ML032940455
| ML032940455 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| 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
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
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:
G2.1.12 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.
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
Controlled Bleed Off
gpm
gum
gPm
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
8
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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:
G2.1.12 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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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
- 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
7/18/2003
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
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
DEG F
DEG F
DEG F
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
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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:
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
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
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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
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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-
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:
UNSAT-
Critical Step
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
JNSAT-
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
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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
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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 -
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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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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.
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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:
F:\\2003 NRC Exam\\JPMs\\PlantK (2K3) NRC [Bank #085].doc
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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.
F:\\2003 NRC Exam\\JPMs\\PlantK (2K3) NRC [Bank #085].doc
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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:
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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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
"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"
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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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
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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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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:
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
UNSAT
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
UNSAT
Critical Step
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
UNSAT
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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
JNSAT
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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
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
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 :
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
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
JNSAT
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.
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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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ATTACHMENT 7
SIMULATOR JOB PERFORMANCE MEASURE
-
Task Transfer a single control rod to the Auxiliary Power Supply
Alternate Path: NO
-
JPM #:
K/A RatindImDortance:
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
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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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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.
F:\\2003 NRC ExamUPMs\\SimA OK3) NRC [Bank#294].doe
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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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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:
UNSAT-
Critical Step
UNSAT-
Critical Step
UNSAT-
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-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
JNSAT-
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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:
UNSAT-
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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
UNSAT-
UNSAT-
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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:
JNSAT-
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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:
JNSAT-
JNSAT-
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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:
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:
UNSAT-
UNSAT-
UNSAT-
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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:
JNSAT-
UNSAT-
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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
JNSAT-
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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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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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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)
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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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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.
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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.
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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:
JNSAT-
n ..
-ritical Step
JNSAT-
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:
JNSAT-
Critical Step
LJNSAT-
Critical Step
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
Meter for ultrasonic indication is in the Valve Open region.
STANDARD: Candidate locates and verifies the above indications.
ZOMMENTS:
n ..
,ritical Step
JNSAT-
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:
JNSAT-
Critical Step
UNSAT-
UNSAT-
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-
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.
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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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
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:
JNSAT-
JNSAT-
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:
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
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
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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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 :
UNSAT-
UNSAT-
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
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
LTNSAT-
Critical Step
-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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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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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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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:
UNSAT-
UNSAT-
UNSAT-
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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
JNSAT-
UNSAT-
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:
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:
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)
F\\2003 NRC Exam\\JPMs\\SimSpare (2K3) NRC [Bank #250].doc
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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:
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
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.
JNSAT-
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
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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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
SP-312A [Modified Bank]
After completing heat balance determine required TS actions
KIA-G2.1.12 SR04.0
Equipment Control
Radiation Control
I
Perform a n RCS Water Inventory Balance per SP-317
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
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
Operating Test No.: 1
Describe activity to be performed:
Print Reading - Determine criteria for start of AHF-44B during a LOOP.
Multiple electrical prints and flow diagrams [New]
Perform a Daily Heat Balance Comparison
SP-3 12A [Modified Bank]
Perform a n RCS Water Inventory Balance per SP-317
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
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
Describe activity to be performed:
RO & SRO -Print Reading - Determine criteria for start of AHF-44B
during a LOOP.
Multiple electrical prints and flow diagrams [New]
RO & SRO - Perform a Daily Heat Balance comparison
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
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
- 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
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
Control Roomfin-Plant Systems Outline
Form ES-301-2
a. CRDS - Transfer control rod to auxiliary power supply
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
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)
~
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
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