ML100670467
| 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) | |
Text
{{#Wiki_filter:FACILITY NAME: Turkey Point Section 6 REPORT NUMBER: 2009-302 DRAFT ADMINISTRATIVE JPMS CONTENTS: err;raft ADMIN JPMs Location of Electronic Files: Submitted By By: j:L;3?~1
~3?~1 Verified By By: ~~ JI.£Jk 1t/J 111 (J . ~
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- '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: 100
- 2. Rod Height: D-228 Task Standard:
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
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 Identifies and obtains materials and procedures necessary to perform 1 STEP task. - - SAT
- - UNSAT Operator obtains copy of O-OP-046, Attachment 5 and U4 Cycle 24 Standard: 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 Operator enters appropriate values for Rod Worth from U4 Cycle 24 STEP 2 Plant Curve Book, Section 2, Figure 5 and performs computation . - - SAT
,.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 Operator enters appropriate values for Power Defect from U4 Cycle 24
- STEP 3
..j Plant Curve Book, Section 2, Figure 6A and performs computation .
From U4 Cycle 24 Plant Curve Book, Section 2, Figure 6A for 10,000
- - SAT
- - UNSAT 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 Operator calculates the desired change.
- STEP 4
~
Determines value based on f1 rod worth = +170 pcm and f1 power
- - SAT
- - UNSAT 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 Operator determines present boron worth from U4 Cycle 24 Plant STEP 5 Curve Book, Section 2, Figure 7A. - - SAT
.J
- - UNSAT Operator correctly determines present boron worth from U4 Cycle 24 Standard: Plant Curve Book, Section 2, Figure 7A 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 Operator calculates desired boron worth and concentration.
- - - SAT STEP 6
..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 Operator determines if boration or dilution is required. STEP 7 - - SAT
- ..J Standard:
Operator determines that dilution is required.
- - UNSAT 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 Operator determines number of gallons required. STEP 8 - - SAT
- ..j Determines value based on boron concentration in the range of _
ppm to_ppm.
- - UNSAT 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 STOP Cue: the examiner. 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
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:
Page: 137 Approval Date: 0-OP-046 CVCS - Boron Concentration Control 6/27/08 ATTACHMENTS (Page 1 of3) REACTIVITY WORKSHEET NOTE I Boric Acid Thumb Rules are as follows: 10pcm = 1 ppm 10 gallons = 1 ppm
=
1 gallon 1 pcm I
'----- - - - I PART 1: Power Change Only I) Rod Worth (A)
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_)+/7 0 pem
- 2)
Present Rod Worth Performed by Power Defect (B)
- Desired Rod Worth = (+1-)
Verified by (A) 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
[ _ _ pem] - [
/7'# ~ 7.
pem] = (+1-)
-737.:f 7-1 pem Present Pwr Defect - Desired Pwr Defect = (+1-) (8)
Performed by Verified by
- 3) Calculate the Desired Change in pcrn (C)
/7/ -13?:tZ7
[(+I-l..:LLfI pem ] + [(+1-) _ _ pem J = (+1-)
-..)s?:tpem2-7 (A) (8) (C)
Performed by Verified by
- W2003:TNM/ln/ln/ln
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 7A (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
[(-) pem] - [(+1-) pem I (+1-) pem Present boron worth (C) = Desired boron worth from Seet 2, Fig 7A Determ ine desired C B from Section 2, Figure 7A = 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
- 5) IF desired Boron Concentration is less than the current Boron Concentration, THEN calculate the dilution required as follows:
J 50,790 x In t [ Current CB in ppm Desired CB in ppm 770 ppm]
== Gallons of Primary Water
#;0-5'571 50,790 x In L 7oS-~ I?,ppm == Gallons Gallons of Primary Water Performed By Verified By
- 6) L d Boron Concentration is higher than the current Boron Concentration, THEN ~
the boration 'red as follows: ;::::> Gal of Boric Acid
._--",RCS ppm]
_ _ Gallons
- 003:TNM/ln/ln/ln ppm] -[t-__
Performed By
-[L-_ _ Gal of Boric Acid
Appendix C Job Performance Measure ES-C-1 Form ES-C-l Worksheet Facility: _T_
"uu_r_k_ eeLy-'-
" 'r.ck"'y"--P_o_in_t __
P-'o"'in.ct_ __ __ __ __ __ _ Task No: Task
Title:
Perform A OPTR QPTR Calculation JPM No: NRC-25-ADMIN-JPM-A.2 2.2.12 2:2.12 Knowledge of of surveillance procedures. procedures. KIA KJA
Reference:
Reference : 3.7 / 4.l 4.1 Examinee: _ __ _ _ _ _ _ _ _ _ _ Examiner:
- - - - - - -- -- - - NRC Evaluator: _ _ _ _ _ _ _ _ _ _ _ Date:
Facility Evaluator: Date: Method of testing : _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ __ _ _ Simulated Performance _ _ _ _ _ _ _ _ _ _ Actual Performance _ _ _ _ _ _ _ _ _ _ __ Classroom Simulator _ _ _ _ _ _ __ Plant -_ __ _ __ _ Read to the examinee: I wilt will explain the initial conditions, conditions, which steps to simulate or discuss, and provide initiating cuescues.. When you complete the task successfully, the objective for this job performance measure wilt will be satisfied. 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: Top : 179.8 N-41 Bottom: Bottom: 153.0 N-42 Top: Top: 142.0 N-42 Bottom: 142.2 142 .2 N-43 Top: Top: 151 .3 Bottom: N-43 Bottom: 127.1 Top : N-44 Top: 183.1 183.1 N-44 Bottom: 160.6 Task Standard: Standard: RO Candidate: Calculates QPTR value using 3-0SP-059.10, 3-0SP-059.1 0, DETERMINATION OF QUADRANT POWER TILT RATIO . SRO Candidate: Candidate :
- 1. Calculates QPTR value using 3-0SP-059.1 3-0SP-059.10,0, 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. manner.
Required Materials: Materials:
- 1. Calculator 2.
- 2. 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TILT RATIO 3.
- 3. Unit 3 Cycle 22 Plant Curve Book
- 4. Technical Specifications Section 3.2.4 4.
General References
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
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 Page 4 of 12 Form ES-C-1 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 5 of 12 ES-C-1 Form ES-C-l I Denote critical steps with a check mark( J) /) Start Time Obtain copy of procedure. Obtain procedure. STEP STE P 1 - - SAT
- - UNSAT Obtains copy of 3-0SP-059.1 3-0SP-059.10.O.
Standard: Standa rd:
- 1. Provide copy/access 3-0SP-059.10, DETERMINATION OF QUADRANT POWER TilT 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 to obtain the procedure.
procedure . NUREG 1021 Rev 9 Appendix C
Appendix C Page 6 of 12 Form ES-C-1 Record date, time and initials on page 1 of Attachment 1.
- 2 - - SAT STEP
- - 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:
NOTE Attachments 1, 2, and 3 may be performed without interim rounding. 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
..j each in service power range nuclear instrumentation detector. (Refer to plant curve book for the 100 percent power current values.)
- 1. Obtains values from plant curve book and records them in
- - SAT UNSAT 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 Appe Appendix ndix C Page 9 of 12 Form ES I
-C-l I ES-C-1 7.1.4 Complete calculations of Attachment 1.
- - - SAT STEP 5
..j 1. Determination normalized detector currents.
currents .
" 2. Determination average normalized power.
- 2. power. - - UNSAT
- 3. Determine QPTR.
QPTR. 44.. Determine NIS QPTR. 5.
- 5. Determine jfif N NIS QPTR IS Q =
or 1.02 (2.0%). PTR is << or::; (2.0%).
- 1. Calculates normalized detector currents.
N-41 Top Top:: = 179.8/189.8 = 0.9473 N-42 Top: Top : 142.0/140.6 = = 1.00996 N-43 Top: 151 .3/156.4 = = 0.9674 N-44 Top Top:: 180.3 =1.0155 183.1/180.3 183.1/ Upper Section Normalized Current Total ==3.9402 N-41 Bottom = Bottom:: 153.0/162.3 = 0.9427 142.2/142.4 =0.9986 0 N-42 Bottom: Bottom: 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 = 3.9402/4 0.98511
.9402/4 = 0.985 Average Lower Section Normalized Power = =3.884914 3.8849/4 =00.9712
.9712 3.
- 3. QPTR.
Calculates OPTR. Upper Section Tilt Ratio =1.0155/0.9851 1.0155/0.9851 =1.0309 Lower Section Tilt Ratio =1.0063/0.9712 =1.0361 4.. 4 Calculates NIS QPTR. NIS QPTR =Highest Section Tilt Ratio =1.0361 1.036 1 55.. Correctly evaluates NIS QPTR. Tilt ratio =1.0362 range: 1.036 to 1.037) (Acceptable range: NUREG 1021 Rev 9 Appendix C
Appendix C Page 10 of 12 Form ES-C-1 Tell RO candidate that JPM is Terminated after Attachment 1 has Cue completed . been completed. Comment Precautions and Limitations 4.2.3 With QPTR greater than 1.02 (2.0 percent), percent). QPTR determination NOTE: is required at least once per hour (Tech Spec 3/4.2.4). Terminating STOP The task is complete for RO candidates when Attachment 1 has 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
- - - SAT STEP 6 yields suspect QPTR results, THEN perform Subsection 7.2 .
7.2.5 IF QPTR is greater than 1.02 (2.0 percent), THEN refer to Subsection 7.4 for additional actions while continuing with this section
- - UNSAT of the procedure.
Standard: Cue Inform applicant that another operator will perform any remaining procedural requirements. Comment Precautions and Limitations 4.2.3 With QPTR greater than 1.02 (2.0 percent), QPTR determination NOTE: 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
..j FOR SROs: Determines that TS 3.2.4 applies .
SAT
- - UNSAT
- 1. Calculate the QUADRANT POWER TILT 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 STOP The task is complete when the Examinee returns the cue sheet to the Cue: examiner. Stop Time - - - - NUREG 1021 Rev 9 Appendix C
I Appendix C Page 13 of 12 Form ES-C-1 II Verification of Completion - Job Performance Measure No. Examinee's Exa minee 's Name: No. NRC-25-ADMIN-JPM-A.2 NRC-2S-ADMIN-JPM-A.2
~~~~~~~~~=---------------------------------
Examiner's Name: Examiner's Name: Performed : Date Peliormed: Facility Evaluator: Number of Attempts: Attempts : Time to Complete: Complete : Question Documentation: Question: Question:
Response
Result: Satisfactory/Unsatisfactory
- Examiner's signature and date:
date: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ NUREG 1021 Rev 9 Appendix C
JPM BRIEFING SHEET cues. The examiner will explain the initial conditions, which steps to simulate or discuss, and provide initiating cues. When you complete the tas taskk successfully successfully,t the objective for this job performance measure will be satisfied. satisfied . INITIAL CONDITIONS: power. The plant is operating at 100% power. Detector currents for all in service power range nuclear instrumentation channels are as follows: follows: N-41 Top: Top : 179.8 N-41 Bottom: 153.0 Top: N-42 Top: 142.0 N-42 Bottom: Bottom: 142.2 N-43 Top: Top: 151 .3 N-43 Bottom: 127.1 127.1 N-44 Top: 183.1 N-44 Bottom: 160.6 Cue : Initiating Cue: RO:: RO Calculate Ca currents . lculate NIS QPTR using excore detector currents. SRO:
- 3. CaCalculate lculate NIS QPTR using excore detector currents.
currents .
- 4. Determine all necessary Technical Specification actions that must be com completed pleted within the next eight (8) hours.
TERMINA TlON CUE: WHEN YOU FEEL THAT YOU HAVE SATI SATISFACTORILY SFACTORI LY COMPLETED THE ASS ASSIGNED IGNED TASK, HAND YOUR JPM BRIEFING SHEET BACK TO ME. ME. DO YOU HAVE ANY QUESTI QUESTIONS? ONS? YOU MAY BEGIN. Acknowledge to the exa examiner miner 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: 11 Approval Date:
- 3-0SP-059.10 Determination of Quadrant Power Tilt Ratio ATTACHMENT 1 (Page 1 of 2) 8/30/05 DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS Time _-,-W~.:);::..*l.::..v::..\
\, .
.---<J,I.
,IV
_....;..~ Initials: - 1
.---<J. .~
IV:::..-__
- 1. W.)lV
--'---=-~-- --" -=---
- 2. Determination normalized detector currents:
Upper Section Normalized Detector Currents N41 TOQ Current Il(t.~ micro amQs
= = (), Cf473 100 Percent Top Current I3 'c1*;S micro amps 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 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
- Page:
Page. Procedure No.: No .: Procedure Pwccdure TTitle: itl e: 12 Approval Date: Dak:
- 3-0SP-059.IO 3-0SP-059.10 Determination of Quadrant Power Tilt Ratio ATTACHMENT 1I (page 2 of2) 8/30/05 DETERMINATION OF NIS QPTR USING EXCORE DETECTOR CURRENTS
- 3. Determination average normalized power:
Average Upper Section Normalized Power Upper Section Normalized Current TTotal otal '_~' , Ofo _",< . 1'</0 ';" .:~ CJ, C)I c:; 'i':J I
.~, CJ5J51 Upper detectors used (3 or 4)
= T 4
'-f Average Lower Section Normalized Power Lower Section Normalized 8 ~3 o
o ,.9 (i 7!;.l 7 (:;< Current Total 3.8
..:;, , '3 ; 4 C'1
'-1(1 Lower detectors used (3 or 4)
= ?
=
4<I 4.
- 4. Determine QPTR:
QPTR: Upper Section Tilt Ratio Largest La rgest Upper Section
- Normalized Detector Current I . [) 1 1.0 1~ ::,5' 5
1.0:309
- 1. 0 .')0 9 Average Upper Section
= =
Normalized Power C(),C;.9'6';-/S 5"J Lower Section T Tilt ilt Ratio Largest La rgest Lower Section ,03{( Ii
/ .03{,c Normalized Detector Current CUrrent CD (c II.. CC LC :::'
~
Average Lower Section
= =
Normalized Power O ,Q7/d, C),Lf7/d 5.
- 5. NIS QPTR ~ hi ghest Section QPTR =
= highest ~ I . c..-;' (,c' I 6.
- 6. NtS QPTR is less than or equal NIS eq ual 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 fo r additional additiona l guidance.
Perfurmedby Perform ed by:: ________________ Date: - - - - - Time: T ime: --------- Reviewed Reviewed by:by: _________________________.D ate: ________ Date: I Approved by:by: _ _ _ _~=-:--;:-::-:------=-:--:--::::---_:____:_-----.DDate: ate : _ _ _ _ __ (Shift Manager or Unit Supervisor) I
- W97:1JBSlldfmr
\rV97 :/JBSJldImr fmr Imr
Appendix C Job Performance Measure Form Fo ES-C-1 rm ES-C -1 Worksheet Works heet Facility: Turkey Point No: Task No: Perform 3-EOP-F-0 3-EOP-F-O,, Evaluate Critical Safety Function Status Task
Title:
Trees JPM No: NRC-25-ADMIN-JPM-A.4 2.4.22 Knowledge of of the bases for prioritizing safety functions funciions during abnormal/emergency abnonnallcmergency KIA Reference : _o-'pp"'-'o" _o"' e_ra_t_io_n_s _ __ r"a:t:.io"'n"'s'-_ ____ __ __ ___ Examinee: NRC Examiner: Facility Evaluator: Date : Date: testing:: _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ __ _ __ Method of testing Simulated Performance _ _ _ _ _ _ _ _ _ _ Actual Performance _ _ _ _ _ _ _ _ _ __ Classroom _ _ _ _ __ __ Simulator - __ _ _ _ _ __ Plant _ _ _ _ _ __ Read to th Read the examinee: e exami nee: I will explain the initial conditions conditions,, which steps to simulate or discuss, and provide initiating cues cues.. When you complete the task successfully, successfully, the objective for this job performance measure will be satisfied. Initial Conditions: 3-EOP-E-O, Reactor Trip or Safety Injection,
- 3-EOP-E-0, Injecti on, has directed the performance of 3-EOP-F-O, Critical Safety Function Status Trees. Trees.
Current Unit Conditions: Conditions:
- TE-3-6700 = 272 TE-3-6700' 0
- TE-3-6701 = 272 TE-3-6701' 0
- TE-3-6702 = 272 TE-3-6702' 00
- N-3-41= 0%
- N-3-42= 0%
- N-3-43=
N-3-43' 0%
- N-3-44= 0%O OCI/
- N-3-35= 1x 10E-11 N-3-35'1x 10E -11
- N-3-36= 1 N-3-36' 1xx 10E -11
- SUR= -0.3 DPM and lowering N-3-35 SUR'
- SUR= -0 N-3-36 SUR' -0.3 .3 DPM and lowering
- N-3-31 = 4000 cps N-3-31'
- N-3-32= 4000 cps
- Gamma-Metrics NI-3-6649A= 1000cps and 10E-5 % PWR and lowering
- Gamma-Metrics NI-3-66498= NI 66498= 1000cps and 10E-5 % PWR and lowering
- 3 CETS -=
All Unit 3 = 715 0
- Unit 3 CET Subcooling = 35 35°° Superheat NUREG 1021 Rev 9 Appendix C
Appendix C Page 2 of 12 Form ES-C-1
=0 gpm
- Auxiliary Feedwater Flow Train 1
- 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
Appendix C Page 4 of 12 Form ES-C-1 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 5 of 12 Form ES-C-1 I Denote critical steps with a check mark(./) Start Time STEP 1 1 Determine Containment Conditions
- a. Check containment temperature - - SAT
..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 2 Monitor Critical Safety Functions STEP 2 Using Rules Of Usage Provided In - - SAT 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
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:
* = 0 Unit 3 CET Subcooling 35 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 Monitor Heat Sink using Enclosure 3 STEP 5 - - 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 Cue: STOP 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
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 Pressurizer Level = 0%
RVLMS Indicates Voids
=5.92 x E-2 R
- 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 Job Performance Measure Form ES-C-1 Worksheet
- Facility:
Facility: _T",u
,:-r"k",e~yc:Point Turkey P:,o"in,,;,t,,===-,;-;=_ _ TaskTask No:
No: Determine Allowable Stay Time & Determine Task
Title:
Title : Radiological Reguirements Requirements JPM No: NRC-25-ADMIN-JPM-A.3 NRC-25-ADMtN-JPM-A.3 2.3 .7 Ability to comply with 2.3.7 radiation radiati on work permit requirements during normal or abnormal conditions. 3.5/3.6 KIA
Reference:
Reference : Examinee: _ _ _ _ _ _ _ _ _ _ _ NRC Examiner: Examiner: Facility Evaluator: Date: Method of testing : Simulated Performance _X X
" --_ _ _ _ _ _ _ _ _ Actual Performance
~------------------
Classroom _ _ _--"X X'---_ __ _ _ _ _ _ _ __ Simulator - _ _ _ _ _ __ Plant - Read to the examinee: I will explain the initial conditions, conditions, which steps to simulate or discuss, discuss, and provide initiating cues. 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 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.
SN PO .
- You are discussing RWP requirements and ALARA concerns prior to commencing the task. task, Task Standard:
- Four of five questions from the Initiating Cue are answered correctly. correctly .
Required Materials:
- Radiation Work Permit 09-001 09-001,, Routine Operations and Surveillances Tasks 1-4
- PTN Unit 4 4,, Residual Heat Removal "A" Pump Room Monthly Survey Map
- PTN Unit 4, Residual Heat Removal "B" "8" Pump Room Monthly Survey Map
- PTN Unit 4 4,, Residual Heat Removal Heat Exchangers Room Monthly Survey Map
- PTN Unit 4, 4 , 10 foot Elevation (Access to RHR Pits) Room Monthly Survey Map
- Radiation Radia lion Controlled Area Valve Locator Zones 102,103,104, and 105 General References
References:
- 1. 0-HPS-025.1, "General Posting Requirements for Radiological Hazards" Hazards ~
NUREG 1021 Rev 9 Appendix C
Appendix C Page 2 of 15 Form ES-C-1 2.
- 2. O-ADM-600 0-ADM-600,, "Radiation Protection Manual" Manual"
- 3. O-ADM-604 0-ADM-604,, "Radiological Protection Guidelines and Practices" Practices"
- 4. 0-HPS-020, "Radiation Surveys" 5.
- 5. O-HPS-021 0-HPS-021,, ~"Surface Surface Contamination Surveys~
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
Appendix C Page 4 of 15 Form ES-C-1 SIMULATOR SETUP IC # 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 Obtain a copy of Radiation Work Permit 09-001, Routine Operations STEP 1 and Surveillances and PTN Unit 4 Room Monthly RHR Survey Maps - - SAT
- - 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 The examinee needs to differentiate between the Survey Maps and Valve EXAMINER 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 Use Radiation Controlled Area Valve Locator to determine location of STEP 2 - - 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 What is the maximum stay time based on the radiological conditions in STEP 3 the room without exceeding any dose limits? - - SAT
.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 25 mrem is the maximum dose allowed by RWP 09-0001 NOTE: 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
I Appendix C Page 9 of 15 Form ES-C-1 I What is the minimum required dosimetry required for entry into the
- 5 - - SAT STEP 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 What is the surface contamination in the vicinity of HCV-4-758? STEP 6 - - SAT
- .J Standard: The examinee determines < mda by interpreting the PTN Unit 4, 10 foot
- - UNSAT 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 Where is the lowest dose location in the area where the operator STEP 7 should stand in the event that he/she is required to wait there? - - SAT
.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 What is the maximum stay time based on the highest general area radiation in the room?
- 1.
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 What is the surface contamination in the vicinity of HCV-4-758?
- 4.
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
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
T urkey Turk Point Nuclear y Point Nu clea r Plant RADIATION WORK PERM RADIATION PERMIT T Nude .. O l.i~i. ft COpy Rw r Tit le: ROlllin' Operations and 'ur t illances RWP umber: 09-000 I Rev. 03
--------------~~mmmnmnmr! ~mnmnn_*~
111 3
- 1 -': -'
Ceneral Instruction.: A TI. and IcclrOnic Dosiml!tct :Irc i I)osunctcr reqtlir~
- tre requi red to cnler enter the RCA, RCA.
A PAM /I. Tclemetric IJosimetcr r/\M or l'ch::mctric LJosimc r is requirequired red for working in IIa high hilOh noise Nell ru-t'!I. Rc\ ic:w RI:\ iew elmen! ~\If"'cy current sur
- dam pril.M' 10 d"ta priur to entering the woO: work area.
BI'elI Notir NOI thc work iry the wor' .'area I rca RI' Tcchnician rechnician pricwpriCtr 10 to 1,entering overhead areas.
-'1ltcnngovcrhe:ul uc&s.
C ycrllse i~ KI' CovcnlGe It!' is required 10to Icmove mated I, tOOls remOVe ma:c:nlll, ols Of cquipmellt rrom or cijuipmcllt rom 3.a Conllolmimlted Contaminated An:1I. Ncn. Page I
Turkey Point Nuclear Nucl ea r Plant
~ RADI TION WORK PERMIT RADIATION N.etHtDm..!
Nuclcer Division ... COpy TII sk TA Numbt r : II
~ k Number: RWP N umher; Number:
09 -000 I Rc~ 09-0001 Rov.. 03 Tas~~crip lI ~ k Dtl d llion: ion : Radialion Proteclion Routi ROlltine Task T Statu s: A ask StIlIUS: live Active ~A~L7A~n~ At.AnA '~\~ID ~ II): Radia tion Pruh:clion
- __~______________ ~I~~._ . ,,,
la~~T~I. lc ne Activ
' n~e~A~I~
Acti\'itics
='r~rn
- ities
~_~(lt~ II1~ 1 :~
~I~~~
- ,\!of Il~:: ~118:00 8~:0~O~__~__________________~ ____ ____
Do ~e: 900 J.:~ t i nlilltr. Dose: Estimate 9O<J mrtm mr m I ....J1i..M E.s1:,:;im.-a.;,;t
£.sl im.lle H:.;,;:
o_
*c;.,*lIours: u ,;,;
rs:;;.:..:32~IO.::O.::.O 32000 _ _ _ _ _ _.J......_ _- y_ _ _ _ _ _ _ _ _ _- I I. o~krllll Locked h:h* lbci.: High-Had: NO No I Hie,b-Rad : Yes IIigh- lb d: High-Co ntomination: 1IIIth-Conl aniinalion: Yes Yes II llot-Parlicl,,: lI ul- Pll nicle': Yes
. Alarm Sttlin Settin g~ s .' '., -, ---
Ilighh J:iallllnn Ilig (;1110111:1 D on DC!sc I-!igh ellmmn High GlImmll Ra Rale Il' 25 mrC'm mrcm 350
.)50 mremJhr mrem/hr I ..
Requirements Requireme nts -- - - , III Requirement Rctlul r tmcn t "roups Groups Requirement Rrll UirtlllC'. nl Descripfions Dest rlpll ons Authori zcd Access AUlhorilCJ A~css ~tuln.'n ,'~a
- NcutrC'n Ar~a aIICC~~ CCSli is authorized autlmrizcJ Airbomj; R!ldiOllctlvll),
- Airbome R:lciio3Clivil'l Are.l r.C_3 access *_
15;_a~u_ a_r.,..c....,c_ss__i:" th_()_r_ aulhl'lr; ~d i ..?:-
- e_d.,....".-,-:-::- _ _ _ _ _ _ _ _ _ _ _ _ _-i c
I Ondin&s Briefings ..Required Rcq\llr~d I -,\ 1-" shiflly shlfllv Ihgh
- Iligh Radiation' RadIatIon Area AI't'3 bmflng brit:Iing -is - 1~ requital required ror liRA tlCCr:5$ access ContUlliinati II Control
('0111.1/11;":111011 COntrol - To wor!: work in iIa High J-ligh COnl.lmin8tilln Cont minalion Area An.'D one Orr more morc orlhcorlhe rollowing mll)' mlly be:bt: required: AJ A) DcconL."lmin;nc arc' I>cconL1min:lIc equipl11 nlto atf:aJc'll,lijmll:nt 10 < 100.000 100,000 dprn/ dpmllOOcm2 (Decontamination shall be pcrfunnl:d I Ocm2 (l>e<:on!(lIninotion perfonned l\.<; din:c!.Cd by as din:ckd b ' HP), HI ). I)) A) t):;e U~ IIIEPA IEPA ",:n!itation"cntilmion!J vacuum. vacuum, C) KCI;p KCI.'P urenlcquipnl~nl arca/equ ipment wet durin~
\\'4't during rep:.irs, D) Co\cr repairs, CO\ er or eonillin COTll3illlU'c3lcqu arc:v'cquipmerll ipmcnl T1osjllwlr~'
Do. im 'lr~' -* PAMrAM or reknU'lrit: D orTeI'metric simeter i~ required DO:iimC1CT rf'.quitoo for vorl-ing in Ii high nuise ror working n ise BrCJ and/or a !Iigh are.! :uuJ/or Hi gh i{odl:ltion Radiation Arca Are:t J'roH:cliYec ClOlhml! l'roK'Cli Clothmg .* Shoc CIJIICrs and gloves Shoe cover glollcs arc are the mi minimum nimum protective clothing required requireJ for ror entry cntry in intol0 a mill:lteu !\rc.l. C0:1111nl:n:l!eJ Con Area. (tA la coal IIS required lobb COlli rl'quired in 11ghl ighl nreas) areas)
-." ,\ full ~et prOlective d.)thi ScI of protc:clive ch)thing ng ill' required for kneeling is rl'qllired knccling or crnw!ing cm\ ling in aII C(\TtI:lIninalrd Conllllninaled Arca Area r~lrn protcClivc
*- 1:.'lrn prolt..-c:ivc clothln!!clothing is required rCCJuircd 10 to \\ ork \\ Ith llighly Conlnminlllcd
\)rk with Contamin led n13terjl!ls. materiels. The minimum dres. dr~s requiremenl rcquilCnll:nl Lis IIa (li ru l It ScI sel ofofprotccli prolC'(alve vc c/tllhing, clothing. c-:lrn (' Ira gloves gI0\'c5 and/t andlnrr sh !lhf'Ce covers.
CIIVCf'!. fae..: shic:ld
*"\ (aco: shiel d ma) mll) t-c rO:~luired be required
*- In IIiI HOI 11m PanP:lnllclc cic ,\rca.
"rea. the: the minimum dress rcquir~'mcnl i~
dres rcquirl'menl or prole *the clllt.hing. is IItl full <;1:1. OrrrnI4't:li\c clmh;ng. dl~rll'Qhle di pt/5.1ble (IUttr uter coveralls, eovcraUs, c:lrtl cx,,:, gloves. Hh.lVL'S, eXira shoe h c covers co crs and ~nd a fneee shield n fa
*- 'ater
\\later rcsi~an reS;!;Ianll ouler Oliler protccth prolcclh l'c cl(,thing clothing is requi red to work in 9a ~t'l IS rcquired weI Contaminatiun Contamination ."Arca rell I:-
IkspirJlury ,
, Prnu.::Clion .. R~ ~ rlratnr reqUIrements Rcspirmnr rcquircm 'nls Lo I.h: t ~rmm~d on tu be dc\ermitll!cl . case b) ca~e On a 1;:'Isc.: ca~c 1);iSls.. . A/I. TEDE basis. ,
1 F.DI, "LARA
,\1 ARA evahWlilltl c:v81uuLinn I', required pril1r I.* TC'111irl,j prior HI respirator us/!
10 respmuor us\.: ~ ___________________________________Additio ,~
\~ d~d~ it~ io~n na~a~ ll ~
T'usl
~
Ds ~l~ r~D ~c'~ rul' tiioonJi
~n~ I S~_ _ .
G l'nl'r:i IIIl General ~ lr ur tion ~: Ins(ruclloos: Worker tn Wurker I n ~strucli<lns: t ru r li " n ~: ItP IU' I n 5~ lr Iruc udi .i o J1 n ~~:: 1\InA Ilricfing i< IRA Briefing i~ rim rcquirl!d (I)r nm ro.:(julrt.J for H I<P'I'~
.PT s "hen :I 5\11"\ ey meIer
\\h.*11 :I$ur.,,)' me cr is used li,t IS u5Cd I"lr entry inlo inll) II lligh Iligh Uno Pall Aren.
An:a. ('(lnIply l' 1111 Iy \1 \\ ilh nil IIlut Partil:le C()I\lrol~ lUI Partll:lc onLmls as spccllicd speeillcli in i 1 O-Iff'. 0- 111:;.021. -027. I. (1tFII<'~lIcs CRFII. sueS WilrehollSc: WArehouse: 1< RAM
,,:-.1 ;>IiCkdges i"1Ck.!gc5 with wilh clost'dose 1".!1OrolCS >2.0 >2. mtemlhr mrcm/hr shall be: be Irnn'&rreJ transfclT d h) P) Ihe the RP Tcch rcch II" Ihe ltC".RCA. N\!lir~I lllif~
RPSS RP . : if an 10 iran), l\X'Sc se !>urf:tce a~ti"ll~ i.
)urf:lct activil. is found.
roend. All II person personnel nel shall~hall wcn wcarr fLO's rl.O's when halldling handling R RAM M \\\ llh dusc ralc ilh dose rntl!>2.0 mn:mlhr 2.0 mrcmlhr lind \\ hen entering cr.tc:ring 3n ;ltCCl .lrCd "I' :'U.5 rnn:m/hr,
,.1'::-0.5 mn:m/h r. HI' RP shllll shall POSI poSI all areas rm:;c; ",hcrt' where .\ TLO LJ)'~ 's arc required.
Instrumcnt ~ shall Instruml'nI. _hall he be ~ur.*c)'cd surveyed (or f, r loose cOlltaminllllon con18mi nntion prior pri rIo dis<I':sembly. 10 diSclc;scmbly. I:"~ E cl' prnl,, pWlc*{'l.i<mtion is i req cquired uired rorfor IX'rsonnci personnel pcriorming p rform ing inS1rurnCnt InstnllnCnl checks chee 's WIth \ iLh $Ourt:c source II \\ heel. Trunsporring of hed. Transporting of.S(>UfCC Ilrcc \\ h~d shalt
\ *hee. shall pcr ()rml!cI hy RP be f"..'frOrmcd personnel onl)
R.P pt'rs..Jnnd nnJ} lind ~hatl hall Iremainem:!;n 1n cOlltrcll ofr RP in control Personnel al KP Pcrsnnnd II rim> when nm ill ,dllimes not in~;do.: ins; e Ihe dc~jgnl1led the t.h:signateu 10 'ked oren. locked IIrcn. 1116120092:54 P Page 2
Turkey Tu rkey Point Nuclear Plant J=PL RADIATION WORK PERMIT Nucloar Divi.ion
'he"'" Dtmloa COpy rn ~ k 8 u m btr: 2 nwp Number ;
09-0001 Rev. Rev, 03
'f ,uk I)Uc:r! ll l lon: Operations Dcpanm cnt Rout ine Act ivities A1.A UAl t>: Sl a v m ar 1 '.\ .\ :1 8:00 E ~ lilll :l l t n o~(' : 11100 n1 tl' OI ,- [ 5Ii", :II(' lI ours: 20000 l.orktlllligh- I{:IlI ; No 1 .lI lgh- Rll d: Yes ! lIie. h-Conl:tmlna tion: Yes j u ot-Pa rt icle: Yes
- Alarnl s:tuillg, " , ~ , t ~I- -, ,'.. __.,-, ... . ~
I lI il! h Gam m:!; n Oll' I IIlgh Gll mnll~ R:IoIt
! 25 mrem 350 mrem /hr Requlremtnl$
- I'I.!cutrnn Arca ac(*o!..C;~ i~ no' lIulhorilCd Rt' IIU l rt"lI~ nl D('. !lf.riplio ll s
- A~I~'mt Radioactivity Arca :tcce,s [,limited III UfI:'.!S posted aUI! 10 Noble G..~',-______
I 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 adioaClive I J)osimetry J) simclry systems
- 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
[E"posur" J.~h ( ' u\(mgc Conlml
- Notif), AI .AltA iftempornry shielding necd~ t{l be rr.Med or modified
- l ise the Vah 0: l.()CIIIO~ 0001: III JOCl\C the ,*alve.. Usc the book 11(11 your dose
- In 1101 r.mic1c f\ rells. RP Go\\~nse i5 rcquilUl. Wllrkl." shall rccelve., HOi P.lrtide survey :lI 1
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"IOCi lie IluI Particle co'l\rol~ lL't speci fied 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
. h e C(lVeTS Ctl\crs i!ndand ~IIIVCS glnves 1ruem: Ihe minim minimum cJCIlhing, required for pmtc::crive d('thing um proTcctive cntry intu ror cnlry inl a Conlaminated Area . ("
lllll:lmin:ttell ArC<!. (A lahlab coal is i required in light Rrcll.~) lighl llrcas
*- b.lfi\
J-..xlra proh.:t;tiv ptlltct.."lil"c'cloth ing ;:; cluthllll,: is rC'lllilCJ n:quir' II.! to \\\\ork rk with lighly Conlamln~tcd wi!o I !ish!y ontaminaled materials.malerials. Toc ! he minimum dress req mil)imum ui remenl is rcquirement is:)3 (ull sci o0 r pmlt'~,til'e rull sel pr ICCliVI! clothing. clolhing, c. c..litm gloves andlor
' Ira glovcs and/or <;h,ol"c; Ir.Je covers COVeT*.
fu <: lihi..-1J A f:u:c shidd may nm. be rc,\uin:d rc uirl'd
- In tII HUI
-In P~r ic/e Are,.
H I Pllniclt Arc;!, the minimum miuimum dress rcquir menl i:; ilre:iS rcquirement i a fuli full SCI orf pmt;,-clil dnlhi n~. prtllt:cli \'(;C clothing. t!i s po~3blc uu!Cr di<;pos-abk c \cr:lll~. ouu:r c(J\cral c. trn gl vc.~ . c"tlt l~. C~lr:llllullt:.~ 0;;. lNI shsh(\C.* COl CO\cr.; and a ct:\ :)nJ u face racc shiehl shield
\ Iller rc
*- WilIer Istunt I)ull:r re.I~llInt ')Utel' pr Ilel:li ec 'almhing pr\!\cl.'1h I!tlhing. ilo i~ required rc(.!uirecl 10 to work in 1\ 111::1 Contamination "rca t:l (oOlIl",;nllllon Arca
*- The I hI! mrn Pmtecli\*cc .:loll-ing min imum Pmt<,cti, d Iring r..-qUlrc..!
r qllircd ((If for opening resin loading syste m and.,.. lo:uling systf:m lind or
\ cntl"gll~pcni"g CnLlng/llp<!ning :my y~ l em i~
radioacti \IeI,: 'I~$lem
. ny radiollcth is a 1Inb co I and gl
,IIt ('031 ves gloves
*- When oreroiling "'jives .tC'n.It't o[JCl'Jl ing 1I;1lws r!'s eonl3mil1alC'd c nlaminated roundaric!i, Operalors 'Vul1 I>ouni.b ric..... Opcr:uors ~311 rcml'\";
rcmo\c glu\ gl (l \' Co\
~ urd
~rd di 'card them di:;cilu! hem 10'(1 into Ihe In sh recq:ude the Inc.h IC'culcu in the receptacle 11'I."'nlcd he arcn pr 'c;:d dircclI:
- Ire:'! and proceed din.'ClI) tnI !la fri ~ klng.
ri$king I Mallon
!>tnlilm :moJ pcrrllml a ftl~1.
and perform fr isk A rull ~l or full '>l'\ ur Ilftltl'cli proll'clive dlllhing ii~ req VI,: dollhing rc uircu kneclin~ uited for kneeli ng l'r l~r I -rawling. in (.T3whng in:la Cnnlamin~ll'd (nlamin.ncd Arc:u Area A cld il i(l n )l IID ~ lrucii o ll s Addiliunftllnsh'uclioos (;tnl'rll lln\ lnll'linn,; - \ Wo\ 't'I rrker kc-!" InsI n ~ llru r u cti cl ioonn ~:.:
._--- ---------------~------------
RP rut JIl S ' ~~-* 1\I ~ l ru(.'\i l)II~ :
- - - --------------- - -- - ------------- -- - - -1 1116/20092;5'1 PM Page 3
Turkeyurkey Point N uclear Plant 3 FPL. L'> RADIATION RADT TION WORK PERMIT Nueloar Mud.., Division O",;~jO ft COpy Tnsk Tad. N Number: UnlbC'r: 3 RWI' RWt> Number: Numbrr: 09-000 09*000 I Rev, Rev, 03 03 r.r I-Tasklu k Descri D(,ScrJl!l 'l2lion: CI lon! Chcmlstr
' y D~p'artrncnl lc nllstr Dcpurtlllcm R oullnc Rouline ' Activities AC U\< , ,' IUl'S T~~k T. Status: .'\clivc
~ k Stalus: ACTive
~L~RA ALAR,\ 10: ID: I S' IIIt~ TTlI m3!tAj\ la11 rm (' ()JJI:M~t):
11 . 1\ 1 : 18:00 I!:OO Estim a te F.~ l illl .. Dose : 40 l t J)ose: mrem
,10 I1l1'tlll I .Es:sth"u timate lr lI ours: 17000 ouu.: 11000 - --
Loc ked lI Lorktd High- K:III : No igh. Rod: I I Uigb-lHeh. I{nd lUd:: Yes I ii igh,COll bminli llun: Yes ! Uo!- Hil:h-CofltamiDullun: I lI ol- Plu1ic!c: Par1iclr: No., Ala Allirmrm 5(;1111;. Setlio'g-,s ' -:,
~
.... , . , .,0: :, ..
1 II Jlif:,h IHgh G:un GO nlDla nlli Dost' Il O~t I High IIIgh C,m G:l mma m ;1 Rate Rliit I
;I 20 mr mrcm m Il 200 mr mrcm/ m/hr hr r Ke.Qulrc.nlentJ Re-,!u lremellt s
. - " . . 1 .. ,.: ..... .
Rcguiremcnl R('lillirr m l'ni G roups GruU[I) -L _ Rc!]uirllmCnl 1)t:5crilllions RrCluiremtnl Descril!tions I",,"on,," ,,,"" I\ uth(,ril..:d c c~s
* 'ron Ncutrl)O .\,,,
;rhome IhldiclIlt:uvil)
- Airt'olTIl" Area cees is no<
adioaclI'i)' Area nOI hn6,,", ilulhori;r.cd rea a"'~'ces~ ces<; iIs limiled limited to 'rea pos 10 ~retl.s ~Itd ed duc (a obi C;1I~ 10 Noble a
*- High C(lnl:1rr.irUllion Arca High Cronlnminalion nccc.u is limited AtCI! f1ecess li mited 10 II) Sample Sinks I I3rielin Drrdings. Re( ReqUireduired *- ,A sbifilv Hi h Rlldi,Jlion Area brielin , - is ree uircd fur HRA access n...,simctr:;
Dosimelry - PAM 1<'/\ \., or ()f Telcmclri Telemetric Dosimelcr Dos; melC'T is required reqoi red fc., im wnrkworking ing in;, in J high hiSh noi nlliS\:~ arc nndlQr aII Jligh arcl! (IIId!Ot High I l *rt,*.~'CIi\c Clothing ---I Radin Rlldl~l ion
- A lab i()1l A/1::1 Ill b co Arell L shoe covers, COIlt. 1,;,) \ ers, :lOd lovet's lire
- lnd glo\ II e the minimum nll nimum pro'.~tivc clothing rcquirw pm'.cclivc clolhin rcquiteJ fur ror cnl!)'
tnl!)' m inlu inl(t IIAConi
-* Waler W:ilcrto' Ct'lnl.lIminnlcd Conlllminated in ilJ Conbmi nlC minimum
*- Thc min llied ArC'a.
r ist3ni natcd Area nlini rnum PWlI; rmtl:ct,\ Area. /\ 1\ full sci II c d.\lh;l\~ sct of f~I'Ir."cth*e "tc1lhing i t:ll1\ outer prntl'clivc clmhil 9 rctl:J
\If l)rote(:live l)rotc~~t1'.'(" clothing
..J IIhing is required tt' requircu ircu lor r)f mJi-ing, tnJkinc h:md lINk in n \\*cl hand cnttits rot clCllhing iis required for kneeling orr era\\
to work "CI Conluminllliu/1 entries inLO
'ontaminaliun I\r\'\1 into a Contaminated Area crawling rca ling An::t 1 is "i1 lab ':1131 and gJuvc
'oat :lIid jlJOVC\~
(;*e n c rll lln . ln.l S: lio n ~ : - dd ifio na J llllstrl1cl A!!diUollltl ",, iuns
" :..:;.o.;=:.;.;:
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 en clint aminated (Jreas I/TCa.~ ,wilh( n:.sl$1ancc "fRr. ullhe l1'>srSlanl,;c
,*ilhtKlllhc ... fRr. urSler In ~ lructi nns :
NCllify RI' priCol ttt Willing VC r', or U<il> Dc.:.J)' Tank" NII!if)' I{P prior Itl ~:!mprinK mJi(I;lClh e S~S ICtr\S *
*\n...r 'illmplil1!\ ntdi03Cl ivc ~~ ~tem~ till.'\C ~bmpl... 'link with dcuI, WOller II,} rc:duce conlaminatl" n It.:vds.
t-=~:---------- I~P' L IH Inm;Irtlclions:
~lrueli(m .~:
Prinr to Priflr :-ampling lO]'J VeT: I l><lmp!ing restrict IIC<.)Cs..~ VeT "c$lriCI the ,\ux CCl:!>!i tto lhl.' Aux lIldg Bldg 4' 4 clc\'. 0 deY. nnd nntl H()I Hot Chem Chern Lab lAb 10 p~c:lude prcclud exposure e\:posurc whefe where Noble oble gOl'Cl> g'l.'CS lire ' m,wn 10 1'he
- rtc kllt'wn pr $CI1I and P" 1,: prc~nl poYj(llhc~c (h~.;c arClls
.Ircu~ in acconbncc ccordan c wi with th Slali lalion **n pro cdurcs.
ploccdur(:s. t I )(m~~Q~~ Ilpun r.w2p~cli."'_ of .-L~*~:.!.~1~~1!, UJ '"fl :::.rmr:!!.n~ tk:' de- Jlf,,1
,>;llhcsc III'C<l~ aprrl'
- hc..'>C ".-CI$" ,rprnlJlIiuld)riulcly:..;.., _ _ _ _ _ __
TUI-key Turke Point Nuclear Plant FPL RAD TION WORK P RADJAT10N PERMIT RMIT Nuclur OiviJion COpy Tuk Number: 4 RWI ' N um b,",,: I Jl ieh Gamma nO~( I IIi!!h C':lmlllll Ratt -- I 5 Il1 rcm I 8il mrcm/ hr Requirements - ltellu irtmC'nt r.r uupi 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 Oui lding ::cceSi is liN lIulhori7C,j I lItr; l ridirl~~ R"q:Jilcd- -
'lings I{CI.j.-;Trcd .1\ shllil) 111:;11 Ibtlia\i,," Alt3 briefing IS rC(lui rcd filr liRA ~~-
r (I!I,:lInin'.iir;:n ((oJ1lrol ('tlnt8min:l.li"n ,.nlm!
- Ta \\01 \. in a I-l ip. 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 dllflVI 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.:llai 1>> em tr ur cll1l1ui n :m:all...:!ulpml,!'m r.'i. I * '11'11i) Ri' pritlr h) Slar!!'!" "ork wilh I IIBht)" C:{}ntlJ"':"o"~'~"~-'c':":c"~'"'-'::;;""<:-:=:-:::-;;::-::;;;:::;:---, rProtective
~)-
f)usimC" 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:& I)rotectivc: Clmhl~ --I-_="\:'::'<hO,::"::;,c.t.C';;h::~:_c":"c"c"c";_C.:::'d<::'C'"C
- 1\ lab conl. . hl~ clwcrs. and glo"e~ ,:"=,=.,:,.",hC,:::mC;:""'m:::,,:mCp:n:::,,=,,::;T,,,C,:::,'-'oC are the: minimum pl1ltC1:tivc clothing ,;:h","Cg:::'"C_'C'"C;'C"':;O"ro required for C,:,:,:',,~_:--'
cr.lry int<J into u 0 C"Contntnminated . rcu../\ full set vI' minated Arec. tlf protecti"e proteclive clothingcit thing i~ J\ quircd r. is ri"qllircd lOrr 1.!Il"t:iing lnecling 'Ir ur LrJ.wlmS crawling in n Conuunin:ltcd ("mmminlllcd Area rea
-£.,tra
':'1111 pratt:;::!;\
prOle th c cillthing clothi ng is rt(luircrl tn required lU work with \ ilh I!iShl) Col1ttlrnin:tletll11:!u~riaJ$ lfighl} Conlamina lcti materials 1111.: 'nil: minImum tirol, minimum drc.~ requin:lncnl rlll.luirl*mcnt is :, full ~Ct is:1 sCt ufof I'lnJII'~"hc pmlCCli\'c dolhin!!. clflthin!!, eXIra gloves Bnd!or c WI glo\'cs und/or sh~oC sh ,e tIJ\ ers.. co\ "rs t' f~cc shield
.-\ face ma~ I-c
~hidd 1113\ be require,l requi red In II lIIiNt Pnrtic.;h:
- In:a Particle A".-<l.mc min imu m l.Ilt$S
,\rcu. lhc ll1ir.irnum rcquin.:ml:l1t i:>
tires,; fC<luireml.!'lIl fu ll set i:;,n lull sct 01 protc.:ti.,c dNhmg. of proil-..1,v(' cl thing. disp ~l bk OIl1t' db~\:,hk CIl' ernll r CI" { IU l'r C lis. ~'xtril
~, ,' gl vcs, Xlr:\ glove ('X ra!ob I; cn\
... (".:Irn!>hl)(' overs and ,'Ia I:'
crs lind tUI:C hicld
...: shield rt' I',mntl'ut(!r rpr. . 1h""I\'*
Wa h' r !'1'\a~f;lnllllcr I -* WilhT )((:,"1\'1' dl>:hUl~ clot hin!! j" is rcquin*.t rel/uin:tllo """(lrk Itl "" ** rk Inin IIII weI wei ('ulIllllll C.>>II:umn::l1ionin:lIion A:('oArea C~ncr;11 C: IIl ~ tr ll("lion": t'nt"ntllnslrllJ;'lioll'; --- ----_._-- -- ddilionllJ Tn)lruC Additional lustrulions lions
\ orker Instr uctlrlllS:
t----------- 1!1~'rrJ,~"",!,,;:;,",,ti'L""'",,": - - -- nl'lnstrllclinns:
------------------------- --- -----------~
(/1 611009 111 6/ ... 00 2:54 Pt...!I
- !: - P~
REV. 5/14/07 FLORIDA POWER & LIGHT - PTN HP*44:30A
- LOCATION:
DATE: TIME: TECH. : l-~~-O'l 132.Q 13;(0
~f)I£G)
UNIT 4 RESIDUAL HEAT REMOVAL "A" Pump Room (8) (e) (D) (E) A/RBORNE I,REA (A) AIRBORNE RESP!RATORY PROTECTION CONTAMINATED AREA H:GHLYOONTAMINATEDARCA H:GHLYCONTAMINATEDARCA EXCLUSION AREA (l) (.\1) (N) (R) LOCKED HIGH RAO RAD AREA RADIOACTIVE MATERIAL NOTIFY HO PRIOR TO ENTRY "AD/AriON "ADIATION AREA (S) SURVEY METER REQUIRED D 6 o0 6.
/LOG# -O~
CA -o~ IDOSE RATES IN MREMIHR UNLESS OTHERWISE NOTED "GENERAL AREA DOSE RATE "CONTACT DOSE RATE
=SMEAR LOCATION
=NEUTRON DOSE RATE
"" 8ETA DOSE RATE (F) HOT PARTICLE AREA (T) H.P, H.P. COVEPAGE REQUIRED ~G- "CONTAMINATED BOUNDARY PID# : ZQS (H) HIGH RADIATION AREA () N I ..... - ...... - = RAO RAD BOUNDARY
. "" II()
IK) Y.~EPOUT KEEP OUT ( \'., ). "._~'.' f~1. 11:
. .remarks*
~< ~~
........:-... ,1...J.........?--.J
.........:-... .J...J.........?--.J ~ * .- <,< REfE:R""nJ Lt.:.',
REfE:R"to :\~L." ;:.\y",!
"', :'.~L."
Lt.;, .*5, :r'~::'~""(1;'
;;'\},:>!:i "::;' "e'(1;'
.( l ;s.
1 U;in"orly"'" [:;u;in"Orly"" I
-.!I1'Irl.Il,J, _.
ADDITIONAL INFORMATION RWP#: / -l SMEARS dpml100cm (COUNT AT LEAST ONE SMEAR ::50,000 ::.50,000 DPM OPM fOR ALPHA) SMEAR NO.: Instrument RO-dO RD-:.dO IL~
~
In;l~ D;l~ 225
-';"J5
\q3
\q-o lq5 lQS HP/#
HPI# 4 2=1= a+/- 1<'roDA 33 6 207-20"7-
,<mOA12 9
11~ 13{roDA 18 14 N J E\ 16 19 NI A 17~ 23 21 22~ 24 NJA 26 27 28 29 N1A N. A NIA . BETN~AMMA: AL HA: Rtf)* 2.5 RtrI* 2S 1024 :c:2 4--=t- --=t- <.rnot:\ 5 <.rnot:\ 10 ~(,()DA 15 NI A 20 N 25 30 N, A N. A. NJA i3 MDA::: () 1;i9 /1 \3pm REVIEWED BY:
- a. MDA= N/A. dpm PRINT: ---
~-.
SIGN: - ,-- DATE: t~1~~ = SURVEY POINTS
REV. 11 /30/Q6 11130106 ZONE 102 UNIT*4 UNIT -4 "A""An RHR PUMP ROOM F,el Feet Off Floo, Valve
~
Location Valve Floor Location Feet Off Floor 7., 754A .0 .) 1 4-755A 7.5 18 4-754A(V.O.) 4*
"11 2
J3 MOV-4-861A 4-1461 4-14" 6
.J2 "
19 20 4*1(}.{)39 4*10-039 4-753A 4-75JA "2 11 2 4-756A
-'-4 4-769C 5 21 4*756A 3
~
5 4-938A 5 22 <I-16BA 4*768A 4.5 6 7 4-939A 4-8990 5 3.5 3.' 23 24 40-1848 4*769A " 11 3 8 4-1462 3 25 40-1847 11 89 ~766C 4-766C 1 28 26 40-1 846 40-1846 11 0.5 10
'.Q. 4-766E 1 27 4-766A 4*766A
~O) 11 4-762A 6.5 28 4* 756C 4*756C 3.5 12 4-752A(V.O.) 8.5 8.' 29 4-10-040 4*10-040 11 13 14
~4*12*008 MOV-4-862B 1.5 5
JO 30 Jt 31 4-12-007 4*112-009 4* 2'()09 , 1 1 15 16 4-942R 3 J2 32 3J 33 A-12..()10 4*12-010 4*767A (H.W .) (H.W.) , 1.5 1 17 4*70-117 7.5 >I 34 1 2 3 4 5 6 7 8 9 10 11 11 12 13 14 15 x x x x x xx x x xx I 17 18 19 20 21 21 22 23 24 25 26 27 28 29 30 31 32 33 (V.D .) (V.O.) =Location of the valve NOT the hand wheel
= (HW.) = Location of the hand wheel Not the valve (HW,)
- REV. 5/14/07 LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL irS" Pump Room FLORIDA POWER & LIGHT - PTN kOG# 0'1-HP-44:30B O~Y-j O~ y-~)
~",'.;" '::;If".~~,~,
IDOSE
,rOSE RATES IN MREMlHR UNLESS OTHERWISE NOTED
/ c; ,
- " :"?~ rr: , :,: ,-.-
,,: / ,i c; '"~'"
. ~,,',,:. \~"!ft"'t.~ ...... v",,:: '~'"
.<~, .,.",-,,, (;;i.. , " : _,""",,'.'~
~'-~~."'.: __ " '":"
(I , LOCl'ED HIGH RAD AREA I.OCl'ED _ '" GENERALARf'CA DOSE RATE
, * (8) RE-:~HM TORY PROTECT!ON RE:,HM RAOIOACnVC:: MAl'EKiAL
\,\1; RAOIOAcnVC:: "'! "",~,' '::t'.
'::t-. I " jR' ,:-38:~*.;'7~~*;:;:;o.,J::s:;o.::t;;:"0*\,,'~~
/ b .~
/6 5() =SMEAR LOCATION TIME: 5?) tCI CONTAMINATED AREA (N) NOTIFY HP PRIOR TO ENTRY 0 (D) HIGHLY CONT AMINl, AM IN.<, TED AREA (H) RADIATION AREA ARE.. £::" '" NEumON DOSE RATE TECH. : I) ;JVc#--; (E) EXCLUSION AREA IE) (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:
;i)lc:(MJj (.(16; SIGNATURE: REFER TO LOCAL AREA POSTINGS FOR AOJITIONAL INFORMATION G Q 1...'\"(:(, r 1....\..(:( -k r ( L,y L'; -
RWP #: // / ;& SMEARS dpml100cm' (COUNT AT LEAST ONE SMEAR Z. 50,000 DPM 22* RWP#: OPM FOR ALPHA) 1i SMEAR NO.: Instrument HPI # 1..(m/lA-1.4m/lA- 6A)Jr 11 /35 16/-"!)u?A- 21 26 ~-~ r--~
/-1020
/"" 020 /2-2-5
/ 2- 2-5 2.l..fov--t:_
2.l..fov--t:. 7 4, 12 2-0 .5 17~'1- BET::;AMMA: BET"'AMMA: XL6 Xldf 23~* 27 / / tJ 'it~ 18~ ILd ( 3c:'..I~t?d:. 3c:'./~t?d:. 8 3/S- 1'3 6,.'/hM
..I,,/hr:U!::. 2a;U 281-/
.i1mz..-)'
!? (Y)2--S- JcJ- cj c/ 7 4 " a,. /2/r 9,.(hvi,;y 14":::"/1"14.4- 19 14":::"/1'l4.4- tv 24 /.r 2.7 29 /j?r
.?Y
/
YH,A,: 5.LJ~a..*l 5.L..J~,*1 10 £...ib4
£...&::14../1:::.
/t:. 15/;: IfZ/! 4-~
1f2.4 20 'I 25 I 30 / I
!3 MDA= 2.
2..2.,2. Rf Idpm I dpm REVIEWED BY: a MDA= n* "f'f dpm J7' PRINT: SIGN: DATE:
~1~ij = SURVEY POINTS
¥_Vi @ ,§
'f -c)-B cx..o~ ex- ~c;.t. ~G'-
z.. Z-
.---- //2;) 3:::---
---- ~
\.....:.-/
1<C)(J~.---pc,y-}-6-[) -12>P ~,Ce-D~. 1<C)(J~.---pc,y--}-6-[) ~*Ce-D ~. t' R;I
I
- Location 1
Valve 4-7558 4-7548(V.O.) 4-7548iV.O.) Feet Off Floor 7 11 ZONE 103 UNIT-4 "8" RHR PUMP ROOM Location 16 Valve 4-70-1178 REV. 11/30106 Feet Off Floor 2 7 I 2 3 4 4-767B(V.O.) 4-1463 0.5 2 17 18 19 4-887 4-7538 4-7568 2 3 I 5 MOV-4-8618 5 20 4-9398 5 6 7 4-7660 4-899F 1 3.5 21 22 4-9388 4-7690 5 5 I 8 4-1464 3 23 4-7698 4-769B 3 9 10 4-766F 4-7528(V.O.) 1 8 24 25 4-7688 4-7668 4 1 I 11 4-762B 6.5 26 4-7560 3 12 4-12..Q14 4-12.Q14 2 27 4-1091 3.5 13 4-12..Q13 4-12.Q13 1 28 MOV-4-862A 8 14 4-12-011 1 29 4-942P 6 15 4-12-012 2 30 1 2 3 4 5 6 7 8 9 10 11 14 15 x
'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
REV. 5/14/07 FLORIDA POWER & LIGHT - PTN Hp*44:30Hx Hp-44:30Hx LOCATION: UNIT 4 RESIDUAL HEAT REMOVAL Heat Exchangers /LOG# LOG# 0'1 '-0388
~?'i . ::.,LJ DOSE RATES IN MREM/HR UNLESS OTHERWISE NOTED DATE; C'i (A) AIRBORNE ARPA (L) LOCKED lOCKED HIGH MD RAD AREA " GENERAL AREA DOSE RATE
=CONTACT DOSE RATE (8) RESPIRA TOl1Y PROTECTION (I\!)
(1\.') RADIOACTIVE MATERIAL
- TIME; D1~C.' (C) CONTAMINATED AREA (N) NCilFYNCIIFY HP PRIOR TO ENTRY o0 ~
~ SMEAR LOCATION (0) HIGKL Y CONT4MH.ATED AREA HIGHLY (R) RACIATION RADIATION t,REAAREA L\ " NEUTRON DOSE R/,TE TECH. : 'T)(~ ltc '( t:.LS (E) EXCLUSION "',EA REO~IRFD SURVE', ME,ER REO~IRFO (S) SlJRVE', o0 '"
"BETA BETA DOSE RATE
--- COVEPA E REQ~IRED (F) HOi PARTiCLE AREA (T) HP, COVER1" ~ = CONTAMINATED BOUNDARY C
PID# : 2D l (H) HIGH RADIAl ION AflEA () l'.i
\'..i ............. "" "'" RAO BOUNDARY i-\ .f - - - (K) KEEP OllT OUT ( ), f 1\ Rama'~"*
~r~~~ ~ '"7'"77~""ft~ ~~.Y
/..l , ,
. :....,..x~
,-~~~ ,-"",.,.,
1"'" __ J~_ ""_.. -/.
.,. ';; :\'!;;-~,~~-
>'OJ<
~' :',!.-,[~i~ __ ;';;::,-::3,
;';;::;::3, 1 'J1!:; i\o',r;&F:-':;;:
t,;:t::~/;:'1;t ,(.F,c:\ ii_'?t;.~o',{;&Fc;;: It.,;:t::~/;:'l;\, ADDITIONAL INFORMATION lK
"':'.~:"-"'.,...d"l1&I"'iJr.t.
'r,i ::'
'L LQUcirlerly QUarlerly i RWP# : l- i SMEARS dpmll00crn (COUNT AT LEAST ONE SMEAR:: SMEAR;:: 50,000 50.000 DPM FOR ALPHA)
SMEAR NO,: NO.: Instrument HPI# 1 ~ D'\t):fj 6<:jY).o~ 11..( MQA 11-< 16 NJA- 21 N/A-N/A 26 1\1/ A Nl8
.80'
.BtL* J.0 ill:l
~r:l
[-<Ii, LD-:l2cD LJ)22(::C J...0
'.4..:-:'
'1'
'.4..:'
LO-:2. '2cD L~D22(::C ) 1(15:' f1 MDA= 121 Il4*{)
\l4-D
)2-4 '!
)24-r:
I! [13 I (1S' IJJ)J 100 dpm 2<fYJ,D~ 3~ 4:(lflO 5 343 REVIEWED BY: 10
- +/- <YMA
<'l'MA 12.(MIJA 13 {1:13 14 <. fi'\{)A 15 <mDf\
17+/- 18 1 9 +/- 24 20 22~ 22~27 23 25 27 28 29 30
"~wrrM' AL HA:
0; MDA::: !'-l/J\ dpm PRINT: ~~ -,- SIGN: DATE:
- SURVEY POINTS c 2~ *
*UH26tz UH26tz ARr::p., S,MEftR-S S,MEftR.-S (A (A~~ B) ~
- CD~
- Rct,)'M
"'-ICOc dpY>
":'ICOc Rct,,)'M R)S-IED i 3rcss-w1pe n)SIED ~ 'rz; J We, be\-e, .. 9CllVlmq
'R; (a.) i e,)
Ht.."+Sp::+ kt.."+Sp::+ 0,1-/4
.J';2.S/1i With i~O-.zO lo/IC
'5q~
,,' 1}3
11/30/06 REV. 11130/06 ZONE 104 UNIT-4 RHR HX ROOM lLocation ocation Valve Feet Off Floor Feet Off Floor
, location Location Valve 1 4-771E 4-771 E 4-7S9A{V.O.) ,
6 16 4-12.015 4-12-015 2 2 2 3 4*759A(V,O,) 4*77 1F 4*771F 6 9 " 17 18 4-12-018 4- 12-018 4-746C 4*746C 10.5 4 5 4-759B(V.O.J 4-759B(V,O,) 4*J60A 4* 760A 8 3 19 20 4-757 A(V,O.) 4-7S7AN.O. 4.7510 V.D. 4-7570(V.O.) " 10 10 4-1710 5,5 5.5 4-7718 5.5 6 4* 7710 5.5 21 4*771B 5,5 5.5 7 8 4-771C 4-77 1C 4-842 4*842 , 1 22 23 4-771A 4-7S7B{V.O.J 4-757B(V.O.) 9 9 10 4* 943V 4*943'1 4-7460 4-7460 4 10,5 10.5 24 25 4-757C{V.O.) 4-757C(V.O.) 4-757F ",, 10 1 4-943W 1 11 4-9 43W 1 26 4-942T 12 MOV-4*8638 MOV-4*863B 22 27 13 14 MOV-4*863A MQV-4-863A 44**12-{)17 12-017 2 2 28 29 15 4-12*016 4-12-016 2 30 14 15 1. 16 17 18 19 20 X 1 X 21 2 3 -,-
,"R 22 4
--- 23 EXCHANGER 2J 5
6 X 7 8 a
$1 "
24 25 9 10 11 12 13 26 {V. D.) (V.O.) =Location of the valve NOT the hand wheel (HW.) = (H.W.) :: Location location of the hand wheel wheet Not the valve
REV. 12/4/06 REV 12/4/0 6 FLORIDA POWER & LIGHT - PTN HP-44:30.1 LOCATION LOC ATION:: UNIT 410' ELEVATION (ACCESS TO RHR PITS PITS)) ILOG# 6e-13~ 1 o DATE: DATE; TIME; TIME: I 2. - 1 "'" - __ . . .LS_:.g.. 2__ d~ II\} AIRBORNE M~E" (A) "'R6OII><F. (8) ilF.SI'1f1"TO (S) A.REA RE SPIRATORYRvp~o (C) ':CN-:-AM",,,T£(' ceNTPMINATEO PROTEC
> ~R ru;rlON E.Io AREA (0) HIGHL'( CONTAMINA.TEO AREA nON (Ll LOCK£O (l) LOCKED H;Gt<
HIGH R.o.D.o.RE.<. (M) kIoDt(McrrJEMArCRI.L (1'1) RAO AREA RADIOACTIVE MATERIAL NOTIFY HP PRQilTOENTR1 (N) NOlWYHP (R) R.-.OIATION AREA PR IOR TO ENTRY DOSE RATES DOS£ RA rES '" o0 b. IN IoI MREMIHR
=
UNLESS OmEKMS,f R£MlHR UNL£SS
~ CONTACT ~OSE
..= SMEAA SMEAR LOCAno OrHER'oVISE NOTED
~ GENERAL AREA DOSE RArE, DOS E RATE LOCA n O ..
=NEUTRO N DO~E RATE N
RATE TECH. : ___ ::2 ~ , <2."-:4 (E) EXC LU SION AREA (5) SUR'/EY METEH REQUIRG) 0
- SETA DOSE RATE (F) Hor PARnCLEAREA (T) if.P . COVERAGE REQUIRED -o..0-.G = CONTAMINATED BOUNDARY PIDI/
PID# ;: \ ') '1 (H) HIGH RAOIA !ION AREA. ( ) {-.;/ - ~ ... ¥ - = RAD BOUNDARY (K) KEEP OUT ( ) 7 If Remarks: A (I <!~S<. .r '" \-c;; ~ Co<1 d -"'" ,/"-1 SI GNATUR E;
._- - 0')'--- REF ER 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.::....-. _ _ SMEA RS dprn/l00cm' (C O UNT AT LEAST ONE SM EAR ~ 50,000 DPM FO R ALPHA) SM~ARNO/ Q,+
~:-J---
Instrument HPI # 1 .(0 Q 6 6 _s..!1~ 11 ...::....~ 16 . "MQ! 21 ,z'\j.
,--' .... ----- --- -- --- ~C~~- ---
£...~ ~ ,-r-'\ QJ,
- ,kG- 7..
C\ . 7" 2~J2:i 7 ~ 12 \2 ~~ 4t:!lli.... 17~lL 17 22 L \'-\9b
-~ .t:.~12a: BE TN<7MMA
"= 23 c.",-\ vA- If'! / A W<O.1:.UC_=-:L __..:.ii~ ___ ._._.. 3~... 6C 8 __(.rlQ:1r
~~QIf 13 13.'it 2::' * ~~ 18 ..~ ---- 28
.....§.5.:s _':iL ~l..;~~ __ 4 -~-!>~(') 9....L..!..&Q!L 9 ...£1&Q.(L 14 -<:~~ 24 L..<'-1.2 !L I "
7A~PHA'
,/ 5 2[) .~t~ 10 _._sMPA "
~""M 15 <>1'4
~ 19 ",..,
c..,M\~0 1 20~A k:\'-10k 20 t:.r1'lQtL 0--'1-25 £t::lvA-29 30L_ /
.._.. _. J~._ MDA=
(l MOA- "2. 7*. <; j'1 _"-.c.~? _clErn_ dpm flEVIEVJEO fl E VIEVVED nv 8Y na MDA'" MDA= r::~~m J!_ .0~~_ ~Em PRINT PRINT SIGN : DATE: DATE;
..- . ~ ~
- .- -- - -"~
'" SURVE Y POINTS I
mm LINE ('-----....>6)"'--_---r
",O-O_~
. , 0 - 0 I,
,0
. ~,
'c.,. (:!H'i*1r.7~
b.. Ci) ? If
- n.7 17 0O '--0 -~-o L- 0 _ 0 C
\/
8
,.0
-s*o
-5' C
*I-
- Location 1
Valve 4-8358 UNIT-410' UNIT Feet Off Ftoo' 2 ZONE 105
-410' ACCESS TO RHR PITS Floor Location 16 Valve 4-8350 REV. 11/30106 REV.
Feet 11 /30/06 Feel Off Floor 1.5 I 2 4-835A 5 17 4-770B 2 3 4 5 4-770C 4-770D 4816 2 5
'.5 0.5 18 19 20 MOV-4*8608 4*746A (V.O.)
40-1845 2 8.5
'.5
'-6 *-
6 4802 0.5 21 4-7468 (V.O.) 8.5 7 4-770A 5 22 4-40-1905 5.5 4-791K 1 FCV-4-605 8
, 23 5 4-791J 4 24 4 9
10 4-767E , 1 4-761F
,0-""
40-1844 5
"" 4-898N (V.O.) 1
~
25 26 3 11
" 40-1843 12 4-893E 1 27 4-761E 15 13 4-899E 2 28 4-746E 5 14 15 4-767F 4-835C 5 1 29 30 4-746F HCV-4-758 ,
5 1 c:==:Jc:=::=:=J t I
"'-~
--~====~~============~----
RHR LINE 3 J '~ 4 5 6 7
""- : JI 10 11 12 13 14
" " - - 15 16 t.--
17 18 19 II 20 21 L . 33 22 \..34
./"
;25 23 24 26 II
" - - 28 27 II 29 x
x
~31 30 32 35 36 ,
II (V.O.) = Location (v.o.);: location of the valve NOT the hand wheel (H.w.) = Location of the hand wheel Not the valve (HW.)
~
- Localonr Location 31 II 32 v a~
Valve 4-7618 4-7618 4-761A UNIT-410' Feet Off Floor F t Off 14 14 ZONE 105 UNIT -410' ACCESS TO RHR PITS
- e. Location 77 77 78 Valve REV. 11/30106 Feet 11 /30106 Feet Off Off Floor 33 4-40-1898 4-4()..1898 5 79 34 4-40-1896 4-4 0- 1896 6 80
" 4-7658 21 81 35 36 4-765A 4.76SA 21 "
82 37 38 83 84 39 J9 85 40 41 86 67 42 88 43 44 45 89 90 91 46
" 92 47 48 49 93 94 95 50 96 51 97 52 98 99 53 100 54 55 56 57 101 102 103
'03 58 104 59 eo 60 105
'05 106
' 06 107 61 62 ""
108 63 109 110 64 65 '" 111 66 112 67 '" 113 68 "' 114 69 '" 115
'IS 70 10 116 71 11 '"
117 118 72 73 13 "' 119 74 '" 120
'20 121 75 76 16 '"
122
- (V.O.) =
(V.D.) :: Location of of the valve NOT NOT the hand hand wheel :: Location of (HW.) = of the hand wheel Nollhe Not the valve
= ' ... \> . " ..... --- ~
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- Facility: _T_u_r_k--"-e.L.y_P_o_in-'-t'--______ Task No:
---'-T=ur:.-kc..:.e.Ly--'-P-'o:....:..in:.-t'---______
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=--=-_____ X _
---------- -----~'--------
Classroom - X 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
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
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 attachment AND notify the Shift Manager or Unit Supervisor.
- - SAT 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
Appendix C Page 8 of 12 Form ES-C-1 Ordered to Lock Closed HV-3-1, Post Accident Containment Vent and
- - - SAT STEP 5 Sample System Isol Valve (RR) within 1 hour.
..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
- NOTE:
4.0 IMMEDIATE ACTIONS 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 STOP Cue: the examiner. 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.
Examinee's Name: NRC-25-ADMIN-JPM-A 1.2
~~~~~~~~~~--------------------------------
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
Appendix C Job Performance Measure Form ES-C-1 Worksheet
- Facility:
Task
Title:
_T~u_r_k_e,,-:-y _T_u_r_k_ey'--P_o_in_t
- Determine
~~~~~~~~~---
_ _ _ _ _ _ _ Task No: _P:-o.,-in_t----=______ Classify Plant Event and Notifications 2.4.41 Knowledge of the emergency action level thresholds and classifications. Job Performance Measure No: NRC-25-ADMIN-JPM-A.4 2.9/4.6 KIA
Reference:
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
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 .
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
>j 3
Classifies event as a Site Area Emergency in accordance with 0-
- - SAT
- - UNSAT 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. 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 Obtain 0-EPIP-201 01, Attachment 1, "Florida Nuclear Plant STEP 4 Emergency Notification Form." SAT 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. Record time that candidate accesses the State of Florida Cue Notification Form Start time: Comment NOTE:
Appendix C Page 8 of 13 Form ES-C-1 Completes Attachment 1 lAW with standards set in 0-EPIP-201 01, STEP 5 "Duties of Emergency Coordinator." SAT
-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)"
- 1O. 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.
I Appendix C Page 11 of 13 Form ES-C-1 I STOP STEP - - SAT Stop time: (15 minutes acceptance criteria, from - - UNSAT 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.
Examinee's Name: NRC-25-ADMIN-JPM-A.4 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.
FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM Online Verification: )8f STATE B J1 MIAMI-DADE COUNTY )g
)g' MONROE COUNTY A. Il:I (lJ This Is A Drill B. 0D This Is An Actual Event *. A. DateXXIXX/~X.
DateXXIXX,XXX,,< *B.
- B. Contact Time:
Time: x><XX Xl<A C. C. Reported by: by : Name_ __ __ X...;....X~)(_<.l.-
-'-XX-"-' _____
-X-"'>('----c _ _ _ ___
D. Message Number: Number:_ _ _ -L.'I _____ E. Reported From: D 0 Control Room £Sl
. TSC D 0 EOF F. 0D Initial/New Classification OR oD Update Notification 3.
3, SITE A. 0D Crystal River UNIT 3 B.
- 8. D 0 St. Lucie UNIT 1 C. 0
- c. D St. Lucie UNIT 2 O. M D.)&' Turkey Point UNIT 3 E.)8f E. J8f Turkey Point UNIT 4
~4. EMERGENCY CLASSIFICATION: *4. A.
A. D 0 Notification Of Unusual Event B. D 0 Alert C. C. % Site Area Emergency D. D. D 0 General Emergency
'5. A. ~ EMERGENCY DECLARATION: *5. DECLARATION : B. D0 EMERGENCY TERMINATION xx: X><
Date: XX: I >9< IJ XX(P(Time:
~ime : x.cxx x..xxx.
- 6. REASON FOR EMERGENCY DECLARATION:**
'6. DECLARATION :-- A.;g.(EAL Number: A.~ /5.
/5,C C .cr0escription h/Ct?'
OR B . .!4fDescription /.::we&"-- /~
/#
(l/1.;?iF 5//~6I4j)/N& (f/l.:gt r S""~ClJNN6- £:OOP' w'I-rf( Cav'rk""L ,f?>"ht ~"'CWI-rtON
£ 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 .0
- S. WEATHER DATA:
- 8. DATA; A.
A. Wind direction from //6868 degrees. B. 8 . Downwind Sectors Affected 6;}J<;Il,IJ qR/ l, tJ '9. RELEASE STATUS :
- 9. pq-A.. .p? None (Go to Item 11)
A B. D 0 In Progress C. D 0 Has occurred, but Stopp;d stopped
- 10. RELEASE SIGNIFICANCE CATEGORY (at the Site Boundary)
A. D 0 Under evaluation B. D 0 Release within Nonnal Normal Operating Limits (Tech Specs) C. 0 Non-Significant (Fraction of PAG Range)D. D D 0 PAG Range (Protective Actions required) E. D 0 liquid Liquid release (no actions required)
*1 1. UTILITY RECQMMENDED
-1 RECOMMENDED PROTECTIVE ACTIONS FOR THE PUBLIC PUBLIC:: A.~ A .~ No recomrecommended mended actions at this time. B. D D The utility recommends the following followi ng protective actions : pro tective actions: EVACUATE ZONES:NOTZONES :NOT APPLICABLE OR Miles Evacuate Sectors Shelter Shetter Sectors No Action Sectors ZONES :NOT APPLICABLE SHELTER ZOHES:NOT 0-' 0-2 2-5 5 --10 10 AND consider iS5uance issuance of potassium Iodide iodide (KI) If form is ;s completed in the Control Room, Room, go to item 15. If completed in the TSC or EOF, continue with item 12.
- 12. PLANT CONDITIONS:
A. A. Reactor Shutdown? )QYES 0D NO B. Core Adequately Cooled? ~ YES D0 NO C. C. Containment Intact? )3 YES 0 D NO D. Core Condition: J21 Stable D0 Degrading
)2f
- 13. WEATHER DATA: A. Wind Speed .£ 6 mph B. Stability Class 7)
- 14. ADDITIONAL RELEASE INFORMATION : A. D 0 Not applicable (Go to Item 15)
Distance Projected Thyroid Dose ICDE) (CDE) for 1 Hour Projected Total Dose (TEDE) for 1 Hour 1 Mile (Site Boundary) B. ___ __ __ ___ __ __ _ ,mrem C., C._ _ _ _ _ _ _ mrem mrem 2 Miles D. _ _ _ _ _ _ _ ,mrem mrem E. E._ _ _ _ _ _ _,mrem mrem 5 Miles F. ___ __ __ ___ __ __ , _ mrem mrem G. G. _ _ _ _ _ _ _ ,mrem mrem 10 Miles H., H._ __ __ __ __ _ _ _ _,mrem
-,-,---, m rem I.I. _ _ _ _ _ _ _ _ mrem mrem
~C Coror RM Approval Signature_ _ __ __ __-=--'-"'S's----____________ X:xXXX
>(.....:....:;.. _ _ _ _ _ _ _ _ _ _ _ _ ,Da,.XX,xx,WXT;m.
x..:...X..,.,....X,...:x DateXKJ.X.XI.~XXX Time /xxX XXXx.
- 15. MESSAGE RECEIVED BY: Name _ _ -"-='-==
.x..><)(
;X_->( XX x..x.X ____________,Date'><xJX.'{Ix' Da'.!<X'XX' XXXX: >X< TimeXXXX.
T;m.XXXX IF EMERGENCY CLASS Cl.ASS ESCALATION ESCALATION IS KNOWN TO BE NECESSARY AND A NEW NOTIFICATION FORM WILL BE TRANSMITTED TRANSMITIED WITHIN 15 MINUTES. MINUTES, THEN YOU MAY MAY GO TO ECIRM APPROVAL SIGNATURE LINE LINE.
- ITEMS ARE EVALUATED FOR NRC PERFORMANCE INDICATORS (Pi s)
(Pis) F-4 3911 :2 Rev 8 (11/10/08) F-439/1 (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)}}