pem] (+1_)+/70 pem Present Rod Worth Desired Rod Worth = (+1-) (A) Performed by Verified by

2)

Power Defect (B) Plant Curve Book, Section 2, Figure 6A Raise Power = minus (-) reactivity Lower Power = plus (+) reactivity Calculate change in power defect as follows: / :2oLj.:t::;2.o /7'# ~ 7. -737.:f 7-1 [ __ pem] [ pem] = (+1-) pem Present Pwr Defect Desired Pwr Defect = (+1-) (8) Performed by Verified by

3)

Calculate the Desired Change in pcrn (C) /7/ -13?:tZ7 -..)s?:t 2-7 [(+I-l..:LLfI pem ] + [(+1-) __ pem J = (+1-) pem (A) (8) (C) Performed by Verified by W2003:TNM/ln/ln/ln Page: 137 Approval Date: 6/27/08 I I

Procedure No.. Procedure

Title:

Page: 138 Approval Date: 0-OP-046 CVCS - Boron Concentration Control 6/27/08 ATTACHMENT 5 (Page 2 of3) REACTIVITY WORKSHEET

4)

Integral Boron Worth Plant Curve Book, Section 2, Figure 7 A (Do not interpolate between graphs.) Boration = minus (-) reactivity Dilution = plus (+) reactivity For power changes in Mode 1, use Hot Full Power numbers (equilibrium xenon.) For power changes in Mode 2, use Hot Zero Power numbers (no xenon.) Calculate Desired Boron Concentration (CB) as follows: Check current boron concentration (C B) = -7013 ~.uJ - :)"67 = Z 7 ppm _ 6/t/6 ~,7..7

5)

6)

[(-) pem] - [(+1-) pem I (+1-) pem Present boron worth (C) = Desired boron worth from Seet 2, Fig 7 A Determ ine desired CB from Section 2, Figure 7 A = 7{/~ /5 ppm Peiformed By Verified By I I NOTE I I 50,790 is the nominal volume of the ReS and the eves. BAST ppm is the most recent I I BAST concentration or a nominal value of 5664 ppm. I L _______________________ I IF desired Boron Concentration is less than the current Boron Concentration, THEN calculate the dilution required as follows: 50,790 x In 50,790 x In t Current CB in ppm J

== Gallons of Primary Water Desired CB in ppm [ 770 ppm] L 7oS-~ I?,ppm

0-5'571

== Gallons Gallons of Primary Water Performed By Verified By L d Boron Concentration is higher than the current Boron Concentration, THEN ~ the boration 'red as follows: Gal of Boric Acid __ Gallons ppm] -[t-__ Gal of Boric Acid Performed By Procedure No.. Procedure

Title:

Page: 138 Approval Date: 0-OP-046 CVCS - Boron Concentration Control 6/27/08 ATTACHMENT 5 (Page 2 of3) REACTIVITY WORKSHEET

4)

Integral Boron Worth Plant Curve Book, Section 2, Figure 7 A (Do not interpolate between graphs.) Boration = minus (-) reactivity Dilution = plus (+) reactivity For power changes in Mode 1, use Hot Full Power numbers (equilibrium xenon.) For power changes in Mode 2, use Hot Zero Power numbers (no xenon.) Calculate Desired Boron Concentration (CB) as follows: Check current boron concentration (C B) = -7013 ~.uJ - :)"67 = Z 7 ppm _ 6/t/6 ~,7..7

5)

[(-) pem] - [(+1-) pem I (+1-) pem Present boron worth (C) = Desired boron worth from Seet 2, Fig 7 A Determ ine desired CB from Section 2, Figure 7 A = 7{/~ /5 ppm Peiformed By Verified By I I NOTE I I 50,790 is the nominal volume of the ReS and the eves. BAST ppm is the most recent I I BAST concentration or a nominal value of 5664 ppm. I L _______________________ I IF desired Boron Concentration is less than the current Boron Concentration, THEN calculate the dilution required as follows: 50,790 x In 50,790 x In t Current CB in ppm J

== Gallons of Primary Water Desired CB in ppm [ 770 ppm] L 7oS-~ I?,ppm

0-5'571

== Gallons Gallons of Primary Water Performed By Verified By L d Boron Concentration is higher than the current Boron Concentration, THEN ~ the boration 'red as follows: Gal of Boric Acid ._--",RCS ppm] __ Gallons ppm] -[ L-__ Gal of Boric Acid Performed By 003:TNM/ln/ln/ln

Appendix C Facility: Task

Title:

KIA

Reference:

Examinee: Facility Evaluator: Method of testing: Job Performance Measure Worksheet _T_u_r_k_ey"--P_o_in_t _______ Task No: Perform A QPTR Calculation 2.2.12 Knowledge of surveillance procedures. 3.7 / 4.l JPM No: NRC Examiner: Date: Form ES-C-1 NRC-25-ADMIN-JPM-A.2 Simulated Performance Actual Performance Classroom Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: Unit 3 is in Mode 1 operating at 100% power. Detector currents for all in service power range nuclear instrumentation channels are as follows: N-41 Top: 179.8 N-41 Bottom: 153.0 N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Task Standard: RO Candidate: Calculates QPTR value using 3-0SP-059.1 0, DETERMINATION OF QUADRANT POWER TILT RATIO. SRO Candidate:

1. Calculates QPTR value using 3-0SP-059.1 0, DETERMINATION OF QUADRANT POWER TILT RATIO Attachment 1.

2. Applies Tech Spec 3.2.4

3. Determines QPTR is calculated at least once per hour and reduce power within 2 hours 3% from RTP for each 1 % of QPTR in excess of 1 and reduce high flux trip setpoints in a similar manner.

Required Materials:

1. Calculator

2. 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO

3. Unit 3 Cycle 22 Plant Curve Book

4. Technical Specifications Section 3.2.4 General

References:

NUREG 1021 Rev 9 Appendix C Appendix C Facility: Task

Title:

KJA

Reference:

Examinee: Facility Evaluator: Job Performance Measure Worksheet _T" u"'r.ck"'eLy-'-P-'o"'in.ct_______ Task No: Perform A OPTR Calculation 2:2.12 Knowledge of surveillance procedures. 3.7 / 4.1 JPM No: ____________ NRC Examiner: ___________ Date: Form ES-C-l NRC-25-ADMIN-JPM-A.2 Method of testing: ______________________________ _ _ Simulated Performance __________ Actual Performance ___________ _ Classroom Simulator _______ _ Plant ______ _ Read to the examinee: I wilt explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure wilt be satisfied. Initial Conditions: Unit 3 is in Mode 1 operating at 100% power. Detector currents for all in service power range nuclear instrumentation channels are as follows: N-41 Top: 179.8 N-41 Bottom: 153.0 N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Task Standard: RO Candidate: Calculates QPTR value using 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO. SRO Candidate:

1. Calculates QPTR value using 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO Attachment 1.

2. Applies Tech Spec 3.2.4

3. Determines QPTR is calculated at least once per hour and reduce power within 2 hours 3% from RTP for each 1 % of QPTR in excess of 1 and reduce high flux trip setpoints in a similar manner.

Required Materials:

1. Calculator

2. 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO

3. Unit 3 Cycle 22 Plant Curve Book

4. Technical Specifications Section 3.2.4 General

References:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 12 Form ES-C-1

1. 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO

2. Unit 3 Cycle 22 Plant Curve Book

3. Technical Specifications Section 3.2.4 NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Form ES-C-1

1. 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO

2. Unit 3 Cycle 22 Plant Curve Book

3. Technical Specifications Section 3.2.4 NUREG 1021 Rev 9 Appendix C

I Appendix C Page 3 of 12 Form ES-C-1 I Initiating Cue: RO: Calculate NIS QPTR using excore detector currents. SRO:

1. Calculate NIS QPTR using excore detector currents.

2. Determine all necessary Technical Specification actions that must be completed within the next eight (8) hours.

Time Critical Task: No Validation Time: ROs: 15 minutes SROs: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 12 Form ES-C-1 I Initiating Cue: RO: Calculate NIS QPTR using excore detector currents. SRO:

1. Calculate NIS QPTR using excore detector currents.

2. Determine all necessary Technical Specification actions that must be completed within the next eight (8) hours.

Time Critical Task: No Validation Time: ROs: 15 minutes SROs: 20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C

Appendix C Reset to IC # N/A Load Lesson N/A Page 4 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 NUREG 1021 Rev 9 Appendix C Appendix C Reset to IC # N/A Load Lesson N/A Page 4 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 12 Form ES-C-1 I Denote critical steps with a check mark( /) Start Time STEP 1 Obtain copy of procedure. SAT UNSAT Obtains copy of 3-0SP-059.10. Standard:

1. Provide copy/access 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TilT RATIO Cue

2. Provide copy/access to Technical Specifications

3. Provide copy/access to Unit 3 Cycle 22 Plant Curve Book Comment NOTE:

Evaluator may require the candidate to obtain the procedure. NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 12 Form ES-C-l I Denote critical steps with a check mark( J) Start Time STEP 1 Obtain copy of procedure. SAT UNSAT Obtains copy of 3-0SP-059.1 O. Standard:

1. Provide copy/access 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO Cue

2. Provide copy/access to Technical Specifications

3. Provide copy/access to Unit 3 Cycle 22 Plant Curve Book Comment NOTE:

Evaluator may require the candidate to obtain the procedure. NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-1 STEP 2 Record date, time and initials on page 1 of Attachment 1. SAT UNSAT Records date and time and initials. Standard: Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 STEP 2 Record date, time and initials on page 1 of Attachment 1. SAT UNSAT Records date and time and initials. Standard: Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 12 Form ES-C-1 I 7.1.1 Read and record on Attachment 1 the top and bottom detector STEP 3 current for all in service power range nuclear instrumentation channels SAT ~ (meter face). UNSAT

1.

Records detector currents for all in service power range nuclear instrumentation channels: N-41 Top: 179.8 N-41 Bottom: 153.0 Standard: N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Cue Comment 7.0 PROCEDURE NOTE Attachments 1, 2, and 3 may be performed without interim rounding. NOTE: For example, when using a calculator that has storage capabilities, after performance of a calculation and the stored results are added, the final result may not be the same as if each individual calculated value is rounded and then added feR 99-0993]. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 I 7.1.1 Read and record on Attachment 1 the top and bottom detector STEP 3 current for all in service power range nuclear instrumentation channels SAT ~ (meter face). UNSAT

1.

Records detector currents for all in service power range nuclear instrumentation channels: N-41 Top: 179.8 N-41 Bottom: 153.0 Standard: N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Cue Comment 7.0 PROCEDURE NOTE Attachments 1, 2, and 3 may be performed without interim rounding.

NOTE:

For example, when using a calculator that has storage capabilities, after performance of a calculation and the stored results are added, the final result may not be the same as if each individual calculated value is rounded and then added feR 99-0993]. NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 Form ES-C-1 7.1.2 Record the 100 percent power current values on Attachment 1 for STEP 4 each in service power range nuclear instrumentation detector. (Refer to SAT ..j plant curve book for the 100 percent power current values.) UNSAT

1.

Obtains values from plant curve book and records them in appropriate blocks on page 1 of Attachment 1. N-41 Top: 189.8 N-41 Bottom: 162.3 Standard: N-42 Top: 140.6 N-42 Bottom: 142.4 N-43 Top: 156.4 N-43 Bottom: 135.6 N-44 Top: 180.3 N-44 Bottom: 159.6 Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 12 Form ES-C-1 7.1.2 Record the 100 percent power current values on Attachment 1 for STEP 4 each in service power range nuclear instrumentation detector. (Refer to SAT ..j plant curve book for the 100 percent power current values.) UNSAT

1.

Obtains values from plant curve book and records them in appropriate blocks on page 1 of Attachment 1. N-41 Top: 189.8 N-41 Bottom: 162.3 Standard: N-42 Top: 140.6 N-42 Bottom: 142.4 N-43 Top: 156.4 N-43 Bottom: 135.6 N-44 Top: 180.3 N-44 Bottom: 159.6 Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 12 Form ES-C-1 I STEP 5 7.1.4 Complete calculations of Attachment 1. SAT ..j

1. Determination normalized detector currents.

UNSAT

2. Determination average normalized power.

3. Determine QPTR.

4. Determine NIS QPTR.

5. Determine if NIS QPTR is < or = 1.02 (2.0%).

1.

Calculates normalized detector currents. N-41 Top: 179.8/189.8 = 0.9473 N-42 Top: 142.0/140.6 = 1.00996 N-43 Top: 151.3/156.4 = 0.9674 N-44 Top: 183.1/180.3 = 1.0155 Upper Section Normalized Current Total = 3.9402 N-41 Bottom: 153.0/162.3 = 0.9427 N-42 Bottom: 142.2/142.4 = 0.9986 N-43 Bottom: 127.1/135.6 = 0.9373 N-44 Bottom: 160.6/159.6 = 1.0063 Standard: Lower Section Normalized Current Total = 3.8849

2.

Calculates average normalized power. Average Upper Section Normalized Power = 3.9402/4 = 0.9851 Average Lower Section Normalized Power = 3.8849/4 = 0.9712

3.

Calculates QPTR. Upper Section Tilt Ratio = 1.0155/0.9851 = 1.0309 Lower Section Tilt Ratio = 1.0063/0.9712 = 1.0361

4.

Calculates NIS QPTR. NIS QPTR = Highest Section Tilt Ratio = 1.0361

5.

Correctly evaluates NIS QPTR. Tilt ratio = 1.0362 (Acceptable range: 1.036 to 1.037) NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 12 Form ES-C-l I 7.1.4 Complete calculations of Attachment 1. STEP 5 SAT

1. Determination normalized detector currents.

UNSAT

2. Determination average normalized power.

3. Determine QPTR.

4. Determine NIS QPTR.

5. Determine jf NIS QPTR is < or::; 1.02 (2.0%).

1.

Calculates normalized detector currents. N-41 Top: 179.8/189.8 = 0.9473 N-42 Top: 142.0/140.6 = 1.00996 N-43 Top: 151.3/156.4 = 0.9674 N-44 Top: 183.1/180.3 = 1.0155 Upper Section Normalized Current Total = 3.9402 N-41 Bottom: 153.0/162.3 = 0.9427 0 N-42 Bottom: 142.2/142.4 = 0.9986 N-43 Bottom: 127.1/135.6 = 0.9373 N-44 Bottom: 160.6/159.6 = 1.0063 Standard: Lower Section Normalized Current Total = 3.8849

2.

Calculates average normalized power. Average Upper Section Normalized Power = 3.9402/4 = 0.985 1 Average Lower Section Normalized Power = 3.884914 = 0.9712

3.

Calculates OPTR. Upper Section Tilt Ratio = 1.0155/0.9851 = 1.0309 Lower Section Tilt Ratio = 1.0063/0.9712 = 1.0361

4.

Calculates NIS QPTR. NIS QPTR = Highest Section Tilt Ratio = 1.0361 5. Correctly evaluates NIS QPTR. Tilt ratio = 1.0362 (Acceptable range: 1.036 to 1.037) NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 12 Form ES-C-1 Cue Tell RO candidate that JPM is Terminated after Attachment 1 has been completed. Comment Precautions and Limitations NOTE: 4.2.3 With QPTR greater than 1.02 (2.0 percent). QPTR determination is required at least once per hour (Tech Spec 3/4.2.4). Terminating The task is complete for RO candidates when Attachment 1 has STOP Cue: been completed. Stop Time ---- NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 12 Form ES-C-1 Cue Tell RO candidate that JPM is Terminated after Attachment 1 has been completed. Comment Precautions and Limitations NOTE: 4.2.3 With QPTR greater than 1.02 (2.0 percent), QPTR determination is required at least once per hour (Tech Spec 3/4.2.4). Terminating The task is complete for RO candidates when Attachment 1 has STOP Cue: been completed. Stop Time ___ _ NUREG 1021 Rev 9 Appendix C

I Appendix C Page 11 of 12 Form ES-C-1 I 7.1.5 IF QPTR is greater than 1.02 (2.0 percent) OR Attachment 1 STEP 6 yields suspect QPTR results, THEN perform Subsection 7.2. SAT 7.2.5 IF QPTR is greater than 1.02 (2.0 percent), THEN refer to UNSAT Subsection 7.4 for additional actions while continuing with this section of the procedure. Standard: Cue Inform applicant that another operator will perform any remaining procedural requirements. Comment Precautions and Limitations NOTE: 4.2.3 With QPTR greater than 1.02 (2.0 percent), QPTR determination is required at least once per hour (Tech Spec 3/4.2.4). NUREG 1021 Rev 9 Appendix C I Appendix C Page 11 of 12 Form ES-C-1 I 7.1.5 IF QPTR is greater than 1.02 (2.0 percent) OR Attachment 1 STEP 6 yields suspect QPTR results, THEN perform Subsection 7.2. SAT 7.2.5 IF QPTR is greater than 1.02 (2.0 percent), THEN refer to UNSAT Subsection 7.4 for additional actions while continuing with this section of the procedure. Standard: Cue Inform applicant that another operator will perform any remaining procedural requirements. Comment Precautions and Limitations NOTE: 4.2.3 With QPTR greater than 1.02 (2.0 percent), QPTR determination is required at least once per hour (Tech Spec 3/4.2.4). NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 12 Form ES-C-1 STEP 7 FOR SROs: Determines that TS 3.2.4 applies. SAT ..j UNSAT

1. Calculate the QUADRANT POWER TIL T RATIO at least once per hour Standard:

2. Power Reduced to: 91 %-88%

3. High Flux Trip Setpoint Reduced to: 99%-96%

STOP If candidate desires to implement 3-0NOP-059.9, EXCESSIVE Cue QUADRANT POWER TILT RATIO. If candidate attempts to notify Rx Engineering, confinn communication. Comment 7.4 IF the actual QPTR is greater than 1.02 (2.0 percent) OR Subsection 7.3 can NOT be perfonned within 12 hours, THEN go to 3-ONOP-059.9, EXCESSIVE QUADRANT POWER TILT RATIO, AND notify Rx Engineering. Per TS 3.2.4, applicant identifies the following requirements: ACTION:

a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour NOTE:

until either: a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2. Within 2 hours either:

a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours. Terminating The task is complete when the Examinee returns the cue sheet to the STOP Cue: examiner. Stop Time ---- NUREG 1021 Rev 9 Appendix C Appendix C Page 12 of 12 Form ES-C-1 STEP 7 FOR SROs: Determines that TS 3.2.4 applies. SAT ..j UNSAT

1. Calculate the QUADRANT POWER TIL T RATIO at least once per hour Standard:

2. Power Reduced to: 91 %-88%

3. High Flux Trip Setpoint Reduced to: 99%-96%

STOP If candidate desires to implement 3-0NOP-059.9, EXCESSIVE Cue QUADRANT POWER TILT RATIO. If candidate attempts to notify Rx Engineering, confinn communication. Comment 7.4 IF the actual QPTR is greater than 1.02 (2.0 percent) OR Subsection 7.3 can NOT be perfonned within 12 hours, THEN go to 3-ONOP-059.9, EXCESSIVE QUADRANT POWER TILT RATIO, AND notify Rx Engineering. Per TS 3.2.4, applicant identifies the following requirements: ACTION:

a. With the QUADRANT POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:

1. Calculate the QUADRANT POWER TILT RATIO at least once per hour NOTE:

until either: a) The QUADRANT POWER TILT RATIO is reduced to within its limit, or b) THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2. Within 2 hours either:

a) Reduce the QUADRANT POWER TILT RATIO to within its limit, or b) Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1 and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours. Terminating The task is complete when the Examinee returns the cue sheet to the STOP Cue: examiner. Stop Time ---- NUREG 1021 Rev 9 Appendix C

I Appendix C Page 13 of 12 Form ES-C-1 I Verification of Completion Job Performance Measure No. NRC-25-ADMIN-JPM-A.2 ~~~~~~~~~=--------------------------------- Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ---------------------------------- NUREG 1021 Rev 9 Appendix C I Appendix C Page 13 of 12 Form ES-C-1 I Verification of Completion Job Performance Measure No. NRC-2S-ADMIN-JPM-A.2 Examinee's Name: Examiner's Name: Date Peliormed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _________________ _ NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: The plant is operating at 100% power. Detector currents for all in service power range nuclear instrumentation channels are as follows: N-41 Top: 179.8 N-41 Bottom: 153.0 N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Initiating Cue: RO: Calculate NIS QPTR using excore detector currents. SRO:

3. Calculate NIS QPTR using excore detector currents.

4. Determine all necessary Technical Specification actions that must be completed within the next eight (8) hours.

TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully t the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: The plant is operating at 100% power. Detector currents for all in service power range nuclear instrumentation channels are as follows: N-41 Top: 179.8 N-41 Bottom: 153.0 N-42 Top: 142.0 N-42 Bottom: 142.2 N-43 Top: 151.3 N-43 Bottom: 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Initiating Cue: RO: Calculate NIS QPTR using excore detector currents. SRO:

3. Calculate NIS QPTR using excore detector currents.

4. Determine all necessary Technical Specification actions that must be completed within the next eight (8) hours.

TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C

Procedure No.: Procedure

Title:

Page:

1.

2.

3-0SP-059.10 Determination of Quadrant Power Tilt Ratio ATTACHMENT 1 (Page 1 of 2) 11 Approval Date: 8/30/05 DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS .---<J,I..~ Initials: ,IV ---"-=--- \\, Time W.)lV --'---=-~-- Determination normalized detector currents: Upper Section Normalized Detector Currents N41 TOQ Current = Il(t.~ micro amQs = (), Cf473 100 Percent Top Current 3c S micro amps I' 1*; N42 TOQ Current = 14;),0 micro amQs = /,OOCfC,(c 100 Percent Top Current ILta ~ micro amps N43 TOQ Current = [5\\.3 micro amQs = O,CJ(v7L/ 100 Percent Top Current 15O,4 micro amps N44 TOQ Current = (Cj3, ( micro amQs = I,D155 100 Percent Top Current 11')0,3 micro amps Upper Section Normalized Current Total = 3, qL/O;) Lower Section Normalized Detector Currents N41 Bottom Current = 153*0 micro amQs = 0/ (;'/)7 100 Percent Bottom Current iloa-, 3 micro amps N42 Bottom Current = 14~i~ micro amQs = 0,9930 100 Percent Bottom Current \\ 4,:),4 micro amps N43 Bottom Current = 1)1, ! micro amQs = 01 Ct373 100 Percent Bottom Current 135,(0 micro amps N44 Bottom Current = lCDC,(o micro amQs = /,[){)(O3 100 Percent Bottom Current (5C1,Co micro amps Lower Section Normalized Current Total =.3, S'OL{q W97:/J8SlId/mr Imr Procedure No.: 3-0SP-059.10 Procedure

Title:

Determination of Quadrant Power Tilt Ratio ATTACHMENT 1 (Page 1 of 2) Page: 11 Approval Date: 8/30/05 DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS

1.

\\, Time _-,-W~.:);::..*l.::..v::..\\ __ .---<J.

1.

.~ Initials: _....;..~ IV:::..-__

2.

Determination normalized detector currents: Upper Section Normalized Detector Currents N41 TOQ Current = Il(t.~ micro amQs = (), Cf473 100 Percent Top Current 3c S micro amps I' 1*; N42 TOQ Current = 14;),0 micro amQs = /,OOCfC,(c 100 Percent Top Current ILta ~ micro amps N43 TOQ Current = [5\\.3 micro amQs = O,CJ(v7L/ 100 Percent Top Current 15O,4 micro amps N44 TOQ Current = (Cj3, ( micro amQs = I,D155 100 Percent Top Current l~o,3 micro amps Upper Section Normalized Current Total = 3, qL/O;) Lower Section Normalized Detector Currents N41 Bottom Current = 153*0 micro amQs = 0/ (;'/)7 100 Percent Bottom Current iloa-, 3 micro amps N42 Bottom Current = 14~i~ micro amQs = 0,9930 100 Percent Bottom Current \\ 4,:),4 micro amps N43 Bottom Current = 1)1, ! micro amQs = 01 Ct373 100 Percent Bottom Current 135,(0 micro amps N44 Bottom Current = lCDC,(o micro amQs = /,[){)(O3 100 Percent Bottom Current (5C1,Co micro amps Lower Section Normalized Current Total =.3, S'OL{q W97:/J8SlId/mr Imr

Procedure No.: Procedure

Title:

Page: 3-0SP-059.10 Determination of Quadrant Power Tilt Ratio ATTACHMENT 1 (page 2 of2) 12 Approval Date: 8/30/05 DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS

3.

Determination average normalized power: Average Upper Section Normalized Power Upper Section Normalized ~.. Ofo :~ .~, CJ5J51 Current Total C)I = '_', T Upper detectors used (3 or 4) 4 Average Lower Section Normalized Power Lower Section Normalized ? 8 ~3 4 C' o,9 7!;.l Current Total = 1 = Lower detectors used (3 or 4) 4

4.

Determine QPTR:

5.

6.

7.

Upper Section Tilt Ratio Largest Upper Section I. [) 1~ 5 1.0:309 Normalized Detector Current = = Average Upper Section (),C; S 5"J Normalized Power Lower Section Tilt Ratio Largest Lower Section I. CD LC ~ /,03{( I Normalized Detector Current = = Average Lower Section C),Lf7/d Normalized Power NIS QPTR = highest Section QPTR = NIS QPTR is less than or equal to 1.02 (2.0 percent) [TS 3.2.4] (Circle one): ~ YES IF QPTR results are suspect or the above step is circled NO, THEN return to procedure Subsection 7.2 for additional guidance. Perfurmedby: ______________ __ Date: ----- Time: --------- Reviewed by: _________________________.Date: _______ _ Approved by: ____ ~=-:--;:-::-:------=-:--:--::::---_:____:_-----.Date : _____ _ (Shift Manager or Unit Supervisor) W97:1JBSlldfmr fmr Procedure No.: Pwccdure

Title:

Page. 12 Approval Dak: 3-0SP-059.IO Determination of Quadrant Power Tilt Ratio 8/30/05 ATTACHMENT I (page 2 of2) DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS

3.

Determination average normalized power: Average Upper Section Normalized Power Upper Section Normalized _",<1'</0 ';" CJ, c:; 'i ':J I Current Total = Upper detectors used (3 or 4) '-f Average Lower Section Normalized Power Lower Section Normalized 3.8 '3'-1(1 o. (i 7 (:;< Current Total = = Lower detectors used (3 or 4) <I

4.

Determine QPTR: Upper Section Tilt Ratio La rgest Upper Section 1.0 1 ::,5'

1. 0.')0 9 Normalized Detector Current

= = Average Upper Section C.9'6';-/ Normalized Power Lower Section Tilt Ratio Largest Lower Section I. CC (c:::' /.03{,c i Normalized Detector CUrrent = = Average Lower Section O,Q7/d, Normalized Power

5.

NIS QPTR ~ highest Section QPTR ~ I. c..-;' (,c' I

6.

NtS QPTR is less than or equal to 1.02 (2.0 percent) [TS 3.2.4] (Circle one): G YES

7.

IF QPTR results are suspect or the above step is circled NO, THEN return to procedure Subsection 7.2 for additional guidance. Performed by: Date: Time: Reviewed by: Date: I Approved by: Date: I (Shift Manager or Unit Supervisor) \\rV97:/JBSJldImr Imr

Appendix C Facility: Job Performance Measure Worksheet Turkey Point Task No: Perform 3-EOP-F-O, Evaluate Critical Safety Function Status Form ES-C-1 Task

Title:

Trees JPM No: NRC-25-ADMIN-JPM-A.4 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency KIA

Reference:

_o-'p'-e_ra_t_io_n_s _______ _ Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance Classroom Simulator Read to the examinee: Plant ------- I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: 3-EOP-E-O, Reactor Trip or Safety Injection, has directed the performance of 3-EOP-F-O, Critical Safety Function Status Trees. Current Unit Conditions: TE-3-6700 = 272 0 TE-3-6701 = 272 0 TE-3-6702 = 272 0 N-3-41= 0% N-3-42= 0% N-3-43= 0% N-3-44= 0% N-3-35= 1x 10E -11 N-3-36= 1 x 10E -11 N-3-35 SUR= -0.3 DPM and lowering N-3-36 SUR= -0.3 DPM and lowering N-3-31 = 4000 cps N-3-32= 4000 cps Gamma-Metrics NI-3-6649A= 1000cps and 10E-5 % PWR and lowering Gamma-Metrics NI-3-66498= 1000cps and 10E-5 % PWR and lowering All Unit 3 CETS = 715 0 Unit 3 CET Subcooling = 35° Superheat NUREG 1021 Rev 9 Appendix C Appendix C Facility: Task

Title:

Job Performance Measure Worksheet Turkey Point Task No: Perform 3-EOP-F-0, Evaluate Critical Safety Function Status Trees JPM No: 2.4.22 Knowledge of the bases for prioritizing safety funciions during abnonnallcmergency KIA

Reference:

_o"'p"'o"r"at::.io"'n"'s'-______ _ Examinee: NRC Examiner: Facility Evaluator: Date: Form ES-C-1 NRC-25-ADMIN-JPM-A.4 Method of testing: _______________________________ _ Simulated Performance __________ Actual Performance __________ _ Classroom _______ _ Simulator _______ _ Plant ______ _ Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the performance of 3-EOP-F-O, Critical Safety Function Status Trees. Current Unit Conditions: TE-3-6700' 272 0 TE-3-6701' 272 0 TE-3-6702' 272 0 N-3-41= 0% N-3-42= 0%

N-3-43' 0%

N-3-44= OCI/O N-3-35'1x 10E-11 N-3-36' 1x 10E -11 N-3-35 SUR' -0.3 DPM and lowering N-3-36 SUR' -0.3 DPM and lowering N-3-31' 4000 cps N-3-32= 4000 cps Gamma-Metrics NI-3-6649A= 1000cps and 10E-5 % PWR and lowering Gamma-Metrics NI-3-66498= 1000cps and 10E-5 % PWR and lowering All Unit 3 CETS -= 715 0 Unit 3 CET Subcooling = 35° Superheat NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 12 Form ES-C-1 Auxiliary Feedwater Flow Train 1 = 0 gpm Auxiliary Feedwater Flow Train 2 = 0 gpm A S/G NR = 7% B S/G NR = 8% C S/G NR = 8% A S/G Press = 0 psig B S/G Press = 400 psig C S/G Press = 400 psig Cold Leg Decrease in the last 60 min = 154 0 Lowest Cold Leg Temperature = 249.4 0 Current Cold Leg Temperature = 253.7 0 Containment Pressure = 15.7 psig Containment Recirculation Sump = 404 inches Containment Radiation = 5.92 x E-2 R Pressurizer Level = 0% RVLMS Indicates Voids Task Standard: Operator determines the need to transition to 3-EOP-FR-H.1, Respond to Loss of Secondary Heat Sink Required Materials: 3-EOP-F-0, Critical Safety Function Status Trees General

References:

3-EOP-F-0, Critical Safety Function Status Trees NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Form ES-C-1 Auxiliary Feedwater Flow Train 1 = 0 gpm Auxiliary Feedwater Flow Train 2 = 0 gpm A S/G NR = 7% B S/G NR = 8% C S/G NR = 8% A S/G Press = 0 psig B S/G Press = 400 psig C S/G Press = 400 psig Cold Leg Decrease in the last 60 min = 154 0 Lowest Cold Leg Temperature = 249.4 0 Current Cold Leg Temperature = 253.7 0 Containment Pressure = 15.7 psig Containment Recirculation Sump = 404 inches Containment Radiation = 5.92 x E-2 R Pressurizer Level = 0% RVLMS Indicates Voids Task Standard: Operator determines the need to transition to 3-EOP-FR-H.1, Respond to Loss of Secondary Heat Sink Required Materials: 3-EOP-F-0, Critical Safety Function Status Trees General

References:

3-EOP-F-0, Critical Safety Function Status Trees NUREG 1021 Rev 9 Appendix C

I Appendix C Page 3 of 12 Form ES-C-1 I Initiating Cue: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the perfonnance of 3-EOP-F-O, Critical Safety Function Status Trees. You are the Reactor Operator and have been directed to perfonn 3-EOP-F-O, Critical Safety Function Status Trees. Notify Unit Supervisor of any required actions by writing them down in the space below. Time Critical Task: No Validation Time: 17 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 12 Form ES-C-1 I Initiating Cue: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the perfonnance of 3-EOP-F-O, Critical Safety Function Status Trees. You are the Reactor Operator and have been directed to perfonn 3-EOP-F-O, Critical Safety Function Status Trees. Notify Unit Supervisor of any required actions by writing them down in the space below. Time Critical Task: No Validation Time: 17 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C

Appendix C Reset to IC # N/A Load Lesson N/A Page 4 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 NUREG 1021 Rev 9 Appendix C Appendix C Reset to IC # N/A Load Lesson N/A Page 4 of 12 SIMULATOR SETUP Ensure Simulator Operator Checklist is complete N/A Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 12 Form ES-C-1 I Denote critical steps with a check mark(./) Start Time STEP 1 1 Determine Containment Conditions SAT

a. Check containment temperature

..j

TE-3-6700 UNSAT
TE-3-6701
TE-3-6702

a. Use adverse containment

- LESS THAN 180°F setpoints AND go to Step 2. From Initial Conditions Operator observes Containment Temperature to be 272 ° Standard: Operator concludes Containment atmosphere is adverse and proceeds to Step 2. Cue Comment

NOTE:

NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 12 Form ES-C-1 I Denote critical steps with a check mark(./) Start Time STEP 1 1 Determine Containment Conditions SAT

a. Check containment temperature

..j

TE-3-6700 UNSAT
TE-3-6701
TE-3-6702

a. Use adverse containment

- LESS THAN 180°F setpoints AND go to Step 2. From Initial Conditions Operator observes Containment Temperature to be 272 ° Standard: Operator concludes Containment atmosphere is adverse and proceeds to Step 2. Cue Comment

NOTE:

NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-1 STEP 2 2 Monitor Critical Safety Functions SAT Using Rules Of Usage Provided In ATTACHMENT 1 UNSAT Standard: Operator proceeds to Attachment 1 of 3-EOP-F-0, Critical Safety Function Status Trees. Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 STEP 2 2 Monitor Critical Safety Functions SAT Using Rules Of Usage Provided In ATTACHMENT 1 UNSAT Standard: Operator proceeds to Attachment 1 of 3-EOP-F-0, Critical Safety Function Status Trees. Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 12 Form ES-C-1 Monitor Subcriticality using Enclosure 1 STEP 3 SAT UNSAT Subcriticality monitored using Enclosure 1 Using current Unit conditions determined CSF for Subcriticality to be Standard: (SAT) Green Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 Monitor Subcriticality using Enclosure 1 STEP 3 SAT UNSAT Subcriticality monitored using Enclosure 1 Using current Unit conditions determined CSF for Subcriticality to be Standard: (SAT) Green Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 Form ES-C-1 Monitor Core Cooling using Enclosure 2 STEP 4 SAT -J UNSAT Monitored Core Cooling using Enclosure 2: Unit 3 CET Subcooling = 35 0 Superheat Standard:

All Unit 3 CETS = 715 0 Used current Unit conditions determined CSF for Core Cooling to be ORANGE Candidate continues through F-O to determine if a RED path exists.

Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 12 Form ES-C-1 Monitor Core Cooling using Enclosure 2 STEP 4 SAT -J UNSAT Monitored Core Cooling using Enclosure 2: Unit 3 CET Subcooling = 35 0 Superheat Standard:

All Unit 3 CETS = 715 0 Used current Unit conditions determined CSF for Core Cooling to be ORANGE Candidate continues through F-O to determine if a RED path exists.

Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 12 Form ES-C-1 I STEP 5 Monitor Heat Sink using Enclosure 3 SAT UNSAT Heat Sink monitored using Enclosure 3: Operator Evaluates the following:

Auxiliary Feedwater Flow Train 1 = 0 gpm
Auxiliary Feedwater Flow Train 2 = 0 gpm
A S/G NR = 7%

B S/G NR = 8% Standard: C S/G NR = 8% Using Current Unit conditions determined a RED path on Heat Sink CSF. Identified the need to GO TO FR-H.1, Respond to Loss of Secondary Heat Sink. Cue

Comment Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue:

the examiner. Stop Time ---- NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 12 Form ES-C-1 I STEP 5 Monitor Heat Sink using Enclosure 3 SAT UNSAT Heat Sink monitored using Enclosure 3: Operator Evaluates the following:

Auxiliary Feedwater Flow Train 1 = 0 gpm
Auxiliary Feedwater Flow Train 2 = 0 gpm
A S/G NR = 7%

B S/G NR = 8% Standard: C S/G NR = 8% Using Current Unit conditions determined a RED path on Heat Sink CSF. Identified the need to GO TO FR-H.1, Respond to Loss of Secondary Heat Sink. Cue

Comment Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue:

the examiner. Stop Time ---- NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 12 Form ES-C-1 Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A.4 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _________________ _ NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 12 Form ES-C-1 Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A.4 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _________________ _ NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the performance of 3-EOP-F-O, Critical Safety Function Status Trees. Current Unit Conditions: TE-3-6700 = 272 0 TE-3-670i = 272 0 TE-3-6702 = 272 0 N-3-41= 0% N-3-42= 0% N-3-43= 0% N-3-44= 0% N-3-35= ix i0E -11 N-3-36= 1x 10E -11 N-3-35 SUR= -0.3 DPM and lowering N-3-36 SUR= -0.3 DPM and lowering N-3-31 = 4000 cps N-3-32= 4000 cps Gamma-Metrics NI-3-6649A= 1000cps and 10E-5 % PWR and lowering Gamma-Metrics NI-3-66498= 1000cps and 10E-5 % PWR and lowering A" Unit 3 CETS = 715 0 Unit 3 CET Subcooling = 35 0 Superheat Auxiliary Feedwater Flow Train 1 = 0 gpm Auxiliary Feedwater Flow Train 2 = 0 gpm A S/G NR = 7% 8 S/G NR = 8% C S/G NR = 8% A S/G Press = 0 psig 8 S/G Press = 400 psig C S/G Press = 400 psig Cold Leg Decrease in the last 60 min = 154 0 Lowest Cold Leg Temperature = 249.4 0 Current Cold Leg Temperature = 253.7 0 Containment Pressure = 15.7 psig NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the performance of 3-EOP-F-O, Critical Safety Function Status Trees. Current Unit Conditions: TE-3-6700 = 272 0 TE-3-670i = 272 0 TE-3-6702 = 272 0 N-3-41= 0% N-3-42= 0% N-3-43= 0% N-3-44= 0% N-3-35= ix i0E -11 N-3-36= 1x 10E -11 N-3-35 SUR= -0.3 DPM and lowering N-3-36 SUR= -0.3 DPM and lowering N-3-31 = 4000 cps N-3-32= 4000 cps Gamma-Metrics NI-3-6649A= 1000cps and 10E-5 % PWR and lowering Gamma-Metrics NI-3-66498= 1000cps and 10E-5 % PWR and lowering A" Unit 3 CETS = 715 0 Unit 3 CET Subcooling = 35 0 Superheat Auxiliary Feedwater Flow Train 1 = 0 gpm Auxiliary Feedwater Flow Train 2 = 0 gpm A S/G NR = 7% 8 S/G NR = 8% C S/G NR = 8% A S/G Press = 0 psig 8 S/G Press = 400 psig C S/G Press = 400 psig Cold Leg Decrease in the last 60 min = 154 0 Lowest Cold Leg Temperature = 249.4 0 Current Cold Leg Temperature = 253.7 0 Containment Pressure = 15.7 psig NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 12 Form ES-C-1 Containment Recirculation Sump = 404 inches Containment Radiation = 5.92 x E-2 R Pressurizer Level = 0% RVLMS Indicates Voids NUREG 1021 Rev 9 Appendix C Appendix C Page 12 of 12 Form ES-C-1 Containment Recirculation Sump = 404 inches Containment Radiation = 5.92 x E-2 R Pressurizer Level = 0% RVLMS Indicates Voids NUREG 1021 Rev 9 Appendix C

I Appendix C Page 13 of 12 Form ES-C-1 I Initiating Cue: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the perfonnance of 3-EOP-F-O, Critical Safety Function Status Trees. You are the Reactor Operator and have been directed to perfonn 3-EOP-F-O, Critical Safety Function Status Trees. Notify Unit Supervisor of any required actions by writing them down in the space below. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C I Appendix C Page 13 of 12 Form ES-C-1 I Initiating Cue: 3-EOP-E-0, Reactor Trip or Safety Injection, has directed the perfonnance of 3-EOP-F-O, Critical Safety Function Status Trees. You are the Reactor Operator and have been directed to perfonn 3-EOP-F-O, Critical Safety Function Status Trees. Notify Unit Supervisor of any required actions by writing them down in the space below. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C

Appendix C Facility: Job Performance Measure Worksheet Turkey Point Task No: Determine Allowable Stay Time & Determine Form ES-C-1 Task

Title:

Radiological Requirements JPM No: NRC-25-ADMIN-JPM-A.3 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 KIA

Reference:

Examinee: NRC Examiner: Facility Evaluator: ------------------------ Date: Method of testing: Simulated Performance X Actual Performance ~------------------ Classroom X Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: Unit 4 RHR is being placed in Operation for Cooldown. Fail safe test of HCV-4-758 is required to be performed The surveillance involved will require valve manipulations in the vicinity of HCV-4-758 The SNPO has received a whole body dose of 380 mrem TEDE for the current year. You are the the Field Supervisor (Admin RO)or Unit Supervisor and are holding a pre-job brief with the SNPO. You are discussing RWP requirements and ALARA concerns prior to commencing the task. Task Standard: Four of five questions from the Initiating Cue are answered correctly. Required Materials: Radiation Work Permit 09-001, Routine Operations and Surveillances Tasks 1-4 PTN Unit 4, Residual Heat Removal "A" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal "8" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal Heat Exchangers Room Monthly Survey Map PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map Radiation Controlled Area Valve Locator Zones 102,103,104, and 105 General

References:

1. 0-HPS-025.1, "General Posting Requirements for Radiological Hazards" NUREG 1021 Rev 9 Appendix C Appendix C Facility:

Job Performance Measure Worksheet _T",u ,:-r"k",e~yc:P:,o"in,,;,t,,===-,;-;= __ Task No: Determine Allowable Stay Time & Determine Form ES-C-1 Task

Title:

Radiological Reguirements JPM No: NRC-25-ADMtN-JPM-A.3 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5/3.6 KIA

Reference:

Examinee: ___________ NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance _X"--_________ Actual Performance Classroom ___ --"X'---__ _ Simulator _______ _ Plant ______ Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Initial Conditions: Unit 4 RHR is being placed in Operation for Cooldown. Fail safe test of HCV-4-758 is required to be performed The surveillance involved will require valve manipulations in the vicinity of HCV-4-758 The SNPO has received a whole body dose of 380 mrem TEOE for the current year. You are the the Field Supervisor (Admin RO)or Unit Supervisor and are holding a pre-job brief with the SNPO. You are discussing RWP requirements and ALARA concerns prior to commencing the task, Task Standard: Four of five questions from the Initiating Cue are answered correctly. Required Materials: Radiation Work Permit 09-001, Routine Operations and Surveillances Tasks 1-4 PTN Unit 4, Residual Heat Removal "A" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal "B" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal Heat Exchangers Room Monthly Survey Map PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map Radialion Controlled Area Valve Locator Zones 102,103,104, and 105 General

References:

1. 0-HPS-025.1, "General Posting Requirements for Radiological Hazards ~

NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 15 Form ES-C-1

2. 0-ADM-600, "Radiation Protection Manual"

3. 0-ADM-604, "Radiological Protection Guidelines and Practices"

4. 0-HPS-020, "Radiation Surveys"

5. 0-HPS-021, "Surface Contamination Surveys"

6. 4-0P-050, Residual Heat Removal System NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 15 Form ES-C-1

2. O-ADM-600, "Radiation Protection Manual"

3. O-ADM-604, "Radiological Protection Guidelines and Practices"

4. 0-HPS-020, "Radiation Surveys"

5. O-HPS-021, ~Surface Contamination Surveys~

6. 4-0P-050, Residual Heat Removal System NUREG 1021 Rev 9 Appendix C

I Appendix C Page 3 of 15 Form ES-C-1 I Initiating Cue: Using the initial conditions and required references determine the following:

1. What is the maximum stay time based on the radiological conditions in the room without exceeding any RWP dose limits?

2. What are the minimum requirements for protective clothing in the room?

3. What is the minimum required dosimetry required for entry into the room?

4. What is the surface contamination in the vicinity of HCV-4-758?

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

Time Critical Task: No Validation Time: ___ minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 15 Form ES-C-1 I Initiating Cue: Using the initial conditions and required references determine the following:

1. What is the maximum stay time based on the radiological conditions in the room without exceeding any RWP dose limits?

2. What are the minimum requirements for protective clothing in the room?

3. What is the minimum required dosimetry required for entry into the room?

4. What is the surface contamination in the vicinity of HCV-4-758?

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

Time Critical Task: No Validation Time: minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C

Appendix C Reset to IC # N/A Page 4 of 15 SIMULATOR SETUP Form ES-C-1 NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 15 Form ES-C-1 SIMULATOR SETUP Reset to Ie # N/A NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 15 Form ES-C-1 I Denote critical steps with a check mark( /) Start Time STEP 1 Obtain a copy of Radiation Work Permit 09-001, Routine Operations SAT and Surveillances and PTN Unit 4 Room Monthly RHR Survey Maps UNSAT Standard: Copy of the RWP and Survey Maps are obtained. Provide a copy of the following: Radiation Work Permit 09-001, Routine Operations and Surveillances PTN Unit 4, Residual Heat Removal "A" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal "B" Pump Room Monthly Cue Survey Map PTN Unit 4, Residual Heat Removal Heat Exchangers Room Monthly Survey Map PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map Radiation Controlled Area Valve Locator Zones 102,103,104, and 105 Comment EXAMINER The examinee needs to differentiate between the Survey Maps and Valve Locator Zones to get the correct results. NOTE: ALL correct answers are provided on the JPM ANSWER KEY NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 15 Form ES-C-1 I Denote critical steps with a check mark( /) Start Time STEP 1 Obtain a copy of Radiation Work Permit 09-001, Routine Operations SAT and Surveillances and PTN Unit 4 Room Monthly RHR Survey Maps UNSAT Standard: Copy of the RWP and Survey Maps are obtained. Provide a copy of the following: Radiation Work Permit 09-001, Routine Operations and Surveillances PTN Unit 4, Residual Heat Removal "A" Pump Room Monthly Survey Map PTN Unit 4, Residual Heat Removal "B" Pump Room Monthly Cue Survey Map PTN Unit 4, Residual Heat Removal Heat Exchangers Room Monthly Survey Map PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map Radiation Controlled Area Valve Locator Zones 102,103,104, and 105 Comment EXAMINER The examinee needs to differentiate between the Survey Maps and Valve Locator Zones to get the correct results. NOTE: ALL correct answers are provided on the JPM ANSWER KEY NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 15 Form ES-C-1 STEP 2 Use Radiation Controlled Area Valve Locator to determine location of SAT HCV-4-758 UNSAT Standard: Determined Zone 105 location #30 is the location of HCV-4-758. Cue Comment NOTE: Candidate needs to determine correct Zone and Location from Zones 102-105 provided. NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 15 Form ES-C-1 STEP 2 Use Radiation Controlled Area Valve Locator to determine location of SAT HCV-4-758 UNSAT Standard: Determined Zone 105 location #30 is the location of HCV-4-758. Cue Comment NOTE: Candidate needs to determine correct Zone and Location from Zones 102-105 provided. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 15 Form ES-C-1 I STEP 3 What is the maximum stay time based on the radiological conditions in SAT the room without exceeding any dose limits? .J UNSAT The examinee determines the maximum stay time is 1.0 hour by Standard: interpreting the RWP 25 mrem requirements and the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map data. Comment The maximum stay time allowed under this RWP based on PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room highest general area dose rates is 1.0 hour. EXAMINER NOTE: 25 mrem is the maximum dose allowed by RWP 09-0001 25 mrem/hr (from the highest general area dose rate in the Unit Room 25 mrem divided by 25 mrem per hour = 1.0 hr. NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 15 Form ES-C-1 I STEP 3 What is the maximum stay time based on the radiological conditions in SAT the room without exceeding any dose limits? .J UNSAT The examinee determines the maximum stay time is 1.0 hour by Standard: interpreting the RWP 25 mrem requirements and the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map data. Comment The maximum stay time allowed under this RWP based on PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room highest general area dose rates is 1.0 hour. EXAMINER NOTE: 25 mrem is the maximum dose allowed by RWP 09-0001 25 mrem/hr (from the highest general area dose rate in the Unit Room 25 mrem divided by 25 mrem per hour = 1.0 hr. NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 15 Form ES-C-1 What are the minimum requirements for protective clothing in the STEP 4 room? SAT --J UNSAT Standard: The examinee determines no protective clothing is required by interpreting the requirements with the initial conditions given. Comment EXAMINER The candidate should determine that the SNPO will not need to enter NOTE: any contaminated areas. NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 15 Form ES-C-1 What are the minimum requirements for protective clothing in the STEP 4 room? SAT --J UNSAT Standard: The examinee determines no protective clothing is required by interpreting the requirements with the initial conditions given. Comment EXAMINER The candidate should determine that the SNPO will not need to enter NOTE: any contaminated areas. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 15 Form ES-C-1 I STEP 5 What is the minimum required dosimetry required for entry into the SAT area? .,j UNSAT The examinee determines the following dosimetry is required by interpreting the RWP 09-0001 and the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Standard: TLD and Electronic Dosimeter AND PAM or Telemetric Dosimeter for working in a High Noise Area Comment EXAMINER RWP 09-001 specifies that Operators are required to wear a PAM or NOTE: Telemetric Dosimeter for working in a High Noise Area. NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 15 Form ES-C-1 I STEP 5 What is the minimum required dosimetry required for entry into the SAT area? .,j UNSAT The examinee determines the following dosimetry is required by interpreting the RWP 09-0001 and the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room Standard: TLD and Electronic Dosimeter AND PAM or Telemetric Dosimeter for working in a High Noise Area Comment EXAMINER RWP 09-001 specifies that Operators are required to wear a PAM or NOTE: Telemetric Dosimeter for working in a High Noise Area. NUREG 1021 Rev 9 Appendix C

Appendix C Page 10 of 15 Form ES-C-1 STEP 6 What is the surface contamination in the vicinity of HCV-4-758? SAT .J UNSAT Standard: The examinee determines < mda by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data. Comment EXAMINER As found on PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room NOTE: Room Monthly Survey Map, swipe # 15. NUREG 1021 Rev 9 Appendix C Appendix C Page 10 of 15 Form ES-C-1 STEP 6 What is the surface contamination in the vicinity of HCV-4-758? SAT .J UNSAT Standard: The examinee determines < mda by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data. Comment EXAMINER As found on PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room NOTE: Room Monthly Survey Map, swipe # 15. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 11 of 15 Form ES-C-1 I STEP 7 Where is the lowest dose location in the area where the operator SAT should stand in the event that he/she is required to wait there? .y UNSAT The examinee determines the lowest dose area in the PTN Unit 4, 10 Standard: foot Elevation (Access to RHR Pits) Room is near the Stairways Area near swipe # 11 or 13 by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data. Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time ---- NUREG 1021 Rev 9 Appendix C I Appendix C Page 11 of 15 Form ES-C-1 I STEP 7 Where is the lowest dose location in the area where the operator SAT should stand in the event that he/she is required to wait there? .y UNSAT The examinee determines the lowest dose area in the PTN Unit 4, 10 Standard: foot Elevation (Access to RHR Pits) Room is near the Stairways Area near swipe # 11 or 13 by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data. Comment Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time ---- NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 15 Form ES-C-1 JPM ANSWER KEY

1. What is the maximum stay time based on the highest general area radiation in the room?

ANSWER: The maximum stay time allowed under this RWP based on Unit 4 10' Elevation Access to RHR Pits highest general area dose rates near HVC-4-758 is 60 min (1 hour) BASES: 25 mrem is the maximum dose allowed by RWP 09-0001. 25 mrem I 25 mrem/hr (from the highest general area dose rate in the Unit ___ _ Room 25 mrem divided by 25 mrem per hour = 1 hr.

2. What is the minimum requirement for protective clothing?

ANSWER: No protective clothing is required per RWP.

3. What is the minimum required dosimetry required for entry into the area?

ANSWER: The following dosimetry is required: TLD AND PAM or PEA

4. What is the surface contamination in the vicinity of HCV-4-758?

ANSWER: From the survey map, swipe #15 has the surface contamination of <mda.

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

ANSWER: The examinee determines the lowest dose area in the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room is near the Stairways Area near swipe # 11 or 13 by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data.. NUREG 1021 Rev 9 Appendix C Appendix C Page 12 of 15 Form ES-C-1 JPM ANSWER KEY

1. What is the maximum stay time based on the highest general area radiation in the room?

ANSWER: The maximum stay time allowed under this RWP based on Unit 4 10' Elevation Access to RHR Pits highest general area dose rates near HVC-4-758 is 60 min (1 hour) BASES: 25 mrem is the maximum dose allowed by RWP 09-0001. 25 mrem I 25 mrem/hr (from the highest general area dose rate in the Unit ___ _ Room 25 mrem divided by 25 mrem per hour = 1 hr.

2. What is the minimum requirement for protective clothing?

ANSWER: No protective clothing is required per RWP.

3. What is the minimum required dosimetry required for entry into the area?

ANSWER: The following dosimetry is required: TLD AND PAM or PEA

4. What is the surface contamination in the vicinity of HCV-4-758?

ANSWER: From the survey map, swipe #15 has the surface contamination of <mda.

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

ANSWER: The examinee determines the lowest dose area in the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room is near the Stairways Area near swipe # 11 or 13 by interpreting the PTN Unit 4, 10 foot Elevation (Access to RHR Pits) Room survey map data.. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 13 of 15 Form ES-C-1 I Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A.3 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 13 of 15 Form ES-C-1 I Verification of Completion e Job Performance Measure No. NRC-25-ADMIN-JPM-A.3 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question: e ______________________ _

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _ NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 4 RHR is being placed in Operation for Cooldown. Fail safe test of HCV-4-758 is required to be performed The surveillance involved will require valve manipulations in the vicinity of HCV-4-758 The SNPO has received a whole body dose of 380 mrem TEDE for the current year. You are the the Field Supervisor (Admin RO)or Unit Supervisor and are holding a pre-job brief with the SNPO. You are discussing RWP requirements and ALARA concerns prior to commencing the task. INITIA TlNG CUE: Using the initial conditions and required references determine the following:

1. What is the maximum stay time based on the radiological conditions in the room without exceeding any RWP dose limits?

2. What are the minimum requirements for protective clothing in the room?

3. What is the minimum required dosimetry required for entry into the room?

4. What is the surface contamination in the vicinity of HCV-4-758?

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY ANSWERED ALL THE QUESTIONS. NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 4 RHR is being placed in Operation for Cooldown. Fail safe test of HCV-4-758 is required to be performed The surveillance involved will require valve manipulations in the vicinity of HCV-4-758 The SNPO has received a whole body dose of 380 mrem TEDE for the current year. You are the the Field Supervisor (Admin RO)or Unit Supervisor and are holding a pre-job brief with the SNPO. You are discussing RWP requirements and ALARA concerns prior to commencing the task. INITIA TlNG CUE: Using the initial conditions and required references determine the following:

1. What is the maximum stay time based on the radiological conditions in the room without exceeding any RWP dose limits?

2. What are the minimum requirements for protective clothing in the room?

3. What is the minimum required dosimetry required for entry into the room?

4. What is the surface contamination in the vicinity of HCV-4-758?

5. Where is the lowest dose location in the Contaminated Area where the operator should stand in the event that he/she is required to wait there?

Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY ANSWERED ALL THE QUESTIONS. NUREG 1021 Rev 9 Appendix C

I Appendix C Page 15 of 15 Form ES-C-1 I NUREG 1021 Rev 9 Appendix C I Appendix C Page 15 of 15 Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Turk y Point Nuclear Plant RADIATION WORK PERM T Nude.. O l.i~i. ft COpy Rwr

Title:

ROlllin' Operations and 'ur t illances RWP umber: 09-000 I Rev. 03

~~mmmnmnmr!

~mnmnn_*~ 3

1 Ceneral Instruction.:

A TI. and IcclrOnic Dosiml!tct :tre required to enter the RCA. A PAM or Tclemetric LJosimc r is required for working in a high noise ru-t'!I. Rc\\ iew current sur

dam priur to entering the work area.

Notir thc wor' area RI' Tcchnician priCtr to entering overhead areas. KI' C ycrllse is required to remOVe mated I, ols or cquipmellt rom a Contaminated Ncn. Turkey Point Nuclear Plant RADIATION WORK PERMIT 111 i I)osunctcr :Irc reqtlir~ to cnler the RCA, /I. r/\\M or l'ch::mctric IJosimetcr is required for working in II hilOh noise Nell RI:\\ ic:w elmen! ~\\If"'cy d"ta pril.M' 10 entering the woO: BI'elI NOIiry the work.'Irca RI' rechnician pricw 10 1,-'1ltcnngovcrhe:ul uc&s. It!' CovcnlGe i~ required 10 Icmove ma:c:nlll, tOOls Of cijuipmcllt rrom 3. Conllolmimlted An:1I. Page I

Turkey Point Nuclear Plant RADI TION WORK PERMIT Nuclcer Division COpy TAsk Number: I RWP Number: 09-0001 Rc~. 03 Tas~~crip lion: Radialion Proteclion ROlltine Acti\\'itics Task Status: A live ~A~L7A~n~'~\\~ID~

__ ~

______________ ~I~~._ la~~T~lc 'n~e~A~I~ ='r~rn ~_~(lt~ I1~ 1 :~ ~I~~~ Il~

~

1 8~:0~O~ __ ~ __________________ ~ ____ ____ Estimate Do ~e: 900 mr m ....J1i..ME.s1:,:;im.-a.;,;t*c;.,* H:.;,;:o_ u,;,; rs:;;.

..:32~IO.::O.::.O ______

.J...... __ -y __________ -I Locked High-Had: NO I Hie,b-Rad: Yes High-Contomination: Yes I llot-Parlicl,,: Yes Requirement Groups Authorizcd Access Briefings Required ContUlliinati II Control Do. im 'lr~' l'roK'Cli c Clothmg IkspirJlury Prnu.::Clion . Alarm Settin g~ Iligh J:iallllnn DC!sc High GlImmll Rale 25 mrcm .)50 mremJhr Requireme nts Requirement Descripfions - NcutrC'n Ar~a a CCSli is authorized I - Airbome R:lciio3Clivil'l r.C3_ a_r.,..c....,c_ss __ *_ 15;_a~u_ th_()_r_ i ?:-

e_d.,....".-,-:-::-_____________ -i I -,\\ shiflly Iligh Radiation' Area brit:Iing is required ror liRA access I

- To work in a High Cont minalion Area one r more orlhe rollowing mlly bt: required: A) DcconL."lmin;nc arc' equipl11 nlto <100.000 dprn/I Ocm2 (Decontamination shall be perfonned as din:c!.Cd b ' HI ). A) t):;e IIEPA "cntilmion! vacuum, KCI.'P arca/equipment wet durin~ repairs, D) Co\\cr or eonillin arc:v'cquipmerll - PAM orTeI'metric D simeter i~ required for vorl-ing in Ii high n ise BrCJ and/or a High Radiation Are:t . Shoe cover and gloves arc the minimum protective clothing required for cntry into a Con mill:lteu Area. ( lob coal I required in ighl areas) -,\\ full ScI of prOlective ch)thing is required for knccling or cm\\ ling in a Conllllninaled Area - r~lrn protcClivc clothing is rCCJuircd 10 \\\\ork with llighly Contamin led materiels. The minimum dres. requiremenl L a ru I ScI ofprotcclivc c/tllhing, (' Ira gI0\\'c5 and/t r sh e covers. " fae..: shiel d ma) be required - In II HOI Pan lclc,\\rca. the minimum dres rcquirl'menl i~ tl full. or prole *the clmh;ng. di pt/5.1ble uter coveralls, c:lrtl gloves. eXira h c co crs and n fa e shield - \\\\later reS;!;Ianl Oliler prolcclh c clothing is rcquired to work in a weI Contamination Arca I : Rcspirmnr rcquircm 'nls Lo be dc\\ermitll!cl On a case b) ca~c basis. /I. TEDE "LARA c:v81uuLinn I.* required prior 10 respirator us\\.: ~ ___________________________________,~\\~d~d~ it~ io~n~a~ l ~ T~ D s~l~r~ D ~c'~io~n~ I S~_ General Ins(ruclloos: Worker tnstrucli<lns: IU' I n 5 Iruc.i o J1 ~ : \\InA Briefing i~ nm rcquirl!d for H.PT s "hen :I 5\\11"\\ ey me cr is used I"lr entry inlo lligh Pall Aren. l' 1111 Iy \\\\ ilh I lUI Partil:le onLmls as speeillcli i 1 O-Iff'. -027. I. CRFII. sueS WilrehollSc: RAM ;>IiCkdges with dose rolCS >2. mrcm/hr shall be transfclT d P) the RP Tcch I Ihe RCA. I lllif~ RP. : if an 10 se !>urf:tce activil. i. found. II personnel shall wcar rl.O's when handling R M \\ ilh dose ralc 2.0 mrcmlhr lind \\\\ hen entering 3n.lrCd "I':'U.5 mn:m/hr. RP shllll poSI all areas where TLO's arc required. Instruml'nI. _hall be surveyed f, r loose con18minntion pri rIo dis<I':sembly. E c pWlc tion i cquired for personnel p rforming inS1rurnCnt chee 's \\ iLh source \\\\ heel. Trunsporring of. Ilrcc \\ *hee. shall be pcr ()rml!cI hy R.P personnel onl) lind hall remain in control r RP Personnel al II rim> when not ins; e Ihe t.h:signateu 10 'ked oren. 1116120092:54 P Page 2 Turkey Point Nuclea r Plant ~ RADIATION WORK PERMIT N.etHtDm..!... COpy TII ~ k Numbt r : I RWP Numher; 09-000 I Rov. 03 lI ~ k Dtl d lion: Radiation Pruh:clion Routine Activities T ask StIlIUS: Active At.AnA II): J.:~ t i nlilltr. Dose: 9O<J mrtm I. o~krllll h:h* lbci.: No Rctlulrtmcnt "roups AUlhorilCJ A~css c I Ondin&s Rcq\\llr~d ('0111.1/11;":111011 COntrol T1osjllwlr~' J'roH:cliYe ClOlhml! G l'nl'r:i IIIl ~ lr ur tion ~: Wurker I n ~ t ru r li " n ~: ItP I n ~ lr udi o n ~: I.

I :,\\!of : 18:00 I

£.slim.lle lIours: 32000 IIigh-lb d: Yes 1IIIth-Conlaniinalion: Yes I lI ul-Pll nicle': Yes . Alarm Sttlin s Iligh (;1110111:1 Don I-!igh ellmmn RaIl' 25 mrC'm 350 mrem/hr I Requirements RrllUirtlllC'.nl Destrlpllons - ~tuln.'n,'~a IICC~~ is autlmrizcJ - Airbomj; R!ldiOllctlvll), Are.l access i:" aulhl'lr;.. ~d 1-" shlfllv Ihgh RadIatIon AI't'3 bmflng 1~ requital ror liRA tlCCr:5$ - To wor!: in iI J-ligh COnl.lmin8tilln An.'D one Or morc orlhc rollowing mll)' be: required: AJ I>cconL1min:lIc atf:aJc'll,lijmll:nt 10 <100,000 dpmllOOcm2 (l>e<:on!(lIninotion shall be pcrfunnl:d l\\.<; din:ckd by HP), I)) U~ I IEPA ",:n!itation J vacuum. C) KCI;p urenlcquipnl~nl \\\\'4't during rep:.irs, D) CO\\ er or COTll3illlU'c3lcquipmcnl

rAM or reknU'lrit: DO:iimC1CT i~ rf'.quitoo ror working in Ii high nuise are.! :uuJ/or a !Iigh i{odl:ltion Arca
Shoc CIJIICrs and glollcs are the mi nimum protective clothing requireJ ror entry inl0 a C0:1111nl:n:l!eJ !\\rc.l. tA lab COlli IS rl'quired in 11ghl nreas)

." full ~et of protc:clive d.)thing ill' rl'qllired for kneeling or crnw!ing in II C(\\TtI:lIninalrd Arca

1:.'lrn prolt..-c:ivc clothln!! is required to \\\\\\)rk \\\\ Ith llighly Conlnminlllcd n13terjl!ls. The minimum dr~s rcquilCnll:nl is II (lil t sel of prolC'(alve clothing. c-:lrn gloves andlnr !lhf'C CIIVCf'!.
\\ (aco: shic:ld mll) t-c rO:~luired
In iI 11m P:lnlcic "rea. the: minimum dress rcquir~'mcnl is II full <;1:1 OrrrnI4't:li\\c clllt.hing.

dl~rll'Qhle (IUttr eovcraUs, cx,,:, Hh.lVL'S, eXira shoe covers ~nd a fnee shield

'ater rcsi~an l ouler protccth l' cl(,thing IS required to work in 9 ~t'l Contaminatiun." rell I

R~ ~ rlratnr reqUIrements tu be I.h: t ~rmm~d on a 1;:'Isc.: b) ca~e 1);iSls. A 1 F.DI,,\\1 ARA evahWlilltl I', TC'111irl,j pril1r HI respmuor us/! Additional 'uslrul'ti onJi 1 IRA Ilricfing i< rim ro.:(julrt.J (I)r I<P'I'~ \\\\h.*11 :I$ur.,,)' meIer IS u5Cd li,t entry inll) II Iligh Uno An:a. ('(lnIply \\1 nil Ilut Partll:lc C()I\\lrol~ as spccllicd in 0-1 11:;.021. I. (1tFII<'~lIcs WArehouse: 1<,,:-.1 i"1Ck.!gc5 wilh clost' 1".!1O >2.0 mtemlhr shall be: Irnn'&rreJ h) Ihe RP rcch I" Ihe ltC". N\\!lir~ RPSS iran), l\\X'Sc )urf:lct a~ti"ll~ is roend. All personnel ~hall wcnr fLO's when halldling RAM \\\\llh dusc rntl!>2.0 mn:mlhr lind \\\\ hen cr.tc:ring 3n ;ltCCl,.1'::-0.5 rnn:m/hr, HI' shall POSI all rm:;c; ",hcrt'.\\ LJ)'~ arc required. Instrumcnt ~ shall he ~ur.*c)'cd (or loose cOlltaminllllon prior 10 diSclc;scmbly. I:"~ l' prnl,,*{'l.i<m is required ror IX'rsonnci pcriorming InstnllnCnl checks WIth $Ourt:c II hed. Transporting of S(>UfCC \\\\ h~d shalt be f"..'frOrmcd hy RP pt'rs..Jnnd nnJ} lind ~hatl I em:!;n 1n cOlltrcll of KP Pcrsnnnd ill,dllimes when nm in~;do.: the dc~jgnl1led locked IIrcn. ----------------------- Page 2 I

I J) simclry [E"posur" Conlml Worker Inslruction.: Tu rkey Point Nuclear Plant J=PL RADIATION WORK PERMIT Nucloar Divi.ion COpy Rev, 03 adioaClive . h e C(lVeTS and glnves rue Ihe minimum pmtc::crive cJCIlhing, required for cntry inl a Conlaminated Area. (A lab coal i required in lighl llrcas - J-..xlra proh.:t;tiv 'clothing is n:quir' to \\\\ rk wi!o I lighly ontaminaled malerials. Toc minimum dress requiremenl is 3 rull sci 0 pr ICCliVI! clolhing, c. 'Ira gloves andlor c; Ir.Je COVeT *. A fu <: shidd nm. be rc uirl'd - In I H I P~r ic/e Arc;!, the minimum dress rcquir menl i a full SCI f prtllt:cli\\'(; clothing. t!i s po~3blc ouu:r c \\cr:lll~. c. trn gl vc.~. 0;;. lNI sh

CO\\cr.; and u face shiehl

- \\ Iller rc Istunt ')Utel' pr Ilel:li c almhing ilo rc(.!uirecl to work in t:l Contamination Arca - The minimum Pmtecli\\*c d Iring r qllircd for opening resin loading system lind or \\ CnLlng/llp<!ning. ny radioacti \\Ie y~ l em is a Inb co I and gl ves - When o[JCl'Jling "'jives r!'s c nlaminated roundaric!i, Operalors ~311 rcmo\\c gl (l \\ '~ urd di 'card hem into the In sh receptacle IC'culcu in he arcn and pr 'c;:d dircclI: I a ri$king I !>tnlilm and perform a frisk A full ~l ur proll'clive dlllhing i rc uircu for kneeling l'r -rawling. in a (nlamin.ncd Area Addiliunftllnsh'uclioos

~------------

RP JIl S '~~-*

-- --------------- --- - ------------------1 Page 3 Turkey Point Nuclear Plant RADIATION WORK PERMIT

'he"'" Dtmloa COpy rn ~ k 8 um btr: 2 nwp Number; 09-0001 Rev. 03 'f,uk I)Uc:r!lll lon: Operations Dcpanmcnt Routine Activities A1.AUAl t>: Slav m ar 1 '.\\.\\:1 8:00 E ~ lilll :l l t n o~(' : 11100 n1 tl'OI ,- [ 5Ii",:II(' lI ours: 20000 l.orktlllligh-I{:IlI; No 1.lIlgh-Rlld: Yes ! lIie.h-Conl:tmlnation: Yes j u ot-Pa rticle: Yes Alarnl s:tuillg, ~ , t ~I- -,,'.. I lI il!h Gam m:!; n Oll' I IIlgh Gll mnll~ R:IoIt .... ~ 25 mrem 350 mrem/hr Requlremtnl$ R t' IIU l rt"lI~ nl D('.!lf.ripliolls - I'I.!cutrnn Arca ac(*o!..C;~ i~ no' lIulhorilCd I - A~I~'mt Radioactivity Arca :tcce,s [,limited III UfI:'.!S posted aUI! 10 Noble G.. ~',-_____ _ I-i\\.. hinl)' Illgh Ibt!Jtt\\101l I\\rea bllcfing IS rcquJn:d fClr HRA occc!.s ~n;-nlln:iu;m C,)ntr,)1

r() Wink in;t lligh COflUlmillalinn A!'tnl'"C or mo", of the fl'!hw.ing mil)' he: r~Uln:J. A) lJc"lInl~min~lc Jf\\'1!. I:qulplT'lcnl to.-:10fl,OOt.\\ (Jrm I (tfkm2 (Decontamination :;:h:dl ;.: ~rr(,lr!ncd a.~ dlrl'n::d b~ Rf',. 1111 l:C IIF I'A \\cnlihmon * \\a(..uum. C) KCej) :m:3',:quir:menl wet tJurin):.

(epair.., IJI (.~cr \\)r cO:II.un area/cquipm("nl

~ul1r)' RP pdOf lu smn \\\\r \\\\or~ \\\\ itl' Highl}' C'ont:lIninnlcd materials
Poly oogs with nb~()ftk:nl mall:rial should bt: used to contnin liquids when opening rJdiolc\\ivc systems J)osimetry
I'AM or Telemetric Dosimeter is requm:d for Wllrking in a high noise IIrca Jnd10r II High ltadlJllcrn Area r: :\\i~.~UIt' (;t}lIlrul
Notif), AI.AltA iftempornry shielding necd~ t{l be rr.Med or modified 1
l ise the Vah 0: l.()CIIIO~ 0001: III JOCl\\C the,*alve.. Usc the book 11(11 your dose J.~h ( 'u\\(mgc
In 1101 r.mic1c f\\ rells. RP Go\\\\~nse i5 rcquilUl. Wllrkl." shall rccelve., HOi P.lrtide survey :lI lellst (mce t'V1:;fY IWO hc>urs :tnd U["IOfl exit from the 1101 J'urticle Area. [,rior Iu work contact RP 10.li~u ~s SJ"IOCilie IluI Particle co'l\\rol~ lL't specified in O*IIPS*027.1
Cl)ntinuolJ~ RP coverage is required tor opcning any poni(lfI of the resin flll piping
RP tOlcrage j~ required 10 remove milicrial. tools or equipmcnt from;!. COn\\lIminllh.'d Arei!.

PrOlC"\\h c rlmhlu3 ~~h()C Ctl\\crs i!nd ~IIIVCS 1m: Ihe minimum proTcctive d('thing required ror cnlry intu a lllll:lmin:ttell ArC<!. (" lah coal is required in light Rrcll.~)

b.lfi\\ ptlltct.."lil"c cluthllll,: ;:; rC'lllilCJ II.! \\\\ork with I !ish!y Conlamln~tcd materials. ! he mil)imum dress rcquirement is:) (ull sel or pmlt'~,til'e clothing. c..litm glovcs and/or <;h,ol" covers A f:u:c lihi..-1J may be rc,\\uin:d

-In tI HUI Pllniclt Are,. the miuimum ilre:iS rcquirement i:; a fuli SCI or pmt;,-clil C dnlhi n~. di<;pos-abk uu!Cr c(J\\cra l l~. C~lr:llllullt:.~. c"tlt sh(\\C. COl ct:\\ :)nJ a racc shield

WilIer re.I~llInt I)ull:r pr\\!\\cl.'1h e ' I!tlhing. i~ required 10 work in 1\\ 111::1 (oOlIl",;nllllon "rca
I hI! mrn imum Pmt<,cti, c.:loll-ing r..-qUlrc..! ((If opening resin lo:uling systf:m and.,..

\\ cntl"gll~pcni"g :my radiollcth I,: 'I~$lem i~ a 1,IIt ('031 and gloves

When oreroiling 1I;1lws.tC'n.It't eonl3mil1alC'd I>ouni.bric..... Opcr:uors 'Vul1 rcml'\\"; glu\\ Co\\ ~rd di:;cilu! them 10'(1 Ihe Inc.h recq:ude 11'I."'nlcd in the :Ire:'! and proceed din.'ClI) tn !l fri ~ klng.

I Mallon :moJ pcrrllml a ftl~1. A rull '>l'\\ or Ilftltl'cli VI,: dollhing i~ requited for kneclin~ l~r (.T3whng in:l Cnnlamin~ll'd Arc:u A cld il i(l n )l IID ~ lrucii o ll s (;tnl'rlllln\\lnll'linn,; \\ \\ 't'Ir kc-!" I n ~ l r u cl io n ~: rut 1\\I ~ l ru(.'\\i l)II~ : 1116/20092;5'1 PM Page 3

urkey Point uclear Plant 3 FPL. RADT TION WORK PERMIT Nueloar Division COpy Tnsk Number: 3 RWI' Number: 09-000 I Rev, 03 I-Task Descril2lion: Chcmlstr D~p'artrncnl Rouline Activities T~~k Status:.'\\clivc ~L~RA 10: Estimate J)ose: 40 mrem Locked High-Rod: No I I I Rcguiremcnl G roups I\\ uth(,ril..:d c c~s I3rielin. Re( uired Dosimelry I S t~ Tlm3! j\\ larm ()JJI:M~t): I!:OO I Estimate lIours: 17000 I Uigb-I{nd: Yes I Hil:h-CofltamiDullun: Yes I Uo!-Plu1ic!c: No Allirm Setlio'gs .,0: 1 Jlif:,h GO nlDla Dost' I High G:lmma Rate 20 mr m l 200 mr m/hr Re-,!ulremellts 1..,.:...... Rc!]uirllmCnl Descril!tions

Ncutrl)O Area cees is nOI ilulhori;r.cd
;rhome adioaclI'i)'

rea a ces<; i limiled to 'rea pos ed duc (a obi a

High Cronlnminalion Arca f1ecess is li mited 10 Sample Sinks

- A sbifilv Hi h Rlldi,Jlion Area brielin is ree uircd fur HRA access - PAM or Telcmclri Dosimelcr is required im working in;, high noi ~ arc nndlQr a High Radin ion Arell m" lab co L shoe covers, :lOd love II e the minimum pro'.~tivc clolhin rcquirw ror cnl!)' inlu II Coni Iminnlcd Area. /\\ full sci of l)rote(:live clCllhing i required for kneeling r crawling in il Conlllminated Area - Waler r ist3ni outer prntl'clivc..J IIhing is required to work in n "CI 'ontaminaliun rca 1 - nlC minimum PWlI; II c clmhil 9 requircu r)f mJi-ing, hand entries inLO a Contaminated Area is " lab 'oat and gJuvc ~ dd ifionaJ l ",, " :..:;.o.;=:.;.;: en clint aminated (Jreas wilh( ullhe n:.sl$1ancc "fRr. t-=~:---------- ---------- I~P Lm;Irtlclions: Prinr I :-ampling 'J VeT: restrict CCl:!>!i t lhl.' Aux Bldg 4' clc\\'. nnd Hot Chern Lab 10 prcclud exposure whefe oble g'l.'CS lire 'm,wn 10 he pr $CI1I and P" llhc~c arClls in ccordan c with lalion pro cdurcs. t I )(m~~Q~~ of.-L~*~:.!.~1~~1!, de- ,>;llhcsc III'C<l~ aprrl' riulcly:..;., _ _____ _ Turkey Point Nuclear Plant L'> RADIATION WORK PERMIT Mud.., O",;~jO ft COpy Tad. NUnlbC'r: 3 RWt> Numbrr: r.r 'CI D R 09*000 I Rev, 03 lu k D(,ScrJl!llon! lc nllstry cpurtlllcm oullnc ACU\\< IUl'S T. ~ k Stalus: ACTive ALAR,\\ ID: ' III T I tA 11 (' 11. 1\\1: 18:00 F.~ l illl.. lt Dose:,10 I1l1'tlll I. :sth"ulr lIouu.: 11000 Lorktd lIigh. K:III: No I lHeh.lUd: Yes I iiigh,COllbminlillun: Yes ! lIol-Par1iclr: No Alarm 5(;1111;.-, ~ I IHgh G:un nlli Il O~t IIIgh C,m m;1 Rliit 20 mrcm I 200 mrcm/hr Ke.Qulrc.nlentJ R('lillirr m l'ni GruU[I) -L _ RrCluiremtnl 1)t:5crilllions I ",,"on,,",,,"" r 'ron.\\,,,,<<"";, no< hn6,,",

Airt'olTIl" IhldiclIlt:uvil) Area "'~'ces~ Is limited 10 ~retl.s ~Itd duc 10 Noble C;1I~

- High C(lnl:1rr.irUllion AtCI! nccc.u is limited II) Sample Sinks I Drrdings ReqUired I n...,simctr:; I - 1<'/\\ \\., ()f Telemetric Dos;melC'T is reqoired fc., wnrking in J hiSh nlliS\\: arcl! (IIId!Ot II Jligh Rlldl~l i()1l A/1::1 l *rt,*.~'CIi\\c Clothing

A Illb COIlt. shoe 1,;,) \\ ers, :lnd glo\\ t's lire the nllnimum pm'.cclivc clothing rcquiteJ fur tnl!)'

inl(t A Ct'lnl.lminllied ArC'a. 1\\ full sct \\If l)rotc~~t1'.'(" clothing is required rot kneeling or era\\\\ ling in J Conbminatcd Area

W:ilcrto'it:ll1\\ outer f~I'Ir."cth*e "tc1lhing is required tt' lINk in n \\\\*cl Conluminllliu/1 I\\r\\'\\1
Thc nlinirnum rmtl:ct,\\ c d.\\lh;l\\~ rctl:Jircu lor tnJkinc h:md cnttits into a Contaminated An::t is i1 lab ':1131 :lIid jlJOVC\\

(; *e n c rll lln. ln.l S: lio n ~ : - A!!diUollltl lllstrl1cliuns Nu H:Sm procclo\\inll ni:tlvilic~ Me lIU1hori;cd on Ihi~ tuxk. Chcm..!:~lry TI,;.;h~ ~ InJu'{\\.:r ~lJrpll'~J ~tmp!inf cquir..mcn( bc~~Il1Bminalcd I/TCa.~,,*ilhtKlllhc l1'>srSlanl,;c... fRr. urSler In ~ lructi nns : NCllify RI' priCol ttt Willing VC r', or U<il> Dc.:.J)' Tank" NII!if)' I{P prior Itl ~:!mprinK mJi(I;lClh e S~S ICtr\\S *

\\n... r 'illmplil1!\\ ntdi03Clivc ~~ ~tem~ till.'\\C ~bmpl... 'link with dcuI, WOller II,} rc:duce conlaminatl" n It.:vds.

IH ' In ~lrueli(m.~: Priflr to l><lmp!ing lO] VeT "c$lriCI IIC<.)Cs..~ to the,\\ux lIldg 4 0 deY. nntl H()I Chem lAb 10 p~c:lude e\\:posurc where Noble gOl'Cl> :rtc kllt'wn 10 1'1,: prc~nl and poYj( (h~.;c.Ircu~ in acconbncc with Slali ** n ploccdur(:s. Ilpun r.w2p~cli."'_ of UJ '"fl :::.rmr:!!.n~ tk:'Jlf,,1 :hc..'>C ".-CI$",rprnlJlIiuld).

Itr; 'lings R"q:Jilcd-('tlnt8min:l.li"n (oJ1lrol f)usimC" r~ I)rotectivc: C~ncr;11 IIl ~ tr ll("lion": Turke Point Nuclear Plant FPL RAD TION WORK P RMIT Nuclur OiviJion COpy

1\\ lab conl.. hl~ clwcrs. and glo"e~ are the: minimum pl1ltC1:tivc clothing required for cr.lry into 0 Cont minated. rcu.. full set tlf proteclive cit thing is J\\ quircd r. r lnecling ur crawling in n ("mmminlllcd rea ':'1111 prOle th clothing is required lU work \\ ilh lfighl} Conlaminalcti materials 1111.:

minimum drc.~ rlll.luirl*mcnt is:1 full sCt of pmlCCli\\'c clflthin!!, c WI gloves und/or sh,e co\\ "rs. .-\\ face shield ma~ be required - In II II t Particle,\\rcu. lhc minimum tires,; rcquin.:ml:l1t i:;, full sct of protc.:ti.,c cl thing. disp ~l bk { IU l'r CI" C lis. ~'xtril gl vcs, ('X ra!ob I; overs and a tUI:C hicld

Wah'r rt' I',mntl'ut(!r pr )((:,"1\\'1' clot hin!! is rel/uin:tllo """(lrk in II wei ('ulIllllllin:lIion Area ddilionllJ lustrulions

\\ orker InstructlrlllS: t------------------- -- ---- --- nl'lnstrllclinns:

~

(/1 6/... 00 :!: - Pt... ! Tuk Number: 4 I I TUI-key Point Nuclear Plant RADJAT10N WORK PERMIT COpy RWI' Num b,",,: Jl ieh Gamma nO~ ( I IIi!!h C':lmlllll Ratt 5 Il1rcm I 8il mrcm/hr Requirements - ltellu irtmC'nt r.ruupi I Rtquirtmen l n e.'t riplilln ~ f AUlhori7td,\\.:cc.ss

Alrtx'lme Ib..Jj<J;lC'lh II) Arc;'! acce>;:<- is limlh:d In 3rt:a.. pi'.Mcd dut 10 Kohte Gas I

. ({'nI3Jom!:nl Ouilding ::cceSi is liN lIulhori7C,j I l l ridirl~~ I{CI.j.-;Trcd .1\\ shllil) 111:;11 Ibtlia\\i,," Alt3 briefing IS rC(luircd filr liRA ~~- r (I!I,:lInin'.iir;:n (,.nlm!

Ta \\\\01 \\. in a I-lip. C\\!IlI;lmin!ltion,\\rea one::;')f more Mlhe (",nO\\y;n,!! m(J.Y he..... -quircd: '"

th.,(;olnIJlnim:h: arc;! C4uipnlCilt III ~lflO.UOO dllflV I lKk;m2 (I)cconillmi;l:lll<lll shaH he pc:(orr11l:u liS Ji,.:cll'J by KPl, II) l '~~. I IEI'.. \\ wl1IiI:ni('n (\\':1":\\lU1I\\, C, Kl!l'r Ilr'Cl"l:fIUif'IllCUI \\\\cl duriug I n.:llair.'i. 1>> em tr ur cll1l1uin :m:all...:!ulpml,!'m I * '11'11i) Ri' pritlr h) Slar!!'!" "ork wilh I IIBht)" C:{}ntlJ"':"o"~'~"~-'c ' :":c"~'"'-'::;;""<:-:=:-:::-;;::-::;;;:::;:---, r ~)- - -",\\ M "< rc!cnu.:tric rJ.)simctcr l\\ Tliluircd flJf.... ')11..;"10 in II hiGh noise a.re:I.lI,d/nr ~ IliSh RaJiatilln,\\ rl:& Protective Clmhl~ --I-_="\\:'::'<hO,::"::;,c.t.C';;h::~:_c":"c"c"c";_C.:::'d<::'C'"C,:"=,=.,:,.",hC,:::mC;:""'m:::,,:mCp:n:::,,=,,::;T,,,C,:::,'-'oC,;:h","Cg:::'"C_'C'"C;'C"':;O"roC,:,:,:',,~_:--' int<J u C"ntnminated Arec. /\\ full set vI' protecti"e clothing i~ ri"qllircd lOr 1.!Il"t:iing 'Ir LrJ.wlmS C: t'nt"ntllnslrllJ;'lioll'; in n Conuunin:ltcd Area -£.,tra pratt:;::!;\\ c cillthing is rt(luircrl tn work with I!iShl) Col1ttlrnin:tletll11:!u~riaJ$ 'nil: minImum tirol, requin:lncnl is :, full ~Ct uf I'lnJII'~"hc dolhin!!. eXIra glo\\'cs Bnd!or sh~oC tIJ\\ ers. t' f~cc ~hidd 1113\\ I-c require,l - In:a liN Pnrtic.;h: A".-<l.mc ll1ir.irnum l.Ilt$S fC<luireml.!'lIl i:> n lull set 01 proil-..1,v(' dNhmg. db~\\:,hk OIl1t'r CIl' ernll ~,,'Xlr:\\ glove... (".:Irn!>hl)(' cn\\ crs lind,'I I:'...: shield I - WilhT !'1'\\a~f;lnllllcr r.... 1h""I\\'* dl>:hUl~ j" rcquin*.t Itl "" ** rk In II weI C.>>II:umn::l1ion A:('o Additional Tn)lruClions 1!1~'rrJ,~"",!,,;:;,",,ti'L""'",,": - 111 611009 2:54 P~ I

REV. 5/14/07 FLORIDA POWER & LIGHT - PTN HP*44:30A LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL "A" Pump Room /LOG# CA -O~ DATE: l-~~-O'l IDOSE RATES IN MREMIHR UNLESS OTHERWISE NOTED (A) A/RBORNE I,REA (l) LOCKED HIGH RAO AREA "GENERAL AREA DOSE RATE (8) RESP!RATORY PROTECTION (.\\1) RADIOACTIVE MATERIAL "CONTACT DOSE RATE TIME: 132.Q (e) CONTAMINATED AREA (N) NOTIFY HO PRIOR TO ENTRY 0 = SMEAR LOCATION (D) H:GHLYOONTAMINATEDARCA (R) "AD/AriON AREA

6.

= NEUTRON DOSE RATE TECH. : ~f)I£G) (E) EXCLUSION AREA (S) SURVEY METER REQUIRED D " 8ETA DOSE RATE (F) HOT PARTICLE AREA (T) H.P. COVEPAGE REQUIRED ~G- "CONTAMINATED BOUNDARY PID# : ZQS (H) HIGH RADIATION AREA () N I ..... -...... - = RAD BOUNDARY IK) KEEP OUT ().' 1. .remarks* ~< ~~ ........:-...,1...J.........?--.J ~ *. REfE:R"to Lt.:.', 5, :\\~L." ;:.\\y",! :r'~::'~""(1;' 1 [:;u;in"Orly"" < -.!I1'Irl.Il,J, I l ADDITIONAL INFORMATION RWP#: / -l SMEARS dpml100cm (COUNT AT LEAST ONE SMEAR ::50,000 DPM fOR ALPHA) SMEAR NO.: Instrument HPI# 1<'roDA 6 207-11~ 16 NI A 21 NJA 26 N1A NIA RD-:.dO 225 2=1=,<mOA12 17~ 22~ 27 BETN~AMMA: ~ \\q3 3 a+/- 13{roDA 18 23 28 D;l~ lQS 4 9 14 N J E\\ 1 9 24 29 AL HA: Rtf)* 2S :c:2 4--=t-5 <.rnot:\\ 10 ~(,()DA 15 NI A 20 N 25 30 N, A. NJA () MDA::: 1;i9 /1 \\3pm REVIEWED BY:

a. MDA=

N/A. dpm PRINT: ~-. SIGN: DATE: t~1~~ = SURVEY POINTS REV. 5/14/07 FLORIDA POWER & LIGHT - PTN HP*44:30A LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL "A" Pump Room -o~ DATE: TIME: TECH. : PID# : -.!I1'Irl.Il,J, RWP#: Instrument RO-dO IL~ In;l~ RtrI* 2.5 l-~~-O'l 13;(0 .........:-....J...J.........?--.J / -l HP/# -';"J5 \\q-o lq5 1024 --=t-i3 MDA::: 1;i9 /1 \\3pm

a. MDA=

N/A. dpm (A) AIRBORNE I,REA (8) RESP!RATORY PROTECTION (e) CONTAMINATED AREA (D) H:GHLYCONTAMINATEDARCA (E) EXCLUSION AREA (F) HOT PARTICLE AREA (H) HIGH RADIATION AREA (l) LOCKED HIGH RAD AREA (.\\1) RADIOACTIVE MATERIAL (N) NOTIFY HO PRIOR TO ENTRY (R) "ADIATION AREA (S) SURVEY METER REQUIRED (T) H.P, COVEPAGE REQUIRED () N I \\ 11: II() Y.~EPOUT "._~ f~. REfE:R""nJ Lt.;,.* "', :'.~L." ;;'\\},:>!:i "::;' "e'(1;' ADDITIONAL INFORMATION "GENERAL AREA DOSE RATE "CONTACT DOSE RATE o = SMEAR LOCATION 6 = NEUTRON DOSE RATE D " 8ETA DOSE RATE ~G- "CONTAMINATED BOUNDARY = RAO BOUNDARY .remarks* .( l ;s. U;in"orly"'" SMEARS dpml100cm (COUNT AT LEAST ONE SMEAR ::.50,000 OPM fOR ALPHA) SMEAR NO.: 1<'roDA 6 20"7-11~ 16 NI A 21 NJA 26 N. A NIA 2=1=,<mOA12 17~ 22~ 27 BETN~AMMA: 3 a+/- 13{roDA 18 23 28 4 9 14 N J E\\ 1 9 24 29 AL HA: 5 <.rnot:\\ 10 ~(,()DA 15 NI A 20 N 25 30 N. A NJA REVIEWED BY: PRINT: SIGN: DATE: t~1~~ = SURVEY POINTS

ZONE 102 REV. 11130106 UNIT*4 "An RHR PUMP ROOM Location Valve Feet Off Floor 1 4-755A 2 MOV-4-861A 3 4-1461 4 4-769C 5 4-938A 6 4-939A 7 4-8990 8 4-1462 9 4-766C 10 4-766E 11 4-762A 12 4-752A(V.O.) 13 4*12*008 14 MOV-4-862B 15 4-942R 16 17 4*70-117 1 2 3 4 5 6 x x x 17 18 19 20 21 22 33 7.5 6 2 5 5 5 3.5 3 1 1 6.5 8.5 1.5 5 3 7.5 7 Location Valve Feet Off Floor 18 4-754A(V.O.) 11 19 4*10-039 11 20 4-753A 2 21 4*756A 3 22 4*768A 4.5 23 40-1848 11 24 4*769A 3 25 40-1847 11 26 40-1846 11 27 4*766A 0.5 28 4*756C 3.5 29 4*10-040 11 30 4-12-007 1 31 4*12-009 1 32 4*12-010 1.5 33 4*767A (H.W.) 1 34 8 9 10 11 12 13 14 15 24 25 26 27 28 29 30 31 32 (V.O.) = Location of the valve NOT the hand wheel (HW.) = Location of the hand wheel Not the valve ZONE 102 REV. 11 /30/Q6 UNIT -4 "A" RHR PUMP ROOM Location ~ F,el Off Floo, 7., 2 6 Valve Feet Off Floor 4* 754A.0.) 4*1(}.{)39 J 4-14" .J 20 4-75JA 2 4-756A 3 ~ 3.' 8 3 22 <I-16BA 4.5 23 40-1848 24 4*769A 3 25 40-1847 8 ~766C 28 40-1 846 '.Q. 27 4-766A 0.5 ~O) 8.' ~ 1.5 28 4*756C 3.5 29 4-10-040 JO 4-12-007 5 Jt 4*1 2'()09 J2 A-12..()10 1.5 3J 4*767A (H.W.) >I 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 x x x x x x x x x I 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 (V.D.) = Location of the valve NOT the hand wheel (HW,) = Location of the hand wheel Not the valve

REV. 5/14/07 FLORIDA POWER & LIGHT - PTN HP-44:30B LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL irS" Pump Room kOG# 0'1-O~ y-~) ,rOSE RATES IN MREMlHR UNLESS OTHERWISE NOTED " :"?~ rr:, / c; "~'",,','.,.",-,,, '~'" (I, LOCl'ED HIGH RAD AREA '" GENERALARf'CA DOSE RATE ~ .<~, \\~"!ft"'t.~...... v",,:: ~'-~~."'.: _,""",,'.'~ '::t-. I jR',:-38:~*.;'7~~*;:;:;o.,J::s:;o.::t;;:"0*\\,,'~~ (8) RE:,HM TORY PROTECT!ON \\,\\1; RAOIOACnVC:: MAl'EKiAL TIME: / b ~ 5?) tCI CONTAMINATED AREA (N) NOTIFY HP PRIOR TO ENTRY 0 = SMEAR LOCATION I) ;JVc#--; (D) HIGHLY CONT AMINl, TED AREA (H) RADIATION ARE.. £::" '" NEumON DOSE RATE TECH. : (E) EXCLUSION AREA (S) SURVEY METER REQUIRED 0 = BETA DOSE RATE (F) HOT PARTiCLE AREA (T) H,P, COVERAGE REQUIRED ~ "CONTAMiNATED BOUNDARY PID#: c!(3! " (H) HIGH RADIATION AREA ( ) " RAD BOUNDARY (K) KEEP OUT ( ) Remarks: SIGNATURE: ;i)lc:(MJj (.(16; REFER TO LOCAL AREA POSTINGS FOR G 1...'\\"(:(, r -k r ( L'; AOJITIONAL INFORMATION RWP #: / /; SMEARS dpml100cm' (COUNT AT LEAST ONE SMEAR Z. 50,000 DPM FOR ALPHA) 1 SMEAR NO.: Instrument HPI # 1..(m/lA-6A)Jr 11 /35 16/-"!)u?A-21 26 r--~ /-1020 /2-2-5 2.l..fov--t:_ 7 4, 12 2-0.5 17~'1-22* 27 / BET"'AMMA: Xldf ILd ( 3c:'..I~t?d:. 8 3/S-1'3 6,.'/hM 18~ 23~* 281-/ / tJ 'it~ .i1mz..-)' JcJ-c/ 7 4 " a,. /2/r 9,.(hvi,;y 14":::"/1'l4.4-19 tv 24 /.r 29 j?r YH,A,: 5.L..J~,*1 1 0 £...&::14.. /1:::. 1 5/;: 1f2.4 4-~ 20 'I 25 30 I 2..2. Rf Idpm I !3 MDA= REVIEWED BY: a MDA= J7' "f'f dpm PRINT: SIGN: DATE: = SURVEY POINTS ¥_Vi @,§ 'f -c)-B cx..o~ ex- ~G'- z.. //2;) 3:::--- ~ 1<C)(J~.---pc,y-}-6-[) -12>P ~,Ce-D~. t' R;I REV. 5/14/07 FLORIDA POWER & LIGHT - PTN HP-44:30B LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL irS" Pump Room kOG# 0'1-O~Y-j / i c; '. ~",'.;" ',:. '::;If".~~,~, (;;i.., ": __ " '":" IDOSE RATES IN MREMlHR UNLESS OTHERWISE NOTED - " :"?~ rr:, (I, I.OCl'ED HIGH RAD AREA '" GENERALARf'CA DOSE RATE /6 5() (8) RE-:~HM TORY PROTECT!ON \\,\\1; RAOIOAcnVC:: MAl'EKiAL "'!,~,' '::t'. I jR',:-38:~*.;'7~~*;:;:;o.,J::s:;o.::t;;:"0*\\,,'~~ TIME: tCI CONTAMINATED AREA (N) NOTIFY HP PRIOR TO ENTRY 0 = SMEAR LOCATION I) ;JVc#--; (D) HIGHLY CONT AM IN.<, TED AREA (H) RADIATION AREA £::" '" NEumON DOSE RATE TECH. : IE) EXCLUSION AREA (S) SURVEY METER REQUIRED 0 = BETA DOSE RATE (F) HOT PARTiCLE AREA (T) H,P, COVERAGE REQUIRED ~ "CONTAMiNATED BOUNDARY PID#: c!(3! " (H) HIGH RADIATION AREA ( ) " RAD BOUNDARY (K) KEEP OUT ( ) Remarks: SIGNATURE: ;i)lc:(MJj (.(16; REFER TO LOCAL AREA POSTINGS FOR Q 1....\\..(:( r -k r ( L,y AOJITIONAL INFORMATION RWP#: / & SMEARS dpml100cm' (COUNT AT LEAST ONE SMEAR Z. 50,000 OPM FOR ALPHA) i SMEAR NO.: Instrument HPI # 1.4m/lA-6A)Jr 11 /35 16/-"!)u?A-21 26 ~-~ /"" 020 / 2-2-5 2.l..fov--t:. 7 4, 12 2-0.5 17~'1-"* 2.7 / BET::;AMMA: XL6 ILd ( 3c:'./~t?d:. 8 3/S-1'3..I,,/hr:U!::. 18~ 23~* 2a;U / tJ 'it~ !? (Y)2--S-JcJ-cj 7 4 " a,. /2/r 9,.(hvi,;y 14":::"/1"14.4-19 tv 24 /.r 29 /.?Y YH,A,: 5.LJ~a..*l 1 0 £...ib4.. /t:. 1 5/;: IfZ/! 4-~ 20 'I 25 30 /

2.,2. Rf I dpm I

!3 MDA= REVIEWED BY: a MDA= n* "f'f dpm PRINT: SIGN: DATE: ~1~ij = SURVEY POINTS ¥_Vi @,§ 'f -c)-B cx..o~ ex- ~c;.t. Z- //2;) 3:::--- \\.....:.-/ 1<C)(J~.---pc,y--}-6-[) -12>P ~*Ce-D ~. t' R;I

Location Valve 1 4-7558 2 4-7548iV.O.) 3 4-767B(V.O.) 4 4-1463 5 MOV-4-8618 6 4-7660 7 4-899F 8 4-1464 9 4-766F 10 4-7528(V.O.) 11 4-762B 12 4-12..Q14 13 4-12..Q13 14 4-12-011 15 4-12-012 1 2 3 4 ZONE 103 UNIT -4 "8" RHR PUMP ROOM Feet Off Floor Location 7 16 11 17 0.5 18 2 19 5 20 1 21 3.5 22 3 23 1 24 8 25 6.5 26 2 27 1 28 1 29 2 30 5 6 7 8 9 10 11 REV. 11/30106 Valve Feet Off Floor 4-70-1178 7 4-887 2 4-7538 2 4-7568 3 4-9398 5 4-9388 5 4-7690 5 4-7698 3 4-7688 4 4-7668 1 4-7560 3 4-1091 3.5 MOV-4-862A 8 4-942P 6 14 15 'I 16 17 18 19 20 21 22 23 24 25 26 27 28 29 (V.O.) = Location of the valve NOT the hand wheel (H.W.) = Location of the hand wheel Not the valve I I I I I Location Valve 1 4-7558 2 4-7548(V.O.) 3 4-767B(V.O.) 4 4-1463 5 MOV-4-8618 6 4-7660 7 4-899F 8 4-1464 9 4-766F 10 4-7528(V.O.) 11 4-762B 12 4-12.Q14 13 4-12.Q13 14 4-12-011 15 4-12-012 1 2 3 4 x ZONE 103 UNIT -4 "8" RHR PUMP ROOM Feet Off Floor Location 7 16 11 17 0.5 18 2 19 5 20 1 21 3.5 22 3 23 1 24 8 25 6.5 26 2 27 1 28 1 29 2 30 5 6 7 8 9 10 11 REV. 11/30106 Valve Feet Off Floor 4-70-1178 7 4-887 2 4-7538 2 4-7568 3 4-9398 5 4-9388 5 4-7690 5 4-769B 3 4-7688 4 4-7668 1 4-7560 3 4-1091 3.5 MOV-4-862A 8 4-942P 6 14 15 'I 16 17 18 19 20 21 22 23 24 25 26 27 28 29 (V.O.) = Location of the valve NOT the hand wheel (H.W.) = Location of the hand wheel Not the valve I I I I I

,-~~~ REV. 5/14/07 FLORIDA POWER & LIGHT - PTN Hp-44:30Hx LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL Heat Exchangers LOG# 0'1 '-0388 DATE; TIME; TECH. : PID# : 'T)(~ ltc '( t:.LS 2DCl (A) AIRBORNE ARPA (8) RESPIRA TOl1Y PROTECTION (C) CONTAMINATED AREA (0) HIGKL Y CONT4MH.ATED AREA (E) EXCLUSION "',EA (F) HOi PARTiCLE AREA (H) HIGH RADIAl ION AflEA (K) KEEP OUT (L) LOCKED HIGH MD AREA (I\\!) RADIOACTIVE MATERIAL (N) NCIIFY HP PRIOR TO ENTRY (R) RACIATION t,REA (S) SlJRVE', ME,ER REO~IRFD (T) HP, COVEPA E REQ~IRED () l'.i ( DOSE RATES IN MREM/HR UNLESS OTHERWISE NOTED " GENERAL AREA DOSE RATE = CONTACT DOSE RATE o ~ SMEAR LOCATION L\\ " NEUTRON DOSE R/,TE o '" BETA DOSE RATE ~ = CONTAMINATED BOUNDARY '" RAO BOUNDARY ,-"",.,.,.,. ';; :\\'!;;-~,~~-

';;: :,-::3, It.,;:t::~/;:'l;\\,,(.F,c:\\ i_'?t;.~o',{;&Fc;;:

lK 'r,i ' 'L QUcirlerly i ADDITIONAL INFORMATION RWP# : Instrument .80' J.0 ~r:l '1' [-<Ii '.4..:' LO-:2. '2cD LJ)22(::C f1 MDA= 0; MDA::: l-i SMEARS dpmll00crn (COUNT AT LEAST ONE SMEAR;:: 50.000 DPM FOR ALPHA) SMEAR NO.: HPI# 1 ~ D'\\t):fj Il4*{) 2<fYJ,D~ ) 2-4 '! 3~ I! [13 4:(lflO ) 1(15:' 5 343 IJJ) 100 dpm REVIEWED BY: !'-l/J\\ dpm PRINT: kt.."+Sp::+ 0,1-/4 .J';2.S/1i With i~O-.zO lo/IC 6<:jY).o~ :+/- 10 <'l'MA ~~ -,- 11-< MQA 16 NJA-21 N/A-26 1\\1/ A Nl8 12.(MIJA 17+/- 22~27 "~wrrM' 13 {1:13 18 23 28 14 <. fi'\\{)A 19+/- 24 29 AL HA: 15 <mDf\\ 20 25 30 c SIGN: 2~ CD~ DATE: -

SURVEY POINTS

UH26tz ARr::p., S,MEftR-S (A~ B) ~

"'-ICOc dpY> i 3rcss-w1pe J be\\-e,.. 9CllVlmq

Rct,,)'M R)S-IED ~ 'R; (a.) i e,)

. :....,..x~ REV. 5/14/07 FLORIDA POWER & LIGHT - PTN Hp*44:30Hx LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL Heat Exchangers /LOG# 0'1 '-0388 ~?'i. C'i DATE;

.,LJ TIME; D1~C.'

TECH. : 'T)(~ ltc '( t:.LS PID# : 2DCl i-\\ .fl--- J~_ ""_.. -/. >'OJ< /..,, 1"'" __ ~' :',!.-,[~i~ __ RWP# : l-i Instrument HPI# .BtL* J...0 \\l4-D ill:l '1' )24-r: , '.4..:-:' LD-:l2cD I! [13 L~D22(::C ) I (1S' f1 MDA= 121 J 100 dpm 0; MDA::: !'-l/J\\ dpm DOSE RATES IN MREM/HR UNLESS OTHERWISE NOTED (A) AIRBORNE ARPA (L) lOCKED HIGH RAD AREA " GENERAL AREA DOSE RATE (8) RESPIRA TOl1Y PROTECTION (1\\.') RADIOACTIVE MATERIAL = CONTACT DOSE RATE (C) CONTAMINATED AREA (N) NCilFY HP PRIOR TO ENTRY 0 ~ SMEAR LOCATION (0) HIGHLY CONT4MH.ATED AREA (R) RADIATION AREA L\\ " NEUTRON DOSE R/,TE (E) EXCLUSION "',EA (S) SURVE', ME,ER REO~IRFO 0 "BETA DOSE RATE (F) (T) HP, COVER1" REQ~IRED ~ = CONTAMINATED BOUNDARY HOi PARTiCLE AREA (H) HIGH RADIAl ION AflEA () \\'..i " RAO BOUNDARY (K) f 1\\ Rama'~"* KEEP OllT ( ), ~r~~~ ~ '"7'"77~""ft~ ~~.Y "':'.~:"-"'.,... d"l1&I"'iJr.t. ::

';;: :;::3, 1 t,;:t::~/;:'1;t,(.F,c:\\ i 'J1!:; i\\o',r;&F:-':;;:

L QUarlerly i ADDITIONAL INFORMATION SMEARS dpmll00crn (COUNT AT LEAST ONE SMEAR:: 50,000 DPM FOR ALPHA) SMEAR NO,: 1 ~ D'\\t):fj 6<:jY).o~ 2<fYJ,D~ :+/- 3~ 4:(lflO 5 343 10 <YMA REVIEWED BY: PRINT: ~~ -,- 11..( MQA 16 NJA-21 N/A 26 1\\1/ A Nl8 12.(MIJA 17+/- 22~ 27 "~wrrM' 13 {1:13 18 23 28 14 <. fi'\\{)A 19+/- 24 29 AL HA: 15 <mDf\\ 20 25 30 c SIGN: 2~ CD~ DATE: -

SURVEY POINTS UH26tz ARr::p., S,MEftR.-S (A ~ B) ~

":'ICOc dpY> i 3rcss-w1pe J We,.. 9CllVlmq

Rct,)'M n)SIED ~ 'rz; (a.) i e,)

Ht.."+Sp::+ 0,1-/4 .J';2.S/1i With i~O-.zO lo/IC '5q~ 1}3

Location Valve 1 4-771 E 2 4*759A(V,O,) 3 4*771F 4 4-759B(V,O,) 5 4*760A 6 4*7710 7 4-771C 8 4*842 9 4*943V 10 4-7460 11 4-943W 12 MOV-4*863B 13 MOV-4*863A 14 4* 12-017 15 4-12*016 2 3 4 5 6 7 8 9 10 11 12 13 ZONE 104 UNIT -4 RHR HX ROOM Feet Off Floor location 6 16 6 17 9 18 8 19 3 20 5,5 21 5.5 22 1 23 4 24 10,5 25 1 26 2 27 2 28 2 29 2 30 X a REV. 11/30/06 Valve Feet Off Floor 4-12-015 2 4-12-018 2 4*746C 10.5 4-757 A(V,O.) 10 4-7570(V.O.) 10 4-7718 5.5 4-771A 5,5 4-757B(V.O.) 9 4-757C(V.O.) 10 4-757F 1 4-942T 1 14 15 16 17 18 19 20 21 22 23 24 25 26 (V.O.) = Location of the valve NOT the hand wheel (HW.) :: location of the hand wheel Not the valve l ocation Valve 1 4-771E 2 4-7S9A{V.O.) 3 4*77 1F 4 4-759B(V.O.J 5 4*J60A 4-1710 4-77 1C 8 4-842 9 4*943'1 10 4-7460 4-943W MOV-4*8638 MQV-4-863A 14 4*12-{)17 4-12-016 1 2 3 4 5 6 7, 9 10 13 ZONE 104 UNIT -4 RHR HX ROOM Feet Off Floor Location 16 9 18 8 19 3 20 5.5 21 5.5 22 23 4 24 10.5 25 2 27 2 28 2 29 2 30 X ,"R EXCHANGER X $1 REV. 11130/06 Valve Feet Off Floor 4-12.015 2 4-12-018 2 4-746C 10.5 4-7S7AN.O. 4.7510 V.D. 10 4*771B 5.5 4-771A 5.5 4-7S7B{V.O.J 9 4-757C{V.O.) 4-757F 4-942T 14 15

1.

17 18 20 21 22 2J 25 26 {V. D.) = Location of the valve NOT the hand wheel (H.W.) = Location of the hand wheet Not the valve

REV. 12/4/0 6 FLORIDA POWER & LIGHT - PTN HP-44:30.1 LOCATION: UNIT 410' ELEVATION (ACCESS TO RHR PITS) ILOG# 6e-13~ 1 DOSE RA rES IN MREMIHR UNLESS OrHER'oVISE NOTED DATE: I 2. - 1 "'" - d~ (A) AIRBORNE A.REA (Ll LOCKED HIGH RAO AREA ~ GENERAL AREA DOSE RATE (8) RESPIRATORY PROTEC nON (M) RADIOACTIVE MATERIAL = CONTACT DOSE RATE TIME: __.....LS_:.g.. 2 __ (C) ceNT PMINATEO AREA (N) NOTIFY HP PRIOR TO ENTRY 0 = SMEAR LOCA n ON (0) HIGHL'( CONTAMINA.TEO AREA (R) R.-.OIA TION AREA

b.

= NEUTRON DO~E RATE TECH. : ___ ::2 ~ , <2."-:4 (E) EXCLUSION AREA (5) SUR'/EY METEH REQUIRG) 0

SETA DOSE RATE (F) Hor PARnCLEAREA (T) if.P. COVERAGE REQUIRED

-o..0-.G = CONTAMINATED BOUNDARY PID# : \\ ') '1 (H) HIGH RAOIA !ION AREA. ( ) {-.;/ ~... ¥ = RAD BOUNDARY 7 If Remarks: A (I <!~S<. .r '" \\-c;; ~ Co<1 d -"'",/"-1 (K) KEEP OUT ( ) SIGNATURE; 0')'--- REFER TO LOCAL AREA POSTINGS FOf:i-'--- ""'-\\IQS d << <7d~d J I C~ <l.~Y' *HVJ

~

ADDITIONAL INFORM/I, T IO ~J ~~fQ\\N rJ c> ~\\- 1J<l'" <-Ie..;' d.... kc; RWP# : ____. ___ 1.::....-. __ SMEARS dprn/l00cm' (CO UNT AT LEAST ONE SMEAR ~ 50,000 DPM FOR ALPHA) SM~ARNO/ Instrument HPI # 1.(0 Q6 6 _s..!1~ 11...::....~ 16 ,-r-'\\ QJ, 21,z'\\j. Q,+ ~:-J--- ,--'.... -------- -- --- ~C~~- --- kG-7" 2~J2:i 7 -~ 12 ~~ 17~lL 22 L \\'-\\9b BETN<7MMA W<O.1:.UC_=-:L __ ..:.ii~ ___._._.. 3~ ... 6C 8 __ ~~QIf 13 13.'it 18 .. ~ 23 c.",-\\ vA-28 If'! / A 7A~PHA' .....§.5.:s _':iL ~l..;~~ __ 4 -~-!>~(') 9 14 -<:~~ 19 k:\\'-10k 24 L..<'-1.2!L 29 I ...£1&Q.(L ,/ 5 2[).~t~ 10 _._sMPA 15 c..,M\\~ 20 t:.r1'lQtL 25 £t::lvA-30L_ / .. _.. _. J~._ MDA= _"-.c.~? '1 _clErn_ fl EVIEVVED 8Y a MDA= J!_.0~~_ ~Em PRINT SIGN: DATE: . ~ ~ -"~ '" SURVEY POINTS mm LINE . ~,. .,-0-0-0, 'c.,. Ci) ? If

n.7 17 OL- 0 -~-o C

s*o \\/ 8 o REV 12/4/06 LOCATION: DATE; TIME; TECH. : PIDI/ ; RWP# ; Instrument C\\. 7.. (l MOA-n MDA'" FLORIDA POWER & LIGHT - PTN UNIT 410' ELEVATION (ACCESS TO RHR PITS) DOS£ RATES '" IoIR£MlHR UNL£SS OmEKMS,f NOTED II\\} "'R6OII><F. M~E" (S) ilF.SI'1f1"TORvp~o ru;rlON (C) ':CN-:-AM",,,T£('> ~R E.Io "2. 7 *. <; j dpm flEVIEVJEO nv r::~~m PRINT 6 £...~ 7 ~ 8 (.rlQ:1r 9....L..!..&Q!L 10 ~""M I (l) LOCK£O H;Gt< R.o.D.o.RE.<. (M) kIoDt(McrrJEMArCRI.L (1'1) NOlWYHP PRQilTOENTR1 11 ~ 16. "MQ! \\2 4t:!lli.... 17 .t:.~12a: 13 2::'

~~ " =

" ~ 19 ",.., 0--'1-15 <>1'401 20~A SIGN o .. GENERAL AREA DOSE RArE, ~ CONTACT ~OSE RATE .. SMEAA LOCAno.. DATE; ('-----....>6)"'--_---r ,0 - ",O-O_~ I b.. (:!H'i*1r.7~ 0 '--0 _ 0 C 5' C - ,.0 -

ZONE 105 REV. 11/30106 I UNIT-410' ACCESS TO RHR PITS Location Valve Feet Off Floor Location Valve 1 4-8358 2 16 4-8350 Feet Off Floor I 1.5 2 4-835A 5 17 4-770B 2 3 4-770C 2 18 MOV-4*8608 4 4-770D 5 19 4*746A (V.O.) 2 8.5 5 4816 0.5 20 40-1845 6 6 4802 0.5 21 4-7468 (V.O.) 7 4-770A 5 22 4-40-1905 8 4-791K 1 23 FCV-4-605 8.5 5.5 5 9 4-791J 4 24 4-761F 4 10 4-767E 1 25 40-1844 11 4-898N (V.O.) 1 26 40-1843 5 3 12 4-893E 1 27 4-761E 15 13 4-899E 2 28 4-746E 14 4-767F 1 29 4-746F 15 4-835C 5 30 HCV-4-758 5 5 1 c:==:Jc:=::=:=J t I "'-~ 3 4 5 RHR LINE --~====~~============~---- '~ 6 7 10 11 12 13 14 ""-- 15 16 17 t.-- 18 19 20 21 L 33 22 \\..34 23 ./" 24

25 26 27

"-- 28 29 30 x 35 x 36 ~31 32 (V.O.) = location of the valve NOT the hand wheel (HW.) = Location of the hand wheel Not the valve 5,, Valve J ZONE 105 UNIT -410' ACCESS TO RHR PITS Feet Off Ftoo' 5 '.5 ~ 5 25 30 ,0-"" REV. 11 /30/06 Feel Off Floor '.5 5 3 (v.o.);: Location of the valve NOT the hand wheel (H.w.) = Location of the hand wheel Not the valve I JI II II II II, ~

Location Valve 31 4-7618 32 4-761A 33 4-40-1898 34 4-40-1896 35 4-7658 36 4-765A 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 70 71 72 73 74 75 76 ZONE 105 UNIT-410' ACCESS TO RHR PITS Feet Off Floor Location 14 77 14 78 5 79 6 80 21 81 21 82 83 84 85 86 67 88 89 90 91 92 93 94 95 96 97 98 99 100 101 102 103 104 105 106 107 108 109 110 111 112 113 114 115 116 117 118 119 120 121 122 REV. 11/30106 Valve Feet Off Floor (V.O.) :: Location of the valve NOT the hand wheel (HW.) :: Location of the hand wheel Not the valve L r ocalon v ~ a

II 4-7618 32 4-761A 33 4-4()..1898 4 1896 35 4-7658 36 4.76SA 37,.

J9 50 51 52 53 55.. 57 58 59 eo 61 62 65 66 67 68 69 10 11 72 13,. 75 16 ZONE 105 UNIT -410' ACCESS TO RHR PITS F t Off Floor

e.

Location 77 78 5 79 6 80 21 21 82 84 85 86 90 92 93.. 95 96 97 98 100 '03 '05 ' 06 'IS 117 '20 122 REV. 11/30106 Valve Feet Off Floor (V.D.) = Location of the valve NOT the hand wheel (HW.) = Location of the hand wheel Nollhe valve = . \\>. "..... --- ~

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: _T_u_r_k--"-e.L.y_P_o_in-'-t'--______ Task No: Perform Review of O-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches Task

Title:

JPM No: NRC-25-ADMIN-JPM-A 1.2 2.1.29 KIA

Reference:

Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance Actual Performance X

~'--------

Classroom X Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 3 is in Mode 1 at 100% Power 0-OSP-205, Verification of Administratively Controlled Valves, Locks and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification are in progress. HV-3-1, Post Accident Containment Vent and Sample System Isolation Valve (RR) has been found Locked Open. Task Standard: SRO determines that Containment Integrity is not satisfied and directs that it be restored within 1 hour. Required Materials: 0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches 3-0SP-053.4, Containment Integrity Penetration Alignment Technical Specification: 4.6.1.1.a FSAR Chapter 6 Section 6 General

References:

0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches 3-0SP-053.4, Containment Integrity Penetration Alignment Verification Technical Specification: 4.6.1.1.a FSAR Chapter 6 Section 6 NUREG 1021 Rev 9 Appendix C Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility: ---'-T=ur:.-kc..:.e.Ly--'-P-'o:....:..in:.-t'---______ Task No: Perform Review of O-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches Task

Title:

JPM No: NRC-25-ADMIN-JPM-A 1.2 2.1.29 KIA

Reference:

Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Simulated Performance ____________ Actual Performance _____ ....:X=--=-_____ _ Classroom X Simulator ---------- Plant ________ _ Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 3 is in Mode 1 at 100% Power 0-OSP-205, Verification of Administratively Controlled Valves, Locks and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification are in progress. HV-3-1, Post Accident Containment Vent and Sample System Isolation Valve (RR) has been found Locked Open. Task Standard: SRO determines that Containment Integrity is not satisfied and directs that it be restored within 1 hour. Required Materials: 0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches 3-0SP-053.4, Containment Integrity Penetration Alignment Technical Specification: 4.6.1.1.a FSAR Chapter 6 Section 6 General

References:

0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches 3-0SP-053.4, Containment Integrity Penetration Alignment Verification Technical Specification: 4.6.1.1.a FSAR Chapter 6 Section 6 NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 12 Form ES-C-1 Initiating Cue: Evaluate Unit Conditions and and determine corrective actions. Time Critical Task: Yes (1 hour) Validation Time: 18 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C Appendix C Page 2 of 12 Form ES-C-1 Initiating Cue: Evaluate Unit Conditions and and determine corrective actions. Time Critical Task: Yes (1 hour) Validation Time: 18 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS TIME! NUREG 1021 Rev 9 Appendix C

I Appendix C Page 3 of 12 Form ES-C-1 I SIMULATOR SETUP Reset to IC # N/A Load Lesson N/A Ensure Simulator Operator Checklist is complete N/A NUREG 1021 Rev 9 Appendix C I Appendix C Page 3 of 12 Form ES-C-1 I SIMULATOR SETUP Reset to IC # N/A Load Lesson N/A Ensure Simulator Operator Checklist is complete N/A NUREG 1021 Rev 9 Appendix C

Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark( I) Start Time Obtain 0-OSP-205, Verification of Administratively Controlled STEP 1 Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity SAT Penetration Alignment Verification from NPO. UNSAT Obtained marked up copy of 0-OSP-205, Verification of Standard: Administratively Controlled Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification from NPO. Provide marked up copy of 0-OSP-205, Verification of Administratively Cue Controlled Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification. Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 4 of 12 Form ES-C-1 Denote critical steps with a check mark( I) Start Time Obtain 0-OSP-205, Verification of Administratively Controlled STEP 1 Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity SAT Penetration Alignment Verification from NPO. UNSAT Obtained marked up copy of 0-OSP-205, Verification of Standard: Administratively Controlled Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification from NPO. Provide marked up copy of 0-OSP-205, Verification of Administratively Cue Controlled Valves, Locks, and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification. Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 12 Form ES-C-1 I Determine HV-3-1, Post Accident Containment Vent and Sample STEP 2 System Isol Valve (RR) LOCKED OPEN does not meet the SAT ~ requirements of 3-0SP-053.4, Containment Integrity Penetration Alignment Verification, and 0-OSP-205, Verification of Administratively UNSAT Controlled Valves, Locks, and Switches. Determines HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) LOCKED OPEN does not meet the Standard: requirements of 3-0SP-053.4, Containment Integrity Penetration Alignment Verification, and 0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches. Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C I Appendix C Page 5 of 12 Form ES-C-1 I Determine HV-3-1, Post Accident Containment Vent and Sample STEP 2 System Isol Valve (RR) LOCKED OPEN does not meet the SAT ~ requirements of 3-0SP-053.4, Containment Integrity Penetration Alignment Verification, and 0-OSP-205, Verification of Administratively UNSAT Controlled Valves, Locks, and Switches. Determines HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) LOCKED OPEN does not meet the Standard: requirements of 3-0SP-053.4, Containment Integrity Penetration Alignment Verification, and 0-OSP-205, Verification of Administratively Controlled Valves, Locks, and Switches. Cue Comment NOTE: NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 12 Form ES-C-1 7.4 IF a component is NOT in the position specified in Attachments 1, STEP 3 2, or 3, THEN list the component under Remarks in the applicable SAT attachment AND notify the Shift Manager or Unit Supervisor. UNSAT Standard: Informs Unit Supervisor/Shift Manager of deviation. If candidate attempts communication with Unit Supervisor/Shift Cue Manager, confirm communication and as Shift Manager direct Unit Supervisor to take any appropriate action(s) if any are required. Comment NOTE: NUREG 1021 Rev 9 Appendix C Appendix C Page 6 of 12 Form ES-C-1 7.4 IF a component is NOT in the position specified in Attachments 1, STEP 3 2, or 3, THEN list the component under Remarks in the applicable SAT attachment AND notify the Shift Manager or Unit Supervisor. UNSAT Standard: Informs Unit Supervisor/Shift Manager of deviation. If candidate attempts communication with Unit Supervisor/Shift Cue Manager, confirm communication and as Shift Manager direct Unit Supervisor to take any appropriate action(s) if any are required. Comment NOTE: NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 12 Form ES-C-1 7.4.1 The Shift Manager or Unit Supervisor shall evaluate the STEP 4 configuration of the component and penetration to ensure that SAT ~ CONTAINMENT INTEGRITY requirements are satisfied. UNSAT Standard: SRO Candidate determines Containment Integrity is NOT satisfied. Cue Comment Uses any or all of the following to determine Containment Integrity: FSAR Chapter 6 Section 6 : Manual and remote manual valves which do not receive an automatic actuation signal are administratively controlled to preserve containment integrity. -OR-Technical Specification: 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION NOTE: 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.* APPLICABILITY: MODES 1, 2, 3, and 4 ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their closed positions; NUREG 1021 Rev 9 Appendix C I Appendix C Page 7 of 12 Form ES-C-1 7.4.1 The Shift Manager or Unit Supervisor shall evaluate the STEP 4

configuration of the component and penetration to ensure that SAT ~ CONTAINMENT INTEGRITY requirements are satisfied. UNSAT Standard: SRO Candidate determines Containment Integrity is NOT satisfied. Cue Comment Uses any or all of the following to determine Containment Integrity: FSAR Chapter 6 Section 6 : Manual and remote manual valves which do not receive an automatic actuation signal are administratively controlled to preserve containment integrity. -OR-Technical Specification: 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION NOTE: 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.* APPLICABILITY: MODES 1, 2, 3, and 4 ACTION: Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. SURVEILLANCE REQUIREMENTS 4.6.1.1 CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that all penetrations** not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their closed positions; NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 12 Form ES-C-1 Ordered to Lock Closed HV-3-1, Post Accident Containment Vent and STEP 5 Sample System Isol Valve (RR) within 1 hour. SAT ..j UNSAT 3-0NOP-053, Loss of Containment Integrity entered and action ordered to Lock Closed HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) within 1 hour. -OR-Standard: Ordered to Lock Closed HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) within 1 hour based on required Technical Specifications requirement. Cue Comment 3-0NOP-053, Loss of Containment Integrity 4.0 IMMEDIATE ACTIONS NOTE: 4.1 IF in Modes 1,2,3, or 4, THEN restore containment integrity within one hour. Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time ---- NUREG 1021 Rev 9 Appendix C Appendix C Page 8 of 12 Form ES-C-1 Ordered to Lock Closed HV-3-1, Post Accident Containment Vent and STEP 5 Sample System Isol Valve (RR) within 1 hour. SAT ..j UNSAT 3-0NOP-053, Loss of Containment Integrity entered and action ordered to Lock Closed HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) within 1 hour. -OR-Standard: Ordered to Lock Closed HV-3-1, Post Accident Containment Vent and Sample System Isol Valve (RR) within 1 hour based on required Technical Specifications requirement. Cue Comment 3-0NOP-053, Loss of Containment Integrity 4.0 IMMEDIATE ACTIONS NOTE: 4.1 IF in Modes 1,2,3, or 4, THEN restore containment integrity within one hour. Terminating The task is complete when the Examinee returns the cue sheet to Cue: the examiner. STOP Stop Time ---- NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 12 Form ES-C-1 I Verification of Completion Job Performance Measure No. NRC-25-ADMIN-JPM-A 1.2 ~~~~~~~~~~-------------------------------- Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ____________________________ _ NUREG 1021 Rev 9 Appendix C I Appendix C Page 9 of 12 Form ES-C-1 I Verification of Completion Job Performance Measure No. NRC-25-ADMIN-JPM-A 1.2 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: ________________ _ NUREG 1021 Rev 9 Appendix C

JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 3 is in Mode 1 at 100% Power 0-OSP-205, Verification of Administratively Controlled Valves, Locks and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification are in progress. HV-3-1, Post Accident Containment Vent and Sample System Isolation Valve (RR) has been found Locked Open. INITIA TlNG CUE: Evaluate Unit Conditions and and determine corrective actions. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C JPM BRIEFING SHEET The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS: Unit 3 is in Mode 1 at 100% Power 0-OSP-205, Verification of Administratively Controlled Valves, Locks and Switches, and 3-0SP-053.4, Containment Integrity Penetration Alignment Verification are in progress. HV-3-1, Post Accident Containment Vent and Sample System Isolation Valve (RR) has been found Locked Open. INITIA TlNG CUE: Evaluate Unit Conditions and and determine corrective actions. Acknowledge to the examiner when you are ready to begin. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. NUREG 1021 Rev 9 Appendix C

Appendix C Facility: Job Performance Measure Worksheet _T_u_r_k_ey'--P_o_in_t _______ Task No: Classify Plant Event and Job Performance Form ES-C-1 Task

Title:

Determine Notifications Measure No: NRC-25-ADMIN-JPM-A.4 KIA

Reference:

2.4.41 Knowledge of the emergency action level thresholds and classifications. 2.9/4.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Perform ~~~~---------------------------- Simulated Performance Yes Actual Performance

~~----

Classroom Yes Simulator -------- Plant --------- Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: 0700: 0705: 0710: 0723: Both units are at 100% power. A fire starts in the Cable Spreading Room. The Shift Manager orders Control Room Evacuation and proceeds to the TSC. The fire is quickly extinguished by the Fire Team. The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICA TlON FORM COMPLETION: Wind direction is from 168 0 Wind speed is 5 mph. MET Tower ~T = -1.0 MET Tower Sigma Theta = 7.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values. Task Standard:

1. The current level of classification is made.

2. The Florida Nuclear Plant Emergency Notification Form is completed with the current classification in accordance with standards set in 0-EPIP-201 01, "Duties of Emergency Coordinator. "

Required Materials:

1. 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR, Enclosure 1

2. 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR, Attachment 1 Appendix C Facility:

Job Performance Measure Worksheet _T~u_r_k_e,,-:-y _P:-o.,-in_t----=______ Task No: Classify Plant Event and Job Performance Form ES-C-1 Task

Title:

Determine Notifications Measure No: ~~~~~~~~~--- NRC-25-ADMIN-JPM-A.4 KIA

Reference:

2.4.41 Knowledge of the emergency action level thresholds and classifications. 2.9/4.6 Examinee: NRC Examiner: Facility Evaluator: Date: Method of testing: Perform --~--------------------------------------- Simulated Performance Yes Actual Performance Classroom Yes Simulator Plant Read to the examinee: I will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: 0700: 0705: 0710: 0723: Both units are at 100% power. A fire starts in the Cable Spreading Room. The Shift Manager orders Control Room Evacuation and proceeds to the TSC. The fire is quickly extinguished by the Fire Team. The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICA TlON FORM COMPLETION: Wind direction is from 168 0 Wind speed is 5 mph. MET Tower ~T = -1.0 MET Tower Sigma Theta = 7.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values. Task Standard:

1. The current level of classification is made.

2. The Florida Nuclear Plant Emergency Notification Form is completed with the current classification in accordance with standards set in 0-EPIP-201 01, "Duties of Emergency Coordinator. "

Required Materials:

1. 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR, Enclosure 1

2. 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR, Attachment 1

Appendix C Page 2 of 13 Form ES-C-1 General

References:

1. 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR Initiating Cue:

You are the Emergency Coordinator. It is now 0723. Identify the current emergency classification that applies. Following the classification, complete the Florida Nuclear Plant Emergency Notification Form. Time Critical Task: Yes Validation Time: 15 minutes for Classification 15 minutes for Notification Form Appendix C Page 2 of 13 Form ES-C-1 General

References:

1. 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR Initiating Cue:

You are the Emergency Coordinator. It is now 0723. Identify the current emergency classification that applies. Following the classification, complete the Florida Nuclear Plant Emergency Notification Form. Time Critical Task: Yes Validation Time: 15 minutes for Classification 15 minutes for Notification Form

I Appendix C Page 3 of 13 Form ES-C-1 I INSTRUCTIONS TO OPERA TOR READ TO OPERA TOR: WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET, PROCEDURE, AND NOTIFICA TION FORM FOR CLASSIFICA TlON TO OPERA TOR A T THIS TIME! INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: Both units are at 100% power. 0700: A fire starts in the Cable Spreading Room. 0705: The Shift Manager orders Control Room Evacuation and proceeds to the TSC. 0710: The fire is quickly extinguished by the Fire Team. 0723: The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM COMPLETION: Wind direction is from 168 0 Wind speed is 5 mph. MET Tower ~T = -1.0 MET Tower Sigma Theta = 9.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values INITIA TlNG CUE: You are the Emergency Coordinator. It is now 0720. Identify the emergency classification that applies. Following classification, complete the Florida Nuclear Plant Emergency Notification Form. NOTE: This is a Time Critical Task. TERMINA TION CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN. I Appendix C Page 3 of 13 Form ES-C-1 I INSTRUCTIONS TO OPERA TOR READ TO OPERA TOR: WHEN I TELL YOU TO BEGIN, YOU ARE TO PERFORM THE ACTIONS AS DIRECTED IN THE INITIATING CUES. I WILL DESCRIBE THE GENERAL CONDITIONS UNDER WHICH THIS TASK IS TO BE PERFORMED AND PROVIDE THE NECESSARY TOOLS WITH WHICH TO PERFORM THIS TASK. BEFORE STARTING, I WILL EXPLAIN THE INITIAL CONDITIONS, WHICH STEPS TO SIMULATE OR DISCUSS, AND PROVIDE INITIATING CUES. WHEN YOU COMPLETE THE TASK SUCCESSFULLY, THE OBJECTIVE FOR THIS JOB PERFORMANCE MEASURE WILL BE SATISFIED. HAND JPM BRIEFING SHEET, PROCEDURE, AND NOTIFICA TION FORM FOR CLASSIFICA TlON TO OPERA TOR A T THIS TIME! INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: Both units are at 100% power. 0700: A fire starts in the Cable Spreading Room. 0705: The Shift Manager orders Control Room Evacuation and proceeds to the TSC. 0710: The fire is quickly extinguished by the Fire Team. 0723: The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM COMPLETION: Wind direction is from 168 0 Wind speed is 5 mph. MET Tower ~T = -1.0 MET Tower Sigma Theta = 9.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values INITIA TlNG CUE: You are the Emergency Coordinator. It is now 0720. Identify the emergency classification that applies. Following classification, complete the Florida Nuclear Plant Emergency Notification Form. NOTE: This is a Time Critical Task. TERMINA TION CUE: WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. DO YOU HAVE ANY QUESTIONS? YOU MAY BEGIN.

Appendix C Page 4 of 13 Form ES-C-1 Denote critical steps with a check mark Start Time Obtain 0-EPIP-201 01. STEP 1 SAT UNSAT 0-EPIP-20101 obtained in a timely manner. Candidates may use STANDARD: authorized computers to access procedures CUE: Provide procedure when correctly identified, or have Cue candidate obtain procedure. Comment NOTE: Candidates may use authorized computers to access procedures. Appendix C Page 4 of 13 Form ES-C-1 Denote critical steps with a check mark Start Time Obtain 0-EPIP-201 01. STEP 1 SAT UNSAT 0-EPIP-20101 obtained in a timely manner. Candidates may use STANDARD: authorized computers to access procedures CUE: Provide procedure when correctly identified, or have Cue candidate obtain procedure. Comment NOTE: Candidates may use authorized computers to access procedures.

I Appendix C Page 5 of 13 Form ES-C-1 I Review 0-EPIP-201 01. STEP 2 SAT UNSAT

1.

Reviews 0-EPIP-201 01, Enclosure 1, for the event in progress. STANDARD:

2.

Reviews each classification in Enclosure 1 in sequence.

3.

Reviews Enclosure 1 in its entirety. Cue Comment NOTE: I Appendix C Page 5 of 13 Form ES-C-1 I Review 0-EPIP-201 01. STEP 2 SAT UNSAT

1.

Reviews 0-EPIP-201 01, Enclosure 1, for the event in progress. STANDARD:

2.

Reviews each classification in Enclosure 1 in sequence.

3.

Reviews Enclosure 1 in its entirety. Cue Comment NOTE:

Appendix C Page 6 of 13 Form ES-C-1

1.

Identify appropriate emergency classification.

STEP 3

SAT >j UNSAT Classifies event as a Site Area Emergency in accordance with 0-EPIP-201 01, Enclosure 1, Category 15C : Control Room has been evacuated AND Local control of shutdown systems has NOT been established from local stations within 15 minutes. STANDARD: The examinee classifies the event by interpreting the information given in the initial conditions within 15 minutes of starting the JPM. Cue Once candidate completes classification portion of the JPM, then direct candidate to fill out State of Florida Notification form.

Comment Annotate the stop time for the event classification.

NOTE: Annotate the stop time for the event classification here. Stop Time ---- Appendix C Page 6 of 13 Form ES-C-1

1.

Identify appropriate emergency classification.

STEP 3

SAT >j UNSAT Classifies event as a Site Area Emergency in accordance with 0-EPIP-201 01, Enclosure 1, Category 15C : Control Room has been evacuated AND Local control of shutdown systems has NOT been established from local stations within 15 minutes. STANDARD: The examinee classifies the event by interpreting the information given in the initial conditions within 15 minutes of starting the JPM. Cue Once candidate completes classification portion of the JPM, then direct candidate to fill out State of Florida Notification form.

Comment Annotate the stop time for the event classification.

NOTE: Annotate the stop time for the event classification here. Stop Time

I Appendix C Page 7 of 13 Form ES-C-1 I STEP 4 Obtain 0-EPIP-201 01, Attachment 1, "Florida Nuclear Plant SAT Emergency Notification Form." UNSAT Correctly identified/obtained 0-EPIP-20101, Attachment 1, "Florida Nuclear Plant Emergency Notification Form." STANDARD CUE: Provide Attachment 1 when correctly identified, or allow candidate to access authorized computer. Cue Record time that candidate accesses the State of Florida Notification Form Start time: Comment NOTE: I Appendix C Page 7 of 13 Form ES-C-1 I STEP 4 Obtain 0-EPIP-201 01, Attachment 1, "Florida Nuclear Plant SAT Emergency Notification Form." UNSAT Correctly identified/obtained 0-EPIP-20101, Attachment 1, "Florida Nuclear Plant Emergency Notification Form." STANDARD CUE: Provide Attachment 1 when correctly identified, or allow candidate to access authorized computer. Cue Record time that candidate accesses the State of Florida Notification Form Start time: Comment NOTE:

Appendix C Page 8 of 13 Form ES-C-1 STEP 5 Completes Attachment 1 lAW with standards set in 0-EPIP-201 01, SAT "Duties of Emergency Coordinator." -V UNSAT Appendix C Page 8 of 13 Form ES-C-1 STEP 5 Completes Attachment 1 lAW with standards set in 0-EPIP-201 01, SAT "Duties of Emergency Coordinator." -V UNSAT

I Appendix C Page 9 of 13 Form ES-C-1 I Checks STATE and/or MDC and/or Monroe County 1A. Checks "This is a Drill" 2A. Enters today's DATE 2B. Does not enter CONTACT TIME until contact made with State Warning Point 2C. Enters applicant's NAME

20. Enters Message Number 1 2E. Checks Reported from TSC (NOTE: Control Room evacuated.)

3.

Checks "D. TP UNIT 3" & "E. TP UNIT 4" *

4.

Checks SITE AREA EMERGENCY *

5.

Checks box "A. EMERGENCY DECLARATION"* and enters Date and Time of declaration *

6.

Checks "A. EAL Number" and enters 15.C OR checks "B. Description" and enter info related to fire in Control Room and Control Room Evacuation. *

7.

Checks "A. None" OR if 6A checked above may check "B." and enter info related to fire in Control Room and Control Room STANDARD Evacuation. SA. Enters 16S

SB. Enters Q, R, A, B
9A. Checks "A. None (Go to Item 11)"
1 O. Makes no entries since release not occurring.

11A. Checks "A. No recommended actions at this time."

11B. No entry 12A1B/C. Checks "YES" for each 120. Checks "Stable" 13A. Enters 5 mph 13B. Enters "0" based on 6T=-1.0 & 1.:8=9.0

14. Makes no entries since release not occurring.

15. Enters MESSAGE RECEIVED BY information Submits form for EC Approval.

NOTE: Standards marked with an

are critical to this Step.

Cue Comment I Appendix C Page 9 of 13 Form ES-C-1 I Checks STATE and/or MDC and/or Monroe County 1A. Checks "This is a Drill" 2A. Enters today's DATE 2B. Does not enter CONTACT TIME until contact made with State Warning Point 2C. Enters applicant's NAME

20. Enters Message Number 1 2E. Checks Reported from TSC (NOTE: Control Room evacuated.)

3.

Checks "D. TP UNIT 3" & "E. TP UNIT 4" *

4.

Checks SITE AREA EMERGENCY *

5.

Checks box "A. EMERGENCY DECLARATION"* and enters Date and Time of declaration *

6.

Checks "A. EAL Number" and enters 15.C OR checks "B. Description" and enter info related to fire in Control Room and Control Room Evacuation. *

7.

Checks "A. None" OR if 6A checked above may check "B." and enter info related to fire in Control Room and Control Room STANDARD Evacuation. SA. Enters 16S

SB. Enters Q, R, A, B
9A. Checks "A. None (Go to Item 11)"
1 O. Makes no entries since release not occurring.

11A. Checks "A. No recommended actions at this time."

11B. No entry 12A1B/C. Checks "YES" for each 120. Checks "Stable" 13A. Enters 5 mph 13B. Enters "0" based on 6T=-1.0 & 1.:8=9.0

14. Makes no entries since release not occurring.

15. Enters MESSAGE RECEIVED BY information Submits form for EC Approval.

NOTE: Standards marked with an

are critical to this Step.

Cue Comment

Appendix C Page 10 of 13 Form ES-C-1 NOTE: Standards marked with an

are critical to this Step.

Appendix C Page 10 of 13 Form ES-C-1 NOTE: Standards marked with an

are critical to this Step.

I Appendix C Page 11 of 13 Form ES-C-1 I STOP STEP SAT UNSAT Stop time: (15 minutes acceptance criteria, from classification completion) 0-EPIP-201 01: STANDARD: 5.1.6 Emergency notification to State and Local Counties is required within15 minutes of declaring an emergency. Comment NOTE: Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue: the examiner. Stop Time ---- I Appendix C Page 11 of 13 Form ES-C-1 I STOP STEP SAT UNSAT Stop time: (15 minutes acceptance criteria, from classification completion) 0-EPIP-201 01: STANDARD: 5.1.6 Emergency notification to State and Local Counties is required within15 minutes of declaring an emergency. Comment NOTE: Terminating The task is complete when the Examinee returns the cue sheet to STOP Cue: the examiner. Stop Time ----

Appendix C Page 12 of 13 Form ES-C-1 Verification of Completion Job Performance Measure No. NRC-25-ADMIN-JPM-A.4 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _________________ _ Appendix C Page 12 of 13 Form ES-C-1 Verification of Completion Job Performance Measure No. NRC-25-ADMIN-JPM-A.4 Examinee's Name: Examiner's Name: Date Performed: Facility Evaluator: Number of Attempts: Time to Complete: Question Documentation: Question:

Response

Result: Satisfactory/Unsatisfactory Examiner's signature and date: _________________ _

JPM BRIEFING SHEET INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: Both units are at 100% power. 0700: A fire starts in the Cable Spreading Room. 0705: The Shift Manager orders Control Room Evacuation and proceeds to the TSC. 0710: The fire is quickly extinguished by the Fire Team. 0723: The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICA TlON FORM COMPLETION: Wind direction is from 168°. Wind speed is 5 mph. MET Tower L'l T = -1.0 MET Tower Sigma Theta = 9.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values INITIA TlNG CUE: You are the Emergency Coordinator. It is now 0723. Identify the current emergency classification that applies. Following the classification, complete the Florida Nuclear Plant Emergency Notification Form. NOTE: This is a Time Critical Task. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK. JPM BRIEFING SHEET INITIAL CONDITIONS FOR CLASSIFICA TlON: 0659: Both units are at 100% power. 0700: A fire starts in the Cable Spreading Room. 0705: The Shift Manager orders Control Room Evacuation and proceeds to the TSC. 0710: The fire is quickly extinguished by the Fire Team. 0723: The Unit ROs have not yet established control of shutdown systems on either unit. ADDITIONAL INITIAL CONDITIONS FOR FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICA TlON FORM COMPLETION: Wind direction is from 168°. Wind speed is 5 mph. MET Tower L'l T = -1.0 MET Tower Sigma Theta = 9.0 TSC ERDADS data implies normal post shutdown core parameters being maintained. Process and Area Radiation monitors are reading normal post shutdown values INITIA TlNG CUE: You are the Emergency Coordinator. It is now 0723. Identify the current emergency classification that applies. Following the classification, complete the Florida Nuclear Plant Emergency Notification Form. NOTE: This is a Time Critical Task. HAND THIS PAPER BACK TO YOUR EVALUATOR WHEN YOU FEEL THAT YOU HAVE SATISFACTORILY COMPLETED THE ASSIGNED TASK.

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM Online Verification: )8f STATE B MIAMI-DADE COUNTY )g MONROE COUNTY B. D This Is An Actual Event

B. Contact Time: x><XX C.

Reported by: Name ___ X...;....X~)(_<.l.-_____ _ A. Il:I This Is A Drill A. DateXXIXX,XXX,,< D. Message Number: ___ -L.' ____ _ E. Reported From: D Control Room £Sl TSC D EOF F. D Initial/New Classification OR D Update Notification

3.

SITE A. D Crystal River UNIT 3 B. D St. Lucie UNIT 1

c. D St. Lucie UNIT 2 D.)&'

Turkey Point UNIT 3 E.)8f Turkey Point UNIT 4

4. EMERGENCY CLASSIFICATION:

A. D Notification Of Unusual Event B. D Alert C. % Site Area Emergency D. D General Emergency

5. A. ~ EMERGENCY DECLARATION: B. D EMERGENCY TERMINATION Date: XX: I X>< I XX(P(Time: x..xxx.
6. REASON FOR EMERGENCY DECLARATION:** A.~ EAL Number: /5,C OR B..!4fDescription h/Ct?' /~

(l/1.;?iF 5//~6I4j)/N& £ OO/ff tJ;ffl C 4 t/ /'/f't7L @ OM 6::V~Ct/Il-rION

7.

ADDITIONAL INFORMATION OR UPDATE: A.){None OR B. D Description _____________ _

8. WEATHER DATA:

A. Wind direction from / 68 degrees. B. Downwind Sectors Affected 6;}J<;Il,IJ

9. RELEASE STATUS:

A..p? None (Go to Item 11) B. D In Progress C. D Has occurred, but Stopp;d

10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)

A. D Under evaluation B. D Release within Normal Operating Limits (Tech Specs) C. D Non-Significant (Fraction of PAG Range)D. D PAG Range (Protective Actions required) E. D Liquid release (no actions required) -1 1. UTILITY RECOMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC: A.~ No recommended actions at this time. B. D The utility recommends the following protective actions: EVACUATE ZONES:NOT APPLICABLE OR SHELTER ZONES:NOT APPLICABLE Miles 0-2 2-5 5 -10 Evacuate Sectors Shelter Sectors No Action Sectors AND consider issuance of potassium iodide (KI) If form is completed in the Control Room, go to item 15. If completed in the TSC or EOF, continue with item 12.

12. PLANT CONDITIONS:

A. Reactor Shutdown? )QYES D NO B. Core Adequately Cooled? ~ YES D NO C. Containment Intact? )3 YES D NO D. Core Condition: J21 Stable D Degrading

13. WEATHER DATA:

A. Wind Speed 6 mph B. Stability Class 7)

14. ADDITIONAL RELEASE INFORMATION:

A. D Not applicable (Go to Item 15) Distance Projected Thyroid Dose (CDE) for 1 Hour Projected Total Dose (TEDE) for 1 Hour 1 Mile (Site Boundary) B. ________ mrem C., _______ mrem 2 Miles D. _______ mrem E. _______,mrem 5 Miles F. ________ mrem G. _______,mrem 10 Miles H., ________,mrem I. ________ mrem ~C or RM Approval Signature _____ >(.....:....:;..x..:...X..,.,....X,...:x DateXKJ.X.XI.~XXX Time /xxX

15. MESSAGE RECEIVED BY: Name
X_->( XX X Date'><xJX.'{Ix'>X< TimeXXXX.

IF EMERGENCY CLASS ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICATION FORM WILL BE TRANSMITTED WITHIN 15 MINUTES, THEN YOU MAY GO TO ECIRM APPROVAL SIGNATURE LINE. ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (Pis) F-439/1 :2 Rev 8 (11/10/08) FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM Online Verification: )8f STATE J1 MIAMI-DADE COUNTY )g' MONROE COUNTY A. (lJ This Is A Drill B. 0 This Is An Actual Event A. DateXXIXX/~X. *B. Contact Time: Xl<A C. Reported by: Name __ -'-XX-"-'-X-"'>('----c ____ _ I E. Reported From: 0 Control Room. TSC 0 EOF D. Message Number: F. 0 Initial/New Classification OR o Update Notification 3, SITE A. 0 Crystal River UNIT 3 O. M Turkey Point UNIT 3

8. 0 St. Lucie UNIT 1 C. 0 St. Lucie UNIT 2 E. J8f Turkey Point UNIT 4

~4. EMERGENCY CLASSIFICATION: B. 0 Alert A. 0 Notification Of Unusual Event C. % Site Area Emergency D. 0 General Emergency '5. A. ~ EMERGENCY DECLARATION: B. 0 EMERGENCY TERMINATION Date: xx: I >9< J ~ime : x.cxx '6. REASON FOR EMERGENCY DECLARATION:-- A.;g.( EAL Number: /5. C OR B..cr0escription /.::we&"-- /# (f/l.:gtr S""~ClJNN6- £:OOP' w'I-rf( Cav'rk""L,f?>"ht ~"'CWI-rtON

7.

ADDITIONAL INFORMATION OR UPDATE: A.){None OR 8.0 Description _____________ _

S. WEATHER DATA; A. Wind direction from /68 degrees.

8. Downwind Sectors Affected qR/ l, tJ '9. RELEASE STATUS: A. pq-None (Go to Item 11) B. 0 In Progress C. 0 Has occurred, but stopped

10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)

A. 0 Under evaluation B. 0 Release within Nonnal Operating Limits (Tech Specs) C. 0 Non-Significant (Fraction of PAG Range)D. 0 PAG Range (Protective Actions required) E. 0 liquid release (no actions required)

1 1. UTILITY RECQMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC:

A.~ No recommended actions at this time. B. D The utility recommends the following protective actions: EVACUATE ZONES:NOT APPLICABLE OR SHELTER ZOHES:NOT APPLICABLE Miles 0-' 5 - 10 Evacuate Sectors Shetter Sectors AND consider iS5uance of potassium Iodide (KI) No Action Sectors If form ;s completed in the Control Room, go to item 15. If completed in the TSC or EOF, continue with item 12.

12. PLANT CONDITIONS:

A. Reactor Shutdown? )QYES 0 NO B. Core Adequately Cooled? ~ YES 0 NO C. Containment Intact? )3 YES 0 NO D. Core Condition: )2f Stable 0 Degrading

13. WEATHER DATA:

A. Wind Speed.£ mph B. Stability Class 7)

14. ADDITIONAL RELEASE INFORMATION:

A. 0 Not applicable (Go to Item 15) Distance Projected Thyroid Dose ICDE) for 1 Hour Projected Total Dose (TEDE) for 1 Hour 1 Mile (Site Boundary) B. _______ , mrem C. mrem mrem 2 Miles D. _______, E. mrem mrem 5 Miles F. _______, G. mrem mrem 10 Miles H. _____ -,-,---, I. mrem Cor RM Approval Signature ____ -=--'-"'S's----____________, X:xXXX Da,.XX,xx,WXT;m. XXXx. .x..><)( x..x. Da'.!<X'XX' XXXX: T;m.XXXX

15. MESSAGE RECEIVED BY: Name __ -"-='-== ____________,

IF EMERGENCY Cl.ASS ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICATION FORM WILL BE TRANSMITIED WITHIN 15 MINUTES. THEN YOU MAY GO TO ECIRM APPROVAL SIGNATURE LINE ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (Pis) F-43911:2 Rev 8 (11110108)

FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM ~ECTOR

REFERENCE:

METEOROLOGICAL WORKSHEET The chart below can be used to detennine sectors affected by a radiological release, through comparison with wind direction from the meteorological recorders in the Control Room. If the wind direction is directly on the edge of two sectors (e.g., 11°, 33°, 56°, etc.), an additional sector should be added to the protective action recommendations. For example, if the wind direction is from 78°, then the affected sectors for PARs should be L, M, Nand P. SECTOR INFORMATION: WIND SECTOR WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED [A] N 348-11 S HJK [B] NNE 11-33 SSW JKL [C] NE 33-56 SW KLM [D] ENE 56-78 WSW LMN [E] E 78-10 1 W MNP [F] ESE 10 1-123 WNW NPQ [G] SE 123-146 NW PQR [H] SSE 146-168 NNW QRA [1] S 168-191 N RAB [K] SSW 191-213 NNE ABC [L] SW 213-236 NE BCD [M] WSW 236-258 ENE CDE [N] W 258-281 E DEF [P] WNW 281-303 ESE EFG [Q] NW 303-326 SE FGH [R] NNW 326-348 SSE GHJ STABILITY CLASSIFICATION

REFERENCE:

Either ERDADS or the below chart can be used to detennine atmospheric stability classification for notification to the State of Florida. Primary method is from ~T via the South Dade (60 meter) tower. Backup method is from Sigma Theta via the Ten Meter Tower. If neither meteorological tower is available, Stability Classification shall be detennined using data from National Weather Service (See 0-EPIP-20126, Off-site Dose Calculations). CLASSIFICATION OF ATMOSPHERIC STABILITY: Primary Backup Stability Pasquill Delta T Sigma Theta Classification Categories (OF) Range (Degrees} Extremely unstable A LlT:s:-1.7 ST ~ 22.5 Moderately unstable B -1.7 <LlT:S: -1.5 22.5 > ST ~ 17.5 Slightly unstable C -1.5 <LlT:S:-l.4 17.5> ST ~ 12.5 Neutral D -1.4 <LlT:S: -0.5 12.5 > ST ~ 7.5 Slightly stable E -0.5 <LlT:s:+l.4 7.5> ST ~ 3.8 Moderately stable F +1.4 <LlT:s:+3.6 3.8> ST ~ 2.1 Extremely stable G +3.6 <LlT 2.1> ST Meteorological infonnation needed to fill out the Florida Nuclear Plant Emergency Notification Fonn is available from the Dose Calculation Worksheet (0-EPIP-20126). The Worksheet shall be filled out by Chemistry and given to the Emergency Coordinator. F-439/2:2 Rev 8 (11/10/08) FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM ~ECTOR

REFERENCE:

METEOROLOGICAL WORKSHEET The chart below can be used to detennine sectors affected by a radiological release, through comparison with wind direction from the meteorological recorders in the Control Room. If the wind direction is directly on the edge of two sectors (e.g., 11°, 33°, 56°, etc.), an additional sector should be added to the protective action recommendations. For example, if the wind direction is from 78°, then the affected sectors for PARs should be L, M, Nand P. SECTOR INFORMATION: WIND SECTOR WIND FROM DEGREES WIND TOWARD SECTORS AFFECTED [A] N 348-11 S HJK [B] NNE 11-33 SSW JKL [C] NE 33-56 SW KLM [D] ENE 56-78 WSW LMN [E] E 78-10 1 W MNP [F] ESE 10 1-123 WNW NPQ [G] SE 123-146 NW PQR [H] SSE 146-168 NNW QRA [1] S 168-191 N RAB [K] SSW 191-213 NNE ABC [L] SW 213-236 NE BCD [M] WSW 236-258 ENE CDE [N] W 258-281 E DEF [P] WNW 281-303 ESE EFG [Q] NW 303-326 SE FGH [R] NNW 326-348 SSE GHJ STABILITY CLASSIFICATION

REFERENCE:

Either ERDADS or the below chart can be used to detennine atmospheric stability classification for notification to the State of Florida. Primary method is from ~T via the South Dade (60 meter) tower. Backup method is from Sigma Theta via the Ten Meter Tower. If neither meteorological tower is available, Stability Classification shall be detennined using data from National Weather Service (See 0-EPIP-20126, Off-site Dose Calculations). CLASSIFICATION OF ATMOSPHERIC STABILITY: Primary Backup Stability Pasquill Delta T Sigma Theta Classification Categories (OF) Range (Degrees} Extremely unstable A LlT:s:-1.7 ST ~ 22.5 Moderately unstable B -1.7 <LlT:S: -1.5 22.5 > ST ~ 17.5 Slightly unstable C -1.5 <LlT:S:-l.4 17.5> ST ~ 12.5 Neutral D -1.4 <LlT:S: -0.5 12.5 > ST ~ 7.5 Slightly stable E -0.5 <LlT:s:+l.4 7.5> ST ~ 3.8 Moderately stable F +1.4 <LlT:s:+3.6 3.8> ST ~ 2.1 Extremely stable G +3.6 <LlT 2.1> ST Meteorological infonnation needed to fill out the Florida Nuclear Plant Emergency Notification Fonn is available from the Dose Calculation Worksheet (0-EPIP-20126). The Worksheet shall be filled out by Chemistry and given to the Emergency Coordinator. F-439/2:2 Rev 8 (11/10/08)}}

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