ML040220069
| ML040220069 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 01/15/2004 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Stall J Florida Power & Light Co |
| References | |
| 50-250/03-301, 50-251/03-301 50-250/03-301, 50-251/03-301 | |
| Download: ML040220069 (155) | |
See also: IR 05000250/2003301
Text
Draft Submittal
(Pink Paper)
TURKEY POINT BE@. 2003
EXAM %0-258/2003-301
DECEMBER 3 - 15, 2003
.Through
Administrative Ouestions/JPMs
Job Classification:
JPM Title:
JPM Number:
JPM Type:
Normal Path
JPM Rev. Date:
10/13i03
Time Validation:
XX minutes
Perform a Reactivity Management Calculation
Admin. $1 Conduct ofOps. $1
Time Critical:
NO
KA:
G.2.1.4 (3.4M.4) pg. 2-1
The applicable method(s) of testing which may he used:
PERFORM IK CONIROI. ROOM OR CLASSROOM
Task Standards:
1.
Number of gallons of boric acid calculated to within + or - 5% (30 galions) of
number of gallons shown on Answer Key.
Required Materials:
1.
2.
References:
Attachment 5 of 0-OP-046, CVCS - Boron Concentration Control
Unit 3 Plant Curve Book
1.
2.
3.
0-OP-046, CVCS -- Boron Concentration Control
3-GOP-103, Power Operation to Hot Standby, Step 5.4.1
Unit 3 Plant Curve Book
Terminating Cues:
Applicant returns completed Attachment 5 of 0-OP-046 to examiner.
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Perform a Reactivity Management ralcuiation.
UIRECIIONS:
..~~..
The evaluator will explain the initial conditions of the task to be performed and will provide the
initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.
.~~
INITIAL C0NDITII)NZ;
1.
Unit 3 was at 95% power when the decision was made to reduce power to 40% to
perform the turhine valve test.
Thc following conditions exist before the power change:
a.
Reactor Power:
95%
b.
Core Age:
4,000 MRIYMTU
c.
Boron Concentration:
1500 ppin
d.
Rod Height:
D-200
e.
BAST Concentration:
5420 ppm
The following conditions are desired after the power change:
a.
Reac.tor Power:
40%
b.
Rod Height:
D-110
2.
3.
INIIIATIKG CUE:
You are the Unit 3 KCO.
3-GOP-103, Power Operation to Hot Standby, Step 5.4.1, directs you to calculate the
reactivity addition necessary for the required power reduction using 0-OP-046, CVC:S-
BORON COXEXTRATION CONTROL., Attachment 5 .
2
PERFORM A REACTIVITY
MANAGEMENT CALCULATION
Examiner Instructions:
Hand the:
(1) Initial Conditions Sheet,
(2) Blank copy of Attachment 5 of 0-OP-046
(3) Unit 3 Plant Curve Book
(4) calculator
( 5 ) pencils
to the Applicant and read the following:
L will explain the initial conditions of the task and will provide thc initiating ciic. Ensure
you indicate to me when you understand your assigned task.
INITIAI, comImNs:
~.
1.
Unit 3 was at 95?6 power when the decision was made to reduce power to 30% to
perforin :he turhinc valve test.
The following conditions exist before the power change:
a.
Reactor Power:
95%
b.
Core Ape:
3,000 MWDiM'II:
c .
Boron Concentration:
1500 ppni
e.
HAS?' Concentration:
5720 ppni
'The following conditions are desire.d after the power change:
a.
Reactor Power:
40'!io
i.
7
d.
Rod Height:
r ) - m
3.
h.
Rod 1-leight:
D
E
10
You arc the [!nit 3 KCO.
3-G01'-103, "Power Operation to Hat Standby", Step 5.4.1, directs you to calc.ulate the
reactivity addition necessary for the required power reduction using 0-OP-046, C V C S
BORON COh'C:ENTRATION CONTROL, Attachment 5.
3
PERFORM A REACTIVITY
MANAGEMENT CALCULATION
- C) ELEMENT I : Calculate Change in Rod Worth.
3TANDAWDS:
I .
Performs CMculation #I as follows:
a.
Reviews PCB Section 2, Figure 5 (4,000
MWDIMTU) to determine rod worth at
D-200: 40 pcm
b.
Reviews PCR Section 2, Figure 5 (4,000
MWDIh4TU) to determine rod worth at
D-200: 376 pcm
c.
Subtracts 376 pcm from 40 pcm to
determine reactivity insertion from change
in rod height: -336 pcm.
ZOMMENTS:
Time Start:
UNSAT
4
PERFORM A REACTIVITY
MANAGEMENT CALCULATION
(C) ELEMENT 2: Calculate Change in Power Defect
STANDARDS:
1.
Perfomis Calculation #2 as follows:
a.
Reviews PCB Section 2, Fibare 6A (4,000
MWD/MTU & 1500 pprn) to determine power
defect at 95% power: 1320 pcm
Reviews PCW Section 2, Figure 6A (4,000
MWDIMTU & 1 500 ppm) to determine power
defcct at 40% power: 598 pcm
Subtracts 598 pcrn from 1320 pcm to
determine reactivity insertion from change
in power: -1 722 pcm.
b.
c.
COMMENTS:
NOTE:
UNSAT
PERFORM A REACTIVITY
4 power defect to -336 pcm change due to
A rod position to get: +386 pcm
MANAGEMENT CALCULATION
(C) ELEMENT 3: Calculate Combined Effects ofRods and
Power Defect
STANDARDS :
1.
Performs Calculation #3 as follows:
COMMENTS:
NOTE:
I
6
PERFORM A REACTIVITY
I
MANAGEMENT CALCULATION
L
Ci ELEMENT 4: Calculate Desired Boron Concentration
-__--
-
I
b.
Reviews PCB Section 2, Figure I A (4,000
MWD/MTU) to determine boron worth at
1500 ppm: -12,541 PCtn
c.
Subtracts combined effects of rods and power
defect (+38h pcrn) from present boron worth
(-12,541 pcm) to determine desired boron
worth: -12, 927 pcm
Reviews PCB Section 2, Figure 7A (4,000
MWDIMTU) to determine boron concentration
at boron worth of -12,927 pcm: 1550 ppni
d.
COMMENTS:
NOTE:
Standard 1 .a is not critical for this element.
STANDARDS:
Performs Calculation #4 as follows:
I
!
--
I
7
PERFORM A REACTIVITY
MANAGEMENT CALCUIATION
_ _ _ _ _ _
~~-
- e) ELEMENT 5: Calculate Gallons of Boric Acid
Required
STANDARDS:
1.
Recognizes that desired boron concentration is
higher than the current boron concentration and
calculation #5 is NIA.
2.
Performs Calculation #6 as follows:
COMMENTS:
NOTE:
t or - 5% error equals an acceptable range of
575 to 635 gallons ofBoric Acid. This takes
into account rounding numbers and table
interpolations.
END OF JPM
-SAT
UNSAT
8
Job Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Validation:
lime Critical:
Krl:
Shift Manager
Analyze Tech Specs with a Startup Transformer 00s
Admin. #2 Conduct of Ops. ii2
Noiinal Path
10/13:03
XX minutes
NO
2.1.12 (2.9/4.0) pg. 2-2
Thc applicable method(s) of testing which may be used:
PERFORM IN CONTROL ROOM OR CLASSROOM
Task Standards:
1.
Tech. Specs. Applicable LCOs and Action Statements evaluated
correctly and Required Actions identified for both Units.
Required Materials:
1.
Technical Specifications, Section 3.8.1.1.
References:
1.
2.
3.
Terminating Cues:
Actions required per Tech Specs for Startup Transformer inoperability
identified for Unit 3 and IJnit 4.
Technical Specifications, Section 3.8. I . I.
0-ADM-536, Technical Specification Rases Control Program
5610-T-E-1591, Sheet 1, Operating Diagram - Electrical Distribution.
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Analyze Tech. Specs for Unit 4 Startup Transformer inoperability with IJnit 4 initially at
100% power and IJnit 3 initially in Mode 4.
I
DIRECTIOKS:
The evaluator will explain the initial conditions of the task to be performed and will
provide the initiating cue. Ensure you indicate to the evaluator when you undcrstand
your assigned task.
_______
INITIAL. CONDITIONS:
1.
2.
INITIATING CUE:
You are the Shift Manager and you have been informed that inspection of switchyard
disconnect switch 8664 ha5 revealed severe degradation due to corrosion and 8G67 nmst
be isolated and replaced immediately causing Unit 4 Startup Transformer to be
Station Area Operations (S40) predicts the Unit 4 Startup Transfornler will be
inoperable for 5 days.
On the Applicant Answer Sheets provided, as the Shift h4anager you are to:
1)
Unit 4 is at 100% power.
Unit 3 is in Mode 4 with Tavg = 348°F and heating up for plant startup.
Determine if the applicable Limiting Condition(s) for Operation (LCO(s)) are
satisfied for each unit.
For any I,CO(s) that are not satisfied, describe glJ required actions per the
applicable Action Statements.
For any options that may be provided within the applicable Action Statements,
select the aDpropriate option based on the conditions provided in the Initial
Conditions and the Initiating Cue.
For IJnit 3? Identify any other operiltor actions required by Tech. Specs. related to
the unit heat-up.
2)
3)
4)
2
ANALYZE TECH SPECS WITH UNIT 4
STARTUP TRANSFORMER 00s
Examiner Instructions:
Hand the Initial Conditions Sheet and Applicant Answer Sheets to the Applicant and read
the following:
tZnalyze Tech. Specs for Unit 4 Startup Trmsfonner inoperability with IJnit 4 initially at
IOO% power and Unit 3 initially in Mode 4.
1 will explain the initial conditions of the task and will provide the initiating cue. Ensure
you indicate to me when you understand your assigned task.
..
INITIAL
. . . ..
CQ8pm-S.;
1.
-I
i.
[!nit 4 is at 100% piwcr.
IInit 3 is in Mode 4 with Tavg - 348°F and heating up for plant startup.
INLTIATING CIJE:
You are the Shift hfanager and you have been infornied that inspection of switchyard
disconncc.t switch 8667 has rcvcaled severe dcgra&tion cine to corrosion arid 8G67 must
be isolated and replaced immediately causing Unit 4 Startup Transformer to be
Station Area Operations (SAO) predicts tlic Unit 4 Startup Transfornier will be
inoperable for 5 days.
On the Applicant Answer Sheets provided, as the Shifl Manager you are to:
1) Determine if the applicable I.irniting Condition(s) for Operiitiori (l.CC)(s)) are
satisfied for
unit.
2) For any LCO(,sj that are not satisfied, describe all. required actions per the applicable
Action Statements.
.~
~ .....
~
3 ) For any options that may be provided within the applicable Action Statements, &
t h e a m I m m g t i . o s based on the conditions provided in the Initial Conditions and
the Initiating Cue.
4) For Unit 3, Identify any other operator actions required by Tech. Specs. related to the
unit heat-up.
3
ANALYZE m e H SPECS WITH
UNIT 4 STARTUP TRANSFORMER 00s
ELEMENT 1 :
Obtain Required Materials.
COMMENTS:
NOTE:
The applicant must analyze applicable Tech.
Spec. 3.8.1.1 on Page 3/4 8-1.
rime Start:
I_
mTSAT
ANALYZE TECH SPECS WITH
UNIT 4 STARTUP TRANSFORMER 00s
..
~.
- C) ELEMENT 2: Evaluate Tech. Spec. 3.8.1.1 for
applicability to Unit 4.
S TANDAKDS :
1.
2.
Determines LCO 3.8.1.1 .a is not satisfied for Unit 4.
Applies Action Statement a. (page 3/4 8-2) as follows:
e (Surveillance 4.8.1.1.1 .a, to)# demonstrate
operability of the Unit 3 SU transformer, must be
performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8
hours thereafter.
e Based on estimated return to service, opts to reduce
power to ~ 3 0 %
within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.*
0 Recognizes that based on this option, power
operation may continue for up to 30 days from the
timc of the SU Transformer inoperability and if
after 30 days, the SU Transformer is still not
operable, Unit 4 must be shut down to Hot Standby
(within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the
following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)#.
UNSAT
5
- C) ELEMENT 2: Evaluate Tech. Spec. 3.8. I. 1 for
applicability to Unit 4. (continued)
ZOMMENTS:
VOTE:
- Information in parenthesis () not critical.
TOTE:
- Because Unit 4 is in Mode I, two choices are
available regarding continued operation:
Reduce power to <30% within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and power
operation may continue for up to 30 days from the time of
the SU Transformer inoperability.
Continue operation at >30 YO power for a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
(24 plus an additional 48).
In either case when the 30 days or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is
up, if the SU Transformer is not yet restored to
operability, Unit 4 must be shut down to Hot
Standby within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Note that Option I is the correct choice for this
situation with the estimated 00s time of the SU
Transformer being 5 days. Option 2 would
force unit shutdown to Mode 3 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
which would put the unit in natural circulation
cooling. This undesirable situation is discussed
in 0-ADM-536, Page 94.
-.
UNSA
6
ANALYZE TECH SPECS WITH
UNIT 4 STAKTUP TRANSFORMER OQS
C) ELEMENT 3: Evaluate Tech. Spec. 3.8.1.1 for
applicability to Unit 3.
STAND ARL) S :
I.
Determines LCO 3.8.1.1.a is not satisfied for Unit 3.
!.
Applies Action Statement a. (page 314 8-2) as
follows:
(Surveillance 4.8.1.1. I .a, to)# demonstrate
operability of the Unit 3 SU transformer, must be
performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per E:
hours thereafter.
0 Recognizes that Unit 3 is in a 30 day Action
Statement starting when the SU Transformer is
declared inoperable. If the SU Transformer is
not returned to operability at the end of those 30
days, the unit must be placed in Cold Shutdown
(within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)#.
0 Recognizes that the Unit 3 heatup must he
stopped immediately prior to the imminent Mode
change to Mode 3. (This is required by Tech.
Spec. 3.0.4)#. (page 3/4 0-1)
VOTE:
- Information in parenthesis () not critical.
END OF JPM
-SAT
UNSAT
I
Admin. JPM #2 - Analyze Tech. Specs. With Unit 4 SU
Transformer 00s
Applicant Answer Sheet for Unit 4
For Unit 4, identify any LCOs that are not satisfied.
For m y LCO(s) that are not satisfied, describe all required actions per the
appiicahle Action Statements.
For any options that may he provided within the applicable Action Statements,
~.
select t h e u ~ r q d e - ~ q ~ p m
based on the conditions provided in the Initial
Conditions and the Initiating Cue.
Admin. JPM #2 - Analyze Tech. Specs. With Unit 4 SU
Transformer 00s
Applicant Answer Sheet for Unit 3
Par Unit 3, identify any LGOs that are not satisfied.
For any IJCO(s) that are not satisfied, describe all required actions per the
applicable Action Statements.
For any options that may be provided within the applicable Action Statements,
-~
select the a t o p r i a t e option based on the conditions provided in the Initial
Conditions and the Initiating Cue.
Identify any other operator actions required hy Tech. Specs. related to the unit
heat-up.
Admin. JPM ff2 - Analyze Tech. Specs. With Unit 4 SU
Transformer 00s
Master Answer Sheet for Unit 4
DO NOT GIVE TO APPLICANT!
For Unit 4, identify any LCOs that are not satisfied.
e
LCO 3.8.1.1.a ia not satisfied for llnit 4
For any IJCO(s) that are not satisfied, describe ail required actions per the
applicable Action Statenienb.
demonstrate operability of the Unit 3 SG transfomier within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at least once per 8
hours thereafter.
Because lJnit 4 is in Mode 1, two choices arc available regarding continued operation:
Option 1:
Reduce power to 4 0 % within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and power operation may
continue for up to 30 days from the time of the SL; Transformer inoperability.
-. OK
Option 2:
additional 4X).
Continue operation at >30 04 power for a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (24 plus an
In either case when the 30 days or 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is up if the SI! Transformer is not yet restored to
operability, Unit 4 must be shut down to Hot Standby (urithin 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown
within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)#.
For any options that may be provided within the applicable Action Statements,
select
. the amrolariate op-
based on the conditions provided iaa the Initial
Conditions and the Initiating Cue.
Option 1 is the correct choice (for this situation with the estimated 00s time ofthe SlJ
Transformer being 5 days. Option 2 would force unit shutdown to Mode 3 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> which
would put the unit in natural circulation cooling. This undesirable situation is discussed in 0-
AIM-536, Page 94.) #
- i
Information in parenthesis () not critical.
Admin. JPM #2 - Analyze Tech. Specs. With Unit 4 SU
Transformer QQS
Master Answer Sheet for Unit 3
DO NOT GIVE TO APPLICANT!
For Unit 3, identify any LCOs that are not satisfied.
LCO 3.X.I.l.a is not satisfied for linit 3.
For any LCO(s) that are not satisfied, describe all required actions per the
applicable Action Statements.
demonstrate operability of the Unit 3 SU transformer, must he performed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and at
least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
Recognizes that Unit 3 is in a 30 day Action Statement starting when the SIJ Transformer is
declared inoperable. If the SU Transformer is not returned to operability at the end of those
30 days, the unit must be placed in Cold shutdown (within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />)#.
For any options that may be provided within the applicable Action Statements,
select tlire-mpriateo&
based on the conditions provided in the Initial
Conditions and the Initiating Cue.
Not Applicable ~- No options offered.
Identify any other operator actions required by Tech. Specs. related to the
unit heat-up.
Recognizes that the Unit 3 heatiip must be stopped immediately prior to the iiruninent Mode
change to Mode 3. (This is required by Tech. Spec. 3.0.4)#. (page 3 4 0-1)
- Information in parenthesis () not critica1.
Job Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Validation:
I ime Critical:
m:
I ,.
Shift 1kinager
Determine Contingency Actions in the Event of the Loss of a
CCW Pump During Reduced Inventory Operations
Admin. tf3 Equipment Control
Normal Path
10113103
XX minutes
NO
3.2.2.18 (2.313.6) pg. 2-7
The applicable method(s) of testing which may be used:
PERFORM IN CONTROL ROOM OR CLASSROOM
Task Standards:
1.
Required Materials:
1.
References:
1,
Terminating Cues:
1.
Correct Contingency Actions Identified
Correct Contingency Actions Identified (Ref. Enclosure 6, Page 1 of 9).
0-ADM-05 1, Outage Risk Assessment and Control
0-ADM-051. Outage Risk Assessment and Control
Initial Conditions Sheet
(To be given to Applicant)
Determine Contingency Actions
DIRECTIONS:
The evaluator will explain the initial conditions of the task to be performed and will
provide the initiating cue. Ensure you indicate to the evaluator when you understand
your assigned task.
INITIAL CONDITIONS:
1.
2.
3.
4.
5.
Unit 4 was shutdown 11 days ago.
The RCS is in Reduced Inventory Operations.
Unit 4 is in noimal electrical alignment for the shutdown conditions.
4A CC.W Pump motor fails atid the C.CW pump is declared OOS.
Plant conditions do not allow for realignment of plant electrical buses.
INITIATING CUE:
You are the Shift Manager.
Identify applicable Contingency Action(s) (if any) based on the loss ofthe 4A CCW
pump.
2
DETERMINE CONTINGENCY ACTIONS
DUE TO LOSS OF CCM7 PUMP
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
I will explain the initial conditions ofthe task and will provide the initiating cue. E mure
you indicate to me when you iniderstand your assigned task.
.~
INITIAL CX)?Jul~ION S:.
I.
2.
3 .
4.
5.
Unit 4 was shutdown 11 days ago.
The RCS is in Reduced Inventory Operations.
I.Jnit 4 is in norniai electrical alignment fcx the shutdown conditions.
4%
C:CW Pump motor fails and the CCM; pump is declarcd 00s.
Plant conditions do not allow for realignment of plant electrical buses,
__ INITIATING CUE-;
Yau are the Shift Manager.
lctcntify applicable Contingency Action(s) (ifany) based on the loss ofthe 4A CC.W
pump.
3
DETERMTNE CONTINGENCY ACTIONS
DUE TO LOSS OF CCW PUMP
ELEMENT 1:
Obtain 0-ADh4-05 I.
STANDARDS :
1.
Obtains copy of O-ADM-05 1, Outage Risk
Assessment and Control.
Examiner NOTE: If performed in a classroom setting, the
applicant will bc given a copy of 0-ADR4-0S 1 as part of
the set up for the JPM. In this case, identifying O-ADM-
OS 1 and checking for OTSCs will not be done.
2.
Verifies procedure is latest revision and there are
no outstanding applicable OTSCs.
COMMENTS:
NOTE:
If perfomied in the control room or
simulator, the applicant will look up the
latest revision date and verif>r the OTSC:
status in Lotus Notes. Note that the
applicant will use the frozen revision of O-
ADM-05 1, regardiess of the revision date in
Lotus Notes. Ifthe appCicant qacesfiosrs the
dijJermce, s&te; Kw the provided coggt of
0-A DM-05 1.
rime Start:
__I
UNSAT
A
DETERMIKE CONTINGENCY ACTIONS
DUE TO LOSS OF CCW PUMP
(C) ELEMENT 2: Identify Correct Enclosure.
STANDARDS:
1.
Identifies Enclosure 6 as the correct enclosure.
COMMENTS :
NOTE:
Enclosure 6 is the correct enclosure based on the
following:
a.
Enclosure 6 is for Phase FI which is
defined in Step 4.12.1 as > 240 hours0.00278 days <br />0.0667 hours <br />3.968254e-4 weeks <br />9.132e-5 months <br />
following unit shutdown.
Note that the IC stated the Unit had been
shutdown for 11 days.
b.
Enclosure 6 is for RCS temperature
<200"F without KCS Loops available.
Note that the IC stated Reduced
Inventory, a condition that requires
temperature be < 200°F and renders RCS
loops not available.
5
~
DETERMINE CONTINGENCY ACTIONS
I--- -
I
DUE TO LOSS OF CCU PUMP
_ - _ _ _ _ _ I _
~
__--
c
ELEMENT 3: Identrfy CCW System Condition h m
Meeting Enclosure 6 Criteria.
STANDAKDS:
I.
Reviews Enclosure 6 and discovers under Decay Heat
Removal Function that two CCW Pumps are
required. (Encl. 6, pg. 1 of 9)
Notes that 2 CCW pumps are operable (4B and 4C)
but the associated asterisk * further requires both
pumps be powered from independent power sources if
KCS level is lower than 3 feet below the \\esse1 flange.
Determines that the plant condition does not satisfy the
Required Equipment column in spite of having two
2.
3.
CQMMENTS:
NOTE: * 4B and 4C CCW pumps are not powered from
independent power sources per the IC which stated normal
electrical alignment for the shutdown conditions. This implies
4D Bus is aligned to 4B Bus and the 4R and 4c pumps are
both powered from the same B electrical train.
Additionally, the IC stated Reduced Inventory which is
defined in Step 4.1 3.1 as a condition with fuel in the vessel and
RCS drained to Iowa than 3 feet below the vessel flange.
Therefore the asterisk applies and the plant condition does not
satisfy the Required Equipment column in spite of having
L
DETERMINE CONTINGENCY ACTIONS
DUE TO LOSS OF CCW PUMP
'C) ELEMENT 4:
STANDARDS :
Keviews En(
Determine Applicable Contingency
Actions
osure 6, Page I of9 and identifies the
following Contingency Actions:
From CCW Section:
1.
GO to 4-ONOP-030. (NIA - NO actions
resulting from ONOP-030)
Carry out actions as described in RHR section.
2 .
From RHR Section:
1.
2.
3.
4.
5.
Take immediate action to repair failed punip.
(NIA - Not an RHR Pump failure)
GO to ONOP-050.
Establish vessel level higher than 3' below
flange. Maximize RCS inventory.
(Applicable for the stated conditions)
Maintain KCS temperature as low as possible.
(Applicable, but no additional action required)
Notify the Ops. Mgr., Maint. Mgr., Work Cntrls.
Mgr. and PGM. (Applicable)
UNSAT
rC) ELEMENT 4: Detcrmine Applicablc Contingency
Actions
STANDARDS: (continued)
6.
7.
8.
9.
10.
11.
Ensure Feed & Bleed capability via HHSl
pumps is available.
(N/A Not a loss of KHR)
Ensure Recirc. Sump flow path to remaining
RHK pump is available.
(NIA - hot an RHR pump failure)
Suspend any activities that would risk the
remaining RHR, ICW, or CCW Pumps. ED6
and 4KV Bus.
(Applicable)
Initiate actions to establish containment closure,
except for the equipment hatch.
(N/A - Containment Closurc must be previously
set for Reduced Inventory)
Verify the equipment hatch can be closed within
the prescribed time frame.
QWA - Containment Closure must be previously
set for Reduced Inventory)
Investigate the possibility of flooding the
Reactor Cavity.
(NIA - Cannot flood up when in Reduced
Inventory. lead is on thc vessel.)
COMMENTS :
NOTE: Contingency i\\ctions 3,4, 5, and 8 are critical to this
element.
END OF JPM
-
X
9
Job Classification:
Shift Manager
JPM Title:
JPM Number:
Review Radioactive Liquid Release Perniit
Admin. if4 Radiation Control
JPM Type:
Normal Path
JPM Rev. Date:
10!1403
Time Validation:
XX minutes
Time Critical:
h-0
K.4:
G.2.3.6 (2.1i3.1) pg. 2-9
The applicable niethod(s) of testing which may be used:
PERFORM IN CONTROL ROOM OR CLASSROOM
Task Standards:
1.
2.
3.
Embedded errors identified.
4.
Radioactive I.iquid Release Permit reviewed for approval.
Tank Recirculation and Sampling Verification Sheet reviewed for approval.
Release Perniit and Sampling Verification Sheet not Approved.
Required Materials:
1.
2.
3.
4.
0-OP-061.11, Waste Disposal System, Controlled Radiological Liquid Release
0-NCOP-003. Preparation of Liquid Release Permits
Completed Radioactive Liquid Release Permit
Completed Tank Recirculation and Sampiing Verification Sheet
References:
1.
2.
Terminating Cues:
Embedded errors on Liquid Release Permit identified and permit returned to examiner.
0-OP-061.11, Waste Disposal System, Controlled Radiological Liquid Release
0-h-COP-003, Preparation of Liquid Release Permits
Initial Conditions Sheet
(To be given to Applicant)
&g&
Review for approval a completed Radioactive Liquid Release Permit
DIRECTIOXS:
The evaluator will explain the initial conditions ofthe task to be performed and will
providc the initiating cue. Ensure you indicate to the evaluator when you uiiderstand
your assigned task.
__
ISITIAL (OKDIIIONS;
1.
2.
The A Waste Monitor Tank is full and ready to be relcased.
The A Waste Monitor Tank has been sampled following recirculation on mini rccirc.
NIIATING CUE:
You are the Shift Manager.
Ihe Unit 3 RCO has presented the attached:
(I) Radioactive Iiquid Release Pennit and
(2) Tank Recirculation and Sampling Verification Sheet to you for approval
As the Shift Manager you are to:
Review the Radioactive Liquid Release Pennit and Tank Recirculation and Sampling
Verification Sheet for approval.
If the forms are accurate and ready for approval, provide the needed approval
signature and return the signed forms to the examiner.
If the forms contain error(s), identify the error(5) by circling the error(s) and
annotating on the form(s) what the error(s) is (are). When complete, return the
forms to the examiner.
2
REVIEW RADIOACTIVE LIQUID RELEASE PERMIT
Examiner Instructions:
Hand the:
(1) Initial Conditions Sheet,
(2) Completed Radioactive Liquid Release Permit
(3) Completed Tank Recirculation and Sampling Verification Sheet
(4) Copy of 0-01-061.11, Waste Disposal System Controlled Radiological Liquid
Release
( 5 ) Copy of 0-NCOP-003, Preparation of Liquid Release Permits
to the Applicant and read the following:
Review for approval the completed R.adioactive Liquid Release Permit and rank
Kccirc.iilation and Sampling Verification Sheet.
I will explain the initial conditions of the task and will provide the initiating cue. Ensure
you indicate to me u,hen you understand your assigned task.
IYITIAI, CONDIIIONS;
1.
2.
I.I
1NlTIATING:UF.:
The A Waste Monitor Tank is full and ready to be reieascd
The A Waste hlonitor Tank has heen sampled following recirculation on mini recirc.
You are the Shif! Manager. The [!nit 3 KCO has presented the attached (1) Radioaclive Liquid
Release Permit arid (2) Iauk Recirculation and Snmpling Veriiication Sheet to you for :ipprovnl.
As tlic Shift hfanagcr you are to:
B
Review the Radioactive Liquid Release Permit and Fank RerircuEation and
Sampling Verification Sheet for approval.
If the fornns are accurate and rsady h o g approval, provide the needed
apprwd signature and return the signed forins to the examiner.
If the forms contain srror(s), identify the error(s) by circling the error(s) and
annoeating on the fosm(s) what the csror(s) is (are). When complete, return
the forms to the examiner.
3
REVIEW RADIOACTIVE LIQUID RELEASE PERMIT
XEMENT 1 :
Obtain Required Materials.
STAND ARD S :
I
L .
Obtains copy of:
a. Completed Radioactive Liquid Release Permit
b. Conipleted Tank Recirculation and Sampling
c. Copy of 0-OP-061.11, Waste Disposal System
d. Copy of0-NCOP-003, Preparation of Liquid
Verification Sheet
Controlled Radiological Liquid Release
Release Permits
1)
Initial Conditions Sheet
2)
3)
4)
5 )
Completed Radioactive Liquid Release Permit
Completed Tank Recirculation and Sampling
Verification Sheet
Copy of 0-OP-061.11~ Waste Disposal System
Controlled Radiological Liquid Release
Copy of 0-NCOP-003, Preparation of Liquid
Release Permits
30MMENTS:
VOTE:
The applicant must review the completed forms
and identify 3 embedded errors (Note, one error
appears on both foniis.)
rime Start:
__
-UNSAT
4
REVIEW RADIOACTIVE LIQUID RELEASE PERhlIT
- C) ELEMENT 2: Evaluate Radioactive Liquid Release
Permit
STAKIIARDS:
1.
Circles and describes three embedded errors:
a.
Radiochemistv Supervisor signature required
and missing.
b.
Total Estimated Dose after this Release exceeds
the monthly administrative release limit.
c.
The time the tank was sampled was too soon
following the time the tank was put on
recirculation.
COMMENTS:
ROTE:
a.
Radiochemistry Supervisor signature
required because the tank specific activity
in part 1 exceeds I x
Monthly administrative release limit is
0.25 rnwmonth.
pciiml.
b.
c.
Thc tank was sampled 1% hours after the
start of recirculation instead of the
required 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
UWSAT
5
....
.~.
-. .
....~..
.. . .
... ~ -.
REVIEW RADIOACTIVE LIQUID RELEASE PERMIT
[e) ELEMENT 3: Evaluate Tank Recirculation and
Sampling Verification Sheet
STANDARDS :
1.
Circles and describes one embedded emor:
a.
The time the tank was sampled was too soon
following the time the tank was put on
recirculation.
L'OMMENTS:
NOTE:
a.
This is the same error that appears on the
liquid release permit.
The WMT is on mini recire and must be
recirculated for a minimum of two hours
prior to sampling.
NOTE:
b.
END OF JBM
..
..~.
....
UNSAT
6
Joh Classification:
Shift Manager
JPM Title:
JPM Number:
JPM Type:
Normal Path
JPM Rev. Date:
10/13/03
Time Validation:
XX minutes
Time Critical:
NO
Review Florida Nuclear Plant Emergency Notification Foinl
Admin. #5 Emergency Plan
u:
2.4.40 (2.3/4.0) pg. 2-15
The applicahle method(s) of testing which may be used:
PERFORM IN CONTROL ROOM OR CLASSROOM
Task Standards:
1,
2.
Florida Nuclear Plant Emergency Notification Form reviewed for approval
Embedded errors identified and corrected.
Required Materials:
1.
2.
References:
1.
Terminating Cues:
Embedded errors on Notification Form identified and corrected form returned to
examiner.
O-I?PIP-20101. Duties of Emergency Coordinator
Completed Florida Nuclear Plant Emergency Kotification Form
0-EPIP-20101, Duties of Emergency Coordinator
1
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Review- for approval a completed Florida Nuclear Plant Emergency Notification Form
nrKr~cnoxs.;
The evaluator will explain the initial conditions of the task to be perfoimed and will provide the
initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.
.
INITIAI,
~. . C . O N D I ~ I ~ N ~
1.
Both Units were initially at 100% power when operators were forced to evac.uate the
Control Room due to armed inttziders who quickly gained access to and occupied the
Control Room.
0-ONOP-105, Control Room Evacuation has been implemented and local conrrol of
shutdown systems was established from local stations after 20 minutes.
All operators are at their assigned local stations as described in 0-ONOP-105.
Based on these conditions a General Emergency Classification was declared on
December 1,2003 at 1400.
Wind direction is from 170. Wind speed is 12 mph.
South Dade (60 meter) lower A 1 - +l.OcF
Ten Meter Tower Sigma Theta =: 9.5
b .
9
3.
4.
S.
6.
ERDADS reveals:
a.
h.
ISITIATINCi
. ...
CUE:
You are the Emergency Coordinator. The Communicator has filled out the attached Florida
Nuclear Plant Emergency Notification Form and presented it to you for approval.
As the Emergency Coordinator you are to:
Review the Florida Nuclear Plant Emergency Notification Form for approval.
If the form is accurate and ready for transmittal, provide the needed EC approval
signature and return the signed form to the examiner.
If the form contains error(s), identify the error(s) by circling it (them). Correct the
error(s) and return the corrected form to the examiner.
no evidence ofa radioactive release at this time.
normal post-shutdown KCS temperatures, levels and pressures,
2
REVIEW FLORIDA NUCLEAR PLANT
EMERGNCY NOTIFICATION FORM
Examiner Instructions:
Hand the (1) Initial Conditions Sheet, (2) completed Florida Kuclear Plant Emergency
Notification Form and (3) copy of 0-EPIP-20101, Duties of Emergency Coordinator to
the Applicant and read the following:
Review for approval thc completed Florida Kuclear Plant Einergency Notification Form.
I will explain the initial c.onditions of the task and will provide the initiating cue. Ensure
you iiidicatc to me when you understand your assigned task.
INITIRI, C:OKDITIJIO
1.
Roth t.!nits were initia!ly at I 00?,/0 power when operators were forced to evacuate the
Contr(i1 Room due to armed intruders who quickly gaixd access to arid occupiecl the
Control Koom.
O-O>;OP-105, Contro? Room t;vacuation lias been iniplemented anti local control of
shutdow!: systems was established from local stations after 20 minutes.
All operators are at their
Based on these c(.)ntlitions a General Emergency Classification was declared 011
December I , 2003 at ! 400.
Wind dirtirfion is from 170. Wind spwd is 12 mph.
South 1)ade (60 ~neterj Tower LI .:.- + 1.0V
Ten Mcter Tower Sigma Theta =: Y.5
2.
1.
4.
igned local stations as described in 0-0N01-105.
5 .
6.
IiKDADS revrals:
a.
I>.
no evidence o f a radioactive release at this time.
nonnal post-shutd(Iwn KCS temperaturcs, levcls and pressures.
iNrnkrn\\ici CIUE:
You are the Emergency Coordinator. lhe Communicator lias filled out the attached Florida
Nuclear Plant Emcrgency Notification Form and prcsentcd it to you for approval.
A s the Emergency Coordinator you are to:
1)
Review the Florida Nudear Plznt Emergency Notification Form for approval.
If the fonn is accurate :ind rcady for lransniittal, provide the needed IC approval
signature and return the signed form to the examiner.
ffthe form conlains error(s), identify the error(s) hy circling it (them). Correcl the error(s)
and return the correc.ted form to the examiner.
3
REVIEW FLORIDA PLANT NUCLEAR
EMERGENCY NOTIFICATION FORM
ELEMENT 1:
Obtain Required Materials.
STANDARDS :
1.
Obtains copy of:
a.
Coinpleted Florida Nuclear Plant
Emergency Notification Form
b.
0-EPHP-20101, Duties of Emergency
Coordinator to the Applicant
(I>
Initial Conditions Sheet,
(2)
Completed Florida Nuclear Plant Emergency
Notification Form,
(3)
Copy of Q-EPIP-20101, Duties of Emergency
Coordinator
COMMENTS:
NOTE:
The applicant must review the completed
form and identify
correct 3 embedded
errors.
rime Start: __
-SAT
-UNSAT
4
REVIEW FLORIDA PLANT NUCLEAR
EMERGENCY NOTIFICATION FORM
[C) ELEMENT 2: Evaluate Florida Nuclear Plant
Emergency Notification Form
STANDARDS :
I.
Identifies and corrects three embedded errors:
a.
Item 8:
Wind direction is from I70*.
Downwind sectors affected should
be RAB, not QRA.
b.
Item 11:
Utility recommended PARS are
incorrect. QRA should be RAB as
discussed in Item a. There should
be no entries in the No Action
column. All should be entered in
the 5 - 10 mile row ofthe Shelter
Sectors column.
c.
Item 13.B: Stability Class D is incorrect.
Correct Stability Class is T~
COMMENTS:
NOTE:
Rases for errorsicorrections is as follows:
a.
Item 8: Page 2, Meteorological Worksheet of
the Florida Nuclear Plant Emergency
Notification Forni, reveals that for wind
direction from 170°F. Sectors affected are KAH.
UNSAT
5
(3 ELEMENT 2: Evaluate Florida Nuclear Plant
Emergency Notification Form
I
I
TOMMENTS: (continued)
!
b.
Item 1 I: Attachnient 3, Guidance for
Determining Protective Action
Recommendations (PARs) reveals that for a
loss of physical control ofthe plant, the correct
PARs are 0-2: E(CR), 2-5: E(DW) + S(RS),
5-10: S(CK).
c.
Item 13B: Page 2, Meteorological Worksheet
of the Florida Nuclear Plant Emergency
Notification Fonn, reveals that for a AT of t 1 .O,
the correct Stability Class is E.
UNSAT
6
In-Dlant J PMs
Job Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Validation:
lime Critical:
SystemiKA:
SNPO
Locally Place Unit 4 Hydrogen Monitor in Service Post-LOCA
B.1.i
Alternate Path
10/10/03
XX minutes
NO
028/028A2.02 (3.5/3.9) pg. 3.5-17
The applicable method(s) of testing which may be used: SIMULATE IN PLANT
Task Standards:
1.
PAHMS Alignment Completed per Section 7.1 of 4-OP-094
Required Materials:
1.
2.
3.
A Key
4.
Valve Operating Handle
References:
I.
Terminating Cues:
Alignment completed per Section 7.1 of 4-CdP-094
Two way radio (optional communications device).
4-OP-094, Containment Post-Accident Monitoring Systems
4-OP-094, Containment Post-Accident Monitoring Systems
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Locally Place LJnit 4 Hydrogen Monitor in Service Post-LOCA
DIRECTIONS:
The evaluator will explain the initial conditions of the task to be perfomied and will
provide the initiating cue. Ensure you indicate to the evaluator when you understand
your assigned task.
INITIAL CONDITIONS:
1.
2.
3.
Unit 4 has experienced a valid Safety Injection signal.
All applicable procedure prerequisites are satisfied.
Post Accident Hydrogen Monitoring system is in normal standby alignment.
INITIAIING CUE:
You are the SNPO and you haw been given directions from the Unit 4 RCO to place the
Post Accident Hydrogen Monitor in service per 4-033-094, Section 7.1.
2
LOCALLY PLACE UNIT 4 HYDROGEN MONITOR
1N SERVICE POST-LOCA
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to perfonn is Locally Place Unit 4 Hydrogen Monitor in Service Post-
1,OCA.
1 will explain the initial conditions of the task and will provide the initiating cne. Ensure
you indicate to me when you understand your assigned task.
I .
2.
3.
iinit 3 has expcriencecl a valid Safety Injection signal
All applicable procedure prerequisites are satisfied.
Post Accident Hydrogen Monitoring system is in normal standby alignment.
iN IT1 A'l'lBCj. !?!.WE;
You are the SNPO and you have been given directions fioni the Unit 4 RCO to place thc
Post Accident Hydrogen Monitor in service per 4-OP-094, Section 7. I.
3
PLACE UNIT 4 HYDROGEN itlONITOR IN SERVICE
ELEMENT 1:
Obtain Required Materials.
STANDARDS:
1.
Obtains copy of 4-OP-094, Containment Post
Accident Hydrogen Monitoring System.
2.
Verifies latest revision and no outstanding OTSCs.
3.
Reviews Section 4.0 for applicable P&Ls.
4.
Transitions to Section 7.1 and reviews the NOTE
prior to Step 9.1. I. Notes the statement to
complete the task within 30 minutes.
Signs off the Initial Conditions as complete.
Proceeds to the Aux. Rldg. east-west hallway and
describes how to unlock* and to obtain a T-handle
tool from its rack.
5.
6.
COMMENTS:
NOTE:
None of the Precautions and Limitations in
Section 4.0 specifically apply to this task.
- The lock for the T-handle tools requires an
A key, - normally carried by operators.
NOTE:
rime Start:
UNSAT
4
,. .
~ ....
~
~
PLACE UNIT 4 HYDROGEN MONITOR IN SERVICE.
{C) ELEMENT 2: Align PASS and PAHIM valves near
the junction of the NortWSouth and
East/West Hallways. (Step 7.1 2)
STANDARDS:
1.
Reviews the NOTE prior to Step 7.1.2.1 and proce
~ ds
to the junction of N/S and E/NT hallways.
2.
Inserts tool & removes floor cap for PtzSS-4-008.
(Rotates cap counter clockwise until cap is removed.)
E.xiimimr CUE: When the qqdicant idmtifies &ow1 to
remove the jloor cop, state LTbze.@oor cap is removed.
3.
Inserts tool and opens PASS-4-008. (Step 7.1.2.1 .a>
(Kotates tool counter clockwise until resistance is felt.)
4.
Inserts tool and removes floor cap for PAHM-4-OOlA.
(Rotates cap counter clockwise until cap is removed.)
UNSAT
5
(C) ELEMENT 2: Align PASS and PAHM valves near
the junction of the NortldSouth and
East,West Hallways. (Step 9.1 2)
STANDARDS: (continued)
6.
Inserts tool and removes floor cap for PAHM-4-OOlB.
(Rotates cap counter clockwise until cap is removed.)
Exumimr CUE: When the applicarn f idenb[jies how to
remove bke flour cup, m t e The floor cap is removed.
7.
Inserts tool and opens PAHM-4-O01B. (Step 7.1.2.l.c)
(Rotates tool counter clockwise until resistance is felt.)
Eximiner CUE: IVhen the app8icanf identifies how to open
PAHM--kOOdB, state The tool has been r&tedfully
counter clockwise. p9
8.
Inserts toal and removes floor cap for PAIIM-4-002A.
(Rotates cap counter clockwise until cap is rcrnoved.)
EximiPzer CUE: Whew the applicant identijks how tu
remove the floor cap, state The floor cap is remtoved
9.
Inserts tool and opens PAHM-4-002A. (Step 7.1.2.1.d)
(Rotates tool counter clockwise until resistance is felt.)
Exmnitter CLZ: When eke applicant identifics how tu open
PAHM-4-0024 state The tooB has hem ~ ~ ) ~ a t e ~ , ~ u ~ ~
COMtltW CiQCkWke.
10.
Inscrts tool and removes floor cap for PAHM-4-002B.
(Rotates cap counter clockwise until cap is removed.)
Examifier CXE: BVhei~ tlw upplimnt identiflcps how to
r m ~ c ) w
the floor cap, state The floor cup is remotwi
1 (C) ELEMENT 2: Align PASS and PAIIM valves near
the junction of the NortWSouth and
EastiWest Hallways. (Step 7.1 2)
STANDARDS: (continued)
1 I.
Inserts tool and opens PAHM-4-002B. (Step 7.1.2.1.e)
(Rotates tool counter clockwise until resistance is felt.)
Exainlner CUE: When the ap~9liecant idetififies how to open
P14Bb.M-4-O02B, state The tool hm beer2 rot~tedjXly
coientpr clockwise.
COMMENTS:
NOTE:
Standards 3.5,7,9, and 1 I critical for this
element.
I
7
PLACE UNIT 4 HYDROGEN MONITOR IN SERVICE
IC) ELEMENT 3: Open Post Accident Containment
Ventilation System Containment
Penetration Isolation Valves.
STAND AKDS :
I.
Unlocks* HV-4-3 outside the Unit 4 Pipe and
Valve Room.
2.
Opens HV-4-3 outside the Unit 4 Pipe and Valve
Room. (Step 7.1.2.2)
(Kotates fiilly handwheel counter clockwise)
4.
Opens HV-4-1 outside the Unit 4 Pipe and Valve
Room. (Step 7.1.2.3)
(Rotates handwheel hliy counter clockwise)
Examiner CUE: When the applicant describes how d o
and a.ot&edBd& comterc!ockwise.
o p n MV-4-3, bYtate The 11tared*vheel has beerr Urzl#Ck6?li
COMMENTS:
NOTE
- An A key is required to unlock I-IV-4-3
and HV-4- 1.
NOTE:
Standards 2 and 4 are critical to this
element
.- . .
~
~..
.....
-. . ..
-SAT
-UNSAT
PLACE UNIT 4 HYDROGEN MONITOR IN SERVICE
(C) ELEMENT 4: hotify RCO to Place PAHMs in
Service.
STANDARDS :
1.
Chlis Unit 4 RCO (on radio or plant page) to
perform 4-OP-094, Step 7.1.2.4 and to notify the
applicant when Step 7.1.2.4 is complete.
(Step 9.1.2.4)
Exunairw CUE: Roleyiay as the Unit 4 RCO a d
ackimdedgc Eke directh to perform step 7.1.2.4 uf4-
OP-094. Ajier the direction 2.y given rend
acknowledged, state Step 7-1.2.4 044-OP-094 is
complete* Continue with Step 7J.2.5
COMMENTS:
NOTE:
UNSAT
9
PLACE UNlT 4 HYDROGEN MONITOR IN SERVICE
(C) ELEMENT 5: Isolate WHT Waste Transfer Pump
Discharge to RAD Waste Building.
STANDARDS:
1.
Attempts to remove floor cap to close MPAS-001
located outside the Unit 3 BA Evaporator Room.
(Step 7.1.2.5)
2.
Leaves the Aux. Building and proceeds to the
Waste Evaporator Feed Pump room in the
Radwaste building. (Step 7.1.2.5)
3.
Closes v a l ~ e 1731 located at the south end ofthe
Waste Evaporator Feed Pump room in the
Radwaste building.
(Rotates handwheel fully clockwise until valve
stem is fully inserted.)
(Step 7.1.2.5)
COMMENTS:
NOTE: Standards 1 and 2 are not critical for this
element.
10
PLACE UNIT 4 HYDROGEN MONITOR IN SERVICE
C) ELEMENT 6: Align Waste Holdup Tank
Pump-Back System to Containment
STANDARDS:
L .
Leaves the Radwaste building and proceeds to the
Aux. Building Roof. (Step 7.1.2.6)
l.
Uniocks* MPAS-4-004 on the Aux. Building
roof near the Unit 4 Containment wall.
1.
Opens MPAS-4-004 on the Aux. Building roof
near the Unit 4 Containment wall. (Rotates
handwheel fully counter clockwise until valve
stem is fully withdrawn.)
(Step 7.1.2.6.a)
!katniner CL%: Where the applicant describes how to
p n
MPAS-4-QO4, sme The handwheel has been
mlocked nnd rotatedful& counterclockwise and the
ulve stem isfklly withdrawn.
1.
Closes MPAS-4-005 on the Aux. Building roof
near the Unit 4 Containinent wall.
(Rotates handwheel fully clockwise until the valve
stem is fully inserted.)
(Step 7.1.2.6.b)
Fxaminer CUE: When the q@icant describes how b o
- h e MPAS-4-009, state 66The handwheel has been
wtateilfik[y dockwise and the vahe sfem is fully
imrFed.
-UNSAT
(C) ELEMENT 6: Align Waste Holdup Tank
Pump-Back System to Containment
(continued)
COMMENTS:
NOTE:
- An A? key is required to unlock
MPAS-4-004.
NOTE:
Standards 3 and 4 are critical for this
element.
END OF JPM
Job Classification:
JFM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Vaiidation:
Time Critical:
SystemIKA:
SNPO
Split CCW Headers in Response to Leakage on 4A CCW Header
B.1.j
Normal Path
10/13/03
XX minutes
KO
008/026 AA2.03 (2.62.9) pg.4.2-19
The applicahk method(s) of testing which may he used: SIMULATE IK PLANT
Task Standards:
1.
CCW Headers split in acc.ordance with 4-ONOP-030, Step 14 a. RNO and Cask
Wash Area Component Cooling Water piping isolated in accordance with
4-ONOP-030, Step 24 RNO g.
Required Materials:
I.
2.
References:
1.
Terminating Cues:
Alignment completed per Steps 14 and 24 of4-ONOP-030
Two way radio (optional communications device).
4-ONOP-030, Component Cooling Uater Malfunction
4-ONOP-030, Component Cooling Water Malfunction
Initial Conditions Sheet
(To be given to Applicant)
1.4SK:
Locally Split CCW- Headers in Response to Leakage on 4A (33%
IIeader
DIKECTIONS:
The evaluator will explain the initial conditions of the task to be performed and will provide the
initiating cue. Ensure you indicate to the evaluator when you understand your assigned task.
INITIAL
~
CONDITIONS:
1.
Unit 4 was at 100 % power with normal system alignments except for the IJnit 4 CCW
cask wash area piping which was aligned to 4A CCW header.
A large CCW leak developed in the cask wash area piping.
Operators implemented 4-ONOP-030, Component Cooling Water 54alfiinstion.
2.
3.
IXITIAlING CUE:
You are the SNPC) and you have been given directions from the Unit 4 RCO to isolate the 4A
CCW Header ANI) Cask wash area piping by locally C1,OSING the following valves:
4-7872., C:CW HX 01JILEI IIX SE:CTIONALIZ.ING
02
4-487F, CCW HX OUTLET HIIR SECTIONALIZING
4-787c, ISO VALVE FOR SECTIONALIZING ccw PLJMP rmm HEADER
4-787A, CCW PUMP SUCT. HEADER SECTI(?NAL.UING VALVE
4-737C, CCW SYSTEM DEMIN WATER PRIMARY WATER SUPP1,Y TIE
4-835E, CCW IIDK. B TO CHRG PPS - SFP IIX
~ NRHX - SEAL, WTR HX
4-835F, CCW HDR. A TO CHG PPs.
SFI IIX NON-REGEN HX AND SEAL
WATER HX.
4-835G, CCW HDR. .4 KETURN FROM CHARGIXG PIJMPS, SPEW FUEL PIT
IIX, NON-REGEN I~IX AND SEAL WATER HX.
4-835H, CCW IIDR. B FC3UKN FR.OM CHG PPS, SFP HX, NRIIX; AND SEAL
W i x rIx
2
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
'I'iie task you are to perform is locally split CCW Ileitders in response to leakege on 4A CCW
I will explain the initial conditions of the task and will provide the initiating cue. Ihsure y c ~
indicate to me when yon understand your assigncd task.
.....
INITM; CONDITIONS:
......... ---
1.
I h i t 4 was at 100 ?/o power with nomai system alignments except for thc LJnit 3 CCW
cask wash ares piping which was aligned to 4.4 CCW imder.
A large CCW leak developed in the cask wash area piping.
Operators implemented 3-OXOP-030: "Component Cooling Water Mnlfunction".
6.
7
3,
INITIATING
.......
CUE:
You :ire the SNPO and you have been given dircctions from the llnit 4 R("O to isolate the 4.4
Cask wash arca piping by locally CI.OSING the following valves:
3
C) ELEMENT 1 : Split CCW Headers.
STANDARDS:
Proceeds to Aux. Building Roof (Unit 4 Side -
Directly above Unit 4 CCW Pump Room) and
locally closes 4-787E. (Southernmost Reach rod
hand wheel - Turn clockwise until local position
indicator points to T)
Exmibwr Cue: BVh~.re f h ~
applicant de.wribes
how to ckose 7$7& state: The valve isfidfy
clock wise.
Proceeds to Unit 4 CXW Pump Room and locally
closes 4-787F. (Chainfall located on south side of
4B HX - Pull on side of chain that causes valve to
rotate clockwise until closed)
Proceeds to Aux. Building Roof (Unit 4 Side -
Directly above Unit 4 CCW Pump Room) and
locally closes 4-9876. (4th from the north reach
rod hand wheel - Turn clockwise until local
position indicator points to C)
Examiner Cue: When the app&icarr&
describes
~ Q P V
to close 787C9 stat^: Tho) vdve isSgiei(p
clockwise. 9
rime Start: I
~
-~
UNSAT
4
(C) ELEMENT 1: Split CCW Headers.
STANDARDS: (continued)
3.
4.
Proceeds to Aux. Building Roof(Unit 4 Side -
Directly above Unit 4 CCW Pump Room) and
locally closes 4-787A. (T from the north reach
rod hand wheel - Turn clockwise until local
position indicator points to C,
6 73,
Examiner Cur: FVhm the applicant describes
how to the %?A, state: The valve is,fully
clockwise.
Proceeds to Unit 4 CCW Pump room and locally
closes 4-737C. (4 Rising Stem Valve located
knee-high 3 feet north of 4A HX) Turns valve
handle clockwise until valve stem is fully inserted.
COMMENTS:
NOTE:
For Standard 1, closing either 787E or 787F
satisfies the standard.
5
closes 4-835E. (Chainfall located between 4R & 4C
IIXs at north end Pull on side of chain that c;iuses
valve to rotate clockwise until closed)
!
C) ELEMENT 2: Isolate Cask Wash Area CCU Piping
~
STANDARDS:
i
TJIWAT
Proceeds to Unit 4 CCW Pump Room and locally
l-
Proceeds to Unit 4 CCW Pump Room and locally
closes 4-835F. (Chainfall located west of 4A HX at
the north end - Pull on side of chain that causes
valve to rotate clockwise until closed)
Examher Cue: When the applicant describes
how to close 83W, state: The valve i.~,fuliy
clockwise.
Proceeds to Unit 4 CCW Pump Room and locally
closes 4-83%. (Chainfall located 5 feet south west of
4B CCW pump - Pull on side of chain that causes
valve to rotate clockwise until closed)
Examiner Cue: When the apyiicanP describes
IPOW 60 close 835G, sfute: The vah? i.vfu@
clockwke.
IC) ELEMENT 2: Isolate Cask Wash Area CCW Piping
STANDARDS: (continued)
4.
Proceeds to Unit 4 CCW Pump Room and locally
closes 4-835M. (Chainfall located 10 feet due south of
4B CCW pump - Pull on side of chain that causes
valve to rotate clockwise until closed)
Examiner Cue: Whm the applicant describes
how to close 835%8, state: The vssbvo isfidij;
c!oskwise.
COMMENTS:
NOTE:
I
END OF JPM
7
Job Classification:
JPM Title:
JIM Number:
B.1.k
JPM Type:
Normai Path
JPM Rev. Date:
09/29!03
Time Validation:
XX minutes
Time Critical:
No
Respond to Loss of 120V Vital Instrumcnt Bus 4P08
SystemIKA:
OhY062A2.1
( 03.3) pp. 3.4-4
The applicable niethod(s) of testing which may be used: SIMULATE IN PLAYT
Task Standards:
1.
Power Restored to 4P08 from BS Inverter per Attachment 1 of4-ONOP-003.8.
Required Materials:
I.
2.
Two way radio (optional communications device).
4-ONOP-003.8 Loss of 120V Vital Instrument Panel 4PO8
3.
A Key
References:
1.
4-ONOP-003.8 Loss of 120V Vital Instrument Panel 4108
Terminating Cues:
Alignment completed per Attachment 1 of 4-ONOP-003.8
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Locally Restore Power to 4P08 from the US Inverter following failure of 4B Inverter
DIRECTIONS:
The evaluator will explain the initial conditions of the task to be performed and will
provide the initiating cue. Ensure you indicate to the evaluator when you understand
your assigned task.
INITIAL CONDITIONS:
1.
Unit 4 was at 70% power when the 4B Inverter failed resulting in loss of the 4P08
Vital Instrument Bus. The automatic swap to the CVT also failed.
BS Inverter is in Standby and available to power 4P08.
2.
INITIATING C
u
You are the NPO and you have been given directions from the Unit 4 KCO to restore
power to 4P08 using Attachment 1 of4-ONOP-003.8. I a s of I20V Vital Instrument
Panel 4P08.
2
RESTORE POWER TO 4PO8 FROM BS INVERTER
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you arc to perfomi is locally restore power to 4P08 froin the BS Inverter
ibllowing failure of 4U Inverter.
I will cxplain the initial conditions of the task and will provide the initiating cue. Ensure
you indicate to me when you understand your assigned task.
~ INITIAL COYDITIONS:
". ....
1.
Unit 4 was at 70% power when the 4R Inverter failed resulting in loss ofthe 4PO8
Vital Instrument Bus. The automatic swap to the CVI' also failed.
BS inverter is in Standby and available to power 41'08.
.-3 L.
You are the NPO and loti have been given directions from the IJiiit 4 RCO to restore
power to 4P08 using Attachrnent 1 of 4-ONOP-003.8, "Loss of 120V Vital Instrument
Panel 4P08".
RESTORE POWER TO 4P98 FROM BS INVERTER
ELEMENT 1 :
STANDARDS :
1.
Obtain Required Materials.
Obtains copy of4-ONOP-003.8, Loss of 120V
Vital Instrument Panel 4P08.
Goes directly to Attachment 1 as directed by the
Unit 4 RCO.
2.
ExamimY CUE:
Provide the app/icunt witdt Aftackmeraf 1 qf4-8NOP-
0&13.8.
COMMENTS:
VOTE:
4
RESTORE POWER TO 4POS FROM BS IXVERTER
(C) ELEMENT 2: Open 4B Inverter System Output
STANDARDS:
breaker. (Attach. 1 Step 1)
1.
Proceeds to 4B Inverter behind the Control Room.
(Att. 1, Step 1.a)
Opens (down position) 4B Inverter System Output
Brcaker CR6.
(Att. 1, Step 1.b)
2.
COMMENTS:
NOTE:
Standard 2 is critical for this element.
5
.
.......
......
1
RESTORE POWER TO 4P08 FROM BS INVERTER
~ (C) ELEMENT 3: Strip 4P08 and 4P23
I
STANDARDS:
I
I
~ 1)
Proceeds to 4P0814P23 panels in the Cable
Spreading Room (CSR). (Att. 1, Step 2)
Opens all breakers on 4P08. (SW corner of CSR)
(Att. 1, Step 2.a)
Opens all breakers on 4P23. (South \\?;a11 of CSR)
(Att. 1, Step 2.b)
2)
3 )
Examfszer Ck E: Whan the applicant ien@es the
hueakem to be opened (do oft QP08 rrnd 4P23 and
coiwcfby sfutes how to open them, acknow!edge by
s t d t f f All breakers on 4PO8 and 4P23 are open.
COMMENTS:
NOTE:
Standards 2 and 3 are critical for this
eIement.
I
UNSAT
6
RESTORE POWER TO 4P08 FROM BS INVERTER
(C)ELEMENT 4: Place BS Inverter in service to 4P08.
STANDARDS:
1.
Checks 3P08 not powered by BS Inverter.
(given from Initial Condition #2.)
(Att. 1, Step 3)
2.
Places the Vital Instrument AC Selector Switch
4P08A at Panel 4P08A (Next to 4POX) to the
INVERTER BS position. (Att. 1, Step 5.a)
ALTERNATE SUPPLY STANDBY STATIC
E.uminer CUE: Wlte~t the appliamt 1ocQtes and
identifies the Vital Imtrrrittent AC Selector Switch at
panel ~POCYA
and correctly states how PQ ninnipula'ate it,
state "The sruitc-h is itt the ALTERXATE SIPPLY
STANDBYSTA TIC INVERTER BSyosifi'on.
COMMENTS:
NOTE: Attachment 1, Step 4 and the CAUTION
following Stcp 4 are not applicable because the BS
Inverter is available and not powering 3P08.
NOTE:
Standard 2 is critical for this element.
-UNSAT
4
RESTORE POWER TO 4P08 FROM BS INVERTER
(Cb ELEMENT 5: Reclose breakers on 4P08 and 4'23.
STANDARDS :
1.
Notifies Control Room that cornponents on 4P08 are
about to be energized. (Att. 1, Step 6)
Examiner CUE: B%en the apg~~canf
describbs Fhe
iwtijicstion, uclimwledge the nertijkation as the. RCO.
2.
(Att. I, Step 7.a)
Examiner ClB: When the appkiccsnt identijks fhe MaiB
"The muin hreaker is closed.
Closes the Main breaker at 4P08.
fPrt.cc-ktT 6Zt
and 4'O~i%T&@ .Vf&eS hQW tQ d0.W it,
UNSAT
8
ELEMENT 5: Reclose breakers on 4P08 and 4P23.
(Continued)
3.
Closes the remaining breakers at 4POX using
Attachment 2: allowing 5 seconds between each
breaker. (Att. 1, Step 8)
Cioscs the remaining breakers at 4P23 using
Attachment 3, allowing 5 seconds between each
breaker. (Att. 1, Step 9)
4.
COMMENTS:
NOTE: Standards 2, 3, and 4 are critical for this dement
except the 5 second time delay between each breaker closure
in Standards 3 and 4.
9
RESTORE POWER TO 4POS FROM BS INVERTER
fC) ELEMENT 6: Realign CVT Backup to Spare
Inverter
STANDARDS:
1.
Proceeds to Inverter Room behind the Control
Room.
(Att. 1, Step 10)
2.
Unlocks* the AItcrnate Source Transfer
Switch (4Y02B) (NE corner of CSR)
(Att. 1, Step I0.a)
3.
Places the Alternate Source Transfer Switch
(4Y02B) (NE corner ofCSR) to the BACKUP TO
SPARE INVERTER BS Position.
(Att. 1, Step I0.a)
in
/C) ELEMENT 6: Realign CVT Backup to Spare
Inverter (Continued)
Notifies the RCO that all Breakers arc closed.
5 .
Examliraea CUE: When the uppkicrrnt miikm the
~iotificration, acknowdedge the notijicatioioa as the RCO.
COMMENTS:
XOTE:
- The lock for the AkeHldte Source Transfer
Switch requires an A key, - normally
carried by operators.
Standards 3 and 4 are critical for this
element.
NOTE:
END OF JPM
1 1
Control Room JPMs (simulator JPMs)
Job Classification:
3PM Title:
JPM Number:
B.1.a
JPM Type:
Alternate Path
Transfer to Alternate Hot Leg Recirculation
JPM Rev. Date:
i o i ~
0:03
Time Validation:
XX minutes
Time Critical:
NO
SystemU:
006!011EA1.11 (424.2) pg. 4.1-7
The applicable niethod(s) of testing which may be used: PERFORM IN SIMIJE,ATOK
Task Standards:
1.
Safety Injection hot leg flow established per EBP-E.S-i .4, Attachment I
Required Materials:
1.
2.
References:
1.
2.
3.
Ternnnating Cues:
ES-1.4 complete through Attachment 1, Step 7.
Two way radio (optional communications device).
3-EOP-ES-1.4, Transfer to Hot Leg Recirculation
3-EOP-ES-I .4. Transfer to IIot Leg Recirculation
3-EOP-E-I, 1,oss of Reactor or Secondary Coolant
3-EOP-ES-1.3, Transfer to Cold Leg Recirculation
Initial Conditions Sheet
(To be given to Applicant)
?ASK:
Transfer to Hot Leg Recirculation
DIRECTIONS:
The evaluator will explain the initial conditions ofthe task to be performed and will
provide the initiating cue. Ensure you indicate to the evaluator when you understand
your assigned task.
INITIAI> CONDITIONS :
1.
2.
3.
4.
5.
Unit 3 is on Cold Leg Recirculation.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> have elapsed since the LOCA initiation.
3A RIIK pump is providing flow to the core.
No Containment Spray pumps are running.
No HHSI pumps are running.
INITIATIKG CUE:
You arc the Unit 3 KCO and you have been directed by the Unit Supervisor to establish
Hot Leg Recirculation.
1
L
TRANSFER TO HOT LEG RECIRCULATION
Examiner Instructions:
Iiand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to pcrfonii is Transfcr to Hot I.cg Recirculation.
I wil1 explain the initial conditions of the task and will provide the initiating cue. Eilsurc
you indicate to me whcn you understarid your assigned task.
-.
INITIAL
. .- . .
CONDITIObJS;
I .
A,.
9
3.
5.
5.
Unit 3 is on Cold Leg Recirculation.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> have elapsed since the LOCA initiation.
3A RHR pump is providing flow to the c,ore.
No Containincnt Spray pumps arc iunning.
No HIISI pumps are running.
INITIATING CUE:
You are the Unit 3 RC'O and you have been directed by the [Unit Supervisor to estaldisli
Hot Leg Recirculation.
3
TRANSFER TO HOT LEG RECIRCULATION
ELEMENT 1:
Obtain 3-EOP-ES-1.4.
STANDARDS:
1.
Obtains Control Room Copy of 3-FOP-ES-1.4,
Transfer to Hot Leg Recirculation.
COMMENTS:
NOTE:
The applicant will use the copy located next
to the RCOs desk.
Time Start: _.
TRANSFER TO HOT LEG RECIRCULATION
ELEMENT 2:
Verif>i CCWISI system
alignment.
STANDARDS :
1.
Observes MOV-3-749A & 749B OPEN
(red lights on) on VPB. (Step 1)
Observes MOV-3-869 CLOSED (green light on)
on VPB and attempts to open the MOV using the
control switch. (Step 2)
2.
COMMENTS:
MOV-3-869 is failed closed as part of the initial
simulator alignment.
UNSAT
4
TRANSFER TO MOT LEG RECIRCULATION
(C) ELEMENT 3: Establish Alternate Hot Leg
Recirculation flow path per
Attachment 1.
STANDARDS :
I.
Transitions to Attachment 1, Step 1
(Step 2 RNO)
2.
Directs Primary Operator to locally close both
WIK Pump Manual Suction valves 3-752A &
3-7523. (Att. 1 , Step 1.a)
\\/F Operator Cue 1: Acknowledge applicants
direction to close 3-75213 & 3-752B and repot? back
when vaalves are closed.
l/F Operator Action: CIose 3-752A 8 3-7528 as
foal%ows:
3.
Opens both MOV-3-750 and MOV-3-751 on VPB.
(Att. I, Step 1.b)
COMMENTS:
NOTE:
Both MOV-3-758 and 75 1 will successhlly
open (red light on).
UNSAT
TRANSFER TO MOT LEG RECIRCULATION
jC) ELEMEKT 3 Cont.: Establish Alternate Hot Leg
Recirculation flow path per
Attachment 1.
STANDARDS :
4.
Directs Primary Operator to locally verify KHR
IIX Manual Outlet Valve, 3-759A, on the
operating RHR Train, is OPEN. (Att. I, Step 2)
MF Operator Cue 2 Acknowledge applicants
direcfion to verify 3-759A is open. Report back that
3-759A is open.
COMMENTS:
NOTE:
Standards 2 and 3 are critical for this
Element.
~
IJNSAT
TRANSFER TO HOT LEG RECIRCULATION
ELEMENT 4: Verify SI Flow to the rcactor is stopped.
STAWI1AWT)S :
1.
Verifies 3A & 3E3 Containment Spray Pumps in
Pull-To-Lock on VPB. (Att. 1, Step 3)
Verifies 3A 8( 3B HHSI Pumps in Pull-To-Lock
on VPR. (Att. 1, Step 3)
2.
COMMENTS:
NOTE: The CSPs and HHSI pumps are already in Pull-
To-Lock.
-UNSAT
7
TRANSFER TO HOT LEG RECIRCULATION
ELEMENT 5: Verify Alternate IIot Leg Recirculation
flow path established per Attachment 1.
STANDARDS:
I.
Verifies one or both valves MOV-3-744A andlor
MOV-3-7443 OPEN on VPR. (Att. 1, Step 4)
Verifies both valves MOV-3-863A and MUV-
P63B CLOSED on VPR. (Att. 1, Step 5 )
2.
COMMENTS:
NOTE:
MOV-3-744A/744B are already open (red
lights on).
NOTE:
MOV-4-863AiB are already closed (green
lights on).
UXSAT
-
-
-
-
TRAKSFER TO HOT LEG RECIRCULATION
(C) ELEMENT 6: Directs Primary Operator to complete
Alternate IIot Leg Recirculation
alignment.
STANDARLl:
1.
Directs Primary Operator to locally open RPIR
Recirculation Isolation valve, 3-741A.
(Att. 1, Step 6)
I/F Operator Cue: Acknowledge applicants
dir@ction to open 3-741A. Report back when 3-74lA
is open.
I/F Operator Action: Open 3-741A as fol%ows:
?41A -> Set TAMRfV29 = f.0
COMMENTS:
-UNSAT
9
TRANSFER TO NOT LEG RECIRCULATION
ELEMENT 4:
Verify Status of Core Exit
Thermocouples.
ST'ANDART):
1.
CETs are verified stable or decreasing on QSPDS
screen on VPB or next to KCO desk.
(Att. 1, Step 7)
COMMENTS:
NOTE:
CETs wiil be stable or decreasing.
END OF JPM
BOOTH OPERATOR INSTRUCTIONS
I. Reset to IC-29.
2.
Go to RUN. Close MOV-869 on VPB. Acknowledge
annunciators. Freeze simulator.
3.
Insert MOV-869 failure closed as follows:
Click on Schematics -> SAFETY SYSTEM -> SAFETY
INJECTION PROC -> MOV-869 -> Click on TFMVV07C
MOV-869 FAIL CLOSED -> Click OR TKUE then INSERT
3.
Leave simulator frozen until ready to begin.
Joh Classification:
JPhl Title:
JPM Kumber:
JPM Type:
JPM Rev. Date:
Time Validation:
Time Criticai:
SystemiKA:
KO
Respond to Loss of Residual Heat Removal
B.S.b
Alternate Path
10!10/03
XX minutes
KO
005:025 AA1.03 (3.43.3) pg. 42-17
The applicable method(s) of testing which may be used: PERFORM IN SIMULATOR
Task Standards:
1.
Residual Heat Removal flow restored per ONOP-050, Loss of RIIK.
Required Materials:
I.
2.
3-ONOP-050. Loss of RHR
Two way radio (optional communications device).
References:
1.
3-ONOP-050, Loss of RHR
2.
3-ARP-097.CR, Control Room Annunciator Response
Terminating Cues:
3-OhiOP-050 complete through Step 9 RNO.
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Respond to Plant Conditions
DIRECTIONS:
The evaluator will explain the initial conditions of the task to be performed. The
simulator will provide the initiating cue. Ensure you indicate to the evaluator when you
understand your assigned task.
INITIAI. CONDITIONS:
1.
2.
3.
4.
5.
IJnit 3 is in Mode 4 on RHR cooling.
RCS Loop temperature is approximately 300°F.
RCS pressure is approximately 300 psig.
3A RKR pump is providing RHR cooling
A Standby Steam Generator Feed pump is supplying feed to steam generators.
INITIA1ING CUE:
You are the Unit 3 RCO. Respond to plant conditions.
2
RESPOND TO LOSS OF RWR
Examiner Instructions:
IIand the Initial Conditions Sheet to the Applicant and read the following:
'l'lie task you arc to perform is Respond to Plant Conditions.
I will explain the initial conditions ofthe task. 'The simulator will provide the
initiating cue. Ensure you indicate to me when you understand your assigned
task.
I .
2.
3.
4.
5.
Unit 3 is in Mode 4 on RI IR cooling.
KCS Loop remperaturc is approximately 300°F.
RCS pressure is approxjniately 300 psig.
3A RHR pump is providing RHR cooling
"A" Standby Steam Generator Feed pump is supplying feed to steam generators.
-. INI'IIATING
-~ CUE:
You are the Unit 3 RCO. Respond to phnt condrtions
3
RESPOND TO LOSS OF RHR
ELEMENT 1 :
Direct SNPO to locally monitor RHI
Pumps (ONOP-050, Step 1)
STANDARDS :
1.
Using plant page or radio, directs SNPO to
perform the following:
a.
Obtain a radio.
b.
c.
Maintain Communication.
d.
Monitor 3A RHR pump locally.
Stay near RHR pump until flow is restored
IF Operutor Cue: Respond us the SNPQ. Afler 2
minutes, report buck OH the rudio thut there is nothing
visibiy wrong at the 3A RHRpump.
COMMENTS:
NOTE:
Annunciator EI 612 will alarm when the 3A
RHR pump trips. The applicant may refcr
to the ARP first. The ARP will direct the
applicant to ONOP-050.
Step I of ONOP-050 should be performed
from memory without reference to ONOP-
050.
NOTE:
I
Time Start:
- -1
-SAT
4
RESPOND TO LOSS OF RHR
ELEMENT 2:
Direct Shift Engineer to Monitor RCS
Heatup Rate. (Stcp 2)
STANDARDS :
I.
Directs Shift Engineer or available operator to
perform the following:
a.
b.
Calculate RCS heatup rate.
c.
d.
e.
Plot Core Exit Tcmps every minute for 5
minutes.
Determine time to reach RCS saturation.
Report results to RCO and Shift Manager.
Repeat every I5 minutes until cooling is
restored.
~ COMMEKTS:
NOTE:
Step 2 of ONOP-050 should be performed
from memory without refercnce to ONOP-
050.
5
RESPOND TO LOSS OF RHR
ELEMENT 3:
Checks Loop 3C RIIK Pump Suction
Stop Valves to be OPEN. (Step 3)
STANDARDS:
1.
Observes red light indication for MOV-750 and
751 on VPB.
COMMENTS:
NOTE:
Both MOV-3-750 and 75 1 will be open
(red lights on).
Step 3 of ONOP-050 should be performed
from memory without reference to ONOP-
050.
NOTE:
UNSAT
I__
6
RESPOND TO LOSS OF RHR
STANDARDS:
1.
Observes red light indication for MOV-744A and
MOV-744B on VPB.
ELEMENT 4 :
Obtain ONOP-050 and verify IOAs
complete.
-SAT
STANDARDS:
1.
Obtains Control Room Copy of ONOP-050.
2.
Reviews Steps I through 3 and verifies immediate
Operator Actions complete.
COMMENTS:
NOTE:
The applicant will use the Control Room
copy of ONOP-050 to perform this element.
-UNSAT
RESPOND TO LOSS OF RHR
COMMENTS:
NOTE:
Both MOV-3-744A and 744B will be open
1
(red lights on).
7
RESPOND TO LOSS OF RHR
(CI) ELEMENT 6: Restore Running RI-IR Pump.
(Step 5)
STANDARDS :
1.
Observes green light indication on both RHR
pumps at VPB (neither running). (Step 5)
2.
Attempts to Close IiCV-758 using potentiometer
at VPB. (Step 5 RNO a.)
EXAMINER NOTE: HCV-758 is already closed.
3.
Closes HCV-605 by placing its controller at VPB
in MAN and depressing its DOWN button until
controller demand indicator is at zero.
(Step 5 RNO b.)
I/F Operator Action: When the applicant has closed
FCV-605, click on SCHEMATICS -> SAFETY
TFMDVl5.5 FCV-605 FAIL ASIS -> TRUE then
INSERT.
SYSTEiM -9 RHR PROCESS -> FCV-605 -9
I/F Operator Contingency Action: Ifthe applicant
starts the 3B RIdR puiiip without first closing FCV-605,
fail FCV-605 closed asfollows: click on
SCHEMATICS -> SAFETY SYSTEM -> RHR
PROCESS -9 FCV-405 -> TFMUVISC FCV-605
FAIL CLOSED -> TRUE then INSERT.
LNSAT
X
(C) ELEMENT 6: Restore Running KIIK Pump.
(Step 5 )
STANDARDS: (continued)
4.
5.
6.
7.
8.
Observes red light indication for MOV-950 and
451 on VPB (valves open). (Step 5 RNO c.)
Attempts to restart 3A RHR pump at VPB using
its CS (unsuccessful). (Step 5 RNO d.)
Starts 3B KIIK pump at VPB using its CS
(successful). (Step 5 RNO e.>
Attempts to return HCV-605 to AUTO restoring
normal flow by depressing its UP button andor
depressing the AUTO button (unsuccessful).
(Step 5 RNCI 8.)
After reviewing Step 5 RNO h. determines that
HCV-758 does not have to be manipulated
because it has remained closed. (Step 5 RNO h.)
COMMENTS:
NOTE: Standards 3 and 6 are critical to this element.
9
NDTO LOSS
ELEMENT 7: veri
cavitating. (Step 6)
1.
Bbsewes 3 RHR pump amps on VPB - STABLE
2.
Observes WH
stable at abnomally
Isw value.
3.
Contacts SNPO & inquires about 3B
noise level.
COMMENTS:
NOTE:
No indication of RWR pump cavitation.
E,LEMENT 8:
R Flow Control Valve
Failure. (Step 7)
1
Obsemes FI-685 on VP at abnormally Isw value.
(Step %a)
2.
Goes to Step 8. (Step 7 RNO a.)
COMMENTS:
UNSAT
10
NBTO LOSSOF
ELEMENT 9:
Attempt to control FCV-605
Manually and Locally. (Step 8)
STAN
%:
1.
Attempts to contrd FCV-$85 manually at VP
placing controller in MAN and manipulating
UP/BBW Buttons. (Unsuccessful) (Step $.a)
2.
Directs SNPO to perfom Step 8 RN
ONOP-050.
3.
Goes to CAUTION before Step 9 and notes the
CAUTION is N/A for this condition.
COMMENTS:
NOTE:
FCV-605 is failed closed.
UNSAT
R Cooling using HCV-
758 and MOVs-749A/B. (Step 9)
STANDARDS:
I.
Verifies HCQ-605 controller at VP
and closed (demand meter at zero).
(Step 9 RNO a.)
2.
opens MCV-758 usi
otentiometer at VPB until
een 3508 and 3708 gpm.
FI-605 at VP
(Step 9 WNO b.)
3.
Directs field operators to locally open breakers for
MOV-7498 & MOV-749B: (Step 9 RNO c.)
reaker 3061'3 at MGC 3B.
b.
SNPO: Open breaker 30721 at MCC 3C.
ersrtsr cue: As the 1VPO and SNPO,
acknowledge ~ ~ p ~ i ~ ~ ~ ~ t ' s
direction to open 3061 7 and
307.26.
I/F Operator Action: Click on CCW ->
-> BREAKER LOCAL CLBSE/TRIP -> s d
TCK1A21M = F -> ,yet a"CK1917M = F.
1.F Operator Cue: As the NPO and SNPO, report back
&Itat breakem 3061 7 and 30721 are open.
4.
Directs the SNPB to locally throttle M
749A&B to cont~ol WCS cooldown rate while the:
applicant monitors RCS temperatures on VPB,
(Step 9 RNO d.)
12
- Restore WHR Cooling Using HCV-
758 and MOVs-749AIB. (Step 9)
(continued)
5 .
Coordinating with the SWPO who is throttling
MOVS-749A & Ea, stabilizes RCS temperatures as
or WCO Desk, cs Thot/Tcold
ers
Seen QT1 Control
on VPA, RW Temperature Recorder on
(Step 9 WNO el.)
COMMENTS:
NOTE:
Standard 1 HS not critical to this element.
Subsequent Procedure Steps are N/A or are
not critical actions.
4 .
Reset to IC-30.
2.
Go to RU
walkdown and is ready, fail the operating 3A
(prevent restart) as follows:
. When the applicant has cornpieted board
Click on SCHEMATICS -> MAIN POWER
>TFM=l D3AT 3
then INSERT.
48OV A@ -> 3A 4MV BUS -> BK
15 3A WHR PP
14
Job Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Validation:
Time Critical:
System/U:
Respond to FCV- 1 13A Failure During Boration
B.1.c
Alternate Path
1 @/I 0/03
xx minutes
NO
004/6)04 A4.07 (3.9l3.7) pg. 3.1-19
The applicable method(s) of testing which may be used: PERFOM DJ SIMULATOR
Task Standards:
1.
Calculated Boric Acid Volume has been added.
Required Materials:
1.
2.
3.
Two way radio (optional communications device).
0-OP-046, GVCS - Boron Concentration Contrd
3-ONOP-046.4, Malfunction of Boron Concentration Control System.
References:
1 .
0-OP-046, CVCS - oron Concentration Control
2.
3-ONOP-046.4, Malfunction of Boron Concentration Control System.
Terminating Cues:
1.
Calculated Boric Acid Volume has been added.
1
Initial Conditions Sheet
(TQ be given to Applicant)
TASK:
Borate the WCS to Cold Shutdown Boron Concentration
DIRECTIONS :
The evaluator will explain the initial conditions of the task to be performed and will
provide the initiating cue. Ensure you indicate to the evaluator when you understand
your assigned task.
INITIAL CONDITIONS:
1.
Unit 3 is in MODE 3 with all control rods inserted.
2.
The boron concentration control system is fully operational.
3.
560 gallons of boric acid need to be added to reach Cold Shutdown Boron
Concentration.
INITIATING CUE:
You are the Unit 3 RCO. Borate the RCS to the Cold Shutdown Boron Concentration via
the blender.
RESP
FCV- I I3 A FAILU
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you arc tu perfonn is Borate the RCS to Cold Shutdown Boron Concentration.
I will explain the initial conditions of the task and will provide the initiating cue. Ensure
you indicate to rnc when you uiiderstand your assigned task.
lNITIAL CONDITIONS:
I .
Unit 3 is in MODE 3 with ai1 control rods inserted.
2.
Ths boron concentration ccmtrol system is fully sperational.
3.
560 gallons ofboric acid need to be added to reach Cold Shutdomm Boron
Concentration.
4.
All procedure prerequisites are: satisfied including permission from the
Operations" Supervisor obtained.
INITIATING CUE:
You are the Unit 3 RCQ. Borate the WCS lo the Cold Shuldo\\arn Boron Concentration via
the blender.
3
NB TO FCV-1138 FAILURE
ELEMENT 1 .
Obtain 0-8P-846.
1 *
Obtains Control Room copy of0-8P046, ccvcs
oron concentration Control.
COMMENTS:
NOTE:
The applicant will use the copy located next
to the RCOs desk.
4
- Borate the RCS
STANDARDS:
1 .
Goes to Section 5.2 of 0-
2.
Determimes the quantity of boric acid to be added.
(Given: 560 gallons) (Step 5.2.2.1 .a)
3.
Sets the boric acid totalizer Limit I to 560
gallons at the console. (Step 5.2.2. I .b)
4.
Verifies Operations Supewisor permission
granted for large boration. (Given -
applicant to IC Sheet if necessary.) (Step 5.2.2.1 .c)
5 .
Obtains Shift Manager (NPS) si
O f 0-OB-046.
6.
Adjusts Boric Acid Controller FC-3-1 I3A
potentiometer to desired flow rate at Console.
7.
laces the Reactor
akeup Selector Switch to
BFUTE position at the Console. (Step 5.2.2.3)
8.
Turns the RCS Makeup Control Switch to the
STARTposition at the Console. (Step 5.2.2.4)
9.
Verifies expected bomtion rate by observing
FR-3-113 at the Console. (Step 5.2.2.5)
UNSAT
5
IC) ELEMENT 2:
orate the RCS (Continued)
COMMENTS:
NOTE:
Standard 6: Pot setting value can be set
anywhere at the applicants discretion.
Most probable choice: 8.8 to allow boration
at 40 gpm.
NOTE:
Standards 7 and 8 are critical to this
element.
ELEMENT 3:
~idance sf 3-ARP-897.CR to
Wesp~nd to FCV- 1 13A Failed Closed.
1.
2.
3.
4.
5.
6.
7.
bsemes annunciator A2/5 BORIC AClD MAKE-
UP FLOW DEVIATION, alarm on VPA.
Obsemes low flow on FR-3-113 at the on sole.
Obsemes FCV-1 13A closed (green light on) at the
console.
Refers to 3-ARP-897 .CR for A2/5.
If FCV-I 13B classes due to flow deviation alarm,
reopens FCV- 1 13B at the console per guidance in
the ARP or in 0-OP-046.
S Make-up Control Switch at the console
uidance in the Am.
Transitions to 3-ONOP-046.4 as directed by the
AM?.
COMMENTS:
NOTE:
The applicant may opt to not refer to the
but go directly to 3-ONOP-046.4
ctisns discussed in the ARB will
n the ONOP.
m S A T
7
Use Guidance of 3-ONOP-046.4 to
espond to FCV- 1 13A Failed Closed.
STANDARDS:
1.
2.
3.
4.
5.
Obtains Control Room Copy of ONQP-846.4.
Verifies RCS Make-up control switch is in mid
position at the console with the make-up system
if not done previously) (Step 2)
stopped. (Places Make-up contrsl switch as ST
Checks Reactor Make-up selector switch in
TE. (YES) (Step 3)
Checks if additional boric acid is needed.
(YES) (Step 4)
6.
Checks if A flow rate was less than expected
before Make-up system was stoppe
1 (YES - zero)
(Step 3
7.
Calculates amount of boric acid remaining to be
added. (560 gallons minus amount of aci
before FCV- 1 13A fdure) (Step 6)
8
Use Guidance sf 3-ONOP-846.4 to
Respond to FCV-1 B 3 8 Failed Closed.
(continued)
STANDARDS:
8.
9.
10.
11.
12.
3 3.
14.
Adjusts FC-113A pot setting at console to obtain
desired flow (Not Needed - previously set)
(Step 7)
esets boric acid totalizer Limit I? at console to
value equal to 560 gallons minus amount of acid
added before FCV- 1 13A failure) (Step 8)
Places Reactor Makeup selector switch at console
TE (Not needed - Already in
(Step 91
Turns RCS Makeup control switch at console to
TART. (Step 10)
Checks one Unit 3 Boric acid pump running at
console. (Yes - Auto Staffted). (Step 11)
Checks FCV- 1 138 at console to be open.
(NO - FCV- 1 13A failed closed) (Step 12)
Places FGV- 1 138 control switch at console to
establish desired flow. Observes green light
indication. (Unsuccessful - FCV- 1 13A failed
closed)
OPEN or places FC-113A contrOllef in MAN to
9
fC) ELEMENT 4 : Use Guidance of 3-ONOP-846.4 to
Wesp~nd to FCV-113A Failed Closed.
(continued)
COMMENTS:
NOTE:
Stopping the MU system in Standard 3 is
critical to this element if it was not
perfomed earlier.
Standard 11 is critical to this element
and it is not critical ifa boric acid pump is
already running I It ensures one boric acid
pump auto-started if it had been stopped
following the ori anal FCV-113A failure.
RESPOND TO FCV-ll3A FAILURE
{Cb ELEMENT 5 : Establish Emergency oration Flow
1.
2.
4.
5.
6.
Determines manual control of FCV- 1 13A is not
possible. (Step 12 I0-i
Calculates time required to add the a1nount of
b015c acid needed using MOV-350 WOW path.
(Step 12 RNO b. 1)
opens MQV-3-350 at the console.
tep 12 RNO b.3)
Monitors FT-3-110 at VPA for the expected f l ~ w
rate. (Steps 12 RWO b.2 )
Recognizes flow rate on %;I-3- 1 10 at VPA is
RN6 b. 1 and recalculates time required to add
amount of boric acid needed.
different from the flow rate calculated in step 12
When the total amount of boric acid is ad
stops the boric acid transfer pump and closes
MOV-3-350 at the C O ~ S Q I ~ .
11
I@)
ELEMENT 5 : Establish Erne ency Boratisn Flow
0 b.) (continued)
NOTE:
NOTE:
NOTE:
Calculation in Standard 2 will be based on
remaining boric acid to added (know
quantity) and the anticipated flow rate with
one boric acid pump and two charging
pumps running (estimated quantity). If the
applicant still needs to add 540 gallons of
gpm, the total time will be 9 minutes.
boric acid and ChQOSCS ib WOW pate O f 6 8
Because the calculation made in Step 2 will
prove to be inaccurate, the applicant will
need to recalculate after observing a
different flow rate when MOQ-358 is
opened. For example, if the obsemved flow
rate is 85 gpm instead ofthe expected 60
gpm, the time needed for boration is
shsflened to 540 divided by 8% which equals
6.3 minutes total emergency boration time.
Standards 3 and 6 are critical to this
element.
D
J
12
.~
. . . . . . . . . . . . . . . .
OOPH OP
INSTRUCTIONS
1.
Reset to IC-3.
2.
3.
4.
Go to RUN. Trip the reactor and acknowledge alarms.
Reset boric acid totalizer (Limit 1 ) to 200 gallons.
Freeze simulator until start of exam.
13
Jot9 Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Bate:
Time Validation:
Time Critical:
S ystedKA:
Respond to a Pressurizer Pressure Control Maliblaction
B.1.d
Alternate Path
10/18/03
xx minutes
YES
010/827 AA1.01 (4.0B.9) pg. 4.2-20
The applicable method(s) sf testing which may be used: PERFORM IN SIMULATOR
Task Standards:
1.
2.
Actions Performed to stabilize pressure per
3-ONOP-04 1.5, (Pressurizer Pressure Control Malfraneti~n~
Reactor tripped when pressure decreases below 2000 pig.
Required Materials:
1.
3-ONOP-84 1.5, Pressurizer Pressure Control Malf~nction
References:
1.
2.
3-ONOP-04 I 3, Pressurizer Pressure Control Malfunction
3-ARP-047.CR, ControI Room Annulaciatior Response
Terminating Cues:
1.
Reactor is tripped in response to uncontrolled pressure reduction.
1
Initial Conditions Sheet
(To be given to Applicant)
TASK:
Respond to Plant Conditions
DIRECTIONS:
The evaluator will explain the initial conditions ofthe task to be perfomed. The
simulator will provide the initiating cue. Ensure you indicate ts the evaluator when you
understand your assigned task.
INITIAL CONDITIONS:
1.
Unit 3 is in MODE 1 at 75% power.
2.
All plant systems are fully operational.
INITIATING CUE:
You are the Unit 3 WCO. Respond to plant conditions.
2
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to perfom is Respond to 'hnt &londitions.
I will explain the initial conditions of the task. Thc simulator will provide the initiating
cue. Ensure you indicate to me utien yoti understand yorir assigned task.
INITIAL CONDITIONS:
E.
2.
Unit 3 is in MODE I at 75% powcr.
All plant systems arc fully operational.
INITIATING CUE:
You are thc Unit 3 RCB. Respond to plant conditions.
3
RESPONDTO B Z, PRESS. CONTW L MALFUNCTION
IC) ELEMENT 1 : Perfom Immediate Actions to
Stabilize Pressure.
1.
2.
3.
4.
C ~ m a a r e ~
PI-444 with PI-445, PI-455,
and/or PI-457 on V A and determines PT-444 has
failed high. (Step 1)
Closes PCV-3-4532 or MOV-536 usin
switch at the console. (Step 1
a.
Takes manual control of C-4445 at the console by
depressing its
and drives the
controller output toward zero by depressing its
DOWN button. (Step 1 RNO a.2)
Recognizes manual control sf BC-4445 is not
effective. Takes manual control of pressurizer
spray valves and heaters at the console as follows:
(Step 1 RNOa.3)
a.
b.
C.
epresses the MAN button for controller
CV-3-455A and attempts to drive the
controller output toward zero by depressing
its DOWN button. gunsuccessfua)
Depresses the MAN button for controller
output toward zero by depressing
its DOWN button. (successfid)
PCV-3-455B and drives the controller
Places 3A and 3B Backup Heater Control
S%rditches to ON at the ons sole.
Time Start:
~
CWSAT
4
(C) ELEMENT I : Perform Immediate Actions to
Stabilize Pressure.
5 .
Checks PBRVs Closed by observing green light
indication on esnsok. (BBRVs are closed based
on earlier actions) (Step 2)
6.
Checks PZR Spray valves closed by observing
demand meters on controllers
console,
(PCV-3-455A demand meter reads 180%.
PCV-3-4533 demand meter should read 8% based
on earlier actions.) (Step 3)
7.
With pressure less than normal and decreasing,
and closed (NO - demand is 180%) PCV-3-455B
is in MAN and closed (YES - demand is 0%) and
(Step 3 RNO a.)
verifies at the C O ~ S O ~ ~
BCV-3-455A is in MAN
cv-3-3 I 1 is closed (green li
5
IC) ELEMENT 1 : Perfom Immediate Actions to
Stabilize Pressure. (continued)
NOTE:
When the applicant drives PC-444.J toward
zero, PCV-4533 controller mill follow it.
PCV-455A will remain at 100% output.
NO' 'E:
Standard 2 is critical for this element.
Standard 3 g)r Standard 4.b is critical
depending on which step is performed first
to close spray valve, PCV-45x3.
NOTE:
Standards I through 7 are Immediate Action
steps and should be performed f r ~ n i
memol-gi.
6
ESS. CONTROL MALFUNCTI
Obtain 3-ONOB-04 1.5 and continue
reeovery/mitigating actions.
STANDARDS:
1.
2.
3.
4.
btains Control Room copy of 3-ONOP-(64 1 5.
Reviews Steps 1 through 3 to determine
Immediate Actions have been performed correctly.
Reviews Fold-Out Page Items. Notes that F
page item # 2 applies.
Monitors RCS/Pressurizer pressure on VPA and
SPDS). If pressure as decreasing
llably and is approaching 2000 psig trips
the reactor at the console. If there is significant
margin to 2000 psig, may continue in ON0
04 1.5 while monitoring pressure reduction before
tripping the reactor.
COMMENTS:
NOTE:
Tripping the reactor when pressure re
below 2000 psi is the critical standard for
this element.
F J
m S A T
7
I.
2.
3.
4.
Reset to IC-I 6.
-> PT-444 -> TFHlTU44 -> PT 444
FAIL HIGH -> TRUE then PEN
444G -> TFH244GH -> C444G FAIL
PENDING.
simulator in run.
and examiner are ready, from PEN
w Insert TFH1TU44 'T, then i n s e ~
Job Classification:
JPM Title:
JPM Number:
JPM Type:
9PM Rev. Bate:
Time Validation:
Time Critical:
System/KA:
Respond to a Loss ofa Power Range Charnel (N-44)
B.1.e
Noma1 Path
10/10/03
XX minutes
YES
015/015 82.01 63.513.9) pg. 3.7-7
The applicable method(s) sf testing which may be used: PERFORM IN SIMULATOR
Task Standards:
1.
Plant conditions stabilized.
2.
Failed charnel (N-44) removed from seavice.
Required Materials:
I.
3-ONOP-059.8, Power Range Nuclear Instrumentation Malfunction
References:
1.
2.
3-ONOP-059.8, Power Range Nuclear Instrumentation Malhnction
3-ONOP-028, Reactor Control System Malfunction
Terminating Cues:
1.
Failed Power Range Charnel (N-44) is removed from service.
TASK:
Respond to Plant Conditions
DIRECTIONS:
The evaluator will explain the initial c~nditio~ls
of the task to be perfomed. The
simulator will provide the initiating cue. Ensure YOU indicate to the evaluator when you
understand Y Q U ~ assigned task.
INITIAL CONDITIONS:
1.
2.
Unit 3 is in MODE 1 at 188% power.
All plant systems are frally operational.
INITIATING CUE:
You are the Unit 3 WCO. Respond to plant conditions.
2
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to perform is Respond to Plant Conditions.
I will explain the initial com~dirions of the task. The simulator will provide the initiating
cue. Ensure you indicate to me when YOU understand your assigned task.
INITIAL CONBITTONS:
1.
2.
Unit 3 is in MODE 1 at 100% power.
AB1 plant systems are fu'ully operational.
INlTJATING CUE:
You are the Unit 3 K O . Respoilel to plant conditions.
3
ND TO LOSS OF BOWER RANGE CHANNEL N-44
ELEMENT I :
Respond to N-44 Failure In
Accordance with 3 -0NOP-02 8.
1.
Places the Rod Motion Control Selector switch to
the MAN position prkx to exceeding the Rod
Insertion Limits. (Time Critical)
(ONOP-828, step 4.3.1).
2.
e)btain§ COlltrOl Room COPY of NOB-028 and
verifies Immediate Action of Step 4.3.1 (Rods to
MAN) has been performed correctly.
3.
Goes to Section 5.3 ofOM8P-028.
4.
Requests permission from Unit Supemisor
(ANPS) to withdraw rods in manual to maintain
Tavg within 3" of Tref. (Step 5.3.1
5.
Requests unit Supenvisor notify I
to investigate failure. (Step 5.3 2)
Time Start:
m s A T
4
ELEMENT 1 :
Respond to N-44 Failure In
Accordance with 4-ONOP-028.
6.
7.
Verifies Control Rod Insertion limits have not
been exceeded by either ofthe following:
a.
Compares rod height following failure to
Insertion Limit as seen on recorder on VPA
abs
f Annunc
Q,
EXTRA
IM1T.
b.
Compares rod height to Insertion Limit as
seen in Plant Curve
3.
oak,Section VII, Figure
Goes $8 3-8N P-059.8, Tower
Instrumentation Malfunction.
COMMENTS:
Response per 3-ONOB-28 is optional based
on the same guidance (with the exception of
restoring rod position) being given in 3-
The applicant may use the copy caf3-ONOP-
028 located next to the WCOs desk.
Rod Insertion Limits are not expected to be
exceeded for this event.
5
I@) ELEMENT 2: Respond to N-44 Failure In
Accordance with 3-ONOP-859.8.
STANBAmS:
1.
2.
3.
4.
5.
Identifies failed NIS channel as N-44 by
console indicators or at the NIS drawers behind the
compaHison to other Power Range channels at the
od Motion Control Selector switch at
the console to the MAN position pmor to
exceeding the Rod Insertion Limits.
(May have been performed previously when
ding per ONOP-028) (Time Critical)
-059.8, Step 4.1.1. I >.
Places the DROPPED ROD MODE switch at the
N-44 Drawer '(A')
to BYPASS. (Step 5 . 1
a 1.1 )
STOP BYPASS switch at the
quipment Drawer to the N-44
YPASS position. (Step 5 1 1 2)
Reviews NOTE prior to Step 5. Identifies weed to
peri51111 3-OSP-059.18 for QPTR detemi~~ation.
6.
Transfers the UP ER SECTION c
defeat switch at t e Miscellaneous
Drawer to N-44. (Step 5.1 e 1 3)
UNSAT
6
- Respond to N-44 Failure In
Accordance with 3-ONOP-059.8.
8.
9.
10.
Transfers the L
SECTION comparator
defeat switch at the Miscellaneous Equipment
Drawer to N-44. (Step 5.1.1.4)
Transfers the POWER MISMATCH
switch at the Miscellaneous Equipment
Drawer to N-44. (Step 5. I. 1.5
Transfers the COMBA
TOR CHANNEL
DEFEAT switch at the Coinparator and Rate
Drawer to N-44. (Step 5. 1. 1.6 )
Trips the N-44 Power Range bistakles by
removing the INST UMENT POW
N-44 Drawer bB9. (Step 5.1 - Z .7.a
1 1.
Requests Unit Supervisor notify I&C Department
ate failure. (Step 5.. 1.1.9)
OMMENTS:
NOTE:
Standards 1,5, 8 and 1 I are not critical.
E
J
7
TH
R IN
1.
Reset to IC-I. Verify Control ods are in AUTO.
2.
Go to RUN. When the applicant and examiner are ready, fail
-> NE301b44
INSERT.
I
J'I.8
02
Initial con itions Sheet
iven to Applicant)
TASK:
Perform Section 6.2 of 3-OP-075, Auxiliary Feedwater System
DIRECTIONS:
The evaluator will explain the initial conditions of the task to be performed and will
provide the initiating cue. Ensure YOU indicate to the evaluator when you understand
your assigned task.
INITIAL CONDITIONS:
1.
Unit 3 experienced a Loss of Off Site Power.
2.
All AFW pumps automatically started and have been running for nearly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3.
4.
3-EOP-ES-O.1! Reactor Trip Response is in progress.
Plant Conditions require continued use sf the AFW System for S/S Feed.
INITIATING CUE:
YSU are the Unit 3 BOP and YSU have been directed by the Unit Supervisor to implement
Section 6.2 sf 3-OP-045, Auxiliary Feedwater System.
2
SHUTDOW AFW PUMPS WHILE IN T
Examiner %nstructisns:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to perfom is perfomi Section hm2 of 3-OP-075, Auxiliary Fecdwatcr
System.
I will explain the initial conditions of the task and will provide the initiating cue. Ensure
you indicate to me when you understand your assigned task.
I .
2.
3.
4.
Gnat 3 experienccd a Loss of Off Site Power.
All AFW pumps automatically started and havc been running for nrsarly 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
3-EOP-ES-0.1. Reactor Trip Response is in progress.
Piatit Conditions require continued use ofthc AFW System for SG Fecd.
You are tlae Unit 3 BOP and you have been directed by the Unit Supervisor to irnpleinent
Section 6.2 of 3-OP-075, Auxiliary Feedwater System.
3
SHUTDOWN AFW PU PS WHILE IN THE EOPS
ELEMENT I :
Obtain 3-OP-075.
STAN
S:
1.
Obtains Control Room Copy of 3-OP-095,
Auxiliary Feedwater System.
2.
Goes to Section 6.2, Shutdown of AF
During Emergency Plant Operations.
3.
Notes the CAUTION prior to Step 6.2-1 and Initial
itions are satisfied based on adequate S/G
levels and the given Initial Conditions.
COMMENTS:
cant will use the copy located next
Time Start: -
4
SHUTDOWN APW BUMPS WHILE IN THE EBBS
(C) ELEMENT 2: Veri@ AFW Actuation Signals
Reset.
1.
Proceeds behind VP and observes white li
wso and 3QR51
(white lights on>
(Step 6.2.2.1)
2.
Resets active AFW Actuation signals as follows:
e Observes red AMSAC ACTUATED light
illuminated on VPA and depresses AMSAC
RESET PB on v A. (Step 6.2.2.2.a)
e Observes red flags on 3A and 3B Steam
Generator Feed Pumps control switches and
turns both control switches to STOP.
(Step 6.2 2.2 c)
COMMENTS:
Standard 2 is critical tu this element.
NOTE:
Both white lights will initially be on due to
2 AFW actuation signals not reset.
NOTE:
F~llowing reset of
SAC and the SGFP
switches, applicant may opt to go behind
again to observe white lights which
should be out.
UNSAT
5
SHUTDOWN AFW PUMPS M7 ILE IN THE EOB
(@) ELEMENT 3: Shutdown AFW Pump in Train 2.
I.
Reads Step 6.2.2.3 notes it is N/A because Train
2 has 2 operating AFW Pumps.
(Step f~2.2.3)
2.
Reviews CAUTION @/A for this event) and
recommendation that C AFW pump be stopped
first.
TES prior to Step 6.2.2.4 and notes
Examiner NOTE: If a plicarat chooses to stop
C AFW pump first, continue with Standard
99 pump chosen first,
3.
Places C AFW Pump T&T valve to CLOSE.
(green light csdred light off at Console)
(Step 6.2.2.4)
4.
eviews Step 6.2.2.54 @AUT1 N and NOTE
prior to Step 6.2.2.5.b and Step 6.2.2.5.b and notes
that all are N/A.
5 .
Reviews Step 6.2.2.6, notes that it does apply
because %/S levels are >15% and stable with AFW
flow controllers dialed back to zero. Reviews
CAUTION and NOTES prior to Step 6.2.2.7.
COMMENTS:
NOTE:
Standard 3 is critical to this element.
UNSA
6
SHUTDOWN AFW BUMPS WHILE IN THE EO
AFW Pump in Train I e
pump was stopped
first)
1.
irects field operators to stan
isolate steam Wow to the B AFW pump.
(Step 6.2.2.7.23)
peratof cue 1: no^^@^^^ applicants
direction to ~ t a ~ ~ b y
br@aket-s. Respond as tiem
opefators that you afe s
~
a
~
~
i
~
~
by the breakers.
2.
Places control switches for MOV-4403 an
MOV-1404 at the Consol
(green light on, red light OW)
(Step 6.2.2.7.b)
Con tin ued
(C) ELEMENT 4: Shutdown AFW Pump in Train I.
(continued)
3.
When MOV-1403 and
OV-I404 display green
light-only indication, directs field operators to
open breakers 4DOl-28 and 38833.
(Step 6.2.2.7.c)
UF Operator Action:
en breakers as fo%/ows:
erator Cue 3.. espond as field opefators
that you have opened the breakers.
COMMENTS:
Standard 2 is critical to this element.
8
SHUTDOWN AFW BUMPS WHIL
s
ELEMENT 5: eset 3 AFW pump governor.
first)
9
pump M8S stopped
1
e
Requests field operator be dispatched to AFW
Pump cage to perfom Step 6.2.2.7.d to reset B
AFW pump governor.
COMMENTS:
NOTE:
E
F J
9
SHUTDOWN AF
PUMPS WHILE IN THE EOP
- Shutdown AFW
(To be perform
Pump is stopped first)
If applicant chooses to stop 9 AFW pump first:
1.
2.
a.
Places 3 AFW Pump T&T valve to CLOSE.
(green light odred light off at Console)
(Step 6.2.2.4)
eviews Step 6.2.2.5.a9 CAUTI
prior to Step 6.2.2.5.b and Step 6.2.2.5.b and notes
that all are N/A.
Reviews Step 6.2.2.6, notes that it does apply
because S/G levels are >I 5% and stable with AFW
flow controllers dialed back to zero. Reviews
N and NOTES prior to Step 6.2.2.7.
COMMENTS:
NOTE:
Standard 1 is critical to this element.
WN AFW PUMPS WHILE IN T
- Shutdown T9
AFW Pump in Train 1.
pump was stopped
first)
1.
Directs field operators ts stand by breakers
isolate steam flow to the C AFW pump.
4B01-28 @PO) and 30833 (SNPO) in preparation to
(Step 62.2.7.a)
eratsr C#@ I: ~
c
~
n
~
~
~
@
~
~
@
app
direction ts standby breakers.
operators that you are standin
2.
laces control switches for MOV-1403 and
MOV-AeB04 at the Console to CLOS
(green light on, red light off)
(Step 6.2.2.9.b)
Continue
El
[CB ELEMENT 7: Shutdown C AFW Pump in Train 1
a
(contanued)
3.
When MOV-1403 and MOV-1404 display green
(Step 6.2.2.7.c)
t-only indication, directs fie! operators to
en breakers 4D04 -28 and 38833.
%IF Operator Cue
c
~
n
o
~
i
~
~
~
~
p
p
~
~
~
~
~
t 3
direction to open breakers.
]IF Operator Cue 3:
espond as field operators
that you have opened the breakers.
NOTE:
Standard 2 is critical to this element.
12
SHUTDOWN a
S WHILE IN THE EOPS
bC) ELEMENT 8: Reset C AF
(Assuming 93 pump was stopped
first)
gUKkp gOVeITIQp.
STANDARDS:
I
D
Requests field operator be dispatched to AF
Pump cage to perfom Step 6.2.2.7,d to reset *C9
AFW pump governor.
NOTE:
N
JP
UGB3SAT
I3
1
e
Reset to 16-60.
2.
Click on SCHEMATICS -> N -0P -9 Click on red squares in
UNFREEZE Column to unfreeze the frozen models.
3.
un AFW flow to maximum to increase SIG levels to 9 25%.
4.
When si levels are X X % , reduce AFW flow to zero.
5.
Freeze simulator. Leave frozen until ready to begin.
14
Job Classification:
JPM Title:
JPM Number:
JPM Type:
JPM Rev. Date:
Time Validation:
Time Critical:
Restore Power to 3I) 4KV Bus
B.l .g
Noma1 Path
10/13/03
XX minutes
NO
042/042A2.05 (2.9/3.3) P_P. 3.6-4
The applicable method(s) of testing which may be used: PERFORM IN SlMULATOW
Task Standards:
1
Power Restored to 3D 4KV Bus and 3C @@W Pump Westarted In Accordance
with 3-QNOP-084.5
Required Materials:
B
~
2.
Two way radio (optional communications device).
3-ONOP-004.5, Loss of 3B 4KV Bus.
References:
1.
3-ONOP-004.5, LOSS of3D 4KV BUS.
Terminating Cues:
3c ccw Pump Started.
Initial Conditions Sheet
(To be given t Applicant)
TASK:
Wesp~nd to Plant Conditions
DIRECTIONS:
The evaluator will explain the initial conditions ofthe task to be performed and the
simulator will provide the initiating cue. Ensure you indicate to the evaluator when you
understand your assigned task.
INITIAL CONDITIONS:
1.
2.
3.
4.
5.
6.
7.
Unit 3 is in Mode 4 on
RCS Loop temperature is approximately 300°F.
WCS pressure is approximately 300 pig.
?A WHR pump is providing WHR cooling.
A Standby Steam Generator Feed primp is supplying feed to steam generators.
3B ccw Pump is Out-of-Serviee.
All three CCW Heat Exchangers are in service.
INITIATING CUE:
You are the Unit 3 RCO. Respond to plant conditions.
2
WEB TO 3
Examiner Instructions:
Hand the Initial Conditions Sheet to the Applicant and read the following:
The task you are to pel-fomi is Respond to Plant Conditions.
I will explain the initial conditions of the task and the simulator wiEI provide the initiating
cue. Emure YOU indicate to me errherz YOU understand yoair assigned task.
1.
2.
3.
4.
5 .
6.
7.
lJnit 3 is in Mode 4 on RHR cooling.
RCS Loop temperature is approximately 300°F.
RCS pressure is apprcbxirnately 300 psig.
3A RHR pump is providing RHR cooling.
A Standby Stcam Generator Feed pump is supplying feed to stcarn generators.
3B CCW Pump is Out-of-Service.
All three CCW Hcat Exchangers are in service.
INITIATING CUE:
You are the Unit 3 WCO. Respond ks plant conditions.
3
RESTORE PO
Obtain 3-ONOP-004.5.
1.
Observes annunicators associated with trip of
running 3C CCW pump.
2.
Observes 3C CCW pump red light on with zero
amps at VBB. Recognizes condition as
syrnptonsatic of no power on 3B 4KV
3.
Obsenves green light indication on breaker 3A
on VPA. Recognizes loss of power to 3B 4KV
us.
4.
btains control room copy of 3-ON
NOTE:
The applicant will use the copy located next
Time Start
l.JNSAT
4
ELEMENT 2:
Prepare to Restore Power to 3B 4
Bus
1.
2.
3.
4.
5 .
6.
Checks 3D 4KV Bus Lockout Relay reset at VPA
by observing blue light not flashing. (Lockout
Relay is reset.) (Step 1)
Reviews NOTE pffi~r to Step 2 and determines it is
N/A for this condition.
Checks 3A & 3B 4
observing bus voltmeters at console. (Both
are energized. Voltage agprox. 4 160 V> (Step 2)
Buses energized by
Verifies 3@ ICW pump br
by observing green light i
(3AD05 is already open) (Step 3.a)
Opens 3C GCW pump breaker, 3AB04, using
control switch at VPB. Observes green light
indication when 3AD04 is opened. (Step 3.
COMMENTS:
NOTE:
UNSAT
5
RESTORE P WER TO 3D 4KV
- Re-energize 3D 4KV
STAN
s:
1
e
Takes control switch for 3A 19 to OPEN at VPA
19 is already open.). (Step 5.a)
2.
Opens breaker 3AB06 by taking its control switch
to OPEN at VPA. Observes green light status.
(Step 5.b)
3.
Closes breaker SA 01 by taking its control switch
to CLOSE at VPA. Observes red light status.
(Step 5x1
4.
Closes breaker 3AA17 by taking its cmtrol switch
to CLOSE at VPA. Obsewes red light status.
(Step 5.d)
COMMENTS:
Standards 2,3, and 4 are critical ts this
e 1 ement .
NOTE:
Switch manipulations must be gerfomed in
the order presented in Step 5 of ONOP-
004.5 to satisfy interlocks to allow 3ADO1
and 3AA17 to close.
6
RESTORE POWE
estart 3C CCW Pump.
I.
Verifies 3D 4KV Bus is aligned to 3A 4KV
by observing red light indication on 3ABO1 an
3AAl7 at VBA. (Step 8)
2.
Reviews CAUTION prior to Step 9 and
determines it is N/A for this ~~ndition.
3.
Directs NPO to locally veri@ no breaker targets
exist on 3B 4
reakers. (Step 9)
4.
Review CAUTIONS prior to Step 18 and
recognizes:
a.
that starting the 3G cew pump will not
violate the first requirement (N-1 Rule)
because 3 GCW
SeWiCe.
xckangers are in
b.
the second requirement (Rule of5) will not
be violated because only 3 loads (NCCs -I- 2
W heat exchangers) will exist on the
GCW header at once.
c.
the thir CAUTION is N/A for this
condition.
(6) ELEMENT 4 : Restart 3@ CCW Pump.
STANDARD S : (~ontinued)
5 ,
AAes getting Shift Manager permission, restarts
the 36 CCW pump at VPB by placing its control
indication. (Step IS>
switch tQ STA T. Observes red igbt and amps
COMMENTS:
NOTE:
Only starting the 3c ccw pump in
Standard 5 is critical to this element.
N
J
8
INSTRUCTIONS
1.
2.
3.
4.
5.
4.
eset to IC-30.
Go to RUN.
Start 38 lCW Pump.
Stop 32 ICW Pump.
Start 3c ccw Pump.
CCW Pump and take its
ECO Information Tag o
to Pull-to-bock.
ccw pump control
switch.
Freeze the simulator.
Click on SCHEMATICS -> MAIN POWER DlSTRlB
INSERT.
4KV BUS -> bkr 13 -> TAK1 B13P ->
OSlTlQN -> Selecte Value = 3 then
When the applicant and examiner are ready, click on bkr 19 ->
TFE2D48T -> 3A 49 -> BREAKE FAIL TRIP -> TRUE then
Freeze simulator until start of exam.
Facility: Turkey Point Units 3 $: 4
Date of Examination: December, 2003
Exam Level:
SWO (I)
Operating Test Number: 1
Administrative Topic
{See Note)
Conduct of Operations
Conduct of Operations
Equipment Csntpol
Radiation Control
Describe activity to be perfomled
G.2.1.7 (3.7/4.4)
In preparation for a planned reactor power change, perform a reactivity management
calculation to determine the correct volume of boric acid (or primary water) to be added
to the RCS to achieve the desired power change. (M)
G.2.1.12 (2.W4.0)
Evaluate the applicable Technical Specificationis) in the event of the unexpected outage
ofthe Unit 4 Startup Transformer when Unit 4 is at 108% power and Unit 3 is in Mode
4. List all Limiting Conditions for Operations affected, Action Statement required
operator responses. options and time limits. (N)
(3.2.2.18 (233.6)
Determine Contingency Actions due to loss ofo CCW pump during RCS reduced
inventory operation and Phase I1 decay heat Ioad conditions. (M)
G.2.3.6 (2.li3.1)
Review for the purpose of approving a radioactive liquid release permit. Identify all of
the embedded errors and deny approval of the release permit. (MI
6 2 4 . 4 0 (2.314.0)
Review for the purpose of approving the Florida Nuclear Plant Emergency Notification
Form. Identify all of the embedded errors and deny approval of the emergency
notification form. (M)
NOTE: All items (5 total) are required for SRBs. RO applicants require only 4 items unless they are retaking only
the administrative topics, when 5 are required.
E§-38 1
Control Woodn-Plant Systems
Fom ES-30 1-2
Facility: Turkey Point Units 3 & 4
Date of Examination: December. 2003
Exam Level:
Operating Test Number: 1
Control Room Systems (8 for RC); 3 for SRO-I; 2 or 3 for SRO-84)
Systems/JPM Title
a. O M / Transfer to Alternate Hot Leg Recirculation
(Based on HHSI Hot Leg path valve failure)
2
b. QO5/ Respond to Loss of Residual Heat Removal
(RHR Pump Trip & FCV-685 failure)
4
c. 004/ CVCS Respond to FCV-113A Failure During Boration
(Requiring use of emergency boration valve)
1
d. 0 101' Respond to a Pressurizer Pressure C'ontr~l Malfunction
(PT-444 failure + spray valve stuck open requiring reactor trip)
a
e. 0 1 5/ Respond to loss of a Power Range Channel (N-44)
(Requiring IQA response and removal of Pd-44 from service)
7
f. O61/ Shutdown 2 AFW Pumps with Start Signals Present While in
the EQPs
(A) (S)
4
f 062/ Restore Power to 3B 4KV Bus
(Restores degraded CCW System)
6
In-Plant Systems (3 for RO; 3 for SRO-I: 3 or 2 for SRO-U>
(A) (MI
(W
i. O28/ Locally Place Unit 4 Hydrogen Monitor in Service Post-LOCA
5
(Locally swap to spare inverter)
'Type Codes: ((D)irect from bank, (M)odifed from bank, m)ew. (A)iternate Path, (C)control
room, (S)imulator, (L)ow I'ow7er, (R)CA Bold Print - JPMs performed by SWQ-U