Text

Initial Exam 2009-301 Draft Administrative JPMs
	ML091740128
Person / Time
Site:	Turkey Point
Issue date:	06/23/2009
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	ES-301-1
	Download: ML091740128 (71)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: 2/23/09 Exam Level: RO Administrative Topic (See Note)

A.I Conduct of Operations N/A A.2 Equipment Control A.3 Radiation Control Type Code (See Note)

CR,N N/A C,N Operating Test Number: 2009-301 Describe Activity to be performed Perform a Manual RCS Leakr*~ C<J:)c (2.1.7 RO 4.4)

N/A ates and Radiological Requirements From a Complete a Florida State Notification Form (2.4.39 RO 3.9)

RO applicants require only 4 items unless they are retaking only (C Co rol Room (S) Simulator (CR) Classroom

. ect from bank ( ::;3 for ROs, :s4 for SROs)

( )ew or (M)odified from bank (2:1)

(P)revious 2 Exams (::;1 Randomly selected)

(

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Turkey Point Units 3 & 4 Date of Examination: :

2/23/09 Exam Level:

SRO (U) & (I)

Administrative Topic (See Note)

A.l.a Conduct of Operations A.l.b Conduct of Operations A.2 Equipment Control A.3 Radiation Control Type Code (See Note)

CR,N CR, N CR, N Operating Test Number: 2009-301 Describe Activity to be performed Perform a Review of a (2.1.7 SRO 4.7)

ClassifY Event and Determine PARS (2.4.41 SRO 4.6)

NOTE:

RO applicants require only 4 items unless they are retaking only

Types and Codes (C) Control Room (S) Simulator (CR) Classroom (D)irect from bank ( ::::3 for ROs, ::::4 for SROs)

(N)ew or (M)od ified from bank (::: I)

(P)revious 2 Exams (::::1 Randomly selected)

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet

_T=-u::.:.:r~k-=-ey,,---,--P...:::.o-,:,-in=t_--:-,---,--___ Task No:

Perform a Manual Leakrate Calculation JPM No:

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

KIA

Reference:

2.1.7 RO 4.4

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

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Form ES-C-1 01041036100 RA.1 Simulated Performance X

Actual Performance

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

Classroom X

Simulator -----------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discus, an complete the task successfully, the objective for this job perfor Initial Conditions:

Unit 4 is at 100% power, steady state.

Task Standard:

Acceptance criteria f met to Coolant System Leak Rate Calculation st Leak Rate Calculation is verified NOT Leak Rate Calculation", Attachment 3 Leak Rate Calculation t System Leak Rate Calculation" NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 8 Initiating Cue:

You are the Unit 4 RCO on Peak Shift and have been directed to perform an RCS I calculation by completing 4-0SP-041.1, "Reactor Coolant System Leak Rate Ca 3 Leak Rate Calculation Data Sheet (Manual Method).

The start and stop data for the leakrate calculation are provided to you on Time Critical Task: No Validation Time:

30 minutes HAND JPM BRIEFING SHEET TO EXAMINEE A T THIS Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of 8 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C STEP 1

Standard:

Comment STEP 2

./

Standard:

NOTE:

Page 4 of 8 Denote critical steps with a check mark(./)

Obtain a copy of 4-0SP-041.1, Reactor Coolant System Leak Rate Calculation Copy of 4-0SP-041.1, Reactor Coolant System Lea obtained.

Provide a copy of 4-0SP-041.1, Reactor Calculation Attachment 3, Leak Rate Ca Method) for Peak shift page 32 & 33.

Record Start (4-0SP-041.1, data is provided to the examinee on the JPM briefing sheet.

minimum duration for the calculation is four hours. The provided in the initiating cue is four hours.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 3

I Standard:

Comment NOTE:

STEP 4

I Standard:

NOTE:

Page 5 of 8 Record Stop Data (4-0SP-041.1, step 7.1.2.10.c and Attachment 3 page 1 steps 1-9)

Examinee records the data under "Stop" column on ATT",,,nrnJ:

1.

The stop data is provided to the Determine RCS Leak Rate.

(4-0SP-041.1, ntified Leak Rate of 1.17 ~ 0.1 gpm for this step of the procedure ONLY applies to ng the PC method.

attached ATTACHMENT 3 key for all calculation results and roronro numbers.

Form ES-C-1 I SAT UNSAT NUREG 1021 Rev 9 Appendix C

Appendix C STEP 5

Standard:

Comment STEP 6

I Standard:

Page 6 of 8 SM Notified that gross leak rate is greater than 1 gpm.

(4-0SP-041.1, Attachment 3 page 1 Note 1)

Examinee notifies the Shift Manager that gross leak rate is gpm due to unidentified leakage> 1.0 gpm.

When asked provide the following cue, "The informed."

Determine surveillance acceptance criteria (4-0SP-041.1, Examinee determines su to Unidentified RCS LC:;GI'"'U a are NOT met due gpm..

are NOT met due to Unidentified RCS ee determines acceptance criteria is NOT met, ng cue, "Another Operator will complete the of this procedure."

Stop Time Form ES-C-1 SAT UNSAT STOP NUREG 1021 Rev 9 Appendix C

(

I Appendix C Verification of Completion Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Unsatisfactory Page 7 of 8 Form ES-C-1 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 measu satisfied.

INITIAL CONDITIONS:

Unit 4 is at 100% power, steady state.

All 4-0SP-041.1, "Reactor Coolant System Leak Rate Calculation" prereq Primary to Secondary Leakage is 0.0 gpm Combined Charging Pump primary packing leakage is 0.05 gpm Non-Reactor Coolant Pressure Boundary (RCPB) Leakage is 0.0 INITIA TlNG CUE:

You are the Unit 4 RCO on Peak Shift and have by completing 4-0SP-041.1, "Reactor Coolant S Calculation Data Sheet (Manual Method).

The start and stop data for the leakrate calculation are YOUR EVALUATOR WHEN YOU HAVE TORIL Y COMPLETED THE ASSIGNED TAS NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

KIA

Reference:

Examinee:

Facility Evaluator:

Method of testing:

Job Performance Measure Worksheet Turkey Point Task No:

Review a Leakrate Calculation JPM No:

2.1.7 SRO 4.7 NRC Examiner:

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

Date:

01041036100 S.A1.a

.. /,,/1,\\

Simulated Performance X

Actual Performance

"~/

~'\\~~

"\\',."-,,,::7( '-------'i; x

Form ES-C-1 Plant ---------'

Classroom Simulator --------------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or diSCU~

...,(...... ff

.. ~.' rOvide

.......... i

... n

..... iti51.,

... t

..... I.*.. p.'. 9 cues. When complete the task successfully, the objective for this job perforr~~c( measure }Nill bJ3 satisfied.

"'/c//

Initial Conditions:

~:t,ro-Unit 4 is at 100% power, steady state.

(... "'.......

All 4-0SP-041.1, "Reactor Coolant System Leak(;R

'0 **** cut tion" prerequj?it~'s.t1ave been met.

ERDADS is not available.

Task Standards:

..;::,$.* ''-W*-'-'''''......... ,-*'CA

\\,:

--\\t,,,,v The error in the RCS leak rate/calculated\\~sing 4-0,~P-...... 1 Reactor Coolant System Leak Rate Calculation is discovered.

Determination is made to' ritJria for 4-c)SP:'041.1 Reactor Coolant System Leak Rate Calculation is NOT m.(t'./*/'.,/'i'*....

Determination is madethat.~?mpli~pce Wftt1'**T*ecAnic.~L~*~.~ification LCO 3.4.6.2.b Action b is required within four hours.!o ~if~tai~/centiRYege!

.. ~.~~~J5~ration.

,;{I'/

'!'\\

\\..

~'Q41.1*':\\'{Be~Gtor Coolant System Leak Rate Calculation".

\\::t_

<'\\,\\.

'<>",\\.\\

Gener~~~~fer!3n ces:

"\\.\\.

.l' it 4-0SP-041.. 1, "~eactor C9da~{ System Leak Rate Calculation" Technical S"pecifICqtionsTUgkEY POINT - UNITS 3 & 4

'\\ fr

,\\_,

~vf4f

,~/;;,'J NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 8 Initiating Cue:

You are the Unit 4 Unit Supervisor on Peak Shift and have been directed to pe completed 4-0SP-041.1, "Reactor Coolant System Leak Rate Calculation", and required actions. The RCS leak rate calculation was made using the manual Time Critical Task: No Validation Time:

30 minutes HAND JPM BRIEFING SHEET TO EXAMINEE A T THIS Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of 8 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C

(

STEP 1

Standard:

Comment NOTE:

STEP 2

./

NOTE:

Page 4 of 8 Denote critical steps with a check mark(./)

Obtain a copy of 4-0SP-041.1, Reactor Coolant System Leak Rate Calculation Copy of 4-0SP-041.1, Reactor Coolant System obtained.

Provide a copy of the completed 4-0S Leak Rate Calculation.

Procedure note Review the completed 4-Calculation.

System Leak Rate the RCS leak rates calculated using Leak Rate Calculation by

.1, Attachment 3.

the Primary Water added causes an underestimation of the calculated RCS Gross Leak Rate.

calculated RCS Gross Leak Rate should be 1.3 + 0.1 gpm calculated RCS Unidentified Leak Rate should be 1.12 + 0.1 gpm See the exam key for a copy of the completed attachment.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 3

Standard:

Comment STEP 4

.j Standard:

Page 5 of 8 SM Notified that gross leak rate is greater than 1 gpm.

(4-0SP-041.1, Attachment 3 page 1 Note 1)

Examinee notifies the Shift Manager that gross leak rate is gpm.

When asked provide the following cue, "The S informed."

Determine surveillance acceptance criteria (4-0SP-041.1, Examinee determines to Unidentified RCS Lea are NOT met due gpm..

ults in the surveillance acceptance as acceptable.

is detected and corrected, the surveillance acceptance due to Unidentified RCS Leakage in excess of 1 Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

(

Appendix C STEP 5

Standard:

Comment NOTE:

Terminating Cue:

Page 6 of8 Refer to applicable Tech Specs (4-0SP-041.1, step 7.1.2.21.a)

(Technical Specification LCO 3.4.6.2.b)

Examinee determines Technical Specification LCO 3.4.6 is applicable.

AND Determines continued operation with the allowed for up to four hours.

Provide a copy of Sections 3/4.4.6 R LEAKAGE.

The examinee implement this Form ES-C-1 STOP Stop Time ___ _

NUREG 1021 Rev 9 Appendix C

I Appendix C Page 7 of 8 Form ES-C-1 Verification of Completion Job Performance Measure No.

S.A.1.a Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

ry /U nsatisfactory Exam iner'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 satisfied.

INITIAL CONDITIONS:

Unit 4 is at 100% power, steady state.

All 4-0SP-041.1, "Reactor Coolant System Leak Rate Calculation" prereq ERDADS is not available.

INITIA TlNG CUE:

You are the Unit 4 Unit Supervisor on Peak Shift and have completed 4-0SP-041.1, "Reactor Coolant System Lea actions. The RCS leak rate calculation was made us' NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet

--'--T-=:.:.ucc.rk.:.:ce.LY-'-P-'o:...;..inc.:...t'---______ Task No:

Review Safety Injection Attachments Prior to Mode

_C-=-.-h_an---'9"'-e'------________ JPM No:

KIA

Reference:

2.1.29 SRO 4.0 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

1062009100 S.A.1.b Simulated Performance X

Actual Performance Classroom x

Simulator Plant Read to the examinee:

",r/"

jr, Form ES-C-1 I will explain the initial conditions, which steps to simulate or discu an~ provide iFYffiaJirig cues. When you complete the task successfully, the objective for this job perform a ~e meas/yre v0H'be satisfied.

"v/

/1' Initial Conditions:

Unit 3 is in MODE 4 325' F making preparatio~~~~nSion ~f\\/lob~c 3.

3-GOP-503, Cold Shutdown to Hot Standby is in prog(ess"atster5"§,~5.1 o. '

Unit 4 is in MODE 6.

't

\\

i>i/

Unit 4 Core offload is in progress

\\

/'

The Unit 4 RWST is INOPERAB~e*'cftte*.to low level,.

\\',/fi

.,1" All other equipment is OPE~~~rB~",~-'j --'---'-"'~~_

.,-->\\

,.1'"

., F Task Standard:

fir/'

Examinee identifies five. v (OPERABLE) RWST.

,if

//

- "'~.......... \\ \\

s th~pr~;.I"~~,~thEtt;Flit",.... yptSl pumps from being aligned to the Unit 3

,f/

""'''~:~~.

i-*-

~/>

~.. ""

" '<0<;,,,,>

n<;tby

'/;,/

Req u ired M ate*(ial;*:*~"~**'*~",,\\

,/,::,,<,;,//' "

<:::~::I'/-

,,,~,,.

~"'=>><<",:;:",~,' ~"\\.:\\

3-c;,G?P~?d3, Cold Shuttl~W~\\to Ho 3,:NO~'~062, Safety Inje~n<?n TeistmiCal Specifications

\\\\

'\\,

,I General Reiere1'1'ces:

j

i,i

'\\_~,~,

"'\\--

3-GOP-503':\\<<pl'Cr'~~,Pta';¥vn to Hot Standby 3-NOP-062, Sai~tyV 'e;e1ion Technical SpecifiO NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 7 Initiating Cue:

You are the Unit 3 Unit Supervisor. You have been directed to complete step 5.25 (4) HHSI pumps are aligned to an operable RWST by reviewing the 3-NOP-62 through 3, Safety Injection valve alignments.

Time Critical Task: No Validation Time:

30 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of 7 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C

(

STEP 1

Standard:

Comment STEP 2

J Page 4 of 7 Denote critical steps with a check mark( J)

Obtain a copy of 3-GOP-503, Cold Shutdown to Hot Standby and NOP-062, Safety Injection Copy of 3-GOP-503, Cold Shutdown to Hot Provide a completed copy of 3-GO Standby page 50.

(3-GOP-503, The Examinee reviews d determines E RWST by CLOSED LOCKED CLOSED LOCKED CLOSED

.)

. e a completed copy of 3-NOP-062, Safety Injection Attachments ugh 3.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C Page 5 of 7 Form ES-C-1 I Terminating The task is complete when the Examinee returns the cue sheet to Cue:

the examiner.

(

NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 7 Form ES-C-1 Verification of Completion Job Performance Measure No.

S.A.1.b

~

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

ory IUnsatisfactory Exam iner'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 satisfied.

INITIAL CONDITIONS:

Unit 3 is in MODE 4 3250 F making preparations for mode ascension to M 3-GOP-503, Cold Shutdown to Hot Standby is in progress at step 5.25.10.

Unit 4 is in MODE 6.

Unit 4 Core offload is in progress The Unit 4 RWST is INOPERABLE due to low level.

All other equipment is OPERABLE.

INITIA TlNG CUE:

You are the Unit 3 Unit Supervisor. You have HHSI pumps are aligned to an operable Safety Injection valve alignments.

step 5.25.10, verify a r (4)

Attachments 1 through 3, NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet Turkey Point Task No:

Equip Operability Verification JPM No:

KIA

Reference:

2.2.12 RO 3.7 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Form ES-C-1 1023006200 R.A2 Simulated Performance Actual Performance

-~~~--~~

Classroom Simulator ------~-----

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discuss 'n complete the task successfully, the objective for this job perfor Initial Conditions:

Unit 3 and 4 are both in Mode 1 Preparations are in progress to perform a mon 23.1 Diesel Generator Operability Test section Step 7.2.1 of 4-0SP-23.1 Diesel Generator Ope Task Standard:

0-OSP-023.3, Equipment 0 is complete Required Materials:

enerator using 4-0SP-NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 13 Initiating Cue:

You are the Admin RO and you have been directed to continue with preparations of the Unit 4 B Diesel Generator using 4-0SP-23.1 Diesel Generator Operability 7.2.2.

Time Critical Task: Yes Validation Time:

15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE A T THIS Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of 13 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C

(

STEP 1

Standard:

Comment NOTE:

NOTE:

(

Page 4 of 13 Denote critical steps with a check mark( I)

Obtain a copy of 4-0SP-23.1 Diesel Generator Operability Test (From initiating cue.)

Copy of 4-0SP-23.1 Diesel Generator Operabil When the examinee goes to obtain a copy marked up copy of 4-0SP-23.1 Diesel section 7.2.2 pages 39 and 40.

are duplicated by 4-0P-023, P-023.2, Diesel Generator 24-

. At the discretion of the Shift d N/A if they have been Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 2

Standard:

Comment NOTE:

Page 5 of 13 Perform 0-OSP-023.3, EQUIPMENT OPERABILITY VERIFICATION WITH AN EMERGENCY DIESEL GENERATOR INOPERABLE.

(4-0SP-23.1 Step 7.2.2.1)

Copy of 0-OSP-023.3, Equipment Operability Verification Emergency Diesel Generator Inoperable is obtained.

When the examinee goes to obtain a copy of the copy of 0-OSP-023.3, Equipment Operability Emergency Diesel Generator Inoperable, Unit 3 and 4 are in Mode 1, The LCO for Unit 4 OPERABLE AND one Unit 3 EDG. to be OPERAB OPERABILITY check with LCO 3.8.1.1.

Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C

(

STEP 3

Standard:

Comment NOTE:

Page 6 of 13 Verify the operability of 2 Startup Transformers AND their associated circuits by performing Attachment 9, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter (0-OSP-23.3 Step 6.4.1)

The examinee completes 0-OSP-023.3, Equipment Ope Verification With An Emergency Diesel Generator Inoperable 9, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

When the examinee goes to obtain a copy of the copy of 0-OSP-023.3, Equipment Operability Emergency Diesel Generator Inoperable, STARTUP TRANSFORMER OPERABI 0-OSP-023.3 procedure note:

If Unit 4 is in Modes in the EOOS 4, the LCO action C't",1'ol'Y\\or 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months until Fire ergency Diese 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per y portion of the surveillance that will be Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 4

I Standard:

Comment NOTE:

NOTE:

STEP 5

I Page 7 of 13 Verify startup transformer breaker 3AA05 4 KV Bus 3A Feed From U/3 Startup Xfmr is RACKED IN.

(0-OSP-23.3 Attachment 9)

The examinee observes 3AA05 4 KV Bus 3A Feed From Xfmr is RACKED IN by checking the green lights above the handswitch ON.

3AA05 4 KV Bus 3A Feed From U/3 located on the Unit 3 console far right

- During Unit startup, shutdown, OR after a unit may be in the CLOSED position. With both units in minimum of one of shall be in the CLOS 4AA22 is CLOS shall be verified to be Verify startup transfo Startup Xfmr is RACKED 3B Feed From U/3 Startup lights above the breaker 3B Feed From U/3 Startup Xfmr control switch is it 3 console far right side.

Form ES-C-1 I SAT UNSAT NUREG 1021 Rev 9 Appendix C

Appendix C STEP 6

Standard:

Comment NOTE:

NOTE:

STEP 7

NOTE:

Page 8 of 13 Verify startup transformer breaker 3AA22 4 KV Bus 3A Feed From Ul4 Startup Xfmr is RACKED OUT (0-OSP-23.3 Attachment 9)

The examinee observes 3AA22 4 KV Bus 3A Feed From Xfmr is RACKED OUT by checking the breaker indicating I the breaker handswitch OFF.

3AA22 4 KV Bus 3A Feed From located on the Unit 3 console far right side.

The current operating practice for checking the surveillance is to perform a visual check of the indicati control room. The I verification of this breaker OUT is performed Verify startup transform Startup Xfmr is RACKED Feed From U/4 4A Feed From U/4 Startup reen lights above the breaker 4A Feed From U/4 Startup Xfmr control switch is nit 4 console far right side.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 8

Standard:

Comment NOTE:

STEP 9

Standard:

NOTE:

Page 9 of 13 Verify startup transformer breaker 4AB05 4 KV Bus 4B Feed From U/4 Startup Xfmr is RACKED IN.

(0-OSP-23.3 Attachment 9)

The examinee observes 4AB05 4 KV Bus 4B Feed From Xfmr is RACKED IN by checking the green lights above the handswitch ON.

4AB05 4 KV Bus 4B Feed From U/4 located on the Unit 4 console far right Verify startup transformer breaker 4AA22 4 KV Bus Startup Xfmr is RAC UT (0-OSP-23.3 The examinee observes Xfmr is RACKED OUT by the breaker handswitch U/3 Startup ng lights above practice for checking the breaker status for this rform a visual check of the indicating lights in the actual local verification of this breaker being RACKED ed in the weekly power sources verification check.

ring Unit startup, shutdown, OR after a unit trip, 3AA05 AND 3AB05 be in the CLOSED position. With both units in Mode 5 or 6, a imum of one of these breakers shall be in the CLOSED position. IF is CLOSED, THEN 3AA05 shall be verified to be OPEN.

Form ES-C-1 I SAT UNSAT NUREG 1021 Rev 9 Appendix C

Appendix C STEP 10 I

Standard:

Comment NOTE:

STEP 11 I

Standard:

Page 10 of 13 Verify that the Unit 3 Startup Transformer voltage potential lamp on Unit 3 VPA is lit.

(0-OSP-23.3 Attachment 9)

The examinee observes Unit 3 Startup Transformer vo lamp on Unit 3 VPA is lit by checking the white light' Both the Unit 3 and Unit 4 Startup are located on the Unit 3 Vertical Panel A Verify that the Unit 4 Unit 3 VPA is lit.

(0-OSP-23.3 The examinee observes lamp on Unit 3 VPA is lit voltage potential indication ON.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 12 Standard:

Comment Terminating Cue:

Page 11 of 13 Form ES-C-1 I Acceptance Criteria is verified MET (0-OSP-23.3 Attachment 9)

The examinee determines Acceptance Criteria is sati of all Breakers correctly aligned AND the Startup Transform potential lamps are lit indicating power availability The task is complete when the Equipment Operability Verification With Generator Inoperable Attachment 9.

STOP NUREG 1021 Rev 9 Appendix C

Appendix C Page 12 of 13 Form ES-C-1 Verification of Completion Job Performance Measure No.

R.A.2

~

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

ry/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 *,n,t,<:>tll".n When you complete the task successfully, the objective for this job performance measu INITIAL CONDITIONS:

Unit 3 and 4 are both in Mode 1 Preparations are in progress to perform a monthly test of the Unit 4 B 0 23.1 Diesel Generator Operability Test section 7.2.

Step 7.2.1 of 4-0SP-23.1 Diesel Generator Operability Test is complete.

INITIA TlNG CUE:

You are the Admin RO and you have been directed to the Unit 4 B Diesel Generator using 4-0SP-23.1 Di 7.2.2.

Acknowledge to the examiner when you are ready to NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet

_T-=-.u:::::..:rc:..:k:.=.eYL--=-.P--=o.:..:..i n:..:..t ___________ -- Task No:

Determine Required Actions

_f:...=o.:..:..r -=-:.1 n.:..::s:..::tr-=.u,,-,mc....:e:..:..n:...:..:ta:.:..:t.:...::io.:..::n--=F--=ac..:.:il...:c.u.:....:re=--_ J PM No:

KIA

Reference:

2.2.22 SRO 4.7 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Form ES-C-1 02049004300 S.A2 Simulated Performance X

Actual Performance

~----------

-~~~-~~~---

Classroom X

Simulator -------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discus,an complete the task successfully, the objective for this job perfor Initial Conditions:

Unit 4 is in Mode 1, 100% power.

Pressure transmitter PT-4-475 Steam Generat r Actions to stabilize Unit 4 have taken place.

4-0NOP-049.1, Deviation or Failure of Safety Rela step 5.4 Task Standard:

Required Materials:

Reactor Protection Channels NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 7 Initiating Cue:

You are the Unit 4 Unit Supervisor. Using 4-0NOP-049.1, Deviation or Failure of Reactor Protection Channels, complete the required action starting at step 5.5 to with Unit 4 Technical Specifications.

Time Critical Task: No Validation Time:

15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Page 3 of 7 Form ES-C-1 I SIMULATOR SETUP Reset to IC #

NUREG 1021 Rev 9 Appendix C I

Appendix C STEP 1

Standard:

Comment STEP 2

if Comment Page 4 of 7 Denote critical steps with a check mark( if)

Obtain a copy of 4-0NOP-049.1, Deviation or Failure of Safety Related Reactor Protection Channels.

(From the initiating cue.)

Copy of 4-0NOP-049.1, Deviation or Failure of Safety Protection Channels is obtained.

Provide a copy of 4-0NOP-049.1, Deviati or Reactor Protection Channels (4-0NOP-049.1 Examinee refers to Unit 4 id bles are requ and correctly both the following copy of Technical Specifications Sections 3/4 3.1 REACTOR INSTRUMENTATION and 3/4 3.2 ENGINEERED S ACTUATION SYSTEM INSTRUMENTATION.

e failed channel bistables is required to be placed in the tripped within six (6) hours of the failure determination.

Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 3

I Standard:

Comment NOTE:

Page 5 of 7 Determine bistables that are required to be tripped for the instrument malfunction (4-0NOP-049.1 step 5.11.1.1 and Attachment 4)

Examinee determines the following bisatables are required in TRIP:

P-4-475 Steam Generator A Pressure BS-4-474 Safeguards Logic AND BS-4-475 HI Steam Line ~P SI AND BS-4-478B-1 FW to SF Mismatch Logic Procedure NOTE

>fV',<>t",,,"I alarm to be placed in TRIP, TRIPPED in order to comply with Stop Time Form ES-C-1 I STOP NUREG 1021 Rev 9 Appendix C

Appendix C Page 6 of 7 Form ES-C-1 Verification of Completion Job Performance Measure No.

S.A.2

~

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

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 satisfied.

INITIAL CONDITIONS:

Unit 4 is in Mode 1, 50% power.

Pressure transmitter PT-4-475 Steam Generator A Pressure has failed.

Actions to stabilize Unit 4 have taken place 4-0NOP-049.1, Deviation or Failure of Safety Related or Reactor Protection 5.4

/NITIA TlNG CUE:

You are the Unit 4 Unit Supervisor. Using 4-0NO Reactor Protection Channels, complete the required Unit 4 Technical Specifications.

Acknowledge to the examiner when you are ready to begi YOU HAVE SK.

NUREG 1021 Rev 9 Appendix C

Appendix C Job Performance Measure Worksheet Form ES-C-1 Facility:

_T-,-u-,,-r-,-,k-=-ey~P_o_in-,-t _______ Task No:

02203001100 Task

Title:

Determine Allowable Stay Time & Determine

_R_ad_i_o_lo..... g_ic_a_1 _R_eq-,-u_i_re_m_e_n_t_s __ JPM No:

KIA

Reference:

2.3.7 RO 3.5 SRO 3.6 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

A.3 Simulated Performance X

Actual Performance

/-~r_-----~~~---

Classroom x

Simulator -------f Read to the examinee:

I will explain the initial conditions, which steps to simulate or discu,a complete the task successfully, the objective for this job perform a e

Initial Conditions:

cues. When you be satisfied.

Unit 3 is in MODE 5, making preparations for 0

4 ert~""

Clearance restoration from work on the Letdow pi *ng"i the "'t:tmt.3 Pipe Ive Room is in progress.

The work involved to remove the clearance will re uir kn to remove clearance tags.

You are holding a pre-job bri nd are discussing RWP requirements and ALARA concerns prior to c ration.

Task Standard:

ical Controlled Area, Operations Department, Plant 0 m Monthly Survey Map, Log # 08-5743 0 m Monthly Survey Map, Log # 08-5795 0-HPS-025.1, "

osting Requirements for Radiological Hazards" 0-ADM-600, "Radia Ion Protection Manual" 0-ADM-604, "Radiological Protection Guidelines and Practices" 0-HPS-020, "Radiation Surveys" 0-HPS-021, "Surface Contamination Surveys" 0-HPA-073 Hot Spot Tracking and Reduction Program NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 10 Form ES-C-1 Initiating Cue:

Using the initial conditions and required references determine the following:

What is the maximum allowable dose allowed by the RWP?

What is the maximum stay time based on the highest general area radiation in What is the minimum requirement for protective clothing?

What is the minimum required dosimetry required for entry into the area What is the area of highest surface contamination in the room?

Where is (are) the location of any hot spot(s) in the room?

Where is the lowest dose location in the room where the he/she is required to wait there?

Time Critical Task: No Validation Time:

20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of 10 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C STEP 1

Standard:

Comment NOTE:

STEP Comment Page 4 of 10 Denote critical steps with a check mark( I)

Obtain a copy of Radiation Work Permit 08-005, "Radiological Controlled Area, Operations Department, Plant Operations" and Unit 3 Pipe and Valve Room Monthly Survey Map, Log # 08-57 Copy of the RWP and Survey Map are obtained.

Provide a copy of the following:

Radiation Work Permit 08-005, "

Operations Department, Plant 0 PTN Unit 3 Pipe and Valve Room Monthly 5743 nes the maximum dose allowed by RWP 08-005 is ALL correct answers are provided on the JPM ANSWER SHEET Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 3

Standard:

Comment NOTE:

STEP 4

Standard:

Page 5 of 10 What is the maximum stay time based on the highest general area radiation in the room?

The examinee determines the maximum stay time is 2.5 h interpreting the RWP 08-005 requirements and the Unit 3 Valve Room survey map data.

The maximum stay time allowed u Pipe and Valve Room highest g 25 mrem (from RWP 08-005 maximum dose!

highest general area dose rate in the Unit 3 Pipe full protective clothing is required by uirements with the initial special instruction #1 requires a full set of protective done while kneeling or crawling in a Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

Appendix C STEP 5

./

Page 6 of 10 What is the minimum required dosimetry required for entry into the area?

The examinee determines the following dosimetry is req interpreting the RWP 08-005 and the Unit 3 Pipe and Valve survey map:

Form ES-C-1 Standard:

TLD Comment NOTE:

STEP 6

./

NOTE:

AND PAM or PEA RWP 08-005 spe PEA while entry' cm2 by interpreting the Unit 3 ata.

3 Pipe and Valve Room Monthly Survey Map, Log

18.

SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 7

Standard:

Comment STEP 8

Standard:

(

Comment Page 7 of 10 Where is (are) the location of any hot spot(s) in the room?

The examinee determines there is one hot spot in the Unit 3 Valve Room, between the Letdown pipe and the Contami boundary by interpreting the Unit 3 Pipe and Valve data.

Where is the lowest dose location in the C operator should stand in the event that he/she there?

The examinee Valve Room is and

.n\\A"or-IOTT area of the survey map by i map data.

Room survey inee returns the cue sheet to Stop Time Form ES-C-1 I SAT UNSAT STOP NUREG 1021 Rev 9 Appendix C

Appendix C Page 8 of 10 Form ES-C-1 JPM ANSWER KEY

1. What is the maximum allowable dose allowed by the RWP?

ANSWER: The maximum dose allowed by RWP 08-005 is 25 mrem.

2. What is the maximum stay time based on the highest general area radiation' ANSWER: The maximum stay time allowed under this RWP (based on Pipe general area dose) = (25 mrem I 10 mrem/hr) = 2.5 hr BASES:

25 mrem is the dose at which the DAD alarm is set 30 mrem/hr is the highest general area radiation Room survey map in the vicinity of Letdown p

3. What is the minimum requirement for protective clot ANSWER: A full protective clothing is required

4. What is the minimum required dosimetry required for entry ANSWER: The following dosimetry is required:

TLD PAM or PEA

5. What is the area of highest surface ANSWER: From the survey map, swi Valve Room (1594 dpm/100

6.

contamination in Unit 3 Pipe and Valve Room, between the Letdown pipe and

7.

inated Area where the operator should stand in the ose area in the Unit 3 Pipe and Valve Room is near the Contaminated Area of the survey map.

lowest general area dose in the Unit 3 Pipe and Valve Room is 1 mRlhr of the room (bottom left on the survey map). To minimize dose while wait in the lowest dose area in the room.

NUREG 1021 Rev 9 Appendix C

I Appendix C Page 9 of 10 Form ES-C-1 Verification of Completion

(

iJob Performance Measure No.

A.3

~

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

ry /U nsatisfactory 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 satisfied.

INITIAL CONDITIONS:

Unit 3 is in MODE 5, making preparations for MODE 4 entry.

Clearance restoration from work on the Letdown piping in the Unit 3 Pipe progress.

The work involved to remove the clearance will require kneeling and tags.

You are holding a pre-job brief with the Primary Operator and ALARA concerns prior to commencing the clearance re

!NITIA TlNG CUE:

Using the initial conditions and required references

1. What is the maximum allowable dose allowed by

2. What is the maximum stay time bas

3. What is the minimum requirement for

5.

ation in the room?

hot spot(s) in the room?

room?

dose location in the Contaminated Area where the operator should stand in the is required to wait there?

to the examiner when you are ready to begin.

VE SATISFACTORILY ANSWERED ALL THE QUESTIONS.

NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet Turkey Point Task No:

Complete a State Notification Form JPM No:

KIA

Reference:

2.4.39 RO 3.9

-=~~~~~-----------

Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Form ES-C-1 1001013400 R.A:4 Method of testing: -------------------------------------------;;r"'-_;;:--~-------

Simulated Performance X

Actual Performance

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

-~~r"'-----~~~-----

Simulator -------------

Classroom X

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discus,an complete the task successfully, the objective for this job perfor Initial Conditions:

The SIMULATOR is in Mode 3, an Emergency P The Reactor tripped due toa LOCA in the Conta The Emergency Coordinator declared a GENE The reason for the GENERAL EMERGENCY wa a Severe core damage has occurred.

Wind direction is from 120 Wind speed is 10 mph No radioactive release is in Protective Action Reco LL REMAINING sectors a *.

gency Notification Form is completed in accordance 0-EPIP-20134 ive Action Recommendations, with NO errors on items identified with O-EPIP-20134, s*

Notifications and Protective Action Recommendations FLORIDANUCLEAR PLANT EMERGENCY NOTIFICATION FORM General

References:

O-EPIP-20134, Offsite Notifications and Protective Action Recommendations FLORIDA NUCLEAR PLANT EMERGENCY NOTIFICATION FORM NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 7 Form ES-C-1 Initiating Cue:

You are the Shift Communicator, given the initial conditions, complete the Florida Nuclear Emergency Notification Form and hand it to the examiner when you are complete.

There is an element of this task that is time critical.

Time Critical Task: Yes Validation Time:

15 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT THIS NUREG 1021 Rev 9 Appendix C

(

I Appendix C Reset to IC #

N/A Page 3 of 7 Form ES-C-1 I SIMULATOR SETUP NUREG 1021 Rev 9 Appendix C

Appendix C STEP 1

Standard:

Comment Page 4 of7 Denote critical steps with a check mark( I)

Obtain a Florida Nuclear Plant Emergency Notification Form.

(From initiating cue.)

A Florida Nuclear Plant Emergency Notification Fo Provide a copy of a Florida Nuclear Plant F-439 and O-EPIP-20134, Offsite.T.T.

Recommendations Attachments 1 B Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 2

Standard:

Comment NOTE:

NOTE:

Page 5 of 7 Complete Florida Nuclear Plant Emergency Notification Form.

(O-EPIP-20134, Attachment 1 B)

(Turkey Point Nuclear Form F 439)

The examinee completes a Florida Nuclear Plant Form is with no errors noted on items annotated by a Step by step instructions for comp Emergency Notification Form are contained Offsite Notifications and Protective Action B.

The time critical elem is complete.

See the exam key for a inee returns the State Stop Time Form ES-C-1 STOP NUREG 1021 Rev 9 Appendix C

(

Appendix C Verification of Completion Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Examiner's signature and date:

Page 6 of 7 Form ES-C-1 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 satisfied.

INITIAL CONDITIONS:

The SIMULATOR is in Mode 3, an Emergency Plan Drill is in progress.

The Reactor tripped due to a LOCA in the Containment The Emergency Coordinator declared a GENERAL EMERGENCY at T The reason for the GENERAL EMERGENCY was a Large Break LOCA, Severe core damage has occurred.

Wind direction is from 120 Wind speed is 10 mph No radioactive release is in progress.

Protective Action Recommendations are as follows:

0-2 miles Evacuate ALL sectors 2-5 miles Evacuate (Sectors Affected). Shelter ALL.:

5-10 miles Shelter ALL Sectors INITIA TlNG CUE:

You are the Shift Commu Notification Form and hand it There is an element of this task that is Acknowledge to Nuclear Plant Emergency NUREG 1021 Rev 9 Appendix C

Appendix C Facility:

Task

Title:

Job Performance Measure Worksheet

_T_u-'-'r--'.-k-"-'ey"--P_o_in-'..t _______ Task No:

Classify the Event and Issue PARs JPM No:

KIA

Reference:

2.4.41 SRO 4.6 Examinee:

NRC Examiner:

Facility Evaluator:

Date:

Method of testing:

Form ES-C-1 01001013400 S.A.4 Simulated Performance X

Actual Performance

-~~~---4 Classroom X

=-=----

Simulator --------

Read to the examinee:

I will explain the initial conditions, which steps to simulate or discus complete the task successfully, the objective for this job perfor Initial Conditions:

The Simulator is In Mode 3 The Reactor tripped due to a LOCA in the Contal m The Unit Supervisor is transitioning to 3-EOP-E-1, 0

Sump Levels are responding as anticipated.

RCS Pressure is 1300 psig.

Both Trains of Safety Injection ha HHSI flow is 300 gpm Containment Pressure is 2 Both Trains of Contain t

Number 1 D is declared within 15 minutes of starting the 0-EPIP-20101, D S OF EMERGENCY COORDINATOR O-EPIP-20134, Offsite Notifications and Protective Action Recommendations General

References:

0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR O-EPIP-20134, Offsite Notifications and Protective Action Recommendations NUREG 1021 Rev 9 Appendix C

Appendix C Page 2 of 9 Initiating Cue:

You are the Emergency Coordinator, given the existing conditions in the simulator, cia using 0-EPIP-201 01, DUTIES OF EMERGENCY COORDINATOR and issue protec.

recommendations using O-EPIP-20134, Offsite Notifications and Protective Actio.

Recommendations.

There is an element of this task that is Time Critical.

Time Critical Task: Yes Validation Time:

20 minutes HAND JPM BRIEFING SHEET TO EXAMINEE AT Form ES-C-1 NUREG 1021 Rev 9 Appendix C

I Appendix C Reset to IC #

N/A Page 3 of9 SIMULATOR SETUP Form ES-C-1 I NUREG 1021 Rev 9 Appendix C

Appendix C

(

STEP 1

Standard:

Comment STEP 2

Standard:

Page 4 of 9 Denote critical steps with a check mark( J)

Obtain 0-EPIP-20101, DUTIES OF EMERGENCY COORDINATOR.

(From the initiating cue.)

0-EPIP-201 01, DUTIES OF EMERGENCY COOR obtained.

Provide a copy of O-EPI P-201 01, DUTI E COORDINATOR, Enclosure 1 Emerge Review 0-EPIP-201 (0-EPIP-201 01, Examinee reviews O-EPI CO TOR Enclosure eDlC;Iea in the initial Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 3

Standard:

Comment NOTE:

NOTE:

Page 5 of 9 Classify Off-Normal Event using present available information, AND declare the emergency classification using Enclosure 1.

(0-EPIP-201 01, Enclosure 1)

The examinee classifies the event as a General Emergen Number 1 D by interpreting the information given in the in conditions within 15 minutes of starting the JPM.

Procedure Caution; CAUTION: Consult 0- EPIP-20134, Attach Protective Action Recommendation The GE Classification is based on the following:

EAL number 10 iven in the in conditions AND e greater initial conditi of 300 gpm.

300 gpm.

J\\v'v;: );:) of 20 psig is given in the initial for the event classification here.

nues with the task to issue Protective Action commendations using O-EPIP-20134, Offsite Notifications and

'"\\TcrTI\\,C Action Recommendations. The critical time element Annotate the start time for the Protective Action Recommendations here.

Form ES-C-1 NUREG 1021 Rev 9 Appendix C

Appendix C STEP 4

Standard:

Comment STEP 5

Standard:

Page 6 of9 Obtain 0-EPIP-20134, Offsite Notifications and Protective Action Recommendations.

0-EPIP-20134, Offsite Notifications and Protective Action Recommendations or equivalent is obtained.

Provide a copy of form F-444, Offsite Not"T'"T

Action Recommendations, and form F-439 Review 0-EPIP-20134, Offsite Notifications and P Recommendations.

(0-EPIP-20134, Examinee reviews O-EPI Notifications and Prote F-444, Offsite Form ES-C-1 SAT UNSAT NUREG 1021 Rev 9 Appendix C

I Appendix C STEP 6

I Standard:

Comment NOTE:

(

NOTE:

Page 7 of 9 Issue Protective Action Recommendations.

(0-EPIP-20134, Attachment 3 Note 1)

Examinee determines the following Protective Action Recommendations for Actual or Projected Core Damage interpreting the information given in the initial conditi withi minutes of starting the JPM:

0-2 miles SHELTER ALL sectors 2-5 miles SHELTER Sectors N, P & Q.

5-10 miles NO ACTION.

Protective Action R General Emerg in the initial co ions are based on the Recommendations the protective action Examinee returns the cue sheet to Stop Time Form ES-C-1 STOP NUREG 1021 Rev 9 Appendix C

Appendix C Verification of Completion Job Performance Measure No.

Examinee's Name:

Examiner's Name:

Date Performed:

Facility Evaluator:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Page 8 of 9 Form ES-C-1 C 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 satisfied.

INITIAL CONDITIONS:

The Simulator is in Mode 3 The Reactor tripped due to a LOCA in the Containment The Unit Supervisor is transitioning to 3-EOP-E-1, Loss of Reactor or Sump Levels are responding as anticipated.

RCS Pressure is 1300 psig.

Both Trains of Safety Injection have actuated.

HHSI flow is 300 gpm Containment Pressure is 25 psig and rising slowly Both Trains of Containment Spray have actuated and Adverse conditions exist in the Containment No radioactive release is in progress.

Wind speed is 10 mph Wind direction is from 120 INITIA TlNG CUE:

You are the Emergency Coord using 0-EPIP-201 01, DUTIE recommendations using 0-ulator, classify the event protective action and Protective Action Recommendations.

NUREG 1021 Rev 9 Appendix C

ML091740128

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