ML032940455

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August Exam 50-302/2003-301 Draft JPMs & Outlines
ML032940455
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/29/2003
From:
NRC/RGN-II
To:
Progress Energy Florida
References
50-302/03-301 50-302/03-301
Download: ML032940455 (176)


See also: IR 05000302/2003301

Text

Draft Submittal

(Pink Paper)

CRYSTAL RIVER AUGUST

EXAM 50-30212003-301

AUGUST 25 - 29,2003

1.

2.

3.

4.

5.

I

Administrative Questions/JPMs

In-plant JPMs

Control Room JPMs (simulator JPMs)

Administrative Topics Outline ES-301-1

Control Room Systems and Facility Walk-Through

Test Outline ES-301-2

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminEPl (2K3) NRC [New] (ADMINISTRATIVE)

RO ONLY

ALTERNATE PATH

COMPLETE THE STATE OF FLORIDA NOTIFICATION MESSAGE

FORM FOR NUCLEAR POWER PLANTS

PREPARED/REVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

1

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ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

-

Task: Complete the State of Florida Notification Message Form for Nuclear Power Plants.

Alternate Path: Yes

AdminEPl(2K3) NRC [New]

K/A Ratinflmportance: G2.4.43 RO 2.8

Task Number: 1 IS0402005

Task Standard:

Complete the State of Florida Notification Form and make required

notifications per EM-202.

Preferred Evaluation Location:

Simulator -

IrrPlant -

Admin

References:

EM-202, Rev. 71

Validation Time: 15 min.

Time Critical: No

Preferred Evaluation Method:

Perform X Simulate -

Candidate:

Time Start :

Printed Name

Time Finish

Performance Ratins SAT

UNSAT

Performance Time :

Examiner:

I

Printed Name

Signature

Date

Comment:

1/18/2003

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

NONE

SIMULATOR BOOTH OPERATOR INSTRUCTIONS:

Do not answer the SHRD phone when called. Answer the commercial line when called and perform

roll call.

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ToolslEquipmentmrocedures Needed:

copy of EM-202

Simulator and booth operator are required for this JPM.

READ TO THE OPERATOR

Directions to the Student :

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this P M . I will provide initiating cues and reports on

other actions when directed by you. Ensure you indicate to me when you understand your assigned

task. To indicate that you have completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Reactor Operator.

A Site Area Emergency has been declared due to a SGTR concurrent with a loss of condenser vacuum

at time NOW.

Fission Product Barrier Matrix: 1) Potential Loss of RCS and 2) Loss of Containment.

There are no injuries reported.

Wind direction is from 220 degrees.

Adequate SCM does exist.

No Protective Action Recommendations at this time.

The event has not been terminated.

Initiating Cues:

Using the above information complete the Florida Nuclear Plant Emergency Notification Form and

make required notifications per EM-202.

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-1:

Candidate completes the Florida Nuclear Plaht Emergency

Notification Form.

STANDARD: Candidate completes the notification form correctly. Candidate should

determine for Section IO) a release is occurring and for Section 11)

release category is C. Non-significant, from page 7 of Enclosure 2.

EXAMINERS NOTE:

Critical information on this form includes sections

4,12 and 13. Leaving any other section blank does

not constitute failure of this step

COMMENTS:

-2:

Candidate makes required notifications.

STANDARD: Candidate makes required notifications. When the SHRD phone goes

unanswered the candidate will use the commercial telephone system,

contact SWPT and complete the notification.

EXAMINERS NOTE:

Page 3 of Enclosure 2 contains the instructions for

using an alternate communication network.

COMMENTS:

TERMINATION CRITERIA When candidate completes notification to SWPT

this JPM may be terminated.

END OF TASK

Critical Step

SAT -

JNSAT -

Critical Step

SAT -

JNSAT -

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Reactor Operator.

A Site Area Emergency has been declared due to a SGTR concurrent with a bss of condenser vacuum

at time NOW.

Fission Product Barrier Matrix: 1) Potential Loss of RCS and 2) Loss of Containment.

There are no injuries reported.

Wind direction is from 220 degrees.

Adequate SCM does exist.

No Protective Action Recommendations at this time.

The event has not been terminated.

Initiating Cues:

Using the above information complete the Florida Nuclear Plant Emergency Notification Form and

make required notifications per EM-202.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminCOl(2K3) NRC [Newl (ADMINISTRATIVE)

DETERMINE METHOD FOR CHEMISTRY SAMPLING

WITH A LOOP IN PROGRESS

PREPARED/REVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

1

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ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

Task: Determine method for chemistry sampling during a LOOP.

Alternate Path: No

JPM #: AdminCOl(2K3) NRC [New]

WA Ratindmportance: G2.1.24 RO 2.8

Task Number:

Task Standard:

Preferred Evaluation Location:

Simulator -

In-Plant -

Admin

References:

SRO 3.1

Preferred Evaluation Method:

Perform X Simulate -

Candid at e :

Printed Name

Time Start :

Time Finish

Performance Rating: SAT

UNSAT

Performance Time :

Examiner:

I

Printed Name

Signature

Date

2

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.

ToolsEquipmentErocedures Needed:

The following prints are required 302-752 Sheet 1,302-753 Sheet 1,208-005 AH-OSB, 208-005 AH-

85,208-005 AH-89,208-005 AH-99

Additional prints t h t may be included (not required): 208-005 AH-05,208-005 AH-05A, 208-005

AH-88,208-005 AH-98

READ TO THE OPERATOR

Directions to the Student :

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and reports on

other actions when directed by you. Ensure you indicate to me when you understand your assigned

task. To indicate that you have completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Reactor Operator.

The plant is in Mode 5.

The A ES buses and the A Unit buses were de-energized for maintenance and are unavailable.

A LOOP has occurred.

B EDG is powering the B ES buses.

AHD-34 is in its normal failed open position.

ACDP-20 is energized.

Initiating Cues:

Chemistry sampling is required. Using the furnished material determine the following:

Fans that must be started to support sampling. Record below.

For all solenoid operated dampers in the flowpath determine the solenoid valve (SV) number

that must be energizedde-energized for the dampers to open. Record SVs and dampers below.

Fans

sv

for dampers

sv

for dampers

sv

for damper

3

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m:

Candidate determines correct fans, dampers and solenoid valve

numbers required for Chemistry sampling during a LOOP.

STANDARD: Utilizing the flow diagrams and electrical prints the candidate will

determine the correct flowpath, fans and solenoid valve numbers

needed to establish an exhaust lineup for Chemistry sampling when a

LOOP is in progress.

EXAMINERS NOTE:

Requirements for this critical step are correct fan

determination and correct damper determination.

An incorrect solenoid valve number does not

constitute failure of this step

Fan(s)

AHF-20B & AHF-44B

SV AH-406-SV for damper

AHD-100 .

SV AH-252-SV fordamper

AHD-20

.

SV AH-252-SV fordamper

AHD-21

.

SV AH-923-SV for dampers AHD-38,39.42 & 43 .

COMMENTS:

END OF TASK

Critical Step

SAT _.

LJNSAT -

4

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Reactor Operator.

The plant is in Mode 5.

The A ES buses and the A Unit buses were de-energized for maintenance and are unavailable.

A LOOP has occurred.

B EDG is powering the B ES buses.

AHD-34 is in its normal failed open position.

ACDP-20 is energized.

Initiating Cues:

Chemistry sampling is required. Using the h i s h e d material determine the following:

Fans that must be started to support sampling. Record below.

For all solenoid operated dampers in the flowpath determine the solenoid valve (SV) number

that must be energizedde-energized for the dampers to open. Record SVs and dampers below.

sv

for dampers

sv

for dampers

sv

for damper

5

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminEP2 (2K3) NRC [New] (ADMINISTRATIVE)

SRO ONLY

DETERMINE EMERGENCY ACTION LEVEL

PREPAREDREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

1

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ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

Task: Determine emergency action level for given plant conditions.

Alternate Path: No

JPM #: AdminEP2 (2K3) NRC [New]

K/A Ratine/Importance: G2.4.41 SRO 4.1

Task Number: 1150101002

Task Standard: Determine emergency action level for given plant conditions using EM-202.

Preferred Evaluation Location:

Simulator -

IrrPlant -

Admin X

References:

EM-202, Rev. 71

Validation Time: 10 min.

Time Critical: No

Preferred Evaluation Method:

Perform J-

Simulate -

Candidate:

Time Start :

Printed Name

Time Finish

Performance Rating: SAT

UNSAT

Performance Time :

Examiner:

/

Printed Name

Signature

Date

Comment:

2

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

None

SIMULATOR OPERATOR INSTRUCTIONS:

1.

None

3

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Tools/Equipment/Procedures Needed:

1. EM-202

READ TO THE OPERATOR

Directions to the Student :

I will expfain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and

reports on other actions when directed by you. Ensure you indicate to me when you understand

your assigned task. To indicate that you have completed your assigned task, return the handout

sheet to the examiner.

Initial Conditions :

You are the Superintendent, Shift Operations.

Initiating Cues:

Determine the highest emergency action level for Scenario #2.

4

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711 W O O 3

Candidate determines classification based on Scenario #2.

STANDARD: Candidate determines the classification is a Site Area Emergency.

Loss of Containment (2 points) #3 - An OTSG has > 10 gpm tube

rupture with prolonged steaming to the atmosphere from the affected

OTSG

Potential Loss of RCS (3 points) #I - OTSG tube leak requiring one

or more injection valves.

EXANINERS NOTE: If the scenario deviated from the above conditions then

the lead examiner will determine the correct emergency

action level.

COMMENTS:

END OF TASK

Critical Step

SAT -

JNSAT -

5

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Superintendent, Shift Operations.

Initiating Cues:

Determine the highest emergency action level for Scenario #2.

6

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminECl (2K3) NRC [Bank #283] (ADMINISTRATIVE)

PERFORM RCS WATER INVENTORY BALANCE PER SP-317

PREPAREDREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY

Date:

(Nuclear Training Supervisor)

ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

1

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-

Task: RO - Perform a Reactor Coolant System inventory balance

SRO - Perform safety and technical reviews of plant procedures

Alternate Path: No

JPM: AdminECl (2K3) NRC [Bank #283]

K/A Ratindmportance:

G2.2.12 RO 3.0 SRO 3.4

G2.1.12 SRO 4.0

Task Number/Position:

0020202004 RO

1190101029 SRO

Task Standard: Perform a Reactor Coolant System inventory balance per SP-317.

Preferred Evaluation Location:

Simulator __ IPPlant -

Admin

X

Perform

X

Simulate-

References:

SP-3 17, Rev. 59

Validation Time: 20 min.

Time Critical: NO

Preferred Evaluation Method:

............................................................

Candidate:

Time Start :

Printed Name

Time Finish

Performance Rating: SAT __ UNSAT - Performance Time :

Examiner:

/

Printed Name

Signature

Date

Comment:

2

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Tools/Equipment/Procedures Needed:

1.

SP-317

2.

SRO Only - TS located in exam room

READ TO THE OPERATOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. Ensure you indicate

to me when you understand your assigned task. To indicate that you have completed your

assigned task, return the handout sheet to the examiner.

Initial Conditions:

You are the Reactor Operator

The current time is 0400 on this date.

The plant has been at steady state conditions (100%) for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Relevant plant data is supplied in enclosure one of this JPM.

Plant computer is operable.

Initiatinp Cues:

Using the data supplied, complete a RC System Water Inventory Balance for the period

from 0000 to 0400. Where appropriate, assume that independent reviews have been

completed.

Completion of the following satisfies the requirement to inform the Control Room

Supervisor of your results.

Primary-to- Secondarv Leakage

Identified Leakage

Unidentified Leakage

Controlled Bleed Off

gpm

gum

gPm

EPW

7 -

I

3

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jTEP:

(step 4.1.1)

Zrocedure Note: Dumpster readings are not required if RCV- 150 is open and RCDT

eve1 indication is being used.

Record the following data on Enclosure 1:

Record the instruments selected as sources

Starttime

RCDT Level and Start time

Pressurizer Level

Tave

MUTLevel

RCSPressure

STANDARD:

EXAMINERS NOTE:

Data is recorded on Enclosure 1.

The candidates should use the preferred points for

this surveillance (displayed in bold type) per Step

3.2.2.1.

ZOMMENTS :

STEp:

(step 4.1.2)

Determine and record individual RCP CBO flow.

STANDARD:

Data is recorded on Enclosure 1.

COMMENTS:

STEp: (step 4.1.3)

Obtain and record RCP standpipe flushwater flow rate.

STANDARD:

Data is recorded on Enclosure 1.

COMMENTS:

4

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SAT __

UNSAT -

SAT __

UNSAT -

SAT __

UNSAT -

-4:

(step 4.1.4)

Record component identified leakage.

STANDARD:

COMMENTS:

Data is recorded on Enclosure 1.

-5:

(step 4.1.5)

Obtain Primary to Secondary leakage data and record on Enclosure 1.

STANDARD:

COMMENTS:

Data is recorded on Enclosure 1.

-6:

(step 4.2.2)

Record the following data on Enclosure 1 :

Stop time

RCDT level and stop time

RCP Seal leakage, if applicable

Pressurizer Level

Tave

MUTLevel

RCS Pressure

-

STANDARD:

COMMENTS:

Data is recorded on Enclosure 1.

-7:

(step 4.3.1 )

Calculate the test run time

STANDARD:

COMMENTS:

Per the cue the run time is 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (240 minutes)

5

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SAT __

JNSAT -

SAT __

UNSAT -

SAT _.

UNSAT -

STEP: (step 4.3.2)

Complete Section B of Enclosure 1.

STANDARD:

Values should be within ? .I gpm of value listed on attached

key.

COMMENTS:

-9:

(step 4.3.3)

Calculate total seal leakage, if applicable.

STANDARD:

Not applicable. RCV-150 open.

COMMENTS:

STEP 10: (steps 4.3.4 thru 4.3.7)

Complete Section D of Enclosure 1.

STANDARD:

Values should be within ? .I gpm of value listed on attached

key.

COMMENTS:

STEP 11 : (step 4.3.8)

Total the identified component leakages in Section E of Enclosure 1

Values should be within 2 .I gpm of value listed on attached

key.

STANDARD:

COMMENTS :

6

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SAT __

UNSAT -

SAT -

UNSAT -

SAT -

UNSAT -

SAT -

UNSAT -

STEP 12: (step 4.3.9)

Calculate RCP Seal Leakage Collection Point leakage in Section F of

Enclosure 1.

STANDARD:

Value should be within 2 .l gpm of value listed on attached

key.

COMMENTS:

STEP 13: (step 4.3.10)

Calculate RCS Leakages in Section G of Enclosure 1

STANDARD:

Values should be within 2 . 1 gpm of value listed on attached

key.

COMMENTS:

STEP 14: (step 4.3.11)

Perform an independent review of all calculations on Enclosure 1

N/A. Per the cue all independent reviews are considered

complete.

STANDARD:

COMMENTS:

STEP 15: (step 4.3.12)

INFORM the Control Room Supervisor of the completion and the

results of this procedure.

EXAMINERS NOTE:

This step is finished by completing the data form

provided with the cue supplied to the candidate.

STANDARD:

Calculation results are ?z .1 gpm of the values listed on the

attached key.

COMMENTS:

7

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SAT __

UNSAT -

SAT -

UNSAT -

SAT -

UNSAT -

Critical Step

SAT __

UNSAT -

STEP 16: (SRO only)

STANDARD:

SRO candidates should review TS and determine the required

actions and time frames for the calculated results.

TS 3.4.12 - Reduce leakage to within limits in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

END OF TASK

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Critical Step

(SRO ONLY)

SAT -

UNSAT -

RCS LEAKAGE CALCULATION

ENCLOSURE 1

A,=:

RCP-1A

RCP-1B

-22

X923

(Page 1 of 3)

RCP-IC

RCP-ID

X924

X925

Start datehime

10000

Stop date/time

/ 0400.

Run time (time difference between A1 and A2) 240 min

1.440

1 1.365

1.540

B.RCDRAINTANK:

1.660

C. RCP SEALS:

1) CONTROLLED BLEED OFF

RC-134-FZ

RC-135-FZ

RC-136-FZ

a)

controlled bleed off

b)

total of all pumps

RC-137-FZ

2) DUMPSTER FLOWS

NR

NR

NR

dumpster reading at stop

time

a)

NR

b)

dumpster reading

at start time

c)

dumpster difference

(C2a minus C2b)

NR

NR

d)

dumpster conversion

(galslclick)

NR

NR

NR

NR

NR

NR

e)

dumpster flow-rate

t)

standpi eflush

g)

RCP seal leaka e

(C2c x C2dA3) gpm

water Row-rate gpm

~ 2 e

minus ~

2

8

gpm

0.25

NR

h)

total RCP seal leakage

Pf

oral 4RCPs)

m SUM of C2g values

0.25

0.25

0.25

NR

NR

NR

.05

NR

.05

.05

.05

NR

NR

NR

~

9

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ENCLOSURE 1

(Page 2 of 3)

D.RCS INVENTORY CHANGES : (NOTE: If no change is observed, N/A

respective correction factor.)

R762

RCS PRESSURE

Measurement source

Pressure at start time (Round to whole number)

146

psig

2146 pslg

Pressure at stop time (Round to whole number)

8 Average pressure

2146 PS%

PRESSURIZER (Use computer point R874 or RECL66 for leak rates < 4 hrs in duration)

Measurement source

-

Level at start tnne

LLL. /u5

--

T ,... -1

A+ m+,.-

+;-.a

9

R874

in.

-.

1.993

". m

7A22.F gal.

I-".

. - -

-

-

L G V G l a r o r v y Llll'"

i

Level chany p2[ minus D2c)

X

12.21 gaVin. (Enclosure 3)

-

Correction ac or Round Dld to closest value)

Inventory change D22 -'

Tavg (Use RECL16 or computer point R731 for leak rates < 4 hrs in duration)

Measurement source

R73 1

b)

Temperature at start time

579.102"F

c)

Temperature at stop time

?

579.107'F

-0.005 "F

579.10 "F

-

d)

Temperature change (D3b minus D3c)

-

e)

Average temperature ([D3b + D3c] + 2)

-

-

f)

Correction factor (Based on D3e)

X

96.51

gaWF

p % % n t o r y change (D3d x D3f)

-

-

-0.483 gal.

4)

MAKEUP TANK (Use computer point X359 for leak rates < 4 hrs in duration)

Measurement source

8

Level at start time

Level at stop time

Level chan e (D4b minus D4c)

Inventory change (D4d x D4e)

Correction f actor

x359

.

88.102

7

70.110 m.

m

1 l . V G In

x 30.85

gayin.

-

-

555.053 gal.

-

-

5)

a) Additions

total

WATER ADDITIONS OR REMOVALS (Do not add or remove inventory for leak rates < 4 hrs in

duration)

f

+

+

=

0

gal.

-+-

- - -

b) Removals

total

-+-

-+-

-

+

+

=

0 gal.

6)

TOTAL INVENTORY RATEGOF-CHANGE

(D2f minus D3g plus D4f plus D5a minus D5b) / A3

( 24.335

-- -0.483 + 555.053

+

0

--

0 ) / 240

=

2.416

gpm

10

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E.

COMPONENT IDENTIFIED LEAKAGE

ENCLOSURE 1

(Page 3 of 3)

To obtain leakage i n "gpm", multiply the number of drops per minute by

1.67 x 10

(0.0000167).

Do not round the individual component leakages.

Component

Leakage Rate

DHV-4

,00025

epm

MUV-27

,0008.5

gpm

epm

gam

epm

gpm

gpm

Total component leakage rate

A

p

m

F. RCP SEAL LEAKAGE COLLECTION POINT: WOCS 0404861

Sump (RCV-150 Closed (otherwise N/A)

CDT rate of change plus 4

otaI RCP seal leakage)

B 10 plus C2h)

m

p

r

n

RC Drain Tank (RCV- 150 0 en) (otherwise N/A

w

p

m

&DT

rate of change ""us

Tota P of RCP standpipe tl ush

water flowrates) (B10 rmnus C2

(C2f=RCP-lA+RCP-lB +RC$-lC+RCP-lD)

G.RCS LEAKAGES [NOCS 0005971

Leakage (from Chem. Dept.)

m a p m

2)

Identified Leakage E lus F plus G1)

w a p m

(Round to hundredt LP

s round to tenths if using analog instruments) Fpm

then round to hundredt I, dround to tenths &sing analog instruments

3)

Unidentified Leakage D6 minus [E plus F lus Gl]

4)

Controlled Bleed Off Clb)

6 . 0 1 p m

(Round to hundredths I round to tenths if using Enclosure 4)

Performed By (Start)

Time

Date

Performed By (Stop)

Time

Date

Independently Reviewed By

Time

Date

11

F\\2003 NRC Exam\\JPMs\\AdminECl (2K3) NRC [Bank #283].doc

7/18/2003

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UNPON COMPLETION OF TASK)

Initial Conditions:

You are the Reactor Operator

The current time is 0400 on this date.

The plant has been at steady state conditions (lOOYo) for the past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Relevant plant data is supplied in enclosure one of this JPM.

Plant computer is operable.

Initiating Cues:

Using the data supplied, complete a RC System Water Inventory Balance for the period

from 0000 to 0400. Where appropriate, assume that independent reviews have been

completed.

Completion of the following satisfies the requirement to inform the Control Room

Supervisor of your results.

SROs only: Upon completion of the above, evaluate your results and list any actions

required per Technical Specifications. Include applicable time requirements.

Per TS

VS number) the actions below must be completed within

hours.

12

F:\\2003 NRC Exam\\JPMs\\AdminECl (2K3) NRC [Bank #283].doc

7/18/2003

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminC02 (2K3) NRC [Modified Bank #282] (ADMINISTRATIVE)

PERFORM A DAILY HEAT BALANCE COMPARISON, SP-312A

PREPAREDIREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

1

F\\2003 NRC Exam\\JPMs\\AdminC02 (2K3) NRC [Modified Bank #282].doc

7/18/2003

3:49AM

ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

-

Task: RO/SRO - Perform a Daily Heat Balance Power Comparison, SP-3 12A

SRO - Perform safety and technical reviews of plant procedures

Alternate Path: No

-

JPM #: AdminC02 (2K3) NRC [Modified Bank #282]

K/A Ratinflmportance:

G2.1.23 RO 3.9 SRO 3.1

G2.1.12 SR04.0

Task Number/Position:

0150202003 RO

1190101029 SRO

Task Standard Perform a Daily Heat Balance Power Comparison, SP-312A

Preferred Evaluation Location:

Simulator __ In-Plant -

Admin

X

Perform

X

Simulate-

References:

SP-312A Rev. 14

Preferred Evaluation Method:

Validation Time:

20 min.

Time Critical:

No

Candidate:

Time Start:

Printed Name

Time Finish

Performance Rating: SAT -

UNSAT -

Performance Time :

Examiner:

I

Printed Name

Signature

Date

Comment:

2

F\\2003 NRC Exam\\JPMs\\AdminC02 (2K3) NRC [Modified Bank #282].doc

7/18/2003

3:49AM

Tools/Equipment/Procedures Needed:

SP-312A Rev. 14

READ TO THE OPERATOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. Ensure you indicate to me when

you understand your assigned task. To indicate that you have completed your assigned task, return the

handout sheet to the examiner.

INITIAL CONDITIONS:

You are the Reactor Operator.

SP-312A is being done to coq., with the daily

SP-312A Report was obtained and all points are displaying good data.

The plant has been at steady state conditions for > 15 minutes.

The plant computer and AULD are operable.

Control Console NI power is as follows: NI-5, 100; NI-6, 100; NI-7, 100; NI-8, 100.

requirements.

INITIATING CUES:

You are requested to perform SP-312A. Circle (on Enclosure 1) any calculations which are

unacceptable and record the step numbers for any required actions and/or reviews below.

Group 59 and Group 108 attached.

SROs only: Upon completion of the above, evaluate your results and list any actions required per

Technical Specifications. Include applicable time requirements.

Per TS

(TS number) the actions below must be completed within

hours.

3

F\\2003 NRC Exam\\JPMs\\AdminCOZ (2K3) NRC [Modified Bank #282].doc

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3:49AM

STEP:

(step 4.1)

Ifthe plant computer is available, then go to Step 4.2.

STANDARD:

COMMENTS:

Plant computer is available per cue. Candidate moves to Step 4.2

STEP 2:

(step 4.2)

Obtain an SP-312A Report.

STANDARD:

COMMENTS:

N/A. SP-312A Report was supplied to the candidate.

STEp:

(step 4.3)

Compare the following points to the SP-312A Report.

STANDARD:

COMMENTS:

N/A. SP-312A report is satisfactory per the cue.

STEp:

(step 4.4)

Obtain Group 59, Reactor Core Parameters from the plant computer

STANDARD:

COMMENTS :

N/A. Group 59 was supplied to the candidate.

SAT -

UNSAT -

SAT -

UNSAT -

SAT -

UNSAT -

SAT -

UNSAT -

4

F\\2003 NRC Exam\\JPMs\\AdminCOZ (2K3) NRC [Modified Bank #282].doc

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3:49AM

-5:

(step 4.5)

Record the NI power values for NI-5, NI-6, NI-7, and NI-8 from Group

59 or SP-312D on Enclosure 1 under Column B designated "NI power."

STANDARD:

Candidate accurately transfers data from the group 59 printout to

Enclosure 1.

COMMENTS:

-6:

(step 4.6)

Record the value for Reference Core Power (QCORE) from Group 59 or

% RTP from SP-312D on Enclosure 1 under Column A as the heat

balance power.

STANDARD:

Candidate accurately transfers data from the group 59 printout to

Enclosure 1.

COMMENTS:

STEP 7:

(step 4.7)

Record Control Console indications for NI-5, NI-6, NI-7, and NI-8 on

Enclosure 1 under Column C designated "Control Console NI Power."

STANDARD:

Candidate accurately transfers data from information supplied in

initial conditions to Enclosure 1.

COMMENTS:

SAT __

3NSAT -

SAT __

JNSAT -

SAT __

JNSAT -

5

F\\2003 NRC ExaAJPMs\\AdminCOZ (2K3) NRC [Modified Bank #282].doc

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3:49AM

-8:

(step 4.8)

Perform the calculations for comparing the heat balance power to the NI

power for each channel on Enclosure 1.

STANDARD:

Candidate accurately calculates values indicated on Enclosure 1.

Candidate identifies that NI-7 meets Criteria #2 and refers to

Step 5.2.2 and candidate also identifies that NI-6 meets Criteria

  1. 3 and refers to Step 5.2.1 for required actions.

SRO candidates also determine TS 3.3.1 requires the affected

RPS channel (B) be placed either in trip or bypass within one

hour.

COMMENTS:

STEp:

(step 4.9)

Perform the calculations for comparing the Control Console NI power to

the heat balance power and the NI power on Enclosure 1.

STANDARD:

Candidate accurately calculates values indicated on Enclosure 1.

COMMENTS:

STEP 10:

(step 4.10)

If Gross Electric Megawatts (E700) is available then record Gross W

e

and Average Circulating Water Inlet Temperature (A857) on Enclosure

2.

STANDARD:

Candidate accurately records values indicated on Enclosure 2.

COMMENTS:

Critical Step

SAT -

LJNSAT -

$AT -

JNSAT -

6

F\\2003 NRC Exam\\JPMs\\AdminC02 (2K3) NRC [Modified Bank #282].doc

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3:49AM

STEP 11 :

(step 4.1 1)

Using the values recorded in Step 4.10, and NI power from Enclosure 1,

determine if MWe versus NI Power is in the acceptable band of

Enclosure 2.

STANDARD:

Candidate accurately calculates values indicated on Enclosure 2

and determine that the values are within the acceptable band.

COMMENTS:

STEP 12:

(step 4.12)

If HP Turbine First Stage Pressure (T226) is available, then record it on

Enclosure 3.

STANDARD:

Candidate accurately records values indicated on Enclosure 3.

COMMENTS:

STEP 13:

(step 4.13)

. Using the values recorded in Step 4.12, and NI power from Enclosure 1,

determine if HP Turbine First Stage Pressure versus NI power is in the

acceptable bank of Enclosure 3.

STANDARD:

Candidate accurately calculates values indicated on Enclosure 3

and determines they are outside of the acceptable region. Per

Step 5.2.7.1 the candidate should notify the CRSISSO and

Reactor Engineering or System Engineering that the heat balance

is suspect.

COMMENTS:

END OF TASK

SAT __

JNSAT -

SAT -

JNSAT -

SAT -

JNSAT -

7

F\\2003 NRC Exam\\JPMs\\AdminC02 (2K3) NRC [Modified Bank #282].doc

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3:49AM

r - r - r - r -

E

9 9 9 9

4 4 4 4

II

II

II

I1

II

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

SP-312A is being done to comply with the daily 0200 requirements.

SP-312A Report was obtained and all points are displaying good data.

The plant has been at steady state conditions for > 15 minutes.

The plant computer and AULD are operable.

Control Console NI power is as follows: NI-5, 100; NI-6, 100; NI-7, 100; NI-8, 100.

INITIATING CUES:

You are requested to perform SP-312A. Circle (on Enclosure 1) any calculations which are

unacceptable and record the step numbers for any required actions andor reviews below.

Group 59 and Group 108 attached.

SROs only: Upon completion of the above, evaluate your results and list any actions required per

Technical Specifications. Include applicable time requirements.

Per TS

(TS number) the actions below must be completed within

hours. '

F:\\2003 NRC Exam\\JPMs\\AdminCOZ (2K3) NRC [Modified Bank #282].doc

7/18/2003

07/09/03

GROUP 59 REACTOR CORE PARAMETERS

10:19:00 AM

CORE POWER IMBALANCE TOP - BOTTOM, %FP

INCORE

NE5

NI-6

NI-7

NI-8

NI POWER, Yo

NIA

99.29

98.01

98.78

99.37

IMBALANCE, YoFP

-3.60

-4.56

-4.20

-4.01

-3.65

CALC IMBALANCE LIMITS

NEG=-18.29

POS=15.54

CORE POWER TILT=((QUAD POW/AVG QUAD POW)-1)*1OO=Yo

WXQUAD

XYQUAD

YZQUAD

ZWQUAD

INCORE SYM DET, Yo=

-1.56

-1.19

1.92

1.07

OUTCORE IN DET, Yo=

.26

.14

-.35

-.05

CALC TILT LIMITS, Yo=

CONTROL ROD WITHDRAWAL INDEXES, %WD = 289.97 GPS 5,6,7

CALC GP 5,6,7 INDEX LIMITS, %WD MIN

266.71 MAX

305.00

4.16 STEADY STATE, 10.03 TRANSIENTS

%WD = 32.85 GP 8 (APSR)

CALC GP 8 INDEX LIMIT, %WD MIN -1.00

MAX =z 105.00

BACKUP REF. CORE POWER (PPCS QCORE)=2568.8 MWT=100.03?40 FP (2 MIN)

BACKUP (PPCS) SHIFT AVG CORE POWER (ANY POWER) = 2564.8 MWT

AULD INSTANTANEOUS CORE POWER = 2569.7 MWT

AULD SHIFT AVG CORE POWER = 2568.0

F\\2003 NRC Exam\\JPMs\\AdminCOZ (2K3) NRC [Modified Bank #282].doc

7/18/2003

GROUP 108 -PLANT STATUS

E21 1 GENERATED MEGAWATTS

E700 UNIT 3 GROSS GEN TEN (MW)

T228 2A MAIN STEAM TO TURB PRESS

T226 HP TURB FIRST STAGE PRESS

X208 MAKE U p TANK TEMP

A857 CW INLET AVE TEMP

A858 CW OUTLET AVE TEMP

G200 GENERATOR HYDROGEN PRESURE

G216 STATOR COIL DIS GAS TME, RTD 1A

G2 19 AVERAGE COLD GAS TEMPERTURE

T215 CONDENSER VACUUM (TN-HGA)

875.50

875.30

897.22

720.72

2.86709

119.984

88.2

104.9

60.205

72.703

44.354

F\\2003 NRC Exam\\JPMs\\AdminC02 (2K3) NRC [Modified Bank #282].doc

Mw

MEGAWA

PSIG

PSIG

DEG F

DEG F

DEG F

PSIG

DEG C

DEG C

Ifig

7/18/2003

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

AdminRCl(2K3) NRC [NEW] (ADMINISTRATIVE)

SRO ONLY

DETERMINE EXTERNAL REPORTING REQUIREMENTS

PREPARED/REVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F\\2003 NRC Exam\\JPMs\\AdminRCl (2K3) NRC [New].doc

7/18/2003

ATTACHMENT 8

ADMINISTRATIVE JOB PERFORMANCE MEASURE

-

Task: Determine External Reporting Requirements

Alternate Path: No

JPM #: AdminRC 1 (2K3) NRC mew]

WA RatingKmportance: G2.3.1 SRO 3.0

Task NumberE'osition: 1190101035 SRO

Task Standard: Determine External Reporting Requirements per CP-151

Preferred Evaluation Location:

Simulator-

Plant -

A d m i n L

References:

CP-151, Rev. 13

lOCFR

Validation Time: 10 Minutes

Time Critical: No

Preferred Evaluation Method

Perform X Simulate -

_______ ______-

__

___

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Ratina SAT

UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

Comment:

F:\\2003 NRC Exam\\JPMs\\AdrninRC1(2K3)

NRC [New].doc

7/18/2003

TOOLS/EOUIPMENT/PROCEDURES NEEDED:

CP-151

lOCFR

READ TO THE EXAMINEE:

Directions to the Examinee:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be simulated for this JPM. Under no circumstances are you to operate any plant

equipment, I will provide initiating cues and reports on other actions when directed by you. Ensure you

indicate to me when you understand you assigned task. To indicate that you have completed your

assigned task, return the handout sheet to the examiner.

INITIAL CONDITIONS:

The plant is at 100% rated thermal power.

INITIATING CUE:

You are the Superintendent, Shift Operatiom.

8

A Health Physics Supervisor has called the Control Room reporting a cask rupture in the

yellow room.

=

Access to the room will be limited to HP personnel for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

You are requested to determine external reporting requirements. Record below.

F\\2003 NRC Exam\\JPMs\\AdminRC1(2K3) NRC [New].doc

7/18/2003

-1:

Obtain a copy of CP- 15 1

STANDARD: N/A

EXAMINER NOTE: Provide candidate with a copy of CP-151 and lOCFR if

requested

COMMENTS:

-2:

Using supplied CP- 151, examinee determines reportability.

STANDARD:

required for An unplanned contamination event that requires access to the

contaminated area, by workers or the public, to be restricted for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by

imposing additional radiological controls or by prohibiting entry into the area.

[ 10CFR30.50(b)( l)(i)]

CP-151, Enclosure 2 Section XIILB., states that a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> report is

COMMENTS:

TERMINATION CUE: Notification requirements determined.

END OF TASK

N/A

Critical Step

SAT

UNSAT-

F\\2003 NRC Exam\\JPMs\\AdminRCl (2K3)NRC [New].doc

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CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100% rated thermal power.

INITIATING CUE:

You are the Superintendent, Shift Operations.

9

A Health Physics Supervisor has called the Control Room reporting a cask rupture in the

yellow room.

=

Access to the room will be limited to HP personnel for at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

You are requested to determine external reporting requirements. Record below.

F\\2003 NRC Exam\\JPMs\\AdminRCl (2K3) NRC [New].doc

7/18/2003

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

Plant1 (2K3) NRC [New] (Plant)

SAFETY FUNCTION 4

PLACE AN EFIC CHANNEL IN THE TRIPPED

CONDITION

PREPAREDlREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F:\\2003 NRC Exam\\JPMs\\PlantI (2K3) NRC [New].doc

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3:48 AM

ATTACHMENT 6

IN-PLANT JOB PERFORMANCE MEASURE

Task: Place an EFIC channel in the tripped condition per OP-450.

Alternate Path: No

JPM #: Plant1 (2K3) NRC [New]

K/A Ratingnmportance: 061A2.05 RO 3.1 SRO 3.4

Task NumberPosition:

Task Standard: Manually trip an EFIC channel.

Preferred Evaluation Location:

Simulator-

Plant

Admi-

References:

OP-450, Rev. 40

Validation Time: 10 Minutes

Preferred Evaluation Method

Perform -

Simulate

Time Critical: No

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Ratinv: SAT

UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

F:\\2003 NRC Exam\\JPMs\\Plantl(2K3) NRC [NewJdoc

7/1 S/2003

3:4S AM

TOOLS/EOUIPMENT/PROCEDURES NEEDED:

COPY of OP-450.

Additional copies of Section 4.17 and Enclosures 14, 15 & 16.

Use EFIC cabinets in I & C lab if available.

READ TO THE OPERATOR

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be simulated for this JPM. Under no circumstances are you to operate any

plant equipment. If performing JPM in the I & C lab then you are required to physically manipulate

equipment. I will provide initiating cues and reports on other actions when directed by you. Ensure you

indicate to me when you understand your assigned task. To indicate that you have completed your

assigned task, return the handout sheet to the examiner.

INITIAL CONDITIONS:

You are the Chief Nuclear Operator.

The plant is in Mode 1.

SP-29-LT has been determined to be inoperable.

INITIATING CUE:

The Control Room Supervisor directs you to trip the required EFIC channel to comply with TS.

F\\2003 NRC Exam\\JPMs\\PlantI (2K3) NRC [New].doc

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3:48AM

STEp:

Obtain OP-450.

STANDARD:

Obtain copy of OP-450.

EXAMINERS CUE:

Examiner will provide candidate with a complete copy

of OP-450.

COMMENTS:

STEP 2:

(step4.17.1)

Determine EFIC channel to be tripped:

Channel A

ChannelB

ChannelC

Channel D

STANDARD:

Candidate will utilize Enclosure 14 of OP-450 to determine which

channel should be tripped. Candidate should determine that SP-

29-LT is the Low Range level transmitter on the B OTSG in the

A Channel.

COMMENTS:

AT

JNSAT-

%tical Step

$AT

JNSAT-

F\\2003 NRC Exam\\JPMs\\Planti (2K3) NRC [New].doc

7/1 8/2003

3:48 AM

-3:

(step 4.17.2)

Verify no other EFIC channels are tripped.

EFWIMSLIIMFWINECTOR Actuation Trip Module lights are

dim and steady (Not bright and blinking) in A & B EFIC cabinets

STANDARD:

Candidate will check all trip module lights and ensure lights are

dim and steady.

EXAMINERS NOTE:

If JPM is performed in the lab then you will have to

cue the candidate that there are no trip module lights

flashing in the B EFIC cabinet.

COMMENTS:

-

4

(step 4.17.3)

Verify EFIC channel to be tripped is not in maintenance bypass.

Bypass key NOT inserted and maintenance bypass light is dim

and steady.

STANDARD: Candidate locates keyhole, verifies key is not inserted and that the

maintenance bypass light is dim and steady.

COMMENTS:

AT

JNSAT-

SAT

JNSAT-

F\\2003 NRC Exam\\JPMs\\PlantI (2K3) NRC [New].doc

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3:48 AM

STEp:

(step 4.17.4)

'rocedure Note:

This step only determines which module and device is to be used

to trip an EFIC function.

Determine EFIC system function required to be tripped and which

module and trip device should be used to accomplish this.

Refer to Enclosure 15

EFICChannel: A

Function: Low Level

AffectedOTSG: B

Module: A-3-5

Trip Device: TEST PB

D: Candidate determines the correct c..innel, function, OTSG, module an

trip device using enclosures.

ZOMMENTS:

-6:

(step 4.17.5)

If tripping of level instrument is desired, then depress and hold TEST

pushbutton on affected time delay bistable module for 2 2 seconds and

release.

Test P/B depressed for 2 2 seconds and trip light on bistable

flashes

0

Verify appropriate steam generator Level Initiate light is flashing

on Bistable Tripped section of alarm panel in top of cabinet.

Test P/B released

STANDARD: Candidate locates correct module, depresses the test pushbutton and

verifies the appropriate light is flashing on the alarm panel.

2OMMENTS:

SAT

UNSAT-

Critical Step

SAT

UNSAT-

F\\2003 NRC Exam\\JPMs\\PlantI (2K3) NRC [New].doc

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3:48AM

STEp:

(step 4.17.9)

Verify appropriate combination of Tripped 1 & 2 lights on EFW, MSLI,

MFWI Trip Modules as applicable are flashing, and record on Enclosure

16, Trip Module Tripped Light Status Verification.

STANDARD: Candidate verifies Trip Bus 1 light is flashing on the EFW Trip Module

only.

EXAMINERS NOTE:

If JPM is performed in the lab then you will have to

cue the candidate that the Trip Bus 1 light is flashing

on the EFW Trip module in the B EFIC cabinet.

COMMENTS:

STEp:

(step 4.17.10)

Verify appropriate alarms are received in Control Room.

STANDARD: Candidate simulates call to Control Room to verify alarms.

EXAMINERS CUE: The correct alarms have annunciated.

COMMENTS:

END OF TASK

SAT

JNSAT-

SAT

JNSAT-

F\\2003 NRC Exam\\JPMs\\Plantl(ZK3) NRC [New].doc

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3:48AM

CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Chief Nuclear Operator.

The plant is in Mode 1.

SP-29-LT has been determined to be inoperable.

INITIATING CUE:

The Control Room Supervisor directs you to trip the required EFIC channel to comply with TS.

F\\2003 NRC Exam\\JPMs\\PlantI (2K3) NRC [New].doc

7/18/2003

3:48AM

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

PlantJ (2K3) NRC [Bank #059] (Plant)

SAFETY FUNCTION 8

SW SURGE TANK MAKEUP FROM FIRE SERVICE

PREPARED/REVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F\\2003 NRC Exam\\JPMs\\PlantJ (2K3) NRC [Bank #59].doc

7/18/2003

3 5 8 AM

ATTACHMENT 6

IN-PLANT JOB PERFORMANCE MEASURE

-

Task SW Surge Tank makeup from Fire Service.

Alternate Path: No

JPM: PlantJ (2K3) NRC [Bank #059]

K/A Ratindmuortance: 008A1.04 RO 3.1 SRO 3.2

Task Number/Position: 008040301 1

Task Standard Provide makeup from the Fire Service system to the SW Surge Tank using AP-330,

Enclosure 4.

Preferred Evaluation Location:

Simulator -1rrPlant

Admin -

Perform -Simulate

-&

References:

AP-330, Rev. 17

Validation Time: 10 min.

Time Critical: No

Preferred Evaluation Method:

Candidate:

Time Start :

Printed Name

Time Finish

Performance Rating: SAT -

UNSAT __

Performance Time :

Examiner:

Printed Name

Signature

Date

F\\2003 NRC Exam\\JPMs\\PlantJ (2K3) NRC [Bank #59].doc

7/18/2003

3:58AM

Tools/Equipment/Procedures Needed:

AP-330, Enclosure 4

Simulate opening EOB

READ TO THE OPERATOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be simulated for this JPM. Under no circumstances are you to operate any

plant equipment. I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate that you have

completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Primary Plant Operator.

DW supply to SW has been lost.

Initiating Cues:

You are requested to perform the actions of the Primary Plant Operator (PPO) to establish SW Surge

Tank Makeup from FS, AP-330, Enclosure 4.

F:\\2003 NRC Exam\\JPMs\\PlantJ (2K3) NRC [Bank #59].doc

7/18/2003

3:58 AM

STEP:

Obtain copy of thc appropriate proccdure.

STANDARD:

EXAMINERS NOTE:

Operator obtains a copy of AP-330, Enclosure 4.

Once operator demonstrates he/she can locate the

procedure, provide them with a copy.

COMMENTS:

STEP 2 :

(Step 4.1)

Prepare SW surge tank for FS makeup.

Connect hose between the following valves (hose is located in

EOE-6):

__ FSV-186, Hose Reel Header Drain.

__ SWV-520, SW Supply to Surge Tank Drain.

Operator locates hose in EOE-6, stages hose between FWV- 186

and SWV-520, connects hose at each valve location.

STANDARD:

EXAMINERS CUE Indicate that the hose is connected at FSV-186 and SWV-

520.

COMMENTS:

STEP 3 :

(Step 4.2)

Close SWV-298, DW to SW Surge Tank Iso

STANDARD: Operator locates SWV-298 and rotates hdwheel until valve is fully

closed.

EXAMINERS CUE: SWV-298 is closed.

COMMENTS:

SAT -

UNSAT -

Critical Step

SAT __

UNSAT -

Critical Step

SAT -

UNSAT -

F\\2003 NRC Exam\\JPMs\\PlantJ (2K3) NRC [Bank #59].doc

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3 5 8 AM

STEP 4:

(Step 4.3)

Open SWV-520, DW Supply to Surge Tank Drain.

STANDARD: Operator rotates handwheel until the valve is fully open.

EXAMINERS CUE: SWV-520 is open.

COMMENTS:

STEP 5:

(Step 4.4)

Open FSV- 186, Hose Reel Header Drain.

STANDARD: Operator rotates handwheel until the valve is fully open.

EXAMINERS CUE: FSV-186 is open.

COMMENTS:

STEP 6:

(Step 4.5)

Notify Control Room that FS makeup is aligned to SW surge tank.

STANDARD: Operator communicates (radio preferred) to Control Room that FS

makeup is aligned to SW surge tank.

EXAMINERS NOTE: Simulate Control Room communication.

COMMENTS:

STEP I :

(Step 4.6)

Exit this enclosure.

END OF TASK

Critical Step

SAT -

UNSAT -

Critical Step

SAT __

UNSAT -

SAT -

UNSAT -

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3 5 8 AM

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UNPON COMPLETION OF TASK)

Initial Conditions:

Youare the Primary Plant Operator.

DW supply to SW has been lost.

Initiating Cues:

You are requested to perform the actions of the Primary Plant Operator (PPO) to establish SW Surge

Tank Makeup from FS, AP-330, Enclosure 4.

F\\2003 NRC Exam\\JPMs\\PlantJ (2K3) NRC [Bank #59].doc

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3 5 8 AM

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

PlantK (2K3) NRC [Bank #OS51 (Plant)

SAFETY FUNCTION 1

MANUALLY TRIP THE REACTOR

PREPAREDIREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F\\2003 NRC Exam\\JPMs\\PlantK (2K3) NRC [Bank #085].doc

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3:48 AM

ATTACHMENT 6

IN-PLANT JOB PERFORMANCE MEASURE

-

Task: Manually trip the reactor during a shutdown from outside the control room event.

Alternate Path: Yes

JPM #: PlantK (2K3) NRC [Bank #085]

KIA RatindImportance: E02EAl.1 RO 4.0 SRO 3.6

Task NumberRosition: 1010402004 RO

Task Standard: Manually trip the reactor during a shutdown fromoutside the control room event.

Preferred Evaluation Location:

Simulator-

Plant X Admin-

Preferred Evaluation Method

Perform -

Simulate

References:

AP-990, Rev 19

Validation Time: 5 Minutes

Time Critical: No

Candidate:

Time Started:

Printed Name

Time Finished:

UNSAT

Performance Time:

Performance Rating: SAT __

Examiner:

Printed Name

Signature

Date

Comment:

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3:48 AM

TOOLS/JIOUIPMENT/PROCEDURES NEEDED:

Copy of AP-990 signed off up to Step 3.15.

READ TO THE OPERATOR

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be simulated for this JPM. Under no circumstances are you to operate any

plant equipment. I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate that you have completed

your assigned task, return the handout sheet to the examiner.

INITIAL CONDITIONS:

You are the Reactor Operator.

The Control Room has been evacuated.

"-990

has been completed through Step 3.14

INITIATING CUE:

The Control Room Supervisor directs you to continue AP-990 starting with step 3.15.

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EXAMINERS NOTE: FOR STEPS DENOTED AS CRITICAL STEP, WHICH HAVE

MULTIPLE ACTIONS, THE INDIVIDUAL REQUIRED ACTION WILL BE DENOTED CS. IF

NO INDIVIDUAL ACTIONS ARE DENOTED AS SUCH THEN ALL ACTIONS WITHIN THE

STEP ARE DEEMED CRITICAL .

-1:

Obtain AP-990.

STANDARD:

SAT

UNSAT-

Obtain copy of AP-990 from PPO office.

EXAMINERS CUE:

Examiner will provide candidate with AP-990 signed off

though 3.15.

COMMENTS:

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3:48 AM

jTEP2: (step 3.15)

Verify NI-14-N12 is on scale. IfNI-14-N12 is not on scale, then

Rx is shutdown.

1.

Notify RO ('PO)

to ensure CRD Bkrs are tripped (1 24 ft

CC CRD Room):

"CRD BREAKER A"

(CS.

"CRD BREAKER B"

(CS)

"CRD BREAKER CB3"

(CS)

"CRD BREAKER CB 1 "

(CS)

"CRD BREAKER CB4"

(CS)

"CRD BREAKER CB2"

(CS)

Notify RO (PPO) to verify all CRD "0%" lights for groups

1 through 7 are lit on "POSITION REFERENCE PANEL"

(124 fi CC CRD Room).

If NI-14-N12 is not on scale, then notify TSC to consider

emergency boration.

2.

3.

STANDARD:

Candidate observes NI-14-N12 on RSP.

Candidate locates six CRD Breakers and indicates that he/she

would depress trip pushbuttons.

Candidate locates Position Reference Panel and observes lights

for Group 1 through 7.

Candidate again checks NE 14-N12

EXAMINER'S CUE When candidate observes NI-14-N12 indicate to hidher that

NI-14-N12 is off scale high. Inform the candidate that helshe

is to complete the remaining portion of this step

When candidate indicates that he would depress the trip

pushhutton for each breaker inform himher that they hear a

loud clunk and the open flag is visible

When candidate looks at the Position Reference Panel

indicate to himher that the "0%" lights for Group 1 through

I are on.

When candidate checks NI-14-N12 Indicate a reading that is

on scale (RX shutdown) and decreasing.

ZOMMENTS:

kitical Step

AT

JNSAT-

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I

I

1

TERMINATION CUE: CRD breakers OPEN, CRD groups 1 through 7 fully

inserted and NI-14-N12 on scale and decreasing.

END OF TASK

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3:48 AM

CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

The Control Room has been evacuated.

AP-990 has been completed through Step 3.14

INITIATING CUE:

The Control Room Supervisor directs you to continue AP-990 starting with step 3.15

F:\\2003 NRC Exam\\lPMs\\PlantK (2K3) NRC [Bank #085].doc

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

Plantspare (2K3) NRC [Bank #270] (Plant)

SAFETY FUNCTION 2 & 8

TRANSFER EXCESS CONTAMINATED

SECONDARY INVENTORY TO THE A FIRE

SERVICE TANK

PREPAREDREVIEWED B Y

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F\\2003 NRC Exam\\JPMs\\PlantSpare (2K3) NRC [Bank #270].doc

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3:43 AM

ATTACHMENT 6

IN-PLANT JOB PERFORMANCE MEASURE

-

Task:

Transfer excess contaminated secondary inventory to the "A" Fire Service Tank, FST-I

Alternate Path

No

-

JPM #:

Plantspare (2K3) NRC [BANK #270]

WA Rating/Importance: 037AK3.07 RO 4.2 SRO 4.4

Task Number/Position:

0860504001,0560504005 SPO

Task Standard

Transfer excess contaminated secondw inventory to the "A" Fire Service

Tank, FST- 1

Preferred Evaluation Location:

Simulator - In-Plantx

Admin __

Perform -

Simulate X

References:

I.

Validation Time:

20 min.

Time Critical: No

Preferred Evaluation Method:

EOP-14, Enclosure 9, Rev. 9

Candidate:

Time Start :

Printed Name

Time Finish

Performance Rating:

SAT -

UNSAT -

Performance Time : __

Examiner:

I

Printed Name

Signature

Date

Comment:

~

~

~

~

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Tools/Equipment/Procedures Needed:

1. EOP-14, Enclosure 9, Rev 9

2. A P key is required to gain entry to the Fire Pump House. CDV-103 lock should be

on the SPO key ring

READ TO THE OPERATOR

Directions to the Student :

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JFM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed pur assigned task, return the handout sheet to the examiner.

Initial Conditions:

You are the Turbine Building Operator.

An OTSG tube leak is in progress. EOP-6 has been entered with OTSGs steaming to the

condenser and with at least 1 RCP operating. Additional secondary water inventory storage is

desired.

Initiating Cues:

You are directed to perform EOP-14, Enclosure 9, OTSG Contaminated Waste Water

Management.

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EXAMINERS NOTE: FOR STEPS DENOTED AS CRITICAL STEP, WHICH HAVE

MULTIPLE ACTIONS, THE INDIVIDUAL REQUIRED ACTION WILL BE DENOTED

CS. IF NO INDIVIDUAL ACTIONS ARE DENOTED AS SUCH THEN ALL

ACTIONS WITHIN THE STEP ARE DEEMED CRITICAL.

STEp:

Obtain a copy of appropriate procedure.

STANDARD:

Candidate obtains a copy of EOP- 14, Enclosure 9, Rev. 9

EXAMINER CUE

EXAMINER NOTE:

Once candidate indicates where he/she would acquire the procedures then

provide candidate with a copy of EOP-14, Enclosure 9.

COMMENTS:

SAT

UNSAT

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STEP:

(step9.1 )

Align FSP recirc Hdr to FST-1B

1. Ensure FSV-28 "FST-1B INLET ISO' is open (1 19 ft Berm between

FSTs).

2. Close FSV-27 "FST-1A INLET ISO" (1 19 ft Berm between FSTs).

3. Open FSV-24 "FSP RECIRC LINE TO FST ISO" (1 19 ft FSPH

northwest wall)

STANDARD:

Locate the identified valves and simulate operation to the appropriate position.

EXAMINER CUE

1. FSV-28 is OPEN

2. FSV-27 is CLOSED

3. FSV-24 is OPEN

EXAMINER NOTE:

COMMENTS:

-3:

(step 9.2)

Verify FSP-2B is available.

-

IF FSP-2B is NOT available,

GO TO Step 9.9 in this enclosure.

STANDARD :

Go to Step 9.9

EXAMINER CUE.

FSP-2B is NOT available.

EXAMINER NOTE:

Steps 9.3 through 9.8 are N/A the next step is 9.9

COMMENTS :

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Critical Step

SAT

UNSAT

SAT

JNSAT

3:43AM

STEP 4:

(step 9.9)

Open FSV-41 "FSP SUCTION HDRCROSS-TIE" (1 19 ft FSPH north wall).

STANDARD:

Locate the identified valves and simulate operation to the appropriate

position.

EXAMINER CUE

FSV-41 is OPEN

EXAMINER NOTE: STATUS

FSP-2B not available.

FSP-1 available for alignment to FST-1B to support FS.

FSP-2A available to transfer FST-1A to FST-1B.

COMMENTS :

STEp: (step 9.10)

Close FSV-13 "FSP SUCTION HDR CROSS-TIE (1 19 fi FSPH north wall).

STANDARD:

Locate the identified valve and simulate operation to t k appropriate position.

EXAMINER CUE

FSV-13 is CLOSED

EXAMINER NOTE :

COMMENTS :

Critical Step

SAT

UNSAT

Critical Step

SAT

UNSAT

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STEP 6 :

(step 9.11)

Establish recirc flow to FST-1B

1. Notify Control Room to start FSP-2A

2. Verify FSP-2A is running (1 19 ft FSPH).

3. Throttle open FSV-23 "FSP-2A RECIRC ISO" (1 19 A FSPH southeast

wall) to establish 2100 gpm as indicated on FS-12-FIS "FSP's

COMBINED RECIRC FLOW". (Cs)

IDARD:

1. Call control room to start FSP-2A

2. Observe FSP-2A is running

3. Locate valve and throttle to 2100 gpm

EXAMINER CUE

1. Control room reports that FSP-2A is running

2. Indicate that FSP-2A is running

3. As operator throttles FSV-23 indicate flow increase to 2100 gpm on

FS-12-FIS

EXAMINER NOTE:

FSP-1 or FSP-2B aligned to FST-1B to support FS

FSP-2A available to transfer FST-1A to FST-1B

ZOMMENTS :

Critical Step

SAT

UNSAT

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3:43 AM

STEp: (step 9.12)

Notify Control Room that FST-IA transfer is in progress and request to be

notified when FST-IA level is 6 ft.

STANDARD:

Candidate calls control room and ask for notification.

EXAMINER CUE

Notify candidate that level is 6 ft.

EXAMINER NOTE:

COMMENTS :

F\\2003 NRC Exam\\JPMs\\PtantSpare (2K3) NRC [Bank #270].doc

SAT

JNSAT

7/18/2003

3:43 AM

STEP: (step 9.13)

notified by Control Room that FST-1A level is 6 fi,

stop recirc

flow.

1. Close FSV-23 "FSP-2A RECIRC ISO" (1 19 ft FSPH southeast wall).

2. Select FSP-2A "START MODE SELECTOR SWITCH" to "OFF" (1 19 fi

FSPH).

3.

FSP-2A stops,

select FSP-2A "START MODE

SELECTOR SWITCH" to "AUTO' (1 19 fi FSPH).

4. Close FSV-24 "FSP RECIRC LINE TO FST I S 0 (1 19 ft FSPH northwest

wall).

TANDARD

Locate the identified valves and switches and simulate operation to the

appropriate position.

3XAMINER CUE

1. FSV-23 is CLOSED

2. Start Mode is OFF

3. FSP-2A is stopped Start mode to AUTO

4. FSV-24 is CLOSED

3XAMINER NOTE:

ZOMMENTS :

Critical Step

SAT

UNSAT

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STEP 9:

(step 9.14)

Align FSP suctions to FST-1B

1. Ensure the following pumps are stopped (1 19 ft FSPH):

-FSP-l

F S P - 2 A

2. Close FSV-3 "FST-1A OUTLET ISO" (1 19 ft Berm behind FST-1A).

fcs)

3. Open FSV-41 "FSP SUCTION HDR CROSS-TIE (1 19 ft FSPH north

will). (CS)

4. Ensure FSV-13 "FSP SUCTION HDR CROSS-TIE is open (119 f? FSPH

north wall). (Cs)

STANDARD:

Locate the identified valves and simulate operation to the appropriate

position.

EXAMINER CUE

1. FSP-1 / 2A are stopped

2. FSV-3 is CLOSED

3. FSV-41 is OPEN

4. FSV-13 is OPEN

EXAMINER NOTE: STATUS

FST-1A level = 6 ft

FST transfer complete

COMMENTS :

Critical Step

SAT

UNSAT

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STEP 10:

(step 9.15)

Notify Control Room of FST-1A status.

1. FST- 1A is pumped down and isolated.

2. FST-1A and CDT-1 are to be cross-tied

STANDARD:

Candidate notifies control room of FST-IA status.

EXAMINER CUE

Respond as control room that FST-1A is pumped down and that it will be

cross-tied to CDT-1.

EXAMINER NOTE:

COMMENTS :

SAT

JNSAT

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STEP 11:

(step9.16)

Cross-tie FST-1A to CDT-1

1. Close CDV-288 "FST TO CDT-1 CROSS-TIE DRAIN" (1 19 ft Berm by

2. Open CDV-289 "FST TO CDT-1 CROSS-TIE I S 0 (119 ft Berm by FST-

1A).

3. Open FSV-918 "FST TO CDT-1 CROSS-TIE ISO" (119 ft Berm by FST-

4. Open CDV-103 "CDT-1 TO EFP SUCTION" (1 19 ft Berm by CDT-1).

FST- 1A).

1A)

STANDARD:

Locate the identified valves and simulate operation to the appropriate position.

EXAMINER CUE:

1. CDV-288 is CLOSED

2. CDV-289 is OPEN

3. FSV-918 is OPEN

4. CDV-103 is OPEN

EXAMINER NOTE:

COMMENTS :

n ..

-ntEal Step

SAT

JNSAT

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STEP 12:

(step 9.17)

Notify TSC to monitor FST-1A and CDT-1 level.

STANDARD:

N/A. The control room would perform this step

EXAMINER CUE

EXAMINER NOTE:

COMMENTS :

STEP 13: (step 9.18)

Exit this Enclosure.

STANDARD:

EXAMINER CUE:

EXAMINER NOTE:

COMMENTS :

END OF TASK

SAT

JNSAT

SAT

UNSAT

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Turbine Building Operator.

An OTSG tube leak is in progress. EOP-6 has been entered with OTSGs steaming to the condenser and

with at least 1 RCP operating. Additional secondary water inventory storage is desired.

Initiating Cues:

You are directed to perform EOP-14, Enclosure 9, OTSG Contaminated Waste Water

Management.

F\\2003 NRC Exam\\JPMs\\PlantSpare (2K3) NRC [Bank #270].doc

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3:43 AM

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimA (2K3) NRC [Bank #294] (SIMULATOR)

SAFETY FUNCTION 1

TRANSFER A SINGLE CONTROL ROD TO THE AUXILIARY POWER SUPPLY

PREPARED/REVIEWED BY:

Date: _______________

VALIDATED BY:

APPROVAL BY:

(Nuclear Training Supervisor)

1

F W 0 3 NRC ExamUPMs\\SimA (2K3)NRC [Bank#294].doc

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3:42AM

ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task Transfer a single control rod to the Auxiliary Power Supply

Alternate Path: NO

-

JPM #:

K/A RatindImDortance:

001A4.03 RO 4.0 SRO 3.7

Task NumberlPosition:

0010102010 RO

Task Standard Transfer a single control rod to the Auxiliary Power Supply by using OP-502, Control

Rod Drive System, Section 4.16, Transferring a Group or Rod to the Auxiliary Power

SimA (2K3) NRC [Bank #294]

Supply.

Preferred Evaluation Location:

Simulator

In-Plant -

Admin-

Perform

X

Simulate-

References:

Preferred Evaluation Method:

1. OP-502 Rev. 46

Validation Time: 10 min.

Time Critical: NO

Candidate:

Printed Name

Performance Rating: SAT -

UNSAT __

Time Stalt:

Time Finish:

Performance Time :

Examiner:

I

Printed Name

Signature

Date

Comment

~

~

F:\\2003 NRC ExamUPMs\\SimA (ZK3)NRC [Bank#294].doc

2

7/18/2003

3:42AM

SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

None

SIMULATOR OPERATOR INSTRUCTIONS:

1.

AnypowerIC

3

FU003 NRC ExamWPMs\\SimA (2K3) NRC [Bank#294].dw

7/18/2003

3:42AM

Tools/Equipment/Procedures Needed:

OP-502, Rev. 46, Section 4.16

READ TO THE OPERATOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and reports

on other actions when directed by you. Ensure you indicate to me when you understand your

assigned task. To indicate that you have completed your assigned task, return the handout sheet to

the examiner.

Initial Conditions:

You are the Reactor Operator, the plant is stable at power. Control Rod troubleshooting is

underway.

Initiating Cues:

You are requested to transfer Rod 5-4 to the Auxiliary Power Supply. Following transfer of the rod

leave the reactor diamond and demand stations in manual for further manipulations.

4

F:\\2003 NRC ExamUPMs\\SimA (2K3)NRC [Bank#294].doc

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3:42AM

STEP 1:

Obtain a copy of the appropriate procedure.

STANDARD: Operator obtains a copy of OP-502.

EXAMINER'S NOTE: Once candidate determines correct section of procedure

provide a copy of Section 4.16.

EXAMINER'S CUE: For purposes of this JPM assume the SRO concurs with

each rod manipulation

COMMENTS:

-2:

(Step4.16.1)

CAUTION: Tave control could go to Feedwater regulation.

Place Reactor Diamond in MANUAL.

DEPRESS "MANUAL"

VERIFY "MANUAL" light on, " AUTO" light off

STANDARD:

Operator depresses the Diamond Panel MANUAL pushbutton, and

observes the MANUAL light ON and the AUTO light OFF.

COMMENTS:

STEP 3 :

(Step 4.16.2)

Place Reactor Demand control station in Hand.

DEPRESS HAND

VERIFY "REACTOR DEMAND" in Mini Track rAUT0.I' and "HAND"

ligit$On)

STANDARD:

Operator depresses the HAND pushbutton on the Reactor Demand

(Bailey) HAND/AUTO station and observes that both the HAND

and AUTO lights are "ON".

COMMENTS:

SAT -

UNSAT -

Critical Step

SAT -

UNSAT -

SAT -

JNSAT -

5

ED003 NRC ExamWPMs\\SimA(ZK3)NRC[Bank#294].dac

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3:42AM

STEp:

(Step 4.16.3)

Select GROUP SELECT Switch to desired group.

STANDARD:

Operator verifies that GROUP SELECT Switch is selected to Group

5.

COMMENTS:

-4:

(Step 4.16.4)

Select ALL or desired rod. Use SINGLE SELECT Switch.

STANDARD:

Operator verifies that SINGLE SELECT Switch is selected to 4.

COMMENTS:

STEP:

(Step 4.16.5)

Select SEQ OR. Verify SEQ OR light "ON", SEQ light "ON".

STANDARD:

Operator depresses the SEQ/SEQ OR pushbutton and verifies both

lights "ON".

COMMENTS:

STEP:

(Step 4.16.6)

Select AUXIL.

STANDARD:

Operator depresses the AUXIL/GROUP pushbutton and verifies

AUXIL light "ON' and GROUP light "OFF". Verify TRANS

RESET light OFF and CONTROL ON light for GP 5 "ON".

COMMENTS:

Critical Step

SAT ~

JNSAT -

Critical Step

SAT ~

JNSAT -

Critical Step

SAT -

JNSAT __

Critical Step

SAT -

JNSAT -

6

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3:42AM

m: (Step 4.16.7)

Place SPEED SELECTOR switch in JOG.

STANDARD:

Operator rotates RUN/JOG switch to JOG and verifies SY light

"ON".

COMMENTS:

-8:

(Step 4.16.8)

Select CLAMP.

STANDARD:

Operator depresses CLAMPKLAMP RELEASE pushbutton and

verifies CLAMP light "ON" and CLAMP REL light "OFF".

COMMENTS:

STEp:

(Step 4.16.9)

CAUTION: If Amber control ON lights for more than one group is ON, STOP,

and notify SSO.

Depress MAN TRANS.

STANDARD:

Operator depresses MAN TRANS pushbutton and verifies TR CF

light "ON". The operator will also verify the amber CONTROL ON

light for rod 5-4 is "ON".

COMMENTS:

STEP 10:

(Step 4.16.10)

Select CLAMP REL.

STANDARD:

Operator depresses CLAMWCLAMP RELEASE pushbutton and

verifies CLAMP REL light "ON" and CLAMP light "OFF".

COMMENTS:

Critical Step

SAT __

UNSAT -

Critical Step

SAT _.

UNSAT -

Critical Step

SAT _.

UNSAT -

Critical Step

SAT __

UNSAT -

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STEP 11:

(Step4.16.11)

Select GROUP

STANDARD:

Operator depresses GROUP/AUXIL pushbutton and verifies

GROUP light "ON" and A W L light "OFF". The operator will also

verify the SY light "OFF".

COMMENTS:

STEP 12:

(Step 4.16.12)

If latching Safety Rods in accordance with section 4.2, return to Section 4.2.3

after completion of this step

STANDARD:

N/A

COMMENTS:

STEP 13:

(Step4.16.13)

Place SPEED SELECTOR switch in RUN.

STANDARD:

Operator rotates RUN/JOG switch to RUN, observes the white

(Diamond panel) "CONTROL ON" light for group 5 is "ON, and

the amber (PI panel) "CONTROL ON" light for rod 5-4 is "ON".

COMMENTS:

STEP 14:

(Step4.16.14)

Restore SINGLE SELECT Switch. Place SINGLE SELECT Switch to OFF.

Operator rotates SINGLE SELECT Switch to OFF.

STANDARD:

COMMENTS:

3AT _.

LTNSAT -

SAT _.

"SAT -

SAT __

lTNSAT -

8

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STEP 15:

(Step4.16.15)

Restore GROUP SELECT Switch. Place GROUP SELECT Switch to OFF.

STANDARD:

Operator rotates GROUP SELECT switch to OFF.

COMMENTS:

STEP 16:

(Step 4.16.16)

NOTE:

When in "SEQ the Control ON lamp and Amber Control ON lamps

are on for rods on the Aux Power Supply and controlling rod group

(usually group 7)

Select SEQ. Verify SEQ light "ON" and SEQ OR light "OFF".

STANDARD:

Operator depresses SEQ/SEQ OR pushbutton and verifies SEQ light

"ON" and SEQ OR light "OFF".

EXAMINER'S CUE: You have transferred rod 5-4 to the Auxiliary Power

Supply; the JPM is complete.

COMMENTS:

END OF TASK

SAT __

UNSAT -

3AT -

JNSAT -

9

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator, the plant is stable at power. Control Rod troubleshooting is

underway.

INITIATING CUES:

You are requested to transfer Rod 5-4 to the Auxiliary Power Supply. Following transfer of the rod

leave the reactor diamond and demand stations in manual for further manipulations.

IO

F:\\2003 NRC ExamUPMs\\SimA OK3) NRC [Bank#294].doe

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3:42AM

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimB (2K3) NRC [Bank# 3671 (SIMULATOR)

ALTERNATE PATH

SAFETY FUNCTION 2

ES B HPI DIVERSE CONTAINMENT ISOLATION TEST

PREPAREDIREVIEWED BY:

Date: _______________

VALIDATED BY:

_______________

APPROVAL BY:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task ES B monthly HPI diverse containment isolation test.

Alternate Path: Yes

-

JPM # SimB (2K3) NRC [Bank #367]

KIA Ratinqllmportance: 013A3.01 RO 3.7

SRO 3.9

Task NumberlPosition: 0130202006 RO

Task Standard: Perform ES B monthly HPI diverse Containment isolation test per SP-358A

section 4.6.4.6.

Preferred Evaluation Location:

SimulatorA Plant, Admin-

Perform

Simulate-

References:

SP-358A, Rev. 32

Validation Time: 35-45 Minutes

Time Critical: No

Preferred Evaluation Method

____________________-------------------------------------------

____________________-------------------------------------------

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Ratinq: SAT - UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

Comment:

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

Restore the simulator to a 100% MOL IC or IC# 65 develoDed for this

-

JPM.

If creating IC perform the following:

Place ES B RB IS0 AUTO TEST SELECT switch to PUSH-IN Test 1 position

Set Conditional for MUV-18 amber light on ES cabinet 56 to come on when 6

DCI switch in ES Channel 1 is placed in the TEST position.

Set Pending IA for MUV-18 amber light on ES cabinet 5B to turn off when B

DCI switch in ES Channel 1 is returned to Normal position.

2.

SIMULATOR OPERATOR INSTRUCTIONS:

1.

Trigger Pending IA for MUV-18 amber light on ES cabinet 5B after candidate

discovers MUV-18 failure. This will remove MUV-18 failure when examinee

returns DCI switch to normal.

2.

IC #65 alreadv has the initial MUV-I8 failure in. Trigger the Pending IA after

the candidate has taken the DCI switch to TEST.

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711 812003

3:41 AM

TOOLSlEQUlPMENTlPROCEDURES NEEDED:

Radio (may be simulated)

Copy of SP-358A and replacements for section 4.6.4.6,4.6.5, and Enclosure 2

READ TO THE OPERATOR:

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and

reports on other actions when directed by you. Ensure you indicate to me when you understand

your assigned task. To indicate that you have completed your assigned task, return the handout

sheet to the examiner.

INITIAL CONDITIONS:

100 % power

SP-358A in progress. All steps complete up to 4.6.4.6.

INITIATING CUES;

You are the Balanceof Plant Operator.

The Control Room Supervisor has directed you to perform ES " B HPI Diverse Containment

Isolation test per SP-358A section 4.6.4.6.

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STEP 1 :

STANDARD: Examinee obtains a copy of SP-358A and determines section

4.6.4.6 is the correct section.

EXAMINERS NOTE: Once examinee indicates where helshe would acquire

the working copy of SP-358A, provide them with a copy of SP-358A.

COMMENTS:

Obtain copy of SP-358A

STEP 2: SP-358A Step 4.6.4.6.1

OPEN valve CAV-431

STANDARD: Examinee locates control switch for CAV-431, selects CAV-431 to

OPEN position, and observes CAV-431 GREEN light OFF and CAV-431 RED

light comes ON. Examinee should notify chemistry prior to stroking CAV-431

IAW step 3.2.1.

COMMENTS:

STEP 3:

SP-358A Step 4.6.4.6.2

In the ACT. CHAN. CAB. #I

(ES Test Cabinet #I), SELECT the "ES " B

CHANNEL RCI DIVERSE CONTAINMENT ISOLATION" test switch to the

"TEST" position.

STANDARD: Examinee locates ES Test Cabinet #I, locates ES " B CHANNEL

RCI DIVERSE CONTAINMENT ISOLATION switch, identifies the TEST

position, rotates switch to TEST.

COMMENTS:

SAT

UNSAT-

Critical Step

SAT

UNSAT-

Critical Step

SAT

UNSAT-

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3:41 AM

-4:

SP-358A Step 4.6.4.6.3

lERlFY both amber and red indicating lights are OFF (Actuation Matrix -

3ypass Status) for each of the following ES " 6

RBlC TEST GROUPS 1 thru 4

kquipment:

!NGINEERED SAFEGUARD ACTUATION RELAY CABINET 5A - TEST

GROUP (B)

Check Box

RBC Group 1

CAV-2

RBC Group 1

CFV-25

RBC Group 1

CFV-29

RBC Group 1

MUV-49

RBC Group 1

WDV-4

iNGINEERED SAFEGUARD ACTUATION RELAY CABINET 58

GROUP (E)

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

CAV-6

CFV-26

CFV-42

DWV-160

WDV-61

LRV-73

CAV-7

CFV-27

MSV-130

WDV-62

LRV-71

MUV-18

CFV-28

MSV-148

MUV-27

WDV-405

STANDARD: Examinee locates ES Actuation Relay Cabinet 5A & 58, locates

4mber and Red lights for each of the components above, check Amber and Red

ights for each component above and notes MUV-18 Amber light is not in the

required condition. Refers to L&P 3.5.2 (Do not proceed past a step if any of

.he status (Normal, Bypass or Test) indicating lights at the Test light panel fail to

,perate as specified by the applicable test step. To back out of the procedure,

see Enclosure 2.)

2OMMENTS:

Zritical Step

SAT

JNSAT-

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3:41 AM

STEP 5:

SP-358A Enclosure 2

If it is desired to back out of procedure during its performance, refer to steps

indicated below for GUIDANCE. Depending on the situation, deviation from

these steps may be taken with SSO approval.

PERFORMING

ESB RBIC/SECTION 4.6

TO BACK OUT, PERFORM THE FOLLOWING

4.6.4.1.1 1 thru 4.6.4.1.17,

4.6.4.2.10 thru 4.6.4.2.16,

4.6.4.3.10 thru 4.6.4.3.15,

4.6.4.4.10 thru 4.6.4.4.15,

4.6.4.5.4 thru 4.6.4.5.6,

4.6.4.6.9 thru 4.6.4.6.15,

and entire Sections 4.6.5 and 4.6.6

EXAMINERS CUE: Role play as the SSO and tell the candidate to perform

steps 4.6.4.6.9 thru 4.6.4.6.15, entire sections of 4.6.5 and 4.6.6, and Steps

5.1 .I thru 5.1.5.

STANDARD: Candidate informs SSO of problem and obtains guidance for steps

required to be performed.

COMMENTS:

SAT

UNSAT-

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3:41 AM

STEP 6:

SP-358A Step 4.6.4.6.9

In the ACT. CHAN. CAB. #I

(ES Test Cabinet #I), SELECT the "ES "B"

CHANNEL RCI DIVERSE CONTAINMENT ISOLATION" test switch to the

"NORM" position.

STANDARD: Examinee locates ES Test Cabinet #I,

locates ES " B CHANNEL

RCI DIVERSE CONTAINMENT ISOLATION switch, identifies the NORM

position, rotates snitch to NORM.

COMMENTS:

STEP 7:

SP-358A Step 4.6.4.6.10

OPEN CAV-431

STANDARD: Examinee locates control switch for CAV-431, observes CAV-431

GREEN light OFF and CAV-431 RED light ON.

COMMENTS:

Critical Step

SAT

UNSAT-

SAT

UNSAT-

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3:41 AM

STEP 8:

SP-358A Step 4.6.4.6.1 1

lERlFY both amber and red indicating lights are OFF (Actuation Matrix -

3ypass Status) for each of the following ES " B RBlC TEST GROUPS 1 thru 4

?quipment:

iNGlNEERED SAFEGUARD ACTUATION RELAY CABINET 5A- TEST

GROUP fB)

Check Box

RBC Group 1

CAV-2

RBC Group 1

CFV-25

RBC Group 1

CFV-29

RBC Group 1

MUV-49

RBC Group 1

WDV-4

ENGINEERED SAFEGUARD ACTUATION RELAY CABINET 5B - TEST

GROUP (B)

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

CAV-6

CFV-26

CFV-42

DWV-160

WDV-61

LRV-73

CAV-7

CFV-27

MSV-130

WDV-62

LRV-71

MUV-18

CFV-28

MSV-148

MUV-27

WDV-405

STANDARD: Examinee locates ES Actuation Relay Cabinet 5A & 5B, locates

4mber and Red lights for each of the components above, verifies Amber and

?ed lights for each component above is OFF.

2OMMENTS:

SAT

JNSAT-

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3:41 AM

STEP 9:

SP-358A Step 4.6.4.6.12

VERIFY the following alarms return to NORMAL:

ANN. ESB/JH1/2/01, DIVERSE CONTAINMENT ISOLATION B

E.R. Point Number 11 14, PART CONT IS0 ON HPI ".B"

STANDARD: Examinee locates annunciator panel, observes D-2-1 "Diverse

Containment Isolation B cleared, locates event recorder, observes event point

11 14 is cleared.

COMMENTS:

ALTERNATE TERMINATION CUE: Step 4.6.4.6.12 when completed can be

used as a termination point if time is a constraint.

NOTE: This can only be used if the examination team has decided to use it

before Exams started.

STEP IO:

SP-358A Step 4.6.4.6.13

In the ACT. CHAN. CAB. #2 (ES Test Cabinet #I), SELECT the "ES "B"

CHANNEL RC2 DIVERSE CONTAINMENT ISOLATION" test switch to the

"NORM" position.

STANDARD: Examinee locates ES Test Cabinet #2, locates ES " B CHANNEL

RC2 DIVERSE CONTAINMENT ISOLATION switch, identifies the NORM

position, verifies switch is in NORM.

COMMENTS:

SAT

JNSAT-

SAT

JNSAT-

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3:41 AM

STEP 11

SP-358A Step 4.6.4.6.14

JERIFY both amber and red indicating lights are OFF (Actuation Matrix -

3ypass Status) for each of the following ES " B RBlC TEST GROUPS 1 thru 4

zquipment:

ENGINEERED SAFEGUARD ACTUATION RELAY CABINET 5A- TEST

GROUP (B)

Check Box

RBC Group 1

CAV-2

RBC Group 1

CFV-25

RBC Group 1

CFV-29

RBC Group 1

MUV-49

RBC Group 1

WDV-4

-NGINEERED SAFEGUARD ACTUATION RELAY CABINET 5B - TEST

GROUP (B)

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 2

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 3

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

RBC Group 4

CAV-6

CFV-26

CFV-42

DWV-160

WDV-61

LRV-73

CAV-7

CFV-27

MSV-130

WDV-62

LRV-71

MUV-18

CFV-28

MSV-148

MUV-27

WDV-405

STANDARD: Examinee locates ES Actuation Relay Cabinet 5A & 56, locates

imber and Red lights for each of the components above, verifies Amber and

ied lights for each component above is OFF.

OMMENTS:

SAT

JNSAT-

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3:41 AM

STEP 12

SP-358A Step 4.6.4.6.15

RESTORE CAV-431 to desired position as the present plant operations

dictates.

Position Restored to:

STANDARD: Examinee locates control switch for CAV-431, selects CAV-431 to

CLOSE position, and observes CAV-431 Red light out and CAV-431 GREEN

light comes on.

EXAMINER CUE: If examinee ask what the desired position is, tell them

the valve needs to be closed for present plant conditions.

COMMENTS:

STEP 13

SP358A Step 4.6.5.1

PROCEDURE CAUTION:

Actuation Relay Cabinet light panels (for section under test),

THEN associated end device(s) may actuate to its ES position when selecting

the "AUTO TEST SELECT" switch to the OFF position in the next step.

SELECT the ES " B "RB IS0 AUTO TEST SELECT" pistol grip to the "OFF" and

"PUSH IN" position

STANDARD: Examinee locates ES " B RB ISOAUTO TEST SELECT pistol grip

and observes it is already in the "OFF" and "PUSH IN" position.

COMMENTS:

any red indicating light(s) remain ON at the ES

STEP 14

SP-358A Step 4.6.5.2

VERIFY the ES "B" "RB IS0 AUTO TEST SELECT" Monthly Test red light goes

OFF.

STANDARD: Examinee locates ES " B "RB IS0 AUTO TEST SELECT" Monthly

Test red light and observes it is OFF.

COMMENTS:

SAT

UNSAT-

SAT

UNSAT-

SAT

UNSAT-

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3:41 AM

STEP 15

SP-358A Step 4.6.5.3

VERIFY the ES " B "RB IS0 AUTO TEST SELECT" Refueling Test red light

remains OFF.

STANDARD: Examinee locates ES " B "RB IS0 AUTO TEST SELECT"

Refueling Test red light and observes it is OFF.

COMMENTS:

STEP 16

SP-358A Step 4.6.5.4

VERIFY the following Alarm returns to NORMAL:

ANN. ESB/JH1/8/06, ES B ACTUATION TEST BYPASS

E.R. Point Number 770, ES ACT. B TRAIN TESTlBYPASS

STANDARD: Examinee locates D-8-6 "ES B ACTUATION TEST BYPASS

annunciator alarm is off and event point 770 is not in alarm.

COMMENTS:

SAT

JNSAT-

SAT

UNSAT-

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3:41 AM

STEP 77

SP358A Step 4.6.5.5

VERIFY the indicating lights are ON as specified (Actuation Matrix - Normal

Status) for each of the following ES " B RBIC TEST GROUP 1,2, 3,4, and 5

squipment:

ENGINEERED SAFEGUARD ACTUATION RELAY CABINET 5A- TEST

GROUP (B)

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

RBC Group 1

BSV-4

CAV-2

CFV-25

CFV-29

MUV-49

swv-12

SWV-82

SWV-86

WDV-4

Amber

Amber

Amber

Amber or Red

Amber or Red

Amber or Red

Amber or Red

Amber or Red

Amber

ENGINEERED SAFEGUARD ACTUATION RELAY CABINET 5B - TEST

GROUP (B)

RBC Group 2

CAV-6

Amber

RBC Group 2

CFV-26

Amber

RBC Group 2

CFV-42

Amber

RBC Group 2

CIV-34

Amber or Red

RBC Group 2

DWV-160

Amber

RBC Group 2

swv-353

Amber or Red

RBC Group 2

SWV-81

Amber or Red

RBC Group 2

SWV-85

Amber or Red

RBC Group 2

WDV-61

Amber

RBC Group 3

LRV-73

Amber

RBC Group 3

CAV-7

Amber

RBC Group 3

CFV-27

Amber

RBC Group 3

CIV-35

Amber or Red

RBC Group 3

MSV-130

Amber

RBC Group 3

swv-354

Amber or Red

RBC Group 3

SWV-80

Amber or Red

RBC Group 3

SWV-84

Amber or Red

RBC Group 3

WDV-62

Amber

RBC Group 4

LRV-71

Amber

RBC Group 4

MUV-18

Amber

RBC Group 4

CFV-28

Amber

RBC Group 4

CIV-41

Amber or Red

RBC Group 4

MSV-148

Amber

SAT

JNSAT-

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3:41 AM

RBC Group 4

MUV-27

Amber

RBC Group 4

swv-355

Amber or Red

RBC Group 4

swv-47

Amber or Red

RBC Group 4

SWV-50

Amber or Red

RBC Group 4

swv-79

Amber or Red

RBC Group 4

SWV-83

Amber or Red

RBC Group 4

WDV-405

Amber

RBC Group 5

3ESBR

Amber

RBC Group 5

cIv-40

Amber or Red

RBC Group 5

MUV-253

Amber or Red

RBC Group 5

SWV-109

Amber or Red

RBC Group 5

swv-110

Amber or Red

RBC Group 5

SWV-152

Amber or Red

RBC Group 5

SWV-48

Amber or Red

RBC Group 5

swv-49

Amber or Red

RBC Group 5

wsv-4

Amber

RBC Group 5

WSVB

Amber

STANDARD: Examinee locates ES Actuation Relay Cabinet 5A & 5B, locates

Amber and Red lights for each of the components above, verifies Amber and

Red lights for each component above.

COMMENTS:

~~~

~

TERMINATION CUE: Step 4.6.5.5 completed.

END OF TASK

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3:41 AM

CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

100 % power

SP-358A in progress. All steps complete up to 4.6.4.6.

INITIATING CUES;

You are the Balance of Plant Operator.

The Control Room Supervisor has directed you to perform ES " B HPI Diverse Containment

Isolation test per SP-358A section 4.6.4.6.

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3:41 AM

CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimC (2K3) NRC [New] (SIMULATOR)

(Possible Alternate Path if needed)

SAFETY FUNCTION 3

PORV EXERCISE TEST

PREPARED/REVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

F\\2003 NRC Exam\\JPMs\\SimC (2K3) NRC [New].doc

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task Perform PORV Exercise Test

Alternate Path: No [Possible Alternate Path (fail to close RCV-10 when demanded)]

JPM #: SimC (2K3) NRC [New]

K/A Ratingnmportance: 010A3.01 RO 3.0 SRO 3.2

Task NumberFosition: 0020401005 RO

Task Standard: Perform PORV Exercise Test per SP-379.

Preferred Evaluation Location:

SimulatorA Plant- Admin-

Perform

Simulate-

References:

SP-379, Rev. 8

Validation Time : 15 Minutes

Time Critical: No

Preferred Evaluation Method

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Rating: SAT

UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

Comment:

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3:40 AM

SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1. Restore the simulator to IC# 66

developed for this JPM.

2. If used as an alternate path JPM then when candidate performs Step 4.4 in SP-379 RCV-10 must be

failed AS IS.

SIMULATOR OPERATOR INSTRUCTIONS:

1. Role play as operator at Remote Shutdown Panel.

F:\\2003 NRC Exam\\JPMs\\SimC (2K3) NRC [New].doc

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3:40 AM

TOOLS/EOUIPMENT/PROCEDURES NEEDED:

Radio

copy of SP-379

Stop watch

READ TO THE OPERATOR

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be performed for this JPM. I will provide initiating cues and reports on other

actions when directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed your assigned task return the handout sheet to the examiner.

INITIAL CONDITIONS:

A plant heatup is in progress with RCS pressure at approximately 675 psig.

INITIATING CUES;

You are the Balance of Plant Operator.

The Control Room Supervisor has directed you to perform an operability test on the PORV in accordance

with SP-379. Step 4.1.2 will be used to cycle RCV-11, PORV Block valve.

F\\2003 NRC Exam\\JPMs\\SimC (2K3) NRC [NewJdoc

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3:40 AM

jTEP:

Obtain copy of SP-379

STANDARD: Candidate obtains a copy of SP-379.

EXAMINERS NOTE:

Once candidate indicates where he/she would acquire

the working copy of SP-379, provide them with a copy.

ZOMMENTS:

m: SP-379 Step 4.1.2.1

Close RCV- 11

STANDARD: Candidate locates control switch for RCV- 11, selects RCV- 11 to

CLOSE position and observes the RED light OFF and GREEN light ON.

EOMMENTS:

-3:

SP-379 Step 4.1.2.2

Open RCV- 10 and OBSERVE no changes to any of the following:

0 PZRlevel

RCSpressure

e Tailpipe temperature

RCV- 10 open monitor

0

RCDT level and pressure

STANDARD: Candidate locates all indications for the listed parameters, locates control

switch for RCV-10, selects to OPEN and observes GREEN light OFF

and RED light ON. Candidate verifies no change in the listed

parameters.

EXAMINERS NOTE:

Candidate may display individual computer points for

the listed parameters.

COMMENTS:

SAT

JNSAT-

n ..

-ritical Step

SAT

JNSAT-

SAT

XVSAT-

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-4:

SP-379 Step 4.1.2.3

If any changes are noted in the above parameters then perform the following:

Close RCV- 10

Refer to TS 3.4.10

Refer to Contingencies in Step 5.2

STANDARD: Candidate verifies no changes to parameters noted in step 3.

COMMENTS:

-

5

SP-379 Step 4.1.2.4

Close RCV- 10

STANDARD:

Candidate locates control switch for RCV-10, selects to CLOSE

position and verifies RED light OFF and GREEN light ON.

COMMENTS :

STEp:

SP-379 Step 4.1.2.5

Open RCV- 1 1

STANDARD: Candidate locates control switch for RCV- 11, selects to OPEN position

and verifies GREEN light OFF and RED light ON.

COMMENTS:

SAT

JNSAT-

Critical Step

SAT

LJNSAT-

Critical Step

SAT

LJNSAT-

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jTEp:

SP-379 Step 4.2

Station an operator at the RSP, in communication with the Control Room,

to observe RCV-IO position indication.

STANDARD: Candidate communicates with simulator operator, stations auxiliary

operator at RSP, and gives instructions to observe RCV-10 position

indication.

ZOMMENTS:

m:

SP-319 Step 4.3

Record the following data:

RCS pressure

PZRlevel

Tailpipe temperature

RCDT pressure

RCDT level

STANDARD: Candidate locates MCB andor computer points for the listed parameters

and records data.

COMMENTS:

AT

JNSAT-

AT

JNSAT-

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TEp

SP-379 Step 4.4

ZAUTION: The following step will result in a blowdown of the PZR steam

pace. The blowdown time should be minimized.

Open and Time RCV- 10

TANDARD

Candidate locates control switch for RCV-10, selects to OPEN

position and verifies GREEN light OFF and RED light ON.

OMMENTS:
TEP 10

SP-379 Step 4.5

Record time

ZTANDARD: Candidate records stroke time for RCV- 10.

2OMMENTS:

STEP 11 :

SP-379 Step 4.6

Verify the following open indications for RCV-10:

Indicates open on the ICs panel

Indicates open on the RSP

ICs alarm for EP 1959 (1-5-1)

Meter for ultrasonic indication is in the Valve Open region.

STANDARD: Candidate locates and verifies the above indications.

ZOMMENTS:

n ..

,ritical Step

SAT

JNSAT-

SAT

UNSAT-

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STEP 12:

SP-379 Step 4.7

Verify RCV-10 is opened by a change in the system parameters below:

RCS pressure decreasing

PZR level decreasing

Tailpipe temperature increasing

RCDT pressure increasing

RCDT temperature increasing

STANDARD: Candidate locates and verifies changes in the above parameters.

COMMENTS:

STEP 13:

SP-379 Step 4.8

Close and Time RCV- 10

STANDARD:

Candidate locates control switch for RCV-10, selects to CLOSE

position and verifies RED light OFF and GREEN light ON.

COMMENTS:

STEP 14:

SP-379 Step 4.9

Record time

STANDARD: Candidate records stroke time for RCV-10.

COMMENTS:

STEP 15:

SP-379 Step 4.10

Observe that RCS pressure stabilizes and nor other significant changes occur to

system parameters.

STANDARD: Candidate locates and observes parameters listed in step 11 and ensnres

that the plant is stable.

COMMENTS:

SAT

JNSAT-

Critical Step

SAT

UNSAT-

SAT

UNSAT-

SAT

UNSAT-

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lTEP 16:

SP-379 Step 4.11

IF there is evidence that RCV- 10 did NOT close, then perform the following:

Close RCV- 11

Refer to TS 3.4.10

Refer to Contingencies in Step 5.2

TANDARD
If candidate determines that RCV- 10 did not close then RCV- 1 1 control

switch should be located and closed while observing the RED light OFF

and the GREEN light ON.

CXAMINERS NOTE:

RCV-11 should not be closed unless this JPM is used

as an Alternate Path JPM.

ZOMMENTS:

STEP 17:

SP-379 Step 4.12

Record the following data:

RCSpressure

PZRlevel

Tailpipe temperature

RCDT pressure

RCDT level

RD: Candidate locates MCB and/or c

and records data.

tr

de points for the listed parameters

EOMMENTS:

3

-ntical

.. Step

only if

ilternate

Path)

$AT

lTNSAT-

SAT

UNSAT-

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STEP 18:

SP-379 Step 4.13

Verify the following closed indications for RCV- 10:

Indicates closed on the ICs Panel

Indicates closed at the RSP

Meter for ultrasonic indicator in the Valve Closed region

STANDARD: Candidate locates indications and verifies GREEN light for ICs panel,

ultrasonic indicator in the Valve Closed region and communicates with

the operator at the RSP (simulator operator) for remote indication.

EXAMINERS CUE: RCV-10 has a GREEN light at the RSP.

COMMENTS:

STEP 19:

SP-379 Step 4.14

Reset the PORV Safety Valve Opened alarm with the reset pushbutton located

in the PORV Position IND and TSAT cabinet in the B ES 4160V room.

STANDARD: Candidate instructs operator (simulator operator) to reset the PORV

Safety Valve Opened alarm and verifies EP 1959 clears when reset.

COMMENTS:

STEP 20:

SP-379 Step 4.15

Place the control switch for RCV-10 in AUTO.

STANDARD: Candidate locates control switch for RCV- 10 and places the switch in

AUTO while verifying no change in valve position.

COMMENTS:

TERMINATION CUE: The PORV Exercise Test is complete.

SAT

JNSAT-

AT

JNSAT-

AT

JNSAT-

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CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A plant heatup is in progress with RCS pressure at approximately 675 psig.

INITIATING CUES;

You are the Balance of Plant Operator.

The Control Room Supervisor has directed you to perform an operability test on the PORV in accordance

with SP-379. Step 4.1.2 will be used to cycle RCV- 11, PORV Block valve.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimD (2K3) NRC [Bank#037] (SIMULATOR)

SAFETY FUNCTION 4

PERFORM A CROSSTIE OF DECAY HEAT REMOVAL FLOW TO THE

REACTOR VESSEL

PREPAREDlREVlEWED BY:

Date:

VALIDATED BY:

APPROVAL BY:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

Task: Perform a crosstie of Decay heat Removal flow to the reactor vessel.

Alternate Path: No

JPM #: SimD (2K3) NRC [Bank #037]

KIA Ratincl/lmportance: 005A1.02 RO 3.3 SRO 3.4

Task NumberlPosition: 0050102010 I RO

Task Standard: Perform a crosstie of Decay Heat Removal flow to the reactor vessel with

DHP-1A in service.

Preferred Evaluation Location:

S i m u l a t o r x Plant-

Admin-

References:

OP-404, Rev. 133

Validation Time: 20 Minutes

Time Critical: No

Preferred Evaluation Method

Perform X Simulate-

Examiner:

Printed Name

Signature

Date

Comment:

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3:45 AM

SIMULATOR OPERATOR SETUP INSTRUCTIONS:

Restore the simulator to Mode 5 IC {IC # 19) with PZR steam bubble.

SIMULATOR OPERATOR INSTRUCTIONS:

Hang W s

on the following for the OP-209 clearance:

BSV-3 CIS

BSV-4 CIS

BSV-16 CIS

BSV-17 CIS

MUV-23lMUV-24 A Power

MUV-25lMUV-26 A Power

MUV-23lMUV-24 B Power

MUV-25lMUV-26 B Power

MUV-23 CIS

MUV-24 CIS

MUV-25 CIS

MUV-26 CIS

MUV-53 CIS

MUV-257 CIS

MSV-55 CIS

MSV-56 CIS

CFV-5 CIS

CFV-6 CIS

EFP-1 CIS

EFP-2 CIS

EFV-11 CIS

EFV-14 CIS

EFV-32 CIS

EFV-33 CIS

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TOOLSlEQUlPMENTIPROCEDURES NEEDED:

Radio (may be simulated)

Copy of OP-404

Replacement copies of OP-404 section 4.20

READ TO THE OPERATOR:

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and

reports on other actions when directed by you. Ensure you indicate to me when you understand

your assigned task. To indicate that you have completed your assigned task, return the handout

sheet to the examiner.

INITIAL CONDITIONS:

You are the Reactor Operator.

A DHP is running supplying reactor cooling through DHV-5.

Maintenance is to be performed on DHV-5.

INITIATING CUE:

The Control Room Supervisor directs you to crosstie flow and close DHV-5.

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EXAMINERS NOTE: FOR STEPS DENOTED AS CRITICAL STEP, WHICH HAVE

MULTIPLE ACTIONS, THE INDIVIDUAL REQUIRED ACTION WILL BE DENOTED CS. IF

NO INDIVIDUAL ACTIONS ARE DENOTED AS SUCH THEN ALL ACTIONS WITHIN THE

STEP ARE DEEMED CRITICAL.

STEP 1 :

Locate correct procedure.

STANDARD:

Candidate locates OP-404 Section 4.20

EXAMINERS NOTE:

When candidate identifies the correct procedure

and section provide himlher with Section 4.20 of

OP-404.

COMMENTS:

STEP 2:

(step 4.20.1) Ensure A

DH train in service.

Refer to Section 4.5

STANDARD:

NA

EXAMINERS NOTE:

Per the initial conditions the A DHR Train is in

service.

COMMENTS:

STEP 3:

Procedure Note:

If DHV-7 or 8 do not open electrically due to high differential

pressure across the valve(s), it may be necessary to open the

valve(s) manually.

STANDARD:

Candidate reads note.

COMMENTS:

SAT

JNSAT-

SAT

JNSAT-

SAT

JNSAT-

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STEP 4:

(step 4.20.2) Cross-Connect DH trains.

DETAIL

1.

ENSURE the following are CLOSED:

DHV-9, DH Recirculation to BWST

DHV-IO, (DHV-9 Bypass)

STANDARD:

Candidate notifies the PPO to ensure DHV-9 and DHV-10

are closed.

XAMINERS CUE:

Report as the PPO that DHV-9 and DHV-10 are

closed.

2OMMENTS:

SAT

JNSAT-

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STEP 5:

(step 4.20.2) Cross-Connect DH trains. (Continued)

DETAIL

2._____

Close DHV-211

3._-__

Place DHV-111 controller in manual and position to

-7 seconds OPEN from the CLOSED position

Place DHV-110 controller in MANUAL and adjust

flow to approximately 1550 gpm (CS)

4._---

5. Open the following: (CS)

_____- DHV-6, " B DH Outlet

___---

DHV-8, "A" DH Cross-tie

______ DHV-7, " B DH Cross-tie

STANDARD:

Candidate closes DHV-211 and verifies green (closed) light is lit

and red (open) light is off.

Candidate, starting from closed, holds DHV-111 in the open

direction for -7 seconds.

Candidate places DHV-110 controller in manual and adjust for

1550 gpm.

Candidate calls to PPO and directs him/her to energize DHV-7

and DHV-8.

Candidate places DHV-6, DHV-8, and DHV-7 in the open position

and observes red (open) light on and green (closed) light is off for

each valve.

2OMMENTS:

Critical Step

SAT

JNSAT-

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STEP 6:

(step 4.20.3) Transfer DHP-1A flow to "B" DH train.

DETAIL

1 .-__ Monitor crossover flow on DH-38-FI.

2._-Adjust

DHV-111 controller to maintain approximately 1550

3.----Close

DHV-5. (CS)

4.---Adjust

DHV-111 controller to maintain desired " B DH flow.

5.--Adjust

DHP-1A low amp alarm as desired per Section 4.29.

gpm "8" DH flow as read on DH-38-FI. (CS)

(CS)

I

I STANDARD:

Candidate locates DH-38-FI.

Candidate adjusts DHV-111 in manual to maintain 1550

gpm on DH-38-FI.

Candidate closes DHV-5.

I

Candidate adjusts DHV-111 to maintain -3000 gpm " B

DH

flow.

Candidate locates Section 4.29.

EXAMINER'S NOTE: DH-38-FI instrument referenced by the procedure

does not match the Simulator instrument which is labeled DH-38-Fll.

Inform the candidate as the CRS to establish =3000 gpm flow through

DHV-111. DH-38-FI will not indicate that high therefore use of the "A" DH

flow instrument will be necessary to establish desired flow rate.

Inform student that adjustment of low amps alarm is not required.

COMMENTS:

TERMINATION CUE: Stable flow of 3000 gpm through DHV-6 with " A DHP

running.

Critical Step

SAT

UNSAT-

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CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

"A" DHP is running supplying reactor cooling through DHV-5.

Maintenance is to be performed on DHV-5.

INITIATING CUE:

The Control Room Supervisor directs you to crosstie flow and close DHV-5.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimE (2K3) NRC [Bank#362] (SIMULATOR)

ALTERNATE PATH

SAFETY FUNCTION 5

INITIATE BUILDING SPRAY

VALIDATED BY:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task: Ensure Building Spray (BS) actuation.

Alternate Path: BSP-1A will not start in manual. BSV-4 is set on local.

JPM #: SimE (2K3) NRC [Bank #362]

K/A Rating/Importance: 026A3.01 RO 4.3 SRO 4.5

Task Number: 0260502001

Task Standard: Initiate Building Spray for high Reactor Building temperature using EM-225C.

Preferred Evaluation Location:

Simulator

In-Plant -

Admin -

Preferred Evaluation Method:

Perform X

Simulate -

References:

EM-225C, Rev. 2

Validation Time: 5 min.

Time Critical: No

Candidate:

Time Start :

Printed Name

Time Finish

Performance Ratine: SAT

UNSAT

Performance Time :

Examiner:

Printed Name

Signature

Date

Comment:

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3:47AM

SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

Restore simulator to IC # 67

prepared for this JFM.

2.

If creating this IC perform the following:

1 .A LOCA is in progress.

2.Reactor Building pressure is < 30 psig.

3.BSP-1A will not start in manual.

4.The BWST level is > 20 ft.

5.Use EOP-03 for setq conditions.

6.IC #63 (grandfather).

7.Input encl and enc2.

8.Acknowledge SCM alarm.

9.Check CRTs to ensure RB temperatures (if displayed) are high.

10. Activate LP for Bldl.

11. Set BSV-4 to local.

SIMULATOR OPERATOR INSTRUCTIONS:

1.

Booth operator will take the roles for the various operators for notifications

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TOOLS/EQUIPMENT/PROCEDURES NEEDED:

EM-225C

READ TO THE OPERATOR

Directions to the student

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be performed for this JPM. I will provide initiating cues and reports on other

actions when directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Reactor Operator.

A LOCA is in progress.

The Control Room Sqervisor has entered EOP-03.

Reactor Building (RB) temperatures are high.

The Emergency Coordinator (EC) has given concurrence to start Building Spray to reduce RB

temperatures.

Initiating Cues:

You are requested to start Building Spray (BSP-1A preferred) per section 4.6 of EM-225C.

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STEp:

Obtain a copy of appropriate procedure.

STANDARD:

EXAMINERS NOTE:

COMMENTS:

Candidate obtains a copy of EM-225C.

Provide student a copy of EM-225C.

STEP 2:

(step 4.6)

If a building spray pump is required, and EC concurrence has been

obtained, then perform the following:

STANDARD:

Candidate performs the following steps.

COMMENTS :

STEP 3:

(step 4.6.1)

Ensure load is available on the emergency diesel generators per EOP-

13, Rule 5.

STANDARD: Examinee determines the emergency diesel generators are not

supplying the bus. Step is N/A.

COMMENTS :

SAT

UNSAT-

SAT

UNSAT-

SAT

UNSAT-

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STEP 4:

(step 4.6.2)

Ensure Building Spray flow controls are set at 1500 gpm and Remoteif

pumps are aligned to BWST, or 1200 gpm and Local if aligned to the

RB sump.

STANDARD: Candidate verifies suction source to Building Spray pumps and

ensures the REMOTELOCAL lever on BSV-3 and BSV-4 is set to REMOTE and

the 1500 gpm. (BSV-4 is set to LOCAL and must be moved to REMOTE).

COMMENTS :

STEP 5:

(step 4.6.3)

Notify the control room to start one building spray pump.

EXAMINERS CUE. (If required) the TSC requests you start Building Spray.

STANDARD: Candidate rotates the control handle for BSP-1A to the start position

and notes that the pump did not start (shaft shear, low amps, no flow, red light ON

and green light OFF). Pump start failure is reported to the Control Room Supervisor.

Candidate repeats the guidance of EM-225C section 4.6 to start BSP- 1B (some of the

required steps may have been performed in parallel with BSP-1A alignment).

EXAMINERS NOTE:

Role-play as CRS when candidate discovers start

problem with BSP-1A. Direct candidate to establish

Building Spray flow with the B train.

COMMENTS :

TERMINATION CUE: BSP-1B running with 1500 gpm flow.

Critical Step

SAT

LTNSAT-

Critical Step

SAT

-TNSAT-

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

A LOCA is in progress.

The Control Room Supervisor has entered EOP-03.

Reactor Building (RB) temperatures are high.

The Emergency Coordinator (EC) has given concurrence to start Building Spray to reduce RB

temperatures.

INITIATING CUES:

You are requested to start Building Spray (BSP-1A preferred) per section 4.6 of EM-225C.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimF (2K3) NRC [Bank#004] (SIMULATOR)

SAFETY FUNCTION 6

PERFORM REQUIRED ACTIONS FOR A LOSS OF A 4160 ES BUS

PREPAREDIREVIEWED BY: _________________

Date: _______________

VAL1 DATED BY:

---


__

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task: Perform the required actions for a loss of a 4160 ES Bus

Alternate Path: No

JPM # SimF (2K3) NRC [Bank #004]

KIA Ratingllmportance: 062A2.12 RO 3.2 SRO 3.6

Task NumberlPosition: 0640402003 RO

Task Standard: Perform the required actions to restore power to the 4160 ES Bus from an Off-

Site source.

Preferred Evaluation Location:

Preferred Evaluation Method

S i m u l a t o r L Plant-

Admin-

References:

AP-770, Rev. 32

Perform X Simulate-

Validation Time: 13 Minutes

Time Critical: No

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Ratinq: SAT - UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

Comment:

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3:45AM

SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

Restore the simulator to a 100% MOL IC or IC# 68 developed for this

JPM.

2.

If creating IC perform the following:

Insert EDG-1A fail to start.

Insert a LOOP.

Allow simulator to run until plant is stable.

DeleteLOOP

Perform AP-770 up to step 3.33.

Open breaker 321 1.

Close breakers 4900 and 4902.

SIMULATOR OPERATOR INSTRUCTIONS:

None

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3:45AM

TOOLSIEQUIPMENTIPROCEDURES NEEDED:

Radio (may be simulated)

Copy of AP-770 Steps 3.33 thru 3.38

READ TO THE OPERATOR:

Directions to the student:

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be performed for this JPM. I will provide initiating cues and

reports on other actions when directed by you. Ensure you indicate to me when you understand

your assigned task. To indicate that you have completed your assigned task, return the handout

sheet to the examiner.

INITIAL CONDITIONS:

You are the Reactor Operator.

An undervoltage condition occurred on both 4160V ES Buses. A EDG failed to start. The B

EDG started and loaded the 9

4160 ES Bus. The Rx has tripped and EOP-02 immediate

actions are complete.

The Off-Site Power Transformer has been restored.

INITIATING CUE:

The Control Room Supervisor directs you to RE-ENERGIZE the A ES 4160V bus from the Off

Site Power Transformer. Starting at step 3.33 of AP-770.

Note: Do not restore components to the bus following restoration of power.

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3:45 AM

jTEP:

Candidate obtains AP-770

STANDARD:

Candidate should locate the control room copy of AP-770.

EXAMINERS NOTE:

After candidate locates AP-770 provide himlher with

AP-770 steps 3.33 through 3.38.

2OMMENTS:

STEP 2:

STATUS

Only 1 ES 4160V Bus energized.

STANDARD:

Candidate verifies the plant status of Only 1 ES 4160 Bus

energized.

2OMMENTS:

STEP 3:

(step 3.33) Prevent MUP Auto start on de-energized bus.

Ensure ES actuations are bypassed or reset:

Auto

Manual

Place MUP on de-energized bus in normal after stop.

STANDARD:

Candidate verifies that no ES Actuation has occurred and

ES Channels are in reset.

Candidate then ensures that MUP-1A and MUP-1 B are in

NormaCAfter-Stop.

2OMMENTS:

SAT

UNSAT-

SAT

UNSAT-

SAT

UNSAT-

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3:45AM

STEP 4:

(step 3.34) Ensure all ES 4160V feeder Bkrs are open on

de-energized bus.

3207

3209

3205

321 1

STANDARD:

Candidate locates affected breakers and ensures the

breakers are in the open position.

COMMENTS:

STEP 5:

(step 3.35) If EDG associated with de-energized bus is

running, then ensure proper EDG voltage and frequency.

STANDARD:

Candidate should note that the A EDG is not running.

COMMENTS:

STEP 6:

(step 3.36) If both ES 4160V Buses are energized, then GO

TO Step 3.41 in this procedure.

STANDARD:

Candidate should note that the A ES 4160 Bus is not

energized.

COMMENTS:

Zritical Step

SAT

JNSAT-

SAT

UNSAT-

SAT

UNSAT-

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STEP 7:

(step 3.37) Ensure ES Bus is available for recovery.

Notify PPO to verify lockouts are not tripped:

"868-3209 A EDG LOCKOUT RELAY" (A ES

41 60V SWGR Room)

Verify ES 4160V lockouts are not tripped:

86B-3205

86B-3207

866-321 1

If any lockout is tripped, then CONCURRENTLY

PERFORM Enclosure 1, Recovery of Faulted ES

Bus, in this procedure.

STANDARD:

Candidate notifies the PPO to verify lockouts are not

tripped.

Candidate verifies ES 4160 lockouts are not tripped.

EXAMINER'S NOTE:

When PPO called to check the 86B-3209 lockout, PPO

reports the lockout is not tripped.

COMMENTS:

SAT

JNSAT-

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STEP 8:

(step 3.38)

at any time, &I of the following exist:

A ES 4160V BUS de-energized

Fault does NOT exist

Any offsite power source available

Then energize A ES 4160V BUS.

If "DIESEL GEN A BREAKER CLOSED" annunciator

alarm (Q-02-03) is lit, then defeat A ES 4160V BUS

lockout:

Select feeder Bkr from available power source to

"CLOSE until "4KV ES BUS A DEAD annunciator

alarm clears (normally 4 0 seconds).

Depress"4160V ESA UV RESET" push button.

STANDARD:

Candidate notes that the " A ES 4160 ES Bus is de-

energized and off-site sources are available.

Candidate should note that alarm 002-03 is not in alarm.

Candidate closes selected breaker and holds until alarm

clears.

Candidate locates "4160V ESA UV RESET" push button

and depresses.

EXAMINER'S NOTE:

Inform the candidate that no fault exist on the "A" ES

4160 Bus.

If candidate questions which breaker to close tell him

to close in on normal source. Candidate should then

select the Off-Site Transformer.

SOMMENTS:

TERMINATION CUE: "A"4160 ES Bus Energized

END OF TASK

Xtical Step

?.AT

JNSAT-

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CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

An undervoltage condition occurred on both 4160V ES Buses. " A EDG failed to start. The " B

EDG started and loaded the " B 4160 ES Bus. The Rx has tripped and EOP-02 immediate

actions are complete.

The Off-Site Power Transformer been restored.

INITIATING CUES:

The Control Room Supervisor directs you to RE-ENERGIZE the " A ES 4160V bus from the Off-

Site Power Transformer, starting at step 3.33 of AP-770.

Note: Do not restore components to the bus following restoration of power.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimG (2K3) NRC [Bank #330] (SIMULATOR)

SAFETY FUNCTION 7

PLACE THE RPS IN SHUTDOWN BYPASS

PREPAREDmEVIEWED B Y

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task Place the RPS in shutdown bypass.

Alternate Path No

JPM: SimG (2K3) NRC [Bank #330]

K/A RatindImportance: 012A4.03 RO 3.6 SRO 3.6

Task Number: 0120102009

Task Standard Place the RPS in shutdown bypass using OP-507.

Preferred Evaluation Location:

Simulator X IrrPlant -

Admin -

References:

OP-507, Rev. 23

Validation Time: 15 min.

Time Critical: No

Preferred Evaluation Method:

Perform -

Simulate X

Candidate:

Time Start :

Printed Name

Time Finish

Performance Rating: SAT

UNSAT

Performance Time :

Examiner:

I

Printed Name

Signature

Date

Comment:

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

2.

Restore the simulator to a 100% MOL IC or IC# 3

developed forthis JPM.

If creating an IC perform the following:

1. A plant shutdown is in progress.

2. Control Rod Groups 1 through 7 are fully inserted.

3. The Reactor is tripped.

4. Reactor Coolant pressure is 1750 psig.

5. The High Flux Trip has been reset to 5% (0.032). (FOR THE PURPOSES OF THIS JPM

THE HIGH FLUX TRIP SETPOINTS ARE ONLY SIMULATED TO BE RESET TO

5%)

SIMULATOR OPERATOR INSTRUCTIONS:

Booth operator will take the roles for the various operators

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ToolsEquipmenWrocedures Needed:

1.

2.

OP-507, steps 4.14.1 through 4.14.4 should be already signed.

Replacement copies for Section 4.14

READ TO THE OPERA TOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be performed for this JPM. I will provide initiating cues and reports on other

actions when directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Reactor Operator.

A plant shutdown is in progress.

Control Rod Groups 1 through 7 are fully inserted.

The Reactor is tripped.

Reactor Coolant pressure is approximately 1750 psig.

The High Flux Trip has been reset to 5%.

Initiating Cues:

You are requested to place the RPS in shutdown bypass and reset all RPS channels.

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EXAMINERS NOTE: FOR STEPS DENOTED AS CRITICAL STEP, WHICH HAVE

MULTIPLE ACTIONS, THE INDIVIDUAL REQUIRED ACTION WILL BE DENOTED CS. IF

NO INDIVIDUAL ACTIONSARE DENOTED ASSUCH THENALL ACTIONS WITHIN THE

STEP ARE DEEMED CRITICAL.

STEp: Obtain a copy of appropriate procedure.

STANDARD: Candidate obtains a copy of OP-507. Steps 4.14.1 through 4.14.4 are

signed off.

ZOMMENTS:

m: (step 4.14.5)

PROCEDURE CAUTION: High Flux Trip must be reset to less than 5% RTP in all

four (4) RPS Channels prior to performing this step.

EFIC EFW actuation logic for loss of both MFW pumps is

automatically bypassed when the RPS is placed in

Shutdown Bypass.

PROCEDURE NOTE:

Place the Shutdown Bypass key in the Bypass position in all 4 RPS Channels.

-

A RPS Channel

-

B RPS Channel

-

C RPS Channel

-

D RPS Channel

STANDARD: Candidate obtains the key an docks the RPS cabinet doors.

Candidate obtains the shutdown bypass key for each RPS channel.

Candidate places each key in shutdown bypass key switch and rotates

to the bypass position. Candidate verifies Manual Bypass light at the

top of each cabinet is bright. Candidate initials and dates step.

ZOMMENTS:

SAT -

UNSAT -

Critical Step

SAT -

UNSAT -

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'EP -

3:

(step 4.14.6)

lOCEDURE NOTE: Performance of the previous steps in this section meets

the intent of the OP-209 requirement for placing RPS in

"SHUTDOWN BYPASS". The SSO must ensure that

the CRDs are not capable of being withdrawn until the

remaining steps are completed (refer to ITS 3.3.1).

YAMINER'S CUE

The Shutdown Bypass functional test has been

performed.

Ensure Shutdown Bypass functional test has been performed

RefertoITS 3.3.1 (SR3.3.1.4)

'ANDARD: Candidate initials and dates step.

IMMENTS:

'Ep: (step 4.14.7)

Reset shutdown bypass bistables in all four (4) RPS channels.

1 .-

2.-

Depress both output state and output memory

toggles on Shutdown Bypass bistable (CS)

Verify both output state and output memory lights

are dim

A RPS Channel

-

B RPS Channel

-

C RPS Channel

-

D RPS Channel

Verify the Subsystem Status light on Reactor Trip

Module is dim

'ANDARD: For each RPS cabinet the candidate depresses the output state and

-

3.-

output memory toggles on the shutdown bypass bistable and verifies

that both the output state and output memory lights are dim.

Candidate also verifies that the subsystem status light on the Reactor

Trip Module is dim. Candidate initials and dates step.

IMMENTS:

SAT -

JNSAT -

n 1 .

,ritical Step

SAT -

JNSAT -

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iTEp: (step 4.14.8)

Reset all four (4) RPS channels.

1 .-

2 .-

Depress subsystem reset toggle on Reactor Trip

module (CS)

Verify Protective Subsystem amber indicating

lights, on top of each cabinet, are dim for the

respective channel being reset

__

ARPSChannel

__

BRPSChannel

-

C W S

Channel

D RPS Channel

-

TANDAD
For each RPS cabinet the candidate depresses the subsystem reset

toggle on the Reactor Trip module and verifies that the protective

subsystem amber indicating lights are dim. Candidate initials and

dates step.

ZOMMENTS:

END OF TASK

Zritical Step

SAT -

JNSAT -

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Reactor Operator.

A plant shutdown is in progress.

Control Rod Groups 1 through 7 are fully inserted.

The Reactor is tripped.

Reactor Coolant pressure is approximately 1750 psig.

The High Flux Trip has been reset to 5%.

Initiating Cues:

You are requested to place the RPS in shutdown bypass and reset all RPS channels.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimH (2K3) NRC [New] (SIMULATOR)

ALTERNATE PATH

SAFETY FUNCTION 9

WGDT RELEASE TO VENTILATION

PREPARED/REVIEWED B Y

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

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ATTACHMENT 7

SIMULATOR JOB PERFORMANCE MEASURE

-

Task WGDT release to ventilation.

Alternate Path Yes

JPM: SimH (2K3) NRC

K/A Ratindmportance: 060AA2.05 RO 3.7 SRO 4.2

Task Number:

Task Standard Perform control room actions for a WGDT release.

Preferred Evaluation Location:

Simulator J

In-Plant -

Admin -

References:

OP-412B, Rev. 22

AP-250, Rev. 14

Validation Time: 10 min.

Preferred Evaluation Method:

Perform -

Simulate J

Time Critical: No

Candidate:

Time Start :

Printed Name

Time Finish

Performance Ratine: SAT

UNSAT

Performance Time :

Examiner:

Printed Name

I

Signature

Date

Comment :

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1. Restore to IC #11

0 Set WGDT activity to 1000000 (label TAAARL2)

0 Execute lesson plan #35 in NRCEXAM directory.

oTrigger Step 1

2.

If creating this IC perform the following:

1.

Fail as is AHF- 11A and/or B.

2.

Clear failure(s) conditional on switch being taken to the Trip position.

3.

Set RM-All to about 20K cpm.

4.

Set WGDT activity to 1000000 (label TAAARL2)

4.

Input WGDT leak (.0001) when Step 4.1.37 of OP-412B is started.

SIMULATOR OPERATOR INSTRUCTIONS:

1. Trigger LP Step 2 about a minute after the candidate assumes the watch.

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Tools/EquipmentIProcedures Needed:

1.

2.

Additional copies of AP-250.

OP-412B, Steps 4.1.1 through 4.1.36 should be already signed.

READ TO THE OPERATOR

Directions to the Student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be performed for this JPM. I will provide initiating cues and reports on other

actions when directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed your assigned task, return the handout sheet to the examiner.

Initial Conditions :

You are the Balance of Plant Operator.

WGDT release to ventilation is ready to be started.

OP-412B has been completed through step 4.1.36.

PPO is now performing step 4.1.37.

Initiating Cues:

You are requested to perform control room actions per OP-412B when requested by the PPO.

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STEp:

Candidate may obtain a copy of appropriate procedure.

STANDARD: Candidate may obtain a copy of OP-412B. Steps 4.1.1 through 4.1.36

have been completed per the cue.

COMMENTS:

STEp: (step 4.1.37) OP-412B

Start WGDT Release to Ventilation. (PPO)

STANDARD: No actions performed by candidate at this time.

COMMENTS:

SAT -

UNSAT -

SAT -

UNSAT -

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-3:

AP-250

EXAMINERS NOTE:

When the release is started a gas leak will develop

and trip RM-A3.

Enter AP-250.

STANDARD: Candidate will recognize entry conditions for AP-250 are mef enter

and perform the actions of the AP.

Candidate may use Prompt and Prudent actions to trip AHF-11A

however entry into the AP is required to verify correct actions taken.

2OMMENTS:

jTEP4: (step 3.1)

Ensure AUTO actions of affected radiation monitor(s).

STANDARD: Candidate will refer to Table 1 to ensure automatic actions have

occurred. Candidate will manually secure AHF-11A andor AHF-

11B.

ZOMMENTS:

l'ERMINATION CRITERIA: When both 11 fans are secured this JPM is

omplete.

END OF TASK

SAT -

UNSAT -

Critical Step

SAT -

UNSAT -

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CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

Initial Conditions :

You are the Balance of Plant Operator.

WGDT release to ventilation is ready to be started.

OP-412B has been completed through step 4.1.36.

PPO is now performing step 4.1.37.

Initiating Cues:

You are requested to perform control room actions per OP-412B when requested by the PPO.

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CRYSTAL RIVER UNIT 3

JPM COVER SHEET

SimSpare (2K3) NRC [Bank #250] (SIMULATOR)

SAFETY FUNCTION 2

RESTART A MAKEUP PUMP FOLLOWING AN RCS LEAK

ISOLATION

PREPAREDREVIEWED BY:

Date:

VALIDATED BY:

Date:

APPROVAL BY:

Date:

(Nuclear Training Supervisor)

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ATTACHMENT I

SIMULATOR JOB PERFORMANCE MEASURE

-

Task: Restart a Makeup pump following a Reactor Coolant System leak isolation

Alternate Path: No

-

JPM #: SimSpare (2K3) NRC [Bank #2SO]

K/A RatinpJImportance: 002A2.01 RO 4.3 SRO 4.4

Task NumberlPosition: 0020402013 RO

Task Standard: Restart a Makeup pump following a Reactor Coolant System leak isolation

Preferred Evaluation Location:

S i m u l a t o r 2 Plant- Admin-

References:

AP-520, Rev. S

Validation Time: 6 Minutes

Preferred Evaluation Method

Perform X Simulate-

Time Critical: No

Candidate:

Time Started:

Printed Name

Time Finished:

Performance Rating: SAT

UNSAT

Performance Time:

Examiner:

Printed Name

Signature

Date

Comment:

~

~~

~

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SIMULATOR OPERATOR SETUP INSTRUCTIONS:

1.

Restore the simulator to a 100% power MOL IC or IC# -

70 developed for this

JPM.

If creating IC perform the following:

TripRx.

Perform EOP-14 Enclosure 1 (Expert Mode, Encl)

Fail Event Points 0085 and 0089 FALSE. These are nuisance alarms.

Allow plant to stabilize (Le. OTSGs LLL, DFT level stable).

Lower pressurizer level setpoint to 100.

Allow pressurizer level to return to 100.

Initialize MUT level to 80.

When pressurizer level returns to loo, close MUV-49 and MUV-567.

Shutdown MUP- 1B.

StoreIC.

2.

SIMULATOR OPERATOR INSTRUCTIONS:

None

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TOOLS/EOUIPMENT/PROCEDURES NEEDED:

Radio (may be simulated)

COPY of AP-520

READ TO THE OPERATOR

Directions to tlx student:

I will explain the initial conditions, and state the task to be performed. All steps, including any required

communications, shall be performed for this P M . I will provide initiating cues and reports on other

actions when directed by you. Ensure you indicate to me when you understand your assigned task. To

indicate that you have completed your assigned task, return the handout sheet to the examiner.

INITIAL CONDITIONS:

You are the Reactor Operator.

AP-520 was entered when a small leak was found in the MU system.

The reactor was tripped.

The plant is now in stable Mode 3 conditions.

All MUF's had to be stopped to repair the leak.

The leak has now been repaired.

INITIATING CUE:

You are requested to restart MUP-1B starting with step 3.55 in AP-520.

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EXAMINERS NOTE: FOR STEPS DENOTED AS CRITICAL STEP, WHICH HAVE

MULTIPLE ACTIONS, THE INDIVIDUAL REQUIRED ACTION WILL BE DENOTED CS. IF

NO INDIVIDUAL ACTIONS ARE DENOTED AS SUCH THEN ALL ACTIONS WITHIN THE

STEP ARE DEEMED CRITICAL.

Obtain a copy of appropriate procedure.

STANDARD:

Operator obtains a copy of AP-520, starting with step 3.55.

COMMENTS:

SAT

UNSAT-

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STEP 2:

(Step 3.55) WHEN affected component is isolated OR repaired.

THEN prepare MUP for restart.

1.

IF EDG is supplying power to ES 4160V bus, THEN

ensure adequate EDG margin exists for MUP and required

cooling water pumps.

2.

Ensure MU control valves are closed MUV-16 and

MUV-3 1. (Cs)

3.

4.

Establish MUP cooling water supply.

Ensure MUP recirc. to MUT valves are open: MUV-53

and MUV-257.

5.

Ensure MUP main lube oil pump is running: MUP-2B

(CS)

Ensure MUP main gear oil pump is running: MUP-4B

(CS)

6.

STANDARD:

2OMMENTS:

Operator observes that the EDG is not supplying the bus

Operator selects control station for MUV-3 1 and MUV- 16 to

HAND by depressing pushbutton and verifying HAND white

light ON and AUTO Red light OFF, Operator uses toggle to

lower demand to 0 ensuring valves are closed. (MUV-3 1 may be

left in AUTO and dial rotated to 0).

Operator verifies red light ON and green light OFF for SWP-IC

and RWP- 1.

For each valve operator verifies red light ON and green light

OFF.

Operator verifies MUP-2B red light ON and green light OFF.

Operator rotates control handle for MUP-4B to statt and verifies

red light ON and green light OFF.

Critical Step

SAT

UNSAT-

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STEP 3:

STANDARD:

COMMENTS:

-

STEP 4:

STANDARD:

COMMENTS:

(Step 3.56) IF A Train MUP will be started, THEN ensure

suction alignment to MUT.

1.

IF MUP- 1C is NOT ES selected, THEN notify PPO to

select PUMP 3C on 4160V ES BUS 3B.5

Ensure the following are closed: MUV-73 and MW-62.

Ensure the following are open: MUV-58 and MUV-69.

2.

3.

Operator verifies ES select light for MUP-IC is ON.

Operator verifies green CLOSED light on and red open light OFF

for both valves.

Operator verifies red OPEN light ON and green CLOSED light

OFF for both valves,

(Step 3.57) IF B Train MUP will be started, THEN ensure

suction alignment to MUT.

N/A, A Train pump being started.

SAT

JNSAT-

SAT

UNSAT-

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STEP 5:

(Step 3.58) Start selected MUP.

STANDARD:

Operator rotates MUP-lB to start and verifies red light ON and

green light OFF. Operator should also verify amps increase.

EXAMINER'S CUE:

MUP-1B is running; the task is complete.

COMMENTS:

END OF TASK

Critical Step

SAT

UNSAT-

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CANDIDATE CUE SHEET

(TO BE RETURNED TO THE EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

You are the Reactor Operator.

M-520 was entered when a small leak was found in the MU system.

The reactor was tripped.

The plant is now in stable Mode 3 conditions.

All MUPs had to be stopped to repair the leak.

The leak has now been repaired.

INITIATING CUE:

You are requested to restart MUP-1B starting with step 3.55 in AP-520.

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ES-301

Administrative l'opics Outline

Forrii ES-301-1

Administrative Topic

(see Note)

Describe activity to be performed:

Zonduct of Operations

Perform a Daily Heat Balance Comparison

KIA - G2.1.23 RO 3.9 SRO 4.0

SP-312A [Modified Bank]

After completing heat balance determine required TS actions

KIA-G2.1.12 SR04.0

Equipment Control

Radiation Control

Emergency Plan

I

Perform a n RCS Water Inventory Balance per SP-317

WA - G2.2.12 RO 3.0 SRO 3.4

SP-317 [Direct]

After completing SP-317 determjne required TS actions

K/A - G2.1.12 SRO 4.0

Determine external reporting requirements per CP-151

KIA - G2.3.1 SRO 3.0

CP-151 & NUREG-1022 [New]

Determine Emergency Action Level after Simulator Scenario # 2.

K/A -G2.4.41 SRO 4.1

EM-202 lNew]

NUREG- 102 1, Draft Rev. 9

F:\\2003 NRC Exam\\OUTLINESUPMs\\NRC 2K3 SRO Only Outline Admin JPMs (301 -I).doc

ES-301

Administrative Topics Outline

Form ES-30 1- 1

Facility: Crvstal River Unit 3

Date of Examination: Aueust

. 25.2003

Exam Level RO

Administrative Topic

(see Note)

Conduct of Operations

Equipment Control

Radiation Control

Emergency Plan

Operating Test No.: 1

Describe activity to be performed:

Print Reading - Determine criteria for start of AHF-44B during a LOOP.

WA - G2.1.24 RO 2.8 SRO 3.1

Multiple electrical prints and flow diagrams [New]

Perform a Daily Heat Balance Comparison

KIA-G2.1.23 RO 3.9 SRO 4.0

SP-3 12A [Modified Bank]

Perform a n RCS Water Inventory Balance per SP-317

KIA - G2.2.12 RO 3.0 SRO 3.4

SP-317 [Direct]

Complete the State of Florida Notification Message Form and make

required notifications

K/A - G2.4.43 RO 2.8

EM-202 [New, Alternate Path]

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are

retaking only the administrative topics, when 5 are required.

NUREG- 1021, Draft Rev. 9

F:\\2W3 NRC Enam\\OUTLINESilPMs\\NRC 2K3 RO Only Outline Admin JPMs (301 -I).doc

ES-301

Administrative Topics Outline

Form ES-301- 1

Facility: Crvstal River Unit 3

Exam Level (circle one): ROISRO

Date of Examination: Aueust 25. 2003

Operating Test No.: 1

Administrative Topic

(see Note)

Conduct of Operations

~~

Equipment Control

Radiation Control

Emergency Plan

Describe activity to be performed:

RO & SRO -Print Reading - Determine criteria for start of AHF-44B

during a LOOP.

KIA - G2.1.24 RO 2.8 SRO 3.1

Multiple electrical prints and flow diagrams [New]

RO & SRO - Perform a Daily Heat Balance comparison

KIA- G2.1.23 RO 3.9 SRO 4.0

SP-312A [Modified Bank]

SRO Only - After completing heat balance determine required TS actions

KIA-G2.1.12 S R 0 4 . 0

KO & SliO - Perform a n RCS Water Inventory Balance per SP-317

KIA - G2.2.12 RO 3.0 SRO 3.4

SP-317 [Direct]

SRO Only - After completing SP-317 determine required TS actions

WA - G2.1.12 SRO 4.0

- Determine external reporting requirements per CP-151

KIA - G2.3.1 SRO 3.0

CP-151 & NUREG-1022 [New]

KO O d v - Complete the State of Florida Notification Message Form a n d

make required notifications

KIA - G2.4.43 RO 2.8

EM-202 [New, Alternate Path]

SlZO Only - Determine Emergency Action Level after Simulator Scenario

  1. 2.

KIA - G2.4.41 SRO 4.1

EM-202 [New]

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are

retaking only the administrative topics, when 5 are required.

NUREG- 102 1, Draft Rev. 9

F:\\2003 NRC Exam\\OUTLINESJPMs\\NRC 2K3 Combined Outline Admin JPMs (301-l).doc

ES-301

Control Roomnn-Plant Systems Outline

Form ES-301-2

System / JPM Title

Facility: Crvstal River Unit 3

Exam Level (circle one): RO/ SRO(1) I SRO(U)

Date of Examination: August 25.2003

Operating Test No.: 1

Control Room Systems (8 for RO: 7 for SROI; 2 or 3 for SRO-U)

Type

Safety

Code*

Function

a. CRDS - Transfer control rod to auxiliary power supply

WA- 001A4.03 RO 4.0 SRO 3.7 (OP-502)

1ROl

b. ESFAS - ES "B" HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

[RO, SRO-U, SRO-I]

c. PZR PCS - Perform PORV Exercise Test

WA- 010A3.01 RO 3.0 SRO 3.2 (SP-379)

[RO, SRO-U, SRO-I]

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

WA- 005A1.02 RO 3.3 SRO 3.4 (OP-404)

CSS - Ensure Building Spray actuation

[RO, SRO-USRO-I1

e.

WA - 026A3.01 RO 4.3 SRO 4.5 (EM-225C)

AC - Perform actions for loss of an ES 4 160V Bus

[RO,

SRO-I]

f.

WA-062A2.12 RO 3.2 SRO 3.6 (AP-770)

[RO, SRO-II

g. RPS - Place the RPS in Shutdown Bypass.

WA- 012A4.03 RO 3.6 SRO 3.6 (0P-202/507)

, h. WGDSPRM - Perform actions for an accidental Waste Gas leak

WA- 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

1x0, SRO-I]

[RO, SRO-I/

SPARE

MU- Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

D, S

1

A. D. S

2

L. N, S

3

L. D. S

4

A, D. S

5

A. M, S

6

L, D. S

7

A, C, N,

9

S

D. S

2

1 In-Plant Systems (3 for RO; 3 for SROI; 3 or 2 for SROU)

NUREG- 1 02 1, Draft Rev. 9

i. AFWIEFW - Place EFIC Channel in Tripped condition

WA- 061A2.05 RO 3.1 SRO 3.4 (OP-450)

IRO. SRO-I/

j. CCWS - Fill SW surge tank from the Fire Service system

WA- 028A4.03 RO 3.1 SRO 3.3 (EOP-14, Enclosure 2) /RO, SRO-U, SRO-II

k. CRD - Manually trip reactor from outside control room

WA- 02EAl.l RO 4.0 SRO 3.6 (AP-990)

[RO, SRO-U, SRO-I]

SPARE

FSIOTSG - Transfer excess secondary inventory to FST

WA- 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

F:\\2003 NRC Exam\\OUTLINESilPMs\\NRC 2K3 Combined Outline SIM-Plant lPMs (301-2).doc

N

4

D, R

8

A, D

1

D

2,8

ES-301

Control Roomfin-Plant Systems Outline

Form ES-301-2

a. CRDS - Transfer control rod to auxiliary power supply

b. ESFAS - ES "B"

HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

WA- 001A4.03 RO 4.0 SRO 3.7 (OP-502)

c. PZR PCS - Perform PORV Exercise Test

WA-010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

WA- 005A1.02 RO 3.3 SRO 3.4 (OP-404)

Facility: Crvstal River Unit 3

Exam Level: RO

D, S

1

A, D, S

2

L, N, S

3

L. D. S

4

Date of Examination: Aueust 25. 2003

Operating Test No.: 1

e. CSS - Ensure Building Spray actuation

WA- 026A3.01 RO 4.3 SRO 4.5 (EM-225C)

Control Room Systems (8 for RO; 7 for SROI: 2 or 3 for SRC-U)

A, D. S

5

System / JPM Title

f. AC - Perform actions for loss of an ES 4160V Bus

WA - 062A2.12 RO 3.2 SRO 3.6 (AP-770)

g. RPS -Place the RPS in Shutdown Bypass.

h. WGDS/PRM - Perform actions for anaccidental Waste Gas leak

WA- 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

WA- 012A4.03 RO 3.6 SRO 3.6 (OP-202/507)

SPARE

MU- Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

Code*

Function

I Type I Safety

A. M, S

6

L. D, S

7

A. C, N,

9

S

D, S

2

i. AFWEFW - Place EFIC Channel in Tripped condition

j. CCWS - Fill SW surge tank from the Fire Service system

CRD - Manually trip reactor from outside control room

WA- 061A2.05 RO 3.1 SRO 3.4 (OP-450)

WA - 028A4.03 RO 3.1 SRO 3.3 (EOP-14. Enclosure 2)

k.

WA- 02EAl.l RO 4.0 SRO 3.6 (AP-990)

SPARE

FS/OTSG - Transfer excess secondary inventory to FST

WA - 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

N

4

D. R

8

A, D

1

D

2.8

NUREG- 1021, Draft Rev. 9

FEW3 NRC Exam\\OUTLINESJPMs\\NRC 2K3 RO Only Outline MCR-Plan1 JPMs (301-2).dcc

.-

System / JPM Title

ES-301

Control Roomfln-Plant Systems Outline

Form ES-301-2

TYPe

Safety

Code*

Function

Date of Examination: Aueust 25. 2003

Operating Test No.: 1

Facility: Crvstal River Unit 3

Exam Level: SRO(1)

Control Room Systems (8 for RO: 7 for SROI; 2 or 3 for SRO-U)

~

b. ESFAS - ES "F

HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

c. PZR PCS - Perform PORV Exercise Test

WA- 010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

CSS - Ensure Building Spray actuation

WA- 005A1.02 RO 3.3 SRO 3.4 (OP-404)

e.

WA - 026A3.0 1 RO 4.3 SRO 4.5 (EM-225C)

f. AC - Perform actions for loss of an ES 4160V Bus

WA - 062A2. 12 RO 3.2 SRO 3.6 (AP-770)

g. RPS - Place the RPS in Shutdown Bypass.

WGDS/PRM - Perform actions for an accidental Waste Gas leak

WA- 060AA2.05 RO 3.7 SRO 4.2 (AP-250)

WA- 012A4.03 RO 3.6 SRO 3.6 (OP-202/507)

h.

SPARE

MU - Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

A, D. S

2

L. N, S

3

L. D. S

4

A. D, S

5

A, M. S

6

L, D. S

7

A, C, N,

9

S

D. S

2

i. AFW/EFW - Place EFIC Channel in Tripped condition

WA- 061A2.05 RO 3.1 SRO 3.4 (OP-450)

j. CCWS - Fill SW surge tank from the Fire Service system

WA- 028A4.03 RO 3.1 SRO 3.3 (EOP-14. Enclosure 2)

k. CRD - Manually trip reactor from outside control room

WA- 02EAl.l RO 4.0 SRO 3.6 (AP-990)

SPARE

FS/OTSG - Transfer excess secondary inventory to FST

N

4

D. R

8

A, D

1

D

2,8

NUREG- 1021, Draft Rev. 9

F\\2003 NRC Exam\\OUTLINE3JPMs\\NRC 2K3 SRO-I Only Outline MCR-Plant JPMs (301 -2).dcc

ES-301

Control Roomfin-Plant Systems Outline

Form ES-301-2

Facility: Crvstal River Unit 3

Exam Level: SRO(U)

Operating Test No.: 1

Date of Examination: August 25. 2003

Control Room Systems (8 for RO; 7 for SROI; 2 or 3 for SROU)

System / JPM Title

Type

Safety

Code*

Function

b. ESFAS - ES "B" HPI Diverse Containment Isolation Test

WA- 013A3.01 RO 3.7 SRO 3.9 (SP-358A)

c. PZR PCS - Perform PORV Exercise Test

WA- 010A3.01 RO 3.0 SRO 3.2 (SP-379)

d. RHR - Perform a crosstie of DHR flow to the Reactor Vessel

WA - 005A1.02 RO 3.3 SRO 3.4 (OP-404)

SPARE

MU - Restart a MUP Following an RCS Leak Isolation

WA- 002A2.01 RO 4.3 SRO 4.4 (AP-520)

NUREG- 102 1, Draft Rev. 9

F\\2003 NRC Exam\\OUTLlNEWPMs\\NRC 2K3 SRO-U Only Oulline MCR-Plant lPMs (301 -2).doc

A. D, S

2

L,N.S

3

L, D, S

4

D, S

2

j. CCWS -Fill SW surge tank from the Fire Service system

WA- 028A4.03 RO 3.1 SRO 3.3 (EOP-14. Enclosure 2)

k. CRD - Manually trip reactor from outside control room

WA-02EAl.l R04.0 SR03.6 (AP-990)

SPARE

FS/OTSG - Transfer excess secondary inventory to FST

WA - 037AK3.07 RO 4.2 SRO 4.4 (EOP-14 Enclosure 9)

D, R

8

A. D

1

D

2, 8