ML042450328
| ML042450328 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 04/05/2004 |
| From: | Ernstes M Operator Licensing and Human Performance Branch |
| To: | Scalice J Tennessee Valley Authority |
| References | |
| 50-390/04-301, ES-D-1 50-390/04-301 | |
| Download: ML042450328 (146) | |
See also: IR 05000390/2004301
Text
Final Submittal
WATTS BAR JULY 2004 EXAM
50-39012004-301
JULY 23, & JULY 26-30,2004
Appendix B Scenario Outline Form ES-D-1
Facility: WATTS BAR Scenario No.: 3 (MOD) Op-Best No.:
Examiners: Operators:
initial Conditions:
-.
Rx Power 75%. 1A-A Motor Driven AFW Pump is out of service. Delta I is outside target -
band requiring dilution to return to target. ~ o a descalation to 100% is in progress.
Turnover:
1A-A MBAFW Pur > out of Service for maintenance.
-
Event Malf.
No.
1
- No.
__
2 CV51 Failure of FT-62-142 - Inhibits ability to dilute.
The failure will affects RO's ability to dilute. There are no alarms, so it
3 RXQ7C
4 RX1 1A
ake MANUAL control of control rods. BOP will have
r steam dumps. To continue ramp, with this
should require the RO to manually operate the rods.
-
5 CCOl
Should require BOP to diagnose.
6 MS026
CNTMT. The crew may have transition& to ES-0.1. An MSlV will be
(Trigger on MSO6C
7 RP02B C - RO Auto SI fails to actuate. RO may initiate MANUAL SI prior to auto
actuation.
(Pre-insert)
8 SIOSA c - 80 1BIT outlet valves fail to open automatically on SI.
- (Mjormal, (R)eactivity. (1)nstrurnent. (C)omponent. (M)ajor
Scenario 3
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TITLE: Main Steam Line Break Outside Containment
REVISION: 0
DATE: 07/26/04
PROGRAM: WBN Operator Training - Initial License
PREPARED BY: Albert V. White 107I26l04
(Operations Instructor) (Date)
VAblDATlON
BY: I
(Operations instructor) (Date)
REVIEWED BY: I
(Lead Operations Instructor) (Date)
APPROVED BY: I
(Operations Training Manager) (Date)
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CONCURRED: I
(Operations Superintendent) (Date)
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Nuclear Training
RevisionlUsage Log
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0 initial Issue 07/26/04 ALL
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PROGRAM: WBN Operator Training
SUBJECT: Simulator Examination Guide
TITLE: boss of Train "A" CCSiMain Steam Line Break Outside Containment.
LENGTH: -4.5 tiQLifS
REFERENCES:
SCENARIO OBJECTIVES:
1. Evaluate the candidates ability to use normal and abnormal procedures and control
the plant during nonnal and transient conditions.
2. Evaluate the candidates ability to use E-0 and E-2 in response to a Faulted Steam
Generator.
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SCENARIO SUMMARY:
Initial conditions:
- 75% power, Cb = 978 ppm.
The Train Week is A. Channel Week 1 or 111 ok.
AI is out of target band on the high side requiring dilution to correct.
Unit Startup in progress following shutdown for secondary repairs. GO-4, Section
5.1 Step 35.
MBAFW pump 1A-A is out of service for maintenance.
Scenario Events and Sequence:
Set up simulator to IC-151
1. Performs dilution per SO!-62-02 to correct AI and continues power ascension.
2. 1-FT-fi2-142, Primary Water Flow Transmitter, failure.
3. Failure of Non-controlling Pressurizer Pressure channel.
4. Turbine Impulse Pressure Transmitter 1-PT-1-73 fails Low affecting rod control,
steam dumps, and Tref program.
5. CCS Train A Leak that will be greater than makeup capability. Affects A Train
Component Cooling Water, RCS Letdown, RCP cooling, etc. Should require BOP
to diagnose.
6. Main Stearn Line Break Outside Containment occurs after reactor is tripped..
7. MSlV on # 3 SiG fails to close; Auto SI failure; BIT outlet valves fails to auto open
on SI.
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-
EVENT 1 Raise reactor power from 75% to 100% power.
The crew continues power ascension from 75% power in accordance with General
Operating instruction, G O 4
Malfunctions required: None
0bjectives:
e Evaluates the candidates ability to perform dilution for AI correction.
Evaluates the candidates use of GOs to continue power escalation from 75%
power.
rn Evaluates the candidates ability to conduct operations associated with power
escalation from 75% power including turbine load ascension and corresponding
rise in reactor power.
Suemss Path:
0 Conduct power escalation from 75% power IAW G O 4
-
EVENT 2 Failure of 1-FP-62-142, Primary Water to Blender Flow Transmitter
1-FT-62-142 fails and after 30 seconds the PRIMARY WATER TO FLOW DEVIATION
alarm will annunciate and terminate the dilution by closing 1-FCV-62-128 to the VCT. If
1-FCV-62-128 is reopened manually, flow will be reestablished but there will be no flow
indication or audible clicking from the batch counter. A dilution incident could be the
result.
Malfunctions required: I
0 cv51, Fails FT-62-142 output LOW
Objectives:
Evaluate the candidates ability to recognize loss of dilution flow
e Evaluate the candidates ability to monitor reactor parameters to ensure dilution
stopped andlor prevent from occurring.
Success Path:
e Crew ensures dilution stopped and maintenance notified for repair of controller.
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-
EVENT 3 1-FT-68-323, Non-Controlling Bzr Pressure Transmitter, Falls LOW
Non-Controlling Pressurizer Pressure transmitter, 1-PT-68-323, fails LOW. Operator will
be required to diagnose and determine that alarms and indications support the failure.
Operators should respond using AOl-18.
Malfunctions required: 1
Rx07c 0, PZR Pressure Transmitter, 1-PP-68-323, fails LOW.
Objectives:
- Evaluate the candidates ability to implement 801-18 when Pzr Pressure
Transmitter fails low.
- Evaluates candidates ability to access controi board indications to determine
event in progress.
Success Path:
Crew implements ,401-18, section 3.0, to respond to Pressurizer Pressure
Transmitter failure, determines that RCS pressure is stable and non-controlling
pzr pressure channel has failed.
Tech Spec are evaluated and entered for this failure.
-
EVENT 4 1-FT-1-73, Turbine Impulse Pressure Transmitter, Fails LOW
Turbine Impulse Transmitter, 1-PT-1-73, fails low causing control rods to begin insertion
at a maximum rate. Operator will be required to take manual control of rods. Steam
Dump control will be require to be placed in Steam Pressure Mode. Operators should
respond using AOI-2.
Malfunctions required: 1
r x l l a 0 , Turbine Impulse Pressure Transmitter, 1-PT-2-73, fails LOW.
Objectives:
Evaluate the candidates ability to implement AOI-2 when Turbine Impulse
Pressure Transmitter fails low.
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Evaluates candidates ability to access control board indications to determine
event in progress.
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Success Path:
- Crew implements AOI-2, section 3.2, to respond to Turbine Impulse Pressure
Transmitter failure, places rod control to Manual, and places Steam Dump Control
in Pressure Mode.
-
EVENT 5 CCS Leak A greater than makeup capability.
CCS leak occurs on the outiet of the A CCS Heat Exchanger bringing in CCS Surge
Tank level Low alarms. Makeup to surge tank occurs but leak is greater than makeup
capacity. 801-15 should be implemented.
Malfunctions required: 4
ecO4, Component Cooling System Pump Shaft break IA-A CCS pump.
Objectives:
Evaluate the candidates ability to diagnose that a loss of the ATrain CCS
cooling control board indicators and annunciators.
- Evaluate the candidates ability to implement AOI-15 for CCS leakkupture that
results in loss of A Train CCS cooling.
Success Path:
- Crew recognizes conditions for entry and implements AOI-15 in response to
Component Cooling System leakhupture. CORdibiQnSwill dictate removing A
Train ECCS components from service, manual trip of the reactor, stopping of all
Reactor Coolant Pumps, and aligning ERCW to 1A-A CCP as a contingency for
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EVENT 6 -Main Steam Line Break Outside Containment
- 3 Steam Generator becomes faulted outside containment. This failure causes
excessive cooldown. MSBV closure should be directed. 1-FCV-1-22, MSIV on # 3 S/G
will fail to close.
Malfunctions: 2
0 msQ2c,ramped over 10 minutes to 10% severity.
msQ6c 10Q,fails SIG # 3 MSIV fully open.
0bjectives:
Evahate the candidates ability to diagnose a steam line break, and transition
from E-0 to E-2, Faulted Steam Generator Isolation, to E-I, Loss of Reactor or
Secondary Coolant, and then to ES-1.I, SI Termination.
Success path;
accordance with ES-1.I.
EVENT 7 -AUTO SI Fails to Actuate
Malfunctions required: 1
sp02b, Auto SI Initiation Failure
Objectives:
Evaluate the candidates ability to monitor SI initiation parameters and manually
initiate SI when required.
Success Path:
Crew diagnoses need for Safety Injection and initiates a Manual SI.
Crew determines that Steam Generator Pressure continues to drop and takes
conservative action manually initiates manual Safety Injection.
Crew returned to E-0, implements 4,then transitions to E-2 to isolate faulted
SG, then transitions to E-I then ES-1.Ito terminate SI.
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-
EVENT 8 BIT Outlet Valve 1-FCV-63-25 & 1-FCV-63-26 Fail to Open Upon SI Signal
Malfunctions: 2
SiOSa, Failure of individual SI signal
si09b, Failure of Individual SI signal
Objectives:
Evaluate the candidates abiiity to recognize a failure of BIT Outlet Valves 1-
FCV-63-25 & 26 to OPEN on SI.
Success Path:
Recognize that BIT Outlet Valves failed to OPEN and manually open the valves.
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CONSOLE OPEWTORS INSTRUCTIONS
rst 151I switch check, 75 % RTP, BOh, Cb=970 ppm, Bank
select RUN 3 at 193 steps.
Turn audible sirnulator revents unnecessarily alerting crew
fault alarm to off (down i f a simulator problem that may not
position) 2ffect simulator dynamics.
Place A Train Week 3n entrance side panel. Channel
sign Neek I or 111 ok.
Place Dynamic AFD Nil1 indicate on positive side of target
Display on QAC land. Setup to require dilution on
computer screen. urnover.
Place 1 HS-3-118A in PTL Simulates 1A-A MDAFWP OOS for
and tag I HS-3-118A and naintenance.
1-HS9355.
NOTE: IC 151 has been
setup for this scenario. If
unavailable, new setup for
positive AI and power level
will be required.
ior rlohs3355 close Simulates 1-FCV-3-355, ?A-A
ior rlohs3355[1] off vlDAFWP Recirc, tagged closed.
ior zlohs3355[2] off
Simulates IA-A MDAFWP hand
- witch light out.
imf msQ6c100 -ails SIG # 3IMSlV open.
imf rp02b 4uto SI fails to auto actuate. Manual
3 available.
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CONSOLE OPERBTORS INSTRUCTIONS
(Continued)
LI imf cv51 (e2) 1-FT-62-142, primary water to blender
flow transmitter, signal fails low.
Results in no flow indication or audible
click.
0 imf rxO7c (e31 0 1-FT-68-323 fails low.
imf rxl l a (e4) 0 1-PT-1-73, impulse pressure
transmitter fails low.
0 imf ccOl (e51 50 5: "A" CCS header break makeup
capacity ramp to 50% over 5 min.
D imf ms02c (e19) 10 Main steam Bine break outside
IO: containment with ramp of 10 minutes
to a 10% final severity.
After crew assumes
shift:
When directed by imf itrigger2 1-FT-62-142, primary water to blendes
the evaluator for transmitter fails low.
-
Event 2 (insert after dmf cv51 only if
ROLE PLAY: As Work Control, inform
firsf batch dilution evaluator request it
has been the crew that the transmitter work
completed) package will be initiated.
If dispatched to ROLE PLAY: As AUO if dispatched to
blender station. blender station, acknowledge request,
when makeup occurs report 1-FIT-62-
142 indicates 70 gpm, when makeup
stops report that flow is 0 gpm.
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CONSOLE OPEWTQRS INSTRUCTIONS
(Continued)
When directed by mf itrigger3 Non-controlling PZR pressure channel
the evaluator for 1-PT-68-323 fails low.
Event 3 ROLE PLAY: As Work Control, when
contacted, inform the MCR that IMs
will be dispatched as soon as the work
package is issued.
When directed by rnf itrigger4 1-PT-1-73, Turbine impulse pressure
the evaluator for transmitter, fails low.
Event 4
ROLE PLAY: As Work Control, when
contacted, inform the crew that this
transmitter will be added to the work
scope and ask for a priority between
the two transmitters.
When directed by mf itrigger5 ACCS header break m a k e u p
h e evaluator for capacity ramp to 50% over 5 min.
EVENT 5
ROLE PLAY: As AB AUQlRad Waste
AUQ, when requested, acknowledge
request to check for ieaks in CCS.
ROLE PLAY: As Aux Building AUQ,
3 minutes after
report that the 66s leak is on the
.equested to
outlet of the A CCS Heat Exchanger.
nvestigate
I
3 min after rnrf rwrO8 open ROLE PLAY: As Aux Building AUO,
.equested to perform acknowledge request to align ERCW
4ttachrnent 1 of AOI- to 1A-A CCP per Attachment 1 of AOI-
15 15.
ROLE PLAY: As Aux Building AUQ,
report that ERCW has been aligned
1A-A CCP per Attachment 1 of AOI-
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CONSOLE OPERATORS INSTRUCTIONS
(Continued)
EVENT 6 Auto entry on Reactor Main Steam Line Break outside
trip e19 trigger containment.
ROLE PLAY: As Outside AUO, if
requested, report steam corning from
the North Valve Vault Room.
JVhen requested mrf rnsr26 aux MSIV-2-22 Aux switch to Aux.
ROLE PLAY: As AUO, when
contacted to take local action to close
- 3 MSIV, acknowledge request, wait 2
minutes, then report Aux switch has
been placed to AUX position.
iNhen requested ROLE PLAY: As AUO, when
contacted to check low analyzer temp
lights NOT LIT, acknowledge request,
wait 2 minutes, then report that Low
p lights on H2 Analyzers are NOT
Nhen requested
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APPENDIX A
INFORMATION TO EVALUATORS
1. Assign Crew Positions: Assign positions based on evaluation requirements for
personnel.
US Unit Supervisor
~
OAC - Operator at Controls
CRO - Control Room Operator
2. Review the Shift Briefing Information with the operating crew. Provide the US with a
copy of Appendix B, Shift Turnover Checklist.
3. Allow the crew to familiarize themselves with current control panel condition (up to 18
minutes).
4. Ensure recorders are inking and recording and ICS is active and updating. Note any
deficiencies during shift briefing.
5. If not previously done, review any major differences between plant and simulator.
6. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.
7. Provide copy of G O 4 Normal Power Operation Section 5.1 completed through step
34 for use by the Unit Supervisor.
6. Provide copy of E-0 Reactor Trip or Safety Injection Appendices A and B to the
CRO Evaluator.
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OP Test No: - Scenario No.: 3 Event No.: 1 Page - 1 of -2
Event Crew will continue power ascension from 75% power using G O 4
Dilution to correct AI.
Walks control boards down in
preparation for raising power and
initiates load escalation to 100%
Initiates load escalation to 200% power
Determines and sets in load rate,
e Uses reference control button to set
desired load.
Depresses go to begin raising load.
Directs OAC to initiate dilution per SOI-
52.02 Boron Concentration Control,
Section 6.2.
letermines required quantity of water to Ippendix D 8 Appendix
achieve desired RCS Cb by referring to !were provided as part
Zppendix D and Appendix E of SOI- ~fturnover information
32.02.
ENSURES 2-FC-62-142, PW TO
3LENDER dial [1-M-6], set to 35% (70
jprn), and Manual-Auto toggle in AUTO.
\DJUST 1-FQ-62-142, PW BATCH 4 quantity lower that
- OUNTER [1-NI-6], for required quantity ippendix D value may
rom Appendix D. )e set in.
LACE 1-HS-62-140B, VCT MAKEUP
K I D [1-M-6] in DIL.
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OP Test No: - Scenario No.: 3 Event No.: 1 Page - 2 of __ 2
Event Crew will continue power ascension from 75% power using G O 4
Description: Dilution to correct AI.
...............
-:
..:.:.:.:.:........:.:.:.:.:.,
?&$@a@
.................
P
..
OAC TURN I-HS-62-140A, VCT MAKEUP
CONTROL [I -M-6] to START, and
VERIFY Red light is LIT.
OAC ENSURES 1-HS-68-341H, BACKUP
HEATER C [1-M-4] is ON to equalize
Pnr-RCS C,.
OAC MONITORSthe following parameters: 1-M-6
0 1-PI-62-122----VCT Press.
0 1-LI-62-129A---VCT Level.
0 ?-Fl-62-142----PW to Blender Flow.
0 I-FQ-62-142---PW Batch Counter.
1FQ-62-139----BA Batch Counter.
OAC MONITORS NIS and Rod Movement to Rods will insert to
verify expected response. depress delta I.
OAC IF I-LI-62-129/4, VCT LEVEL [1-M-6]
rises to 63%, THEN ENSURE 1-FCV-62-
11BA, LETDOWN DIVERT TO HUT,
diverts to the HUT.
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QP Test No: - Scenario No.: 3 Event No.: 2 Page - 1 of - 2
Event 1-FT-62-142, Primaw Water To Blender, Flow Transmitter Fails
Description: LOW
-:
........ :.:.:.:.:<
-
T&gi&g
................
OAC Recognizes dilution has stopped either
from flow indication going to 0 , audible
clicking noise from 1-FQ-62-142
stopped, or alarm window 112-E, PW TO
BLENDER FLOW DEVIATION.
Console Operator will insert failure
when first dilution batch has been
completed.
OAC Addresses ARl on window 112-E and
reviews probable cause and corrective
actions:
If dilution controls in Auto, then Zontrols will be in dilute.
v~ii1 y-FCV-62-128 and 1-FCV-62-
144 CLOSE.
- Ensure VCT makeup control system
lined up per Sol-62-02, Boron 3eference to AO8-3 will
Concentration Control. 3 8 of no assistance
- If manual operation of VCT makeup mless dilution event
is required, then go to SOI-62.82 for :reated by the
system alignment and operation. :andidate.
Refer to AQI-3, Malfunction of
Reactor Makeup Control.
- Notify WQKkCentral to initiate
corrective action if necessary.
us Way direct returning controls to \Io flow indication will be
automatic operation and notifying Work available, but flow can
Zontrol of malfunction. )e established if valve to
JCT is manually
Ipened. No clicking of
- ontroller will be heard.
_a__/
Scenario 3
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OP Test No: -Scenario No.: 3 Event No.: 2 Page ~
2 of _
2.
Event 1-FT-62-?42,Primary Water To Blender, Flow Transmitter Fails
Description: LOW
Should postpone power ascension until
primary water flow transmitter fixed.
Directs OAC to re-initiate dilution per If power ascension is
SOI-62.02, Section 6.2. After being desired, w e Console
notified that 1-FT-62-142 transmitter was Operator to delete 1-FT-
improperly valved in and can be signed 62-142 malfunction.
off by performing makeup as PMT.
Scenario 3
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Scenario No.: 3 Event No.: 3 Page ~ I of -1
1-PT-68-323 Pressurizer Pressure Transmitter Fails LOW
Recognizes PZR pressure channel
failure and informs crew. Determines
that it is NOT a controlling channel.
Implement ,401-18 and direct crew
actions.
Ensures PZR pressure stable or rising
and pressure controls responding
normally.
Checks 1-XS-68-340D not selected to a
failed controlling of backup channel.
Notifies Work Control to remove 1-PT-68-
323 from service.
Refer to Tech. Specs and enters
applicable LCO actions. Announce to
the crew entry into the following LCOs:
1 LCO 3.3.1.6. Condition W
1 LCO 3.3.1.8.a & b Condition X & W
1 LCO 3.3.2.1 .d Condition D
LCO 3.3.2.8.b Condition L.
qotifies Work Control to initiate reDairs to
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Scenario 3
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OP Test No: - Scenario No.: 3 Event No.: 4 Page - 1 of - 2
Event 1-PT-I -73 Turbine Impulse Pressure Transmitter Fails LOW
Description:
rn T EmTmm
- .*=
......... -332
- R@
p
.......... -
.................
OAC Places rod bank selector switch in Rods step in at 72 steps
manual, and verifies rods stop. per minute.
___.
us Refers to and implements AOl-2
Malfunction of Reactor Control
System, Section 3.2.
OAC Maintains Tavg on program by use of Control rods should be
control rods or adjusting turbine load stepped back out to 193
(Attachment 2). steps if not moved since
-
QAC
OAC Checks Auct Tavg normal on 1-TR-68-
2B. I
QAC Shecks NIS power range channels
normal.
CRO Identifies failure of PT-1-73 and places
steam dumps in pressure mode.
Place steam dumps to OFF.
a Place mode selector HS to STEAM
PRESS.
Adjust steam dump demand to
zero.
a Place steam dumps to ON.
0 Ensure controller set at 84%.
Scenario 3
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- Scenario No.: 3 EventNo.: 4 Page - 2 of - 2
1-PT-1-73 Turbine Impulse Pressure Transmitter Fails LOW
)ACICR Monitors core power distribution
parameters:
Power range channels
e flux indicators
Tavg
- LoopAT
lncoseTCs
Feed flowlSteam flow
US Refer to Tech Spec and enters b 6 0
3.3.1.16. f Condition S.
US Determines power change not greater
than 25%. and Chemistry does not
need to be notified.
Scenario 3
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Page 28 of 33
I P Pest No: ~
Scenario No.: 3 Event No.: 5 Page - 1 of - 3
Event CCS LeaklRupture on Train Agreater than makeup capability.
Description
CRO Identifies problem with CCS by various
CCS alarms. Dispatches AUQs to
investigate problem with CCS.
I I
I
Implements AOI-15 Section 3.2 and
directs crew actions.
1 CRO Checks that no pumps have tripped and
all are pumping fasward.
CRO Checks surge tank vent 1-FCV-70-66
OPEN, determines CCS Surge Tank Bevel
to be lowering, determines that Z-LCV-
70-66, U.8 Surge Tank Makeup LCV, is
I (open,
CRQ Monitors A and B Surge Tank levels Action to stop affected
greater than 10%. When Asurge tank pumps may occur later
level is 6 10 %, stops affected CCS than indicated here.
pumps. (IA-A CCS pump/l B-B CCS
pump and both thermal barrier booster RCPs can be opefated
pumpsf for up to 10 minutes
after loss of CCS flow.
USlCRO Determines that lass of A Surge Bank
Level is imminent.
Scenario 3
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-:
OAC Starts 1B-B CCP, stops TA-A CCP.
us Dispatches personnel to line up ERCW to AQI-15 directs that
1A-A CCP lube oil Hx using AQl-I5 completion must be withir
Attachment 1. 10-12 min. or damage
may occur if CCP-1A-A is
in service.
OAC Isolates normal charging and letdown
Cfoses letdown orifice isolation 1-
FCV-62-73 or 74.
- Closes RCS letdown valves from
Loop 3 1-FCV-62-69 and 70.
- Closes Charging line isolation
valves 1-FCV-62-90 and 91.
MGICRC STOP and LOCKOUT the following Mofe:This action may be
pumps: 3eiayed as 5 0 fakes
TBBPs I- A & t-B wiority.
CSpumplA-A
SI pump1A-A
CCP-1A-A
us Directs QAC to actuate a manuai Rx trip,
Verify trip, perform immediate actions,
h e n stop all Reactor Coolant Pumps.
Scenario 3
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OQ Test No: -Scenario No.: 3 Event No.: 5 Page - 3 of - 3
CCS LeaWRupture on Train A greater than makeup capability.
Description
tripped, performs immediate actions, then
stops all four reactor coolant pumps.
Scenario 3
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1) OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 1 of - 7
n Event
Description:
Main Steam Line Break, Auto SI failure to actuate. BIT outlet
valves fail to Open on SI.
us Implements E-0 Reactor Trip or Safety
Injection and directs crew actions.
CREW Performs immediate actions of E-0.
CRO 0 Ensures turbine trip.
0 Ensures shutdown boards
energized.
US Transitions to ES-0.1 and directs crew
actions.
CREW Commences monitoring of Status
Trees.
CREW Monitors SI actuation Criteria.
OAC letermines RCS temperature dropping
below 557°F and informs Crew.
Scenario 3
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OP Test No: Scenario No.: 3 Event No.: 6, 7,8 Page - 2 of - 7
Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open on SI.
pmif8d
. ..............
us Directs closure of MSlVs. May direct
manual Safety Injection based on
lowering SG pressure.
CRQ Closes MSlVs as directed by US. Critical Task
Informs crew that # 3 SIG MSlV failed to
close. Dispatch of personnel to
Checks steam dumps dosed locally close MSlV should
Check steam dump controls in OFF. be done after first 4 steps
of E-0 mmpleted.
CREW Determines that safety injection is Event 7
imminent due to dropping SIG pressure.
Note: Auto safety
injection has failed.
us Directs Safety Injection initiation.
OAC Initiates manual safety injection.
us Returns to E-0 and directs crew actions.
Scenario 3
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QP Test No: Scenario No.: 3 Event No.: 6, 7,8 Page - 3 of - 7
Event Main Steam bine Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open on SI.
o Ensures reactor trip is still tripped.
and safety injection.
o Monitors ECCS actuation by
checking pumps running and Event 8
alignments. Manually OPENS BIT
outkt valve 1-FCV-63-25 & 26
Ensures MFW isolation:
o MFW isolation valves closed
MFW bypass isolations closed
MFW reg and bypass reg valves
closed
MFWPT A and B tripped
Standby MFWP StQpped
Cond demin pumps tripped
t Cond booster pumps tripped
Evaluate SI suppoa systems using E-0,
Appendix A.
Monitors ECCS operation by
checking pumps running and
alignments.
Ensures cntmt isolations by
See Attachment for copy
of Appendix A & B of E-0
in back of this guide.
checking Phase A, and CVI on
status panels.
Checks cntmt pressure 2.8 psig.
I
Ensure secondary heat sink available.
Scenario 3
Revision 0
Scenario 3
Revision 0
Page 35 of 33
- P
OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page -4 of - 7
Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open OR SI.
- $.&g
"<$:#
- ................
us May direct isolation of AFW flow to #3
SIG on completion of Step 12 E-0.
OAC Checks excess letdown valves closed (1-
FCV-62-54 and 1-FCV82-55).
QAC Check PZR safety valves, PORVs and
PZR spray valves closed.
-
CRO
in uncontrolled manner.
US Transitions to E-2, "Faulted Steam
Generator Isolation", and directs crew
actions.
CRO Verifies MSIVs and bypasses closed.
Verifies steam dump controls are OFF.
-
CRO Verifies at least 1 intact SIG available.
Scenario 3
Revision 0
Page 36 of 33
OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 5 of - 7
Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open on SI.
................
CREW Determines # 3 SIG as the faulted SIG.
~~~
CRO Isolates # 3 SIG: Critical Task
Isolates AFW to # 3 SIG.
e Ensures MFW isolated to # 3 SIG.
e Ensures # 3 SIG PORV closed.
Ensures # 3 SIG Blowdown isolated.
e Ensures TD AFW supplied from
intact SIG.
CRO Monitors CST level >200,0013gallons.
us Directs CRO to control RCS temp stable
with intact SIG PORV operation when
Faulted SIG is blown down.
us Transitions to E-? "Loss of Reactor or
Secondary Coolant", and directs crew
actions.
OAC Checks RCPs off if RCS pressure
< 1500 psig.
US Refers to EPIP-I or notifies the SM.
CRO Checks SIG pressure is controlled and
Faulted SG has completed, or will soon,
complete blowdewn.
Scenario 3
Revision 0
Page 37 of 33
OP Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 6 of ~ 7
Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open on SI.
CRQ Maintain intact SG NR levels.
Monitors levels > 10%[25%ADvl
e Control level between 10% and 50%
[25% and 50% ADV].
CRO Checks secondary side radiation normal.
May contact Chem Lab and RABCON
since MSlVs closed.
CRO Ensures cntmt hydrogen analyzers in
service to monitor concentration.
OAC Checks PZR PORVs closed and at least
one block valve open.
OAC Determines cntrnt spray never started.
t ACECRQ Ensures pocket sump pumps stopped fl-
HS-77-410 & 1-HS-77-411).
us
and transitions to ES-1.ISI
Termination and directs crew actions.
Scenario 3
Revision 0
Page 38 of 33
OQ Test No: Scenario No.: 3 Event No.: 6, 7, 8 Page - 7 of - 7
Event Main Steam Line Break, Auto SI failure to actuate, BIT outlet
Description: valves fail to Open on SI.
Resets SI,and Phase A.
Ensures Cntmt Air in service.
Stops one running charging pump.
I
~
OAC Determines RCS pressure stable or
rising.
TERMINATE THE EXERCISE I
APPENDIX B
SHIFT TURNOVER CHECKLIST
Page l o f 2
SHIFT TURNOVER CHECKLET
Page -of -
0 SM
US/MCR Unit _s_
UO Unit - Off-going -Name
0 AUB Station
STA (STA Function) On-coming - Name
1) IA-A M D M W Pump is tagged for oil leak repair of motor outer bearine
I.CO 3.7.5 Condition B for past 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2) AI is out of target band on the positive side requiring dilution to correct.
SVTest in progresdpianned (including need for new brief)
See schedule
Major Activities/Procedures in pmgresdplanned:
Radiological changes in plant during shifl:
None
'art 2 Perdormad by on-coming shift
~
0 A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for ALIOS)
A review of the Rounds sheeWAbnormal madings (AUOs only)
Review the following programs for changes since last shifl turnover:
63 Standing Orders LCO(s) in actions (N/A fer AUOs)
Immediate required reading TACF (N/A for AUOs
-
'art 3 Performed by both off-going and on-coming shift
~
P
A walkdown of the MCR control boards (N/A for AUOs)
Relief Time: Relief Date:
TVA 40741 [03-2001] Page 1 of 1 OPBP-1-1 (03-14-20011
APPENDIX B
SHIFT TURNOVER CHECKLIST
Page 2 of 2
SHIFT TURNOVER CHECKLIST
Page -of -
n SM
E US/MCR Unit -
La uo Unit - Off-going - Name
0 AUO Station
[7 STA (STA Function) On-coming -Name
Abnormal equipment lineup/conditions:
1.4-A MDAFW Pump is tagged for oil leak repair of mntor outer hearing.
Slrest in pKgr@§S/plann@d: (including need far new brief)
Major ActivitiedProcedures in progresdplanned:
1) Unit Startup in progress following shutdown for secondary repairs. GO-4, Section 5.1 Step 35
2) Pre Conditioned power level Is 100%.
3) Sol-62.02 Appendix E target boron for load escalation is 936.7
4) Sol-62.02 Appendix D states that 2028 gallons of primary makeup needed to obtain 100%
with Control bank 'D'at 220 steps.
5) Rx Engineering has requested a dilution to be started as soon as possible to address AI concern.
Radiological changes in plant during shifl
N""R
'art 2 - Performed by on-coming shifl
A review of the Operating Log since last held shifi or 3 days, whichever is less (N/A far ALlOs)
0 A review of the Rounds shesWAbnorrna1readings (AUOs only)
Review th6 following programs for Chang6S since last shifl turnover
0 Standing Orders LCO(s) in actians (N/A far AUOs)
'art 3 - Performed by both off-going and on-coming shifl
P &
A walkdown of the MCR control boards (N/A for AUOs)
- -
Relief Time, Relief Dale
Appendix D Scenario Outline Form ES-D-1
P
Facility: WATTS BAR Scenario No.: 2 (MOD) @-Test No.:
Examiners: Operators:
Initial Conditions: Reactor is operating at 42 Yo with one MFW pump in service with power escalation to
continue after the second MFW pump has been placed in service.
Turnover: Place the B turbine driven Main Feedwater pump in service. After the feed pump has been
placed in service resume power ascension to 45% power. The train week is '4'. 1A-A Auxiliary
Feedwater Pump is out of service for motor lead repair.
Event
- Malf. Event Event
NO. No. Type* Description
-
I N - BOP Place 4 B Turbine Driven Main Feedwater pump in service.
2 8-RO Raise reactor power to 45%
___ N - BOP ____ ~
3 ni07b I - RO Power Range Channel II fails high; requires S/G #2 and #3 level
I - BOP control to be placed in and controlled in MANUAL. Control rods must
I - SRO be placed in and controlled in MANUAL. Requires Tech Spec
evaluation.
~
4 rx24 I - BQP Feedwater Pressure Transmitter 3-1 failure high. Requires manual
I - SRO control of fsed pump master controller.
5 rdOl c-80 Continuous control rod withdrawal (requires manual reactor trip).
C - SRO
6 th02b C All
~ Loop 2 Cold Leg LOCA after transition to ES-O.1
7 C-RO Failure of Auto Phase A; requires manual actuation
(Pre-
insert)
8 rp55b C - BOP Failure of IB-BAFW Pump to auto start; requires manual start of
(Pre- pump.
insert) _ _ _ ~ ~
9 C-RO Failure of WHW to swapover automatically to Containment Sump.
- (Pre-
P
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
Scenario 2
Rev. 0
Page 1 of 41
TITLE: Place Second MFP in Service, Power Escalation from 42% to 45%, PR-
N42 Failure High, PT-3-1 Failure High, Continuous Rod Withdrawal, Cold
beg LOCA, Containment Sump Recirculation.
REVISION: 0
BATE: 07/26/04
PROGRAM: WBN Operator Braining - Initial License
PREPARED BY: Albert V. White I 07/26/04
(Operations Instructor) (Date)
VALIDATION I
BY:
(Operations Instructor) (Date)
REVIEWED BY: I
(Lead Operations Instructor) (Date)
APPROVED BY: I
(Operations Training Manager) (Bate)
Scenario 2
Rev. 0
Page 2 of 41
CONCURRED: I
(Operations Superintendent) (Date)
Scenario 2
Rev. 0
Page 3 of 41
Nuclear Training
RevisionlUsage Log
REVISION DESCRIPTION OF DATE PAGES REVIEWED
NUMBER REVISION AFFECTED BY
0 nitial issue 07/26/04 ALL
Scenario 2
Rev. 0
Page 4 of 41
PROGRAM: WBN Operator Training
SUBJIXT: Simulator Examination Guide
TITLE: Place Second MFP in Service, Power Escalation from 42% to
45%, PR-N42 Failure High, PT-3-1 Failure High, Continuous Rod
Withdrawal, Cold Leg LOCA, Containment Sump Recirculation.
LENGTH: -1.5 Hours
REFERENCES:
1. Technical Specifications
2. SPP l Q . O (Rev 2), Plant Operations
3. OPDP-1 (Rev 4), Conduct of Operations
4. GO-4 (Rev 27), Normal Power Operation
5. SO1-2&3.01 (Rev 84), Condensate And Feedwater System
6. AOi-4 (Rev 26), Nuclear Instrumentation Malfunctions
7. AOI-16 (Rev 2&), Loss of Normal Feedwater
8. E-0 (Rev 13), Reactor Trip or Safety Injection
9. ES-0.1 (Rev 1 Reactor Trip Response
IO. E-?, (Rev I O ) , Loss Of Reactor Or Secondary Coolant
If. FR-O (Rev 9), Status Trees
12. FR-Z.1 (Rev 7), High Containment Pressure
13. FR-P.? (Rev 8), Pressurized Thermal Shock
14. FR-C.2 (Rev 91, Degraded Core Cooling
15. 3-4.3 (Rev 91, Transfer To Containment Sump
16. EPIP-I (Rev 25), Emergency Plan Classification Flowchart
SCENARIO OBJECTIVES:
2 . Evaluate the candidates in tReir use of Abnormal Operating Instructions to
address various failures or transients.
2. Evaluate the candidates use of E-0 to respond to manual reactor trip and
subsequent transition to ES-0.2 Reactor Trip Response.
3. Evaluate the candidates in their transition back to E-0 and use of -Iin
response to a Cold Leg LOCA
4. Evaluate the candidates in their use of ES-I .3 to place ECCS in Sump
Recirculation.
Scenario 2
Rev. 0
Page 5 of 41
SCENARIO SUMMARY:
Initial conditions..
Reactor is operating at 42% with one MFP in service and power
escalation to continue after the second MFW pump has been placed in
service. Cb = I100 ppm, 10000 MWD/MTU.
The Train Work Week is A Channel 1.
MDAFW pump 1A-A is out of service for motor lead repair.
Scenario
.-.. Events a n d _ - S q u e m
- Set up simulator to IC-145
1. Piace IB MFPT in service.
2. Raise power to 45%.
3. Power Range Channel II fails high; requires SIG #2 level control to be
placed and controlled in MANUAL.
4. Feedwater Pressure Transmitter 3-1 fails high; requires manual control
of main feedwater pump speeds.
5. Continuous control rod withdrawal (requires manual reactor trip).
6 . Loop 2 Cold Leg LBCA after transition to ES-0.1.
7. Failure of Auto Phase A Train A; requires manual actuation.
8. Failure of 1B-B AFW Pump to auto start; requires manual start of pump.
9. Failure of RHR to automatically swapsver to Containment Sump.
Scenario 2
Rev. 0
Page 6 of 41
-
EVENT I Place 1B Turbine Driven Feedwater Pump In Service
1B Main Feedwater Pump is placed in service between 40 and 45% power.
Malfunctions required: None
Objectives:
Evaluate the CREW use of GO-4,Normal Power Operation, and SOI-
2&3.01, Condensate and Feedwater System, for placing the second Main
Feedwater Pump in sewice.
Evaluates candidates ability to manually control Main Feedwater Pump
speed and establish proper delta P for S/G level control.
Success Path:
- Crew implements the appropriate procedures to place 1El. MFW Pump in
service with master controller in automatic maintaining S/G level program.
-
EVENT 2 Raise Power to 45 %
Raise reactor power from 4%to 45%
Malfunctions required: NONE
Objectives:
Evaluates the CREW use of GO-4 during power escalation operation.
Evaluates the candidates ability to control feedwater to steam generators
utilizing main reg valve controllers and manual control of SGs 2 & 3 NIS
Bias Controllers (when event 3 to is activated).
- Evaluates the candidates ability to controllmonitor reactivity changes.
Success Path:
Use of G8-4, and appropriate use of peer checks for reactivity changes.
Maintain NIS Bias controllers for S/Gs 2 & 3 matched with NIS Bias
controllers for SlGs I& 4 as reactor power is raised (after event 3 has been
responded to).
Scenario 2
Rev. Q
Page 7 of 41
EVENT 3 - Power Range Channel I I fails High
Power Range Channel N-42 fails HIGH causing auctioneered high NI power to
rise?causing rising feedwater flows to steam generators #2 and #3 due to NIS
program level rise due to this failure.
Malfunctions required: I
niQ7b,Power Range Channel I1 failure
0bjectives:
Evaluates the CRWs use of AQi-4 during load escalation while on main
reg valves.
Evaluates candidates ability to manually control feedwater to steam
generators utilizing main regulating valve controllers for #2 and #3 steam
generators.
Success Path:
- Crew implements AQI-4, Section 3.4, taking appropriate WIV Reg
controllers to manual, defeating power range channel N-42, returning
main reg valves Lo auto control, and returning rod control to automatic.
Continue control of SG #%& #3 NIS Bias as load is raised further.
EVENT 4 - Feedwater Prressure Transmitter 1-PT-3-1 Failure HIGH.
Feedwater pressure transmitter 3-1 fails HIGH which causes Main FW pump
speed to lower requiring the operator to take manual control.
This failure will cause much lowered feedwater flow and SG levels will begin to
DROP until the operator takes manual control of MFW pump speed and raises
pump speeds to supply adequate feedwater flow.
Malfunctions required: 1
8x24, Main Feedwater Pressure Transmitter I-PT-3-1 failure to position.
Objectives:
Evaluate the candidates ability to implement AOI-I6 when Main
Feedwater Pressure Transmitter I-PP-3-1 fails HIGH.
Evaluates candidates ability to manually control Main FW pump speed.
Scenario 2
Rev. 0
Page 8 of 41
Scenario 2
Rev. Q
Page 9 of 41
Success Path:
Crew implements. .Ol. 6, section 3.7, to respond to the Main Feedwater
Pump control circuit failure, takes manual control of the pumps and
stabilizes the plant.
EVENT 5 -CONTINUOUS ROD WITHDRAWAL
Malfunctions required: 1
rdOl , Continuous Rod Withdrawal
Objectives
- Evaluate the candidates ability to verify control rods malfunction during
startup
Success Path:
Recognize continuous rod withdrawal without demand for movement (rod
control in manual), initiate manual reactor trip and transition to E-0.
-
EVENT 6 LOOP 2 Cold Leg LQCA
Malfunctions required: 1
thQ2b LOCA Cold Leg Loop 2
Objectives:
Evaluate the candidates ability to diagnose a large break LOCA,
transition back to E-0 from ES-0.1 and then correctly implement E-1, Loss
of Reactor 8 6 Secondary Coolant.
e Evaluate the candidates ability to respond to high containment pressure
in accordance with FR-Z.2 High Containment Pressure, when required by
I
the Status Trees.
Evaluate the candidates ability to recognize conditions requiring transfer
of RHR to the containment sump and transition to E-I 3, Transfer to RHR
Containment Sump.
Scenario 2
Rev. Q
Page 19 of 41
Success Path:
e Crew diagnoses large break LBCA, transitions to E-0 and correctly
implements -I.
e Crew responds to containment high pressure in accordance with FR-Z.l.
e Crew recognizes RWST level 34% and containment sump > 16.1% and
transitions to E-I .3.
-
EVENT 7 Phase A containment isolation fails to actuate
Malfunctions required: 1
e siQ9t Failure Phase A Train A Gntmt Isolation Signal
0bjectives:
e Evaluate the candidates ability to recognize a failure of Phase A to
actuate and initiates manual Phase A.
Success Path:
Crew diagnoses failure of Phase A to actuate and initiates manual Phase
A
-
EVENT 8 Failure of 1B-B AFW Pump to auto start
Malfunctions required: 1
0 rp55b Failure of 1B-B AFW Pump to auto start.
0bjectives:
e Evaluate the candidates ability to recognize a failure of Start signal for
1B-B AFW Bump, and start the pump manually.
Success Path:
e Crew diagnoses failure of 1B-B AFW pump to start, and then get the
pump started manually.
Scenario 2
Rev. 0
Page I 1 of41
-
EVENT 9 Failure of auto swapover to cntmt sump
Malfunctions: "I
0 bjectives:
Evaluate the candidate's ability to respond to a failure of automatic
swapover to cntmt sump
Success Path:
Operator must manually open Cntmt SUMPisolation valves 1-FCV-63-72
and 73 and ensure the RHR suction valves 1-FCV-74-3 and 21 auto
open.
Scenario 2
Rev. 0
Page I 2 of 41
CONSOLE OPERATORS INSTRlBCPlONS
...... . . . . . . . . . . P . . . . . . . . . . . . .
. . . . . . .............. DESCRIPTION
3m Setup rst 145, switch check, 52 % RTP, MOL, Cb=llOO ppm,
select RUN 10000 MWDIMTU
NOTE: IC 145 has
been setup for this
scenario. Continue
with set up if IC 145 is
unavailable. rst 52 and
lower load to 42% and
utilize fast time xenon
and boron changes to
establish 42% and
steady state Xenon
with AI in target band.
Turn audible revents unnecessarily alerting crew
simulator fault alarm if a simulator problem that may not
to off (down affect simulator dynamics.
position)
Place A Train
Week 8, Channel I
signs on control
board
I Place 1 HS-3-118A in 3mulates IA-A MDAFWP 80s for
PTL and tag 1 HS-3- naintenance.
Z 18A and 1-HS-3-355.
I ior zlohs3355[1] off jimuiates 1-FCV-3-355, IA-A
dDAFWP Recirc, tagged closed.
ior zlohs3118a[l] off Simulates 1A-A MDAFWP handswitch
ght out.
Scenario 2
Rev. 0
Page 13 of 41
CONSOLE QPERBTORS INSTRUCTIONS
(Continued)
DESCRIPTION
-...................
Power Range Channel I1 fails High.
0 Imf rx24f (e4) 100 10 Feedwater pressure transmitter 1-PP-
3-1 failure to 100% over 48 seconds.
Continuous Control Rod Withdrawal.
0 imf si091 Containment Phase A Train A Auto
Isolation Failure
8 I Imf rh02 Prevents 1-FCV-63-72 8 73 from auto
opening during swapover to cntmt
sump. Operator must manually open.
Auxiliary Feedwater Pump 13-B Auto
Start Inhibit
D I imf 6hQ2b(e61 35 5: Cold Leg LOCA Loop 2 over 5 minute
ramp (large break LOCA on loop 2
cold leg)
Scenario 2
Rev. 0
Page 14 of 41
CQPJSC E OPEaATQRS lNSTRUCTlONS
(Continued)
... . . . . . . . --
.......................RESCRIPTIQN
.....
Nhen requested ROLE PLAY: As TB AUO, when
requested, assist in startup of 1H
MFWP'I IAW SOI-2&3.Oi, Section
5.10.
When requested by rnf itrigger3 Power Range Channel II fails High.
?valuatorfor EVENT
I
ROLE PLAY: As Work Control, when
contacted inform crew that as soon
work package is issued MlG will come
to control room before tripping
bistables and then will initiate repairs
for Power range channel N-42.
Vhen requested by rnf itrigger4 Main Feedwater Pressure Transmitter
- valuator for EVENT 1-PT-3-1 fails HIGH.
1
ROLE PLAY: AS Work CQntd,when
contacted inform crew that as soon
work package is issued MI6 will
initiate repairs.
Scenario 2
Rev. 0
Page 15 of 41
CONSOLE OPERATORS INSTRUCTIONS
(Continued)
- -. _-
...
-.ELAPSED
....................TIME
. ICIMFIRFIOR
............._ -. ..................DESCRIPTION
....
Vhen requested by irnf itrigger5 Continuous Rod Withdrawal
?valuatorfor EVENT
P
When requested by irnf itrigger 6 FIGS LOCA Cold Leg Loop 2 ramps in
?valuatorfor EVENT over 5 minutes.
i
Vhen requested ROLE PLAY: As AUO, when
contacted to open Ice Condenser
ACBs using Appendix A of FR-2.1,
acknowledge request, wait 2 minutes,
then report that Ice Condenser ACBs
are open per Appendix A of FR-Z.1.
Vhen requested ROLE PLAY: As AUO, when
contacted to check low analyzer temp
lights NOT LIT, acknowledge request,
wait 2 minutes, then report that LOW
temp lights on H2 Analyzers are NOT
LIT.
Yhen requested rnrf sir04 on Restores power to CLA lsol Valves
mrf sir44 on Restores power to 1-FCV-63-1
rnrf sir06 on Restores power to 1-FCV-63-22
ROLE PLAY: As AUO, when
requested to perform Appendices .
4cknowledge requests, wait 2 4
minutes, then report that Appendices
lave been completed.
Scenario 2
Rev. 0
Page 16 of 41
APPENDIX A
INFORMATION TO EVALUATORS
1. Assign Crew Positions: (Assign positions based on evaluation requirements
for personnel.) Log the positions on Appendix C.
US Unit Supervisor
~
O K Operator at Controls
~
CRQ Control Room Qperator
~
2. Review the Shift Briefing Information with the operating crew. Provide the US
with a copy of Appendix 5, Shift Briefing Information.
3. Allow the crew to familiarize themselves with current control panel condition
(up to 10 minutes).
4. Ensure recorders are inking and recording and ICs is active and updating.
Note any deficiencies during shift briefing.
5. If not previously done, review any major differences between plant and
simulator.
6. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.
7. Provide marked up copy of GO-4 Normal Power Operation, Section 5.1
(Step 12 complete) and a marked up copy of SQI-2 & 3.01 Condensate and
Feedwater System Section 5.10 (Step 40 complete).
8. Provide copy of E-0 Reactor Trip or Safety Injection Appendices Aand B
to the CRO Evaluator.
Scenario 2
Rev. 0
Page 17 of41
QP Test No: - Scenario No.: 2 Event No.: 1 Page __1 of - 3
Event Startup of the Second MFW pump.
-
Description:
~
.................................................
......................
............ . . .............
,ositron
-
_
_
_.
..
-
..
..
.
..
..
.
.-
.I
Expected ActionslBehavior
................. ............ ............._
CREW Walks control boards down in
preparation for starting MFP.
us
Operation.
us
service per SBI-2&3.01 Condensate startup of MFP may be
hot start complete through step 40.
CRO Place selected MFP(s) in service:
Ensure MFP speed changer control
in manual, and set to minimum
0 1-SIC-46-2QB,MFPT B Speed
Control.
0 Open MFP B discharge valve, 1-
FCV-3-81.
0 Ensures miniflow control valve, l-
FCV-3-84 in auto at 65%.
Place selected MFP(s) in service
CRO
(Continued)
0 Ensures 1-PI-2-129, MFW Pmps
Suction Pressure as follows:
Greater than 108 psig (below
50% load).
Greater than 250 psig (above
50% load).
Scenario 2
Rev. 0
Page 18 of 41
Scenario 2
Rev. 0
Page 19 of 41
- Scenario No.: 2 Event No.: 1 Page - 2 of - 3
Startup of the Second MFW pump.
Place selected MFP(s) in service
CRO
(Continued)
0 Place MFP I B 1-HS-46-43A,
MFPT B HP Stop Valve, or I-HS-
46448, MFPT B LP Stop Valve in
raise to open the LP and HP stop
valves simultaneously.
cao Place selected Governor Valve
Positioner, 1-HS-46=4QA, to Raise
to roll MFP, and verify Governor
Valve Positioner is at maximum
position by red light indication on
controller panel (green light off).
0 Load the MFP Turbine as desired
with I-SBC-46-20B. MFPT B Speed
Control.
CRQ If placing second MFPT in service
and Auto operation is desired, then
perform the following:
Ensure MFP speed changer
control in manual, 1-SIC-46-
208, and set to minimum and
bias setpoint knob set to 50%.
Slowly adjust MFP B speed
controller output to match the
Master Controller PC-46-20.
Place MFP B speed changer,
l-SlC-36-20B, in Auto.
Adjust bias setpoint slowly to
achieve desired flow balance,
Scenario 2
Rev. 0
Page 20 of 41
OQ Test No: - Scenario No.: 2 Event No.: 1 Page - 34 of -
3
Event Startup of the Second MFW pump.
Description:
.............................................
..................
__1-
.. ........... .. .. .. . . . .
.................
................
..................... . . . . .
)ositjoa
. . . . . . . . Expected ActionslBohavior
.......... -....... ................_
Ensure MFP B Hecirc. 1-FIC-3-84,
CRO
opens by auto or manual action
within one minute after pump start,
and remains open as long as TDMFP
flow is less than 2 X I O 6 PPH/4000
gpm.
m When TD MFP flow is >2 X 1O6/40O0
gpm, then ensure 1-FCV-3-84 Main
Feedwater Pump B Recirc is dosed.
CRO Contacts TB AUO to Adjust MFP B oil
temp control, ?-TCV-24-56!3, as
necessary to maintain oil temp
leaving bearings 140" to 1 6 Q T
CRQ Nhen in service MFPT is loaded greater
- han 40% (approx. 3 X 10' PPH), then
- lose selected MFP Turbine drains:
1-HS-46-14, MFPT A Drain VLVS.
- 1-HS-46-41, MFPT B Drain VLVS.
CRQ Nhen selected MFP is in service and will
emain in service, then close the following
ialves by contacting TB N O .
- 1-ISV-46-451, MFPT 1B HP STOP
VALVE DRN ISOL [T2G/730]
1-BW-1-618, MFPT 1B HP Steam
Warming Line Isolation. F2H/723]
L
1-BYV-1-684, MFPT 15 HP Steam
Scenario 2
Rev. 0
Scenario 2
Rev. 0
Page 22 of 41
OP Test No: - Scenario No.: 2 Event No.: 2 Page - 1 of - 2
Event Power Escalation to 45%
- Description:
-
..........
................
..........
..........
...............
.........
c
'osition
.
US
=. .................................................
Expected ActionslBehavior
Directs OAC & CRO to raise turbine load
and reactor to continue the power
...
I
_____m._
Comment (SATNNSAT)
..................
escalation.
CRO Raises turbine load while coordinating
with OAC.
Sol-62.02 'Boron Concentration
Controi", Section 6.2.
QAC ENSURES 1-FC-62-242, PW PO
BLENDER dial [1-M-6], set to 35% (70
gpm), and Manual-Auto toggle in AUTO.
OAC ADJUST 1-FQ-62-142, PW BATCH A quantity lower that
COUNTER [1-M-6], for required quantity Appendix B value may
from Appendix D. be set in.
OAC PLACE 1-#S-62-14QB, VCT MAKEUP
MODE [1-M-6] in DIL. I
Scenario 2
Rev. 0
Page 23 of 41
Event No.: 2 Page - 2 of - 2
Power Escalation to 45%
.- P -
Expected ActionslBehavior
............... - .:omment
...............(SATIUNSAT
........A
TURN 1-HS-62-240A, VCT MAKEUP
CONTROL [1-M-6] to START, and
VERIFY Red light is LIT.
ENSURES 1-HS-68-341H, BACKUP
HEATER C [1-M-4] is ON to equalize
Pzr-RCS C,.
MONITORSthe following parameters: 1-M-6
1-PI-62-122---VCT Press.
I-LI-62-129A---VCT Level.
I-FI-62-142----PW to Blender Flow.
1-FQ-62-142---PW Batch Counter.
1FQ-62-139----BA Batch Counter.
MONITORS NlS and Rod Movement to
verify expected response.
IF 1-LI-62-129A, VCT LEVEL [1-M-6]
rises to 63%, THEN ENSURE 1-FCV-62-
118A, LETDOWN DIVERT TO HUT,
diverts to the HUT.
Scenario 2
Rev. 0
Page 24 of 41
OF Test No: -ScenarioNo.: 2 EventNo.: 3 Page - 1 of - 3
Event Power Kange Channel N-42 Failure High
Description:
...........
......... P -_I__-_yy______________-------------------
................
................
+ -
..........
..........
.......... ................
................
................
..........
.......... ................
................
..........
/.
,me:;:
................ ri
................
.,:.: :. :.
-
.......... os1tlonri
... . . . . . . . . . Expected ActionsiBehavior -.....- ...... Comment
....
___&_&
(SATIUNSAT)
.................,
OAC Recognize failure of Power Range May use A082 to
Channel N-42 and informs CEW of respond to Gontinuous
failure. rod insertion caused by
this malfunction. (AQI-2
Indications:
will direct crew back to
- Power Range N-42 rising AQI-4 when Nls
checked.)
Alarms
0 Power Range Overpower Rod WB
stop
Power Range Channel Deviation
Power Range Flux High
us Implements A014 Nuclear
Instrumentation Malfunctions section
3.4 and directs crew actions.
OAC Places control rods in MANUAL and
verifies no rod motion.
-
OAC Determines that N-42 has failed HIGH
-
CRO Places Main FW Reg valves for S/G2
and SIG 3 into MANUAL, returns S/G
level to program.
CRO Places NIS bias controllers for SlGs 2
and 3 into manual and adjusts their
output to match S/Gs 1 and 4, returns
all Main Keg Valve to AUTO.
Scenario 2
Rev. 0
Scenario 2
Rev. 0
Page 26 of 41
QP Test No: Scenario No.: 2 Event No.: 3 Page - 2 of ~ 3
Event Power Range Channel N-42 Failure High
--
Description:
.................
.................
.................
posiflarr.
.................
.................
.................
.................
.................
.z,z,,z,,,-
................. Comment ( S A
................ Expected ActionslBehavior ....T
...I..U
....N S g
OAC Maintain T-avg and T-ref within 3°F.
OAC Ensures 1-NR-245 recording an
operabk power range channel.
Ensures 1-XS-68-2B, for AT recorder is
selected to operable power range
channel.
OAC Defeats affected PRM Functions:
Defeats upper & lower detector
current comparator for N-42.
- Bypasses rod stop for N-42.
- Bypasses power mismatch circuit for
N-42.
Defeats comparator channel
comparator for N-42.
Resets positive rate trip for N-42.
US WHEN failed PRM defeated and AUTO
rod control desired, directs OAC to
place rod control to AUTO after
ensuring zero demand on control rod
position indication [l-M-4].
OAC Adjusts control rod position with
appropriate peer check to ensure zero
demand on control rod position
indication (CERPI Display), then places
Scenario 2
Rev. 0
Scenario 2
Rev. 0
Page 28 of 41
OP Test No: - Scenario No.: 2 Event No.: 3 Page - 3 of - 3
Event Power Range Channel N-42 Failure High
-
Description:
................
................
................
................
................
................
!QSRI&
................
................
Comment (SATIUNSAI
................ .......................ActionslBohavior
....Expected ....................... ..
us Contacts Work Control and requests
instrument Maintenance to trip failed
channel bistables, and initiate repairs
on N-42.
US Refers to Tech Specs due to NI failure
and enters CCOs 3.3.1.2a Condition D,
LCO 3.3.1 3.a Condition E, LCO 3.3.2.6
Condition W, LC8 3.3.1 .I6 c & d
Condition S , LCO 3.3.1.16.e Condition
R.
US Contacts Operations Duty Manager and
Rx Engineering of power range channel
N-42
us Returns to G O 4
Scenario 2
Rev. 0
Page 29 of 42
....................
.....................................
_____E
...................
...................
...................
....................
...................
- Po#fibK;
..................
slBe
............... ..
OAC Recognize failure of Main Feedwater
Pressure Transmitter Failure HIGH.
Places rod control in manual while
informing crew of failure.
Indieations:
Feedwater flows to all four steam
generators dropping
- Steam generator levels lowering
- Main Feedwater pump speeds
lowering
Alarms:
MFP 1B FLOW LQW
US Implements 801-16 section 3.7 and
directs crew actions.
CRO Determines MFWPT speed
flay have been
controllerjsj are NOT NORMAL.
3erformed earlier as
Places. Controis MFP speeds using mdent operator action.
MANUAL control of the Master
Controller or individual controllers.
PC-46-20 Master Controller
1-SlC-46-208 MFPT 1A Speed
Controller
1-SIC-46-28B MFPT 1B Speed
Controller
Scenario 2
Rev. 0
Page 30 of 41
-Scenario No.: 2 Event No.: 4 Page - 2 of -2
Main Feedwater Pressure Transmitter 3-1 fails high.
- -
-
.-
.-
.
Position Expected
......... ActionslBehavior
QAC When directed, places control rods in
MANUAL and verities rod motion has
stopped. Ensures Tavg and Tref
within 3°F.
CRO Maintains MFWP discharge pressure )rogram: 45 psig to 195
on PROGRAM. x i g from 0% to 100%.
- Approximately 112 psig
above SG pressure).
>Iackard on M-3 may be
.eferenced.
CRQ Monitors SG levels returning to +ogram: 38% to 60%
PROGRAM ~ 1% to 100%.
CRQ Checks Steam Bump Mode switch is
in T-AVG position.
USIOAC Notifies Work Control to have the
instrument repaired.
OAC When directed returns control rods to
Auto.
0 Ensures T-avg and Tref within 1"F
Ensures zero demand on control
rod position indication [I-M4]
Place rods in AUTO
US Returns to instruction in effect.
Scenario 2
Rev. 0
Page 31 of 41
OP Test No: - Scenario No.: 2 Event No.: 5, 8 Page - 1 of - 2
Event Continuous Rod Withdrawal and Failure of 1B-B AFW to Auto
Description:
-
Start
P _-.-.-.__. ....
-.
..........Expected
...... _____
ActionslBohavior
__..... ...... Comment (SATIUNSAT)
Identify rod withdrawal with rods in
MANUAL and inform crew. Advocate a
Implement AOI-2 Malfunction of
Reactor Control System and direct crew
Direct a manual reactor trip.
Initiate a Manual Reactor Trip.
+
Implement E-IReactor Trip or Safety
Injection and direct crew actions.
ROlOAC Perform immediate actions Qf E-0.
Ensures reactor trip.
I CRO Ensures turbine trip.
energized.
Checks SI not actuated and not
required.
Scenario 2
Rev. 0
Page 32 of 41
ansitions to ES-0.1 Reactor Trip
Scenario 2
Rev. 0
Page 33 of 44
OP Test No: ~
Scenario No.: 2 Event No.: 5, 8 Page - 2 of _
2.
Event Continuous Rod Withdrawal and Failure of 1B-B AFW to Auto
- Description:
............
..................
rime posEti&k
..........
..........
..........
..........
..........
-.................
...............
................
................
................
................
................
................
Start
&
-.-
~
........ ................ Expected ActionslBehavior
CREW Implements Status Tree monitoring.
OAC Monitors RCS temperature stable or
trending to 557°F.
CRO Ensures AFW pump operation. Event 8
Identifies failure of AFW 1B-3to start
and informs crew:
- manually starts 1 5 4 AFW pump.
CRO Ensures MFW isolation:
MFW isolation valves ciosed
MFW bypass isolations closed
MFW reg and bypass reg valves
closed
MFWPT A and B tripped
Standby MFWP stopped
Cond demin pumps tripped
- Cond booster pumps tripped
OAC Verifies all control rods fully inserted
us Announces reactor trip over PA system
CRO Monitors CST volume greater than
200,080gal.
Scenario 2
Rev. 0
Scenario 2
Rev. 0
Page 35 of 41
OP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 1 of -9
Event Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of RHR to swapover automatically to
Cntmt Sump.
CREW Determines major transient in progress
based on Alarms and Indications.
OAC Announces Auto SI on Low PZR
Pressure (May manual SI)
May direct manual SI prior to auto
ICRO~OACIPerform immediate actions of E-O. I
Remove RCPs from service based on
RCS pressure 61500 psig or on 0B.
manually started.
Scenario 2
Rev. 0
Page 36 of 44
OP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 2 of - 9
Event Loop 2 Cold keg LOCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of RHR to swapover automatically to
-
....................................
....................................
Cntmt Sump.
P - 7 - p
LAzGXL,
Comment
.. (SATNNSAT)
See Attachment for copy
Appendix A; and Evaluates Phase B of Appendix A & B of E-0
Pipe Break Contingencies using E-0 in back of this guide.
~
I
US Announces reactor tripkafety injection
over PA system
-
Monitor ECCS operation checking
pumps running and alignments:
Charging pumps running
Charging pump alignment
m RHR pumps running
- SI pumps running
BIT alignment
Identifies failure of Phase A Train A to
actuate and informs crew and manually
actuates Phase A Train A Cntmt
Isolation. (May have been performed
Scenario 2
Rev. 0
Page 37 of 41
Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A
-
Description: Cntmt Isolation, FaiBure of RHR to swapover automatically to
Cntmt Sump.
..................
..................
..................
..................
..................
..................
..................
'i'pQsTtlon
..................
..................
CRO Ensure secondary heat sink available.
0 AFWflow
SG level
QAC
OAC Checks excess letdown valves dosed
(4 -FCV-62-54 and 1-FCV-62-55).
OAC Check PZR safety valves, PORVs and
OAC Determines RCP should not remain in
service due to phase B or RCS
pressure I 1500 psig. (May have been
CRO Check SIG pressures controlled OF
rising.
CRO
OAC
informs crew they are abnormal.
Cntmt temp, press, radiation will ail
indicate abnormal.
us
Secondary Coolant" and directs crew
actions until RWST level drops to less
than 34%.
Scenario 2
Rev. 0
Page 38 of 41
Scenario 2
Rev. 0
Page 39 of 41
-
QP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 4 of - 9
Event Loop 2 Cold Leg LQCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of RHR to swapover automatically to
Cntmt Sump.
- .-:
.
,3
____ _..................
E x p t e d ActionslBehavior
.
Refers to EPIP-1 or notifies the SM.
Implements FR-P.l Pressurized
Thermal Shock iWwhen any RCS cold
leg temperature is less than 240°F as
identified by Status Trees.
Checks RCS pressure 5 159 psig
Verifies RHR is injecting to RCS.
Transition back to E-I from FR-P.l
when it is determined that RCS
pressure is 4 5 0 psig and RHR is
injecting.
lmplernents FR-Z.1High Containment Evaluator: Go to page
Pressure if cntmt press greater than 36 for FR-Z.1 steps then
2.8 psig when status trees are return.
monitored.
Impkments FR-C.2 Degraded Core Evaluator: Go to page
Cooling if RVLlS level falls to 33% or 37 for FR-C.2 steps then
less when status trees are monitored. return.
Checks SIG pressure and determines
that pressure are not indicative of a
faulted SIG.
Checks secondary side radiation
normal.
Monitors CST level >200,000 gallons.
Scenario 2
Rev. 0
Page 40 of 41
- At least one SG NR > 18%[25%AD4
NR SG level 6 58% and controlled.
Scenario 2
Rev. 0
Page 41 of 42
OP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 5 of -9
Event Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of KHR to swapover automatically to
Cntrnt Sump.
OAC When Cntmt pressure is 2.0 psig:
Reset Cntmt Spray signal, stops Cntmt
Spray pump 1B-B, and closes
discharge valve 1-FCV-72-2.
es RHR pumps should not be
NOTE: Grew may transition to ES-1.3
when RWSTXNTMT sump conditions
warrant. This may happen at some
point during the following steps
I CRo I Determines shutdown board
alignment.
Initiates BOP realignment using AOI-
17 "Turbine Trip". (may be done as
conditions permit)
OAC Determines RCS pressure dropping or
stable.
Scenario 2
Rev. 0
Page 42 of 41
n I I I R
Scenario 2
Kev. 0
Page 43 of 41
OP Test No: -Scenario No.: - 2 Event No.: 6, 7, 9 Page - 6 of -9
Event Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of RHR to swapover automatically to
Cntmt Sump.
..............................
. .. . . .. . . .
........................................
rime
-
CROIOAC Dispatches AUO to perform 480V
board breaker alignment. (App.A-D)
CRO Determines if hydrogen igniters
should be energized. Energizes
igniters if conditions permit.
OAC Ensures RHR available for cntmt
sump recirculation. Determines that
CROIOAC
using E-I Appendix E.
CRO I Checks Auxiliary Building radiation. I
Notifies Chemistry of event status and
plant conditions.
OAC Determines that RHR is injecting to
OAC
containment sump.
CREW Determines that auto swapover to
cntmt sump has initiated or RWST
level e 34%.
US Implements ES-2 3, Transfer to
Containment Sump.
OAC I Checks both RHR pumps running. I
Scenario 2
Rev. 0
Page 44 of 41
OP Test No: - Scenario No.: - 2 Event No.: 6, 7, 9 Page - 7 of -9
Event Loop 2 Cold Leg LOCA with Failure Of Auto Train A Phase A
Description: Cntmt Isolation, Failure of RHR to swapover automatically to
Cntmt Sump.
-
.- ................. _I
....................................
..................
grficb'
- ......... ...................ActionslBshavior
..... .Expected ........... ..
exchangers.
- Opens 1-FCV-70-156
Cheeks open 1-FCV-70-153
- Closes 0-FCV-70-2 97
Checks CCS Rows & Surge Tank
Levels.
OAC Check RWST IeveB <34% and Cntmt
sump level >16.1%.
OAC Identifies failure of auto switchover to
Critical Task
Cntmt Sump:
Manually opens I-FCV-63-72 and
1-FCV-63-73.
Ensures 1-FCV-74-3 and 1-FCV-
74-21 close.
OAC Monitors RWST level greater than 8%.
-
OAC leterrnine Cntmt Spray can be
stopped: (may have been performed
2arlier)
Resets Cntmt spray signal.
Closes 1-FCV-72-2 and 1-FCV-72-
39
Scenario 2
Rev. 0
Page 45 of 41
OP Test No: -Scenario No.: - 2 Event No.: 6, 7, 9 Page 8 of _9.
Event Loop 2 Cold beg LOCA with Failure Of Auto Train A Phase A Cntmt
..........
..........
..........
..........
..........
rime-
..........
- - -
Description: Isolation, Failure of RHR to swapover automatically to Cntmt Sump.
..........
..........
~.__y_
-.......... Expected
...............ActionslBehavior
.. ........*..... Csniment (SATIUNSAT)
OAC Perform transfer to RHR cntmt sump: Critical Task
(#I) Isolates SIP mini-flow. (I-FCV-
63-3. 1-FCV-63-175, 1-FCV-63-4)
(#2)Isolates RHR crossties. (I-FCV-
74-33, 1-FCV-74-35)
(#3)Aligns CCP and SIP supply from Monitors respective
RHW. ('I-FCV-63-6, 1-FCV-63-7, 1- ECCS flows and motor
- FCV-63-177)
(#4) Aligns RHR discharge to CCP
and SIP suctions. (I-FCV-63-8, 1-
amps as respective
RWST suction valves
are closed.
FCV-63-11)
- j#5) Resets SI.
(#6) Isolates CCP suction from
RWST. (1-LCV-62-135 and I-LCV-
62-136 with HSs pushed in.)
(#7) Isolates SIP suction from WWST.
( 1-FCV-63-5)
(#8)Isolates RHR suction from
RWST. (1-FCV-63-1).
Scenario 2
Rev. 0
Page 46 of 41
__ Scenario No.: 2 Event No.: 6,7 Page - 9 of - 9
Loop 2 Cold beg LOCA with Failure Of Auto Train A Phase A Cntmt
Description: Isolation, Failure of RHR to swapover automatically to Cntmt Sump.
us Directs OAC to initiate Appendix D of
ES-1.3 to monitor for containment
sump blockage.
I TERMINATE THE EXERCISE I
Scenario 2
Rev. 0
Page 47 of 41
-
.................
.................
.................
.................
.................
.................
.................
.................
...............
Evaluation Guide for Implementation of FR-Z.1.
--.-
Zornrnent (ShTIUNSAT)
US hplements FR-Z.l High Containment
Pressure if cntmt press greater than
2.8 psig when status trees are
monitored.
directed: TAG
Ensures Cntmt Spray operation.
e Ensures Cntmt isolation.
Ensures MSlVs closed.
e Places Steam Dump Controls to OFF
e Ensures RCPs stopped.
e Ensures EGTS and ABGBS running.
e Ensures Cntmt air return fans auto
start 10 min after @B.
- ROIOhC FR-Z.1 actions continued:
e Cheeks SIG pressures controolled
and all greater than 120 psig.
e Directs opening ice condenser AHU
ACBs per Appendix A FR-Z.1.
e Determines RHRS should not be
placed in service at this time.
US Transition back to E-0 upon completion
of FR-z.1.
P
Scenario 2
Rev. 0
Page 48 of 41
OP Test No: - Scenario No.: - 2 Event No.: 6%7 Page - 1 of -
3
--
Event Evaluation Guide for Implementation of FR-C.2.
Description:
...........
.........
.......... ................
................
................
..........
..........
............
.. .. .. .. .. ........ ................
................
................
................
.rme
- .. ............. prrsi:fioi.i
................
Expected Zornrnent (SATIUNSAq
......ActIonslBehavlor
~
. . ... . ... . ... ............... .............................................
us Implements FH-C.2 "Degraded Core Monitor step on RWST
Cooling" if RVLlS drops to 33% or lower level will require
when status trees are nionitoretl. transition to ES-I .3
when RWST level drops
to 34%. GO to page 32
- for auide.
OAC Establish RHR valve alignment as
directed:
Checks RWST level greater than
34%.
Ensures RHR suction valves from
RWST OPEN: 1-FCV-63-1; 1-FCV-
74-3 and 21 OPEN
- Ensures RHR discharge valves
OPEN: 1-FCV-74-16 and 28 OPEN.
1-FCV-63-93 and d-FCV-63-94.
-
OAC Establish SI pump valve alignment as
directed:
- Checks RWST level greater than
34%.
- Ensures SI pump suction valves from
RWST OPEN: 1-FCV-63-5, I-FCV-
63-47, 1-FCV-63-48.
- Ensures SI pump discharge valves
OPEN: 1-FCV-63-152, d-FCV-63-
153, 1-FCV-63-22.
Scenario 2
Rev. 0
Page 49 of 41
OP Pest No: -Scenario No.: - 2 Event No.: 6, 7 Page - 2 of -3
Event Evaluation Guide for Implementation of FR-C.2.
Description:
..........
.......... ..................
..................
..................
..........
..........
.......... ..................
..................
..................
..........
........... ..................
..................
cisrig:Pdsi:tl@i
......... ..................
-.......... ..................
OAC Establish charging pump valve
alignment as directed:
0 Checks RWST Bevel greater than
34%.
0 Ensures charging pump suction
valves from RWST OPEN: 1-FCV-
62-135, 1-FCV-62-136.
Ensures BIT outlet valves OPEN: 1-
- FCV-63-25, 1-FCV-63-26.
OAC Ensure ECCS flow as directed:
0 Ensures charging pumps running
Ensures flow thru BIT.
Ensures SI pumps running and has
flow
0 Ensures RHR pumps running and
flow.
CRO Ensure ECCS flow as directed:
exchangers OPEN: 1-FCV-70-153,
1-FCV-70-256.
0 Ensures SFP heat exchanger A CCS
Supply CLOSED: 0-FCV-70-297.
USlCRO Initiate 480V board room alignment per
Appendix A and Appendix El of FR-6.2.
OAC Ensure PZR depressurization paths
closed:
Checks PORVs , Spray Valves and
Aux Spray Valves closed.
Scenario 2
Rev. 0
Page 50 of 41
OP Test No: - Scenario No.: - 2 Event No.: 6, 7 Page - 3 of 3
Event Evaluation Guide for Implementation of FR-C.2.
-
Description:
................
................
................
................
................
................
................
................
p&@&j
................ Expected ActionslBohavior
.-...............**.,_
OAC Ensure RCS depressurization paths
ISOLATED:
RCS Letdown orifice and Isolation
valves.
- Excess Letdown
Post accident sample valves power
removed.
- Reactor Vessel head vent valves
closed.
us Evaluate WCP status. Attempt to
establish and maintain RCP Support
conditions.
us Check if RCS inventory being restored. At this point anticipate
Check RVblS greater than 44% then level rising or RVblS
return to instruction in effect; if not then greater than 44%.
if RVLlS is rising return to step one of
FR-C.2.
US Keturns to Step 1 of this procedure or
transitions back to E-I.
APPENDIX 3
SHIFT TURNOVER CHECKLIST
Page 1 of 2
SHlFT TURNOVER CHECKLIST
Page of -
US/MCR
uo
Unit
Unit
A Off-ooinq - Name_
AUO Station I
STA S T A Function1 Qncomim Name -
'art 1 - Completed by off-going shiWRevlewed by on-comlng shin: RCS Cb = 1100
Abnormal eouinment lineun/conditions:
__ 1) !A48 AF.W Pump is 00s.for ....motor..!.e.a d r e p ?(00s
jr 1h!iEx4.hyjl ... .... ..
__.. IC0 3 . ~ , 5 . A ~ . ~ j q ~ a s l71. ~hours ~ u r: e ~ i x .. . ..._
SliTest in pmgresslplanned: (including need for new brief)
None in progress - see schedule
Maior Adivities/Procedures in Droaress/slanfled:
i) Power ascension to 100% inprogress, G O 4 Section 5.1 Step 12 complete. Operations
Superintendent has directed crew to place B MFP in sewice and then mise p e r .
2) A hot start of B MFW pump is being performed per SOL 283.01 Section 5.10 has been
completed through Step 40.
3) Electrical Maint. is repairing the motor leads on 1A-A AFW Pump.
4) TI-124 Risk Matrix is Green.
5) PCP 100%
Radiologicai changes in plant during shift:
None
-
'art 2 Performed by en-coming shift
0
_ _ _ _ l _ _ _ y _ _
A review of the Operating Log since last held shift or 3 days! whichever is less (NIA for AUOs)
_ P
0 A review of the Rounds sheets/Abnormal readings (AUOs oniy)
Review the following programs for changes since last shifl turnover:
Standing Orders K O @ ) in actions (N/A for AUOs)
g] immediate required reading 0 TACF (N/A for AUOs
'art 3 - Performed by both off-going and on-coming shift
A walkdown of the MCR control boards (N/A for AUOs)
Reiiif Time: Relief Date:
TVA 40741 [03-20011 Page 1 of 1 OPW-1-1 [03-14-2001]
APPENDIX B
SHIFT TURNOVER CHECKLIST
Paae 2 of 2
1 SHIFT TURNOVER CHECKLIST
Page -of -
0 US/MCR Unit - I
4 uo Unit - Off-aoina - Name
AUO Station - _ I
0 SPA (STA Function) .
On-coming- l Name
li
WTest in progresdplanned: (including need for new brief)
None in progress - see schedule
Major ActivitiedProcedures in progress/planned:
I)Power ascension to 100% in pmgrsss, 60-4Section 5.1 Step 12 complete. Operations
. . ..................
. . . . . . ..................................
_.
L AFW
.........Punp
.................
~~~ .~
is standing by B MFW pump with copy of SO1 2 &3.01 Section 5.10.
I Kadiological changes in plant during shifl:
None
I
0 A review of the Rounds sheetdAbnormai readings (AUOs only)
Relief Time: Relief Date:
TVA 40741 (03-ZOOI] Page 1 of 1 OPBP-1-1 [03-14-2001)
Appendix D Scenario Outline Form ES-D-1
I1 Facility:
Examiners:
WATTS BAR Scenario No.:
Operators:
1 (NEW) Op-Test No.:
I! Turnover ~ ~
Event
li I IN-SRO I
1 -6 I h05a I C - All 1 #1 SIG tube ruptures. Rx trip and SI required.
(N)ormal, (R)eactivity, (I)nstrument, (C)ornpenent, (M)ajor
NUKEG-1021, Draft Revision 9
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 0
Page 1 of 39
TITLE: Steam Generator Tube RupturelMain Steam bine Break Inside Cntml
(SG Ruptured and Faulted)
REVISION: 0
DATE: 07/26/04
PROGRAM: WBN Operator Training - Initial License
PREPARED BY: Albert V. White I 07/26/04
(Operations Instructor) (Date)
VALIDATION I
BY:
(Operations Instructor) (Date)
REVIEWED BY: i
(Lead Operations Instructor) (Date)
APPROVED BY: I
Scenario I
Appendix D WBN NRC Simulator Exam Rev. 0
Page 2 of 39
(Operations Training Manager) (Date)
CONCURRED: I
(Operations Superintendent) (Date)
Scenario 1
Appendix B WBN NRC Simulator Exam Rev. 0
Page 3 of 39
Nuclear Training
RevisionlUsage Log
REVISION DESCRIPTION OF DATE PAGES REVIEWED
NUMBER REVISION BY
0 !nitial issue 07/26/04 ALL
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 0
Page 4 of 39
PROGRAM: WBN Operator Training
SUBJECT: Simulator Examination Guide
TITLE: Steam Generator Tube Rupture/Main Steam Line Break Inside
Cntmt (SS Ruptured and Faulted)
LENGTH: -1.5 Hours
REFERENCES:
I~ Technical Specifications
2. SPP 10.0 (Rev 2), Plant Operations
3. OPDP-1 (Rev4), Conduct of Operations
4. EPIP-1 (Rev 211, Emergency Pian Classification Flow Chart
5. GO-4 (Rev 271, Normal Power Operation
6. ,401-33 (Rev 29 ), Steam Generator Tube beak
7. ,401-16 (Rev ai'), Loss of Normal Feedwater
8. ,401-20 (Rev 23, Malfunction of Pressurizer Level Control System
9. AOE-38 (Rev 38), Main Steam or Feedwater Line Leak
IO. 50 (Rev 24), Reactor Trip or Safety Injection
11. E-2 (Rev IO), Faulted Steam Generator Isolation
12. E-I (Rev 13), Loss of Reactor or Secondary Coolant
13. 4, (Rev 20), Steam Generator Tube Rupture
14. ECA3.1 (Revg), SGTR and LQCA Subcooled Recovery
15. FR-Z.1 (Rev 8) High Containment Pressure
SCENARIO OBJECTIVES:
1. Evaluate the candidates in their use of Abnormal Operating Instructions to
address various failures or transients.
2. Evaluate the candidates in their use of E-0 to respond to a reactor trip and
SI.
3. Evaluate the candidates in their use of E-3 in response to a Steam
Generator Rupture (SGTR & Faulted).
4. Evaluate the candidates in their use of E-3 in response to a Steam
Generator Rupture that is faulted inside containment.
5. Evaiuate the candidates in their use of FR-Z.l in response to High High
Containment pressure.
6. Evaluate the candidates in their use of ECA-3.1 in response to a faulted and
ruptured SG inside containment.
Scenario 1
Appendix B WBN NRC Simulator Exam Rev. 0
Page 5 of 39
SCENARIO SUMMARY:
Initial conditions:
75% power, Cb = 951 ppm, 10000 MWDIMTU.
e Rod Control is in MANUAL, Maintenance is troubleshooting Auto Rod
Control Circuit.
Chemistry is taking routine samples of primary and secondary systems.
Unit Startup in progress following shutdown for secondary repairs. 60-4,
Section 5.1 Step 35.
e Immediately resume power escalation to 100% while maintaining AI in
target band.
Scenario Events and Sequ.gm
......
1. Resume power escalation.
2. Tagging AUO reports to Control Room with two Hold Order Tags for
tagging out 1A-A MD AFW pump. Reports to Unit Supervisor that
Operations Superintendent has requested an immediate clearance to be
placed on 1A-A MD AFW pump to prevent damage to pump. The data
taken pump during Surveillance run last shift, on review by Engineering,
indicates action required due to high vibrations.
3. Chem Lab report of 10 gallonlday tube leak in # I SG, which requires
operator to enhance monitoring of leak rate.
4. Main Steam Pressure Transmitter, 1-PT-1-33, fails HIGH which causes
the main feedwater pumps to raise speed and requires the operator to
take manual control of pump speed.
5. Pressurizer Level Transmitter, 1-LT-68-339, faiis LOW requiring isolation
of charging flow, defeat of channel, and re-establishment of charging
and letdown.
6 . Chem Lab reports that #1 SG tube leak has elevated to 0.15 gpm.
7. Main Steam Line leak #I SG inside containment.
8. Auto SI fails to actuate.
9. VGT Outlet valves fail to close on SI.
I O . Steam Generator tube rupture on #I SG on transition from E-%.
Scenario 1
Appendix B WBN NRC Simulator Exam Rev. 0
Page 6 of 39
EVENT 1 -Continue load escalation
The crew continues plant startup from 75% power in accordance with General
Operating Instruction, (30-4.
Malfunctions required: rdO9 Failure of rods to move in auto (part of simulator
setup.
Objectives:
Evaluates the candidates use of GOs to continue power escalation from
75% power.
Evaluates the candidates ability to conduct operations associated with
power escalation from 95% power including raising turbine load and
corresponding effect on reactor power (rod control in manual).
Opportunities for peer checks of reactivity changes.
Success Path:
0 Conduct power escalation from 75% power.
EVENT 2 - Remove 1A-A AFW pump from
Tagging AUO reports to Control Room with two Hold Order Tags for tagging out
?A-A MB AFW pump. Reports to Unit Supervisor that Operations
Superintendent has requested an immediate clearance to be placed on ? A 4 MD
AFW pump to prevent damage to pump.
Malfunctions required: 0
None
Objectives:
Evaluate the crew's response to report of inoperability of 1A-A MDAFW
pump.
0 Determines the correct conditions to enter for the appropriate Tech Spec
LCO.
Success Path:
Takes actions to remove 1A-A MDAFW pump from service.
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 8
Page 7 of 39
Evaluate and enter appropriate Technical Specification.
EVENT 3 - Respond to Chem Lab report of small 10 gpd tube leak on #1
SG.
Small Steam Generator Tube Leak on #1 Steam generator.
Malfunctions required: 1
thlOa, Steam Generator Tube Leak Loop 1 Steam Generator. (IO gpdj
Objectives:
Evaluate the candidates ability in their use of Abnormal Operating
Instructions AOI-33 in response to the onset of a small SGTL
Evaluates the candidates ability to implement Appendix A of AOI-33 to
provide enhanced leak rate monitoring.
Success Path:
Candidates implement AOI-33 to respond to chemistry report of 10 gpd
tube leak on # I SG.
display CHEM7, ICs net charging flow.
Determines leakage is within Tech Spec limits.
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 8
Page 8 of 39
-
EVENT 4 Main Steam Header Pressure Transmitter I-BT-1-33 fails HIGH
Main steam header pressure transmitter, I-PT-1-33 fails HIGH which causes
Main FW pump speed to raise which requires the operator to take manual
control.
This failure will cause elevated feedwater flow and SG levels will begin to RiSE
until the operator takes manual control and lowers flow.
Malfunctions required: 1
e rx20, Main Steam Header Pressure Transmitter 1-PT-1-33 failure to
position.
0 bjectives:
- Evaluate the candidates ability to implement AOl-16 when main steam
pressure transmitter fails HIGH.
Evaluates candidates ability to manually control Main FW pump speed.
Success Path:
- Crew implements 808-16, section 3.7, to respond to the Main Feedwater
Pump control circuit failure, takes manual control of the pumps and
stabilizes the plant.
-
EVENT 5 Pressurizer Level Transmitter, 1-LT-68-339, Fails LOW
1-LT-68-339 fails low resulting in letdown isolation and subsequent manual
isolation of charging flow. Manual control of charging valve controller, 1-HIC-62-
93A, is required. Failed channel must be defeated and charging and letdown
restored. Operators should respond using AOI-28.
Malfunctions required: 1
e rx05a , Pzr bevel Transmitter I-bT-68-339 fails to 8%.
0bjectives:
- Evaluates the candidates use of AOE-20 for failure of 1-LT-68-339 LOW.
Scenario 1
Appendix 8) WBN NWC Simulator Exam Rev. 0
Page 9 of 39
0 Evaluates candidates ability to properly diagnose control board indications
to determine event in progress.
Scenario 1
Appendix B WBN NRC Simulator Exam Rev. 0
Page 18 of 39
Success Path:
0 Crew recognizes conditions for entry and implements AOI-20 in response
to PZR l w e i transmitter, 1-LT-68-339 (channel I)failing LOW.
- Manual control of PZR Bevel established.
Stabilizes the plant and restore PZR heaters, charging and letdown to
service. Returns charging flow control valve to auto position.
0 Determines the correct conditions to enter for the appropriate LCOs.
EVENT 6 - Steam Generator #Tube I Rupture
Malfunctions required: 1
0 tho% 30, Steam Generator #I tube failure
Objectives:
0 Evaluate the candidates ability to diagnose a steam generator tube
rupture.
Evaluate the candidates ability to implement AOI-33 Steam Generator
Tube Leak with leak that will require manual trip and safety injection
initiation.
Success Path:
Crew responds to tube rupture on # I SG by AOI-33 and then EOP
network procedures (E-0, E-3).
EVENT 7 - AUTQ SI Fails to Actuate
Malfunctions required: 1
rp02b, Auto SI initiation Failure
Objectives:
e Evaluate the candidates ability to monitor SI initiation parameters and
manually initiate SI when required.
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 0
Page 11 of 39
Success Path:
Crew diagnoses need for Safety Injection and initiates a Manual SI.
Crew determines that they cannot keep up with the Steam Generatmtor
Tube beak with charging maximized and manually initiates reactor trip and
SI.
Crew implements E-0 to respond to a Steam Generator Tube Rupture.
EVENT 8- VCT Outlet Valves Fail tQ Close
Malfunctions required: 2
si09e, failure of individual SI signal to 1-LCV-62-132
e si09f, failure of individual SI signal to 4-LCV-62-133
Objectives:
Evaluate the Crew's ability to monitor proper operation of ECCS
equipment following response to manual actuation.
Success path;
Manually closes valve upon discovery of failure to close.
EVENT 9 -#I SIG main steam line break inside containment
Main Stearn line break on SG #'l inside containment when crew transitions to E-
3.
Malfunctions required - 1
msOZa, #SIG I Steam bine Break inside containment (ramped)
0 bjectives:
Evaluates the candidate's ability to identify faulted SG inside containment.
Evaluate the candidate's response to a Ruptured Steam Generator that is
now faulted inside containment.
Scenario I
Appendix D WBN NRC Simulator Exam Rev. 0
Page ? 2of 39
- Evaluate the candidates response to High High Containment pressure
per implementation of FR-Z.1.
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 0
Page 13 of 39
Success Path:
Recognize Main Steam line break.
Ensure that Faulted Steam Generator has been isolated.
Crew does not feed a ruptured and faulted steam generator.
Crew transitions from E-3 to ECA-3.2 for appropriate guidance.
Recognize entry conditions and implement FR-Z.1.
Crew monitors containment pressure and when containment pressure
less than 2 psig, resets containment spray signal, stops containment
spray pumps and placed then in F-Auto. These steps conserve RWST for
Scenario 1
Appendix B WBN NRC Simulator Exam Rev. 0
Page 14 of 39
CONSOLE OPERATORS INSTRUCTIONS
............... TIME
ELAPSED IClMFlRFlOW ....................DESCRIPTIOH
_. .........................
Sim Setup rst 144, switch check,
select RUN
NOTE: Bf unavailable
then continue with
setup with IC 51.
Turn audible Prevents unnecessarily alerting crew
simulator fault alarm of a simulator problem that may not
to off (down affect simulator dynamics.
position)
0 irnf rd09 Control rods fail to move in AUTO.
n
v imf siO9e VCT outlet valves 1-LCV-62-132 &
233 fail to close.
imf si09f
J imf thlOa (el) 4 Small SGTL on #I SG at -10 gpd.
3
imf 1x20(e4) 100 Main steam I-PT-1-33 fails high and
causes MFPT speed to rise.
3 imf rx05a (e5) 0 1-LT-68-339, Pnr Level fails low.
3 irnf msOla (e6) 1 5: Main Steam Break inside containment
on SG 1 at 1% over 5 minutes.
irnf th05a (e7) 30 #I SG Tube Rupture a -690 gpm
3 imf rp02b Auto SI Initiation Failure
Scenario 1
Appendix D WBN NWC Simulator Exam Rev. 0
Page 15 of 39
CONSOLE OPERATORS INSTRUCTIONS
(Continued)
......................................
DESCRIPTION
imf itrigger Inserts small SGBL on # I SG at -10
gpd. This will cause condenser
vacuum exhaust monitors lo start
slowly rising with no perceptible
change in charging. Event 3 will
provide a chem lab report of small -10
aod tube leak on SG # 1.
When directed by Have crew Place Z Role Play: Tagging AUO enters
the evaluator. HS-3-118A in BTL and Control Room with two Hold Order
then tag 1-HS-3-118A Tags for tagging out 1A-A MB AFW
Enter Control Room and 1-HS-3-355. pump. Reports to Unit Supervisor that
with two hold order Operations Superintendent has
tags for clearance on requested an immediate clearance to
1A-A MD AFW be placed on 1A-A MD AFW pump to
prevent damage to pump. The data
taken pump during Surveillance run
Request permission
last shift, on review by Engineering,
to hang HO tags for
indicates action required due to high
vibrations.
on the MCR panel.
Role Play: If called confirm that you
have directed that an immediate
clearance be placed on 7A-A MD AFW
pump.
After crew has ior zlohs3355[1] off Simulates 1-FCV-3-355, 1A-A
placed HO tags for MDAFWP Recirc, tagged closed.
pump, wait ior zlohs3118a[~]off Simulates 1A-A MDAFWP handswitch
approximately 2 lights out.
ior zlohs3118a[2] off
minutes then enter
override.
Scenario I
Appendix D WEN NRC Simulator Exam Rev. 0
Page I 6 of 39
CONSOLE OPERATORS INSTKUCTIONS
(Continued;
DESCRIPTION......................
If/when called by Role Play: As the Work Week
MCR. Manager and respond to the MCW
request to take immediate actions to
restore an AFW pump to operable
status. Also, we will perform a risk
assessment for the situation per TI-
124.
When directed by ROLE PLAY: As Chern Lab, Inform
the evaluator. the MCR that #I SIG sample is
indicating approximately 10 gpd leak
rate on the initial count.
When requested by ROLE PLAY: As Chemistry
the crew to initiate: acknowledge the request.
CM-5.01.
When requested ROLE PLAY: As Chemistry,
acknowledge request to adjust
radiation monitor setpoints for I-RM-
90-119, -120, -121 to provide prompt
indication of leakage rise.
When directed by imf itrigger4 Main steam PT 1-33 fails high
the evaluator.
ROLE PLAY: As Work Control, when
contacted, inform the MCR that the
failed 1-PT-1-33 will be added to the
work list for the IMs.
When directed by imf itrigger5 1-CT-68-339, Pzr Level Transmitter
the evaluator. fails LOW.
ROLE PLAY: As Work Control, when
contacted, inform the crew a work
package will be initiated for repairs.
Scenario 1
Appendix D WBN NRC Simulator Exam Rev. 0
Page 17 of 39
CONSOLE OPERATORS INSTRUCTIONS
(Continued)
. . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . .
................... ... . . . . ......... ................. ..
When directed by imf itrigger6 SG tube leak propagates into a rupture
the evaluator. on#1 SG.
- 8 minutes after ROLE PLAY: As Radcon, report that
there are higher levels of radiation
indicated on #? SG blowdown and
steam lines.
- 10 minutes after ROLE PLAY: As Chemistry, report
that there are higher levels of radiation
chemistry samples. indicated on #I SG blowdown.
Currently running analysis to
determine leak rate.
1) When Crew enters imf itrigger7 Main steam break inside containment
E-3. at 1% on SG #I. Ramps in over 5
minutes.
When requested, mrf sir14 on Restores power to 1-FCV-63-1
wait 2 minutes then
insert over ride. ROLE PLAY: As AUO, acknowledge
request; then report power has been
- stored to 1-FCV-63-I
- ~
Scenario 1
Appendix D WBN NWC Simulator Exam Rev. 0
Page 18 of 39
APPENDIX A
INFORMATION TO EVALUATORS
1. Assign Crew Positions: (Assign positions based on evaluation requirements
for personnel.) Log the positions on Appendix C.
US Unit Supervisor
~
OAC - Operator at Controls
CRO - Control Room Operator
2. Review the Shift Briefing Information with the operating crew. Provide the US
with a copy of Appendix E, Shift Briefing Information.
3. Allow the crew to familiarize themselves with current control panel condition
(up to 10 minutes).
4. Ensure recorders are inking and recording and ERFBS is active and
updating. Note any deficiencies during shift briefing.
5. Ensure ICs computer active and updating.
6. If not previousby done, review any major differences between plant and
simulator.
7. Review CONSOLE OPERATORS INSTRUCTON for INITIATING CUES.
8. Provide copy of G O 4 Normal Power Operation Section 5.1 completed
through step 34 for use by the Unit Supervisor.
9. Provide copy of E-O Reactor Trip or Safety Injection Appendices Aand
5 to the CRO Evaluator.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 19 of 39
The crew continues plant startup from 75% power in accordance
Description: with General Operating Instruction, GO-4.
.............
................
................
................
................
................
................
................
~
................
- ......................
.................
..y$&f~
CREW Walks control boards down in
preparation for raising power and
initiates load escalation to 100%
CRO Initiates load escalation to 100% power
0 Determines and sets in load rate,
Uses reference control button to set
desired load.
0 Depresses go to begin raising load.
OAC Compares Tavg, AT and NIS to verify
indications are consistent with expected
values. Adjust control rods as
necessary to maintain Tave-Tref
mismatch.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 20 of 39
Scenario Z
Appendix B Operator Actions Rev. 0
Page 21 of 39
OF' Test No: - Scenario Ne.: 1 Event No.: 2 Page - 1 of __1
-
Event
..........
$. .#$..........
-
Description:
................
................
................
................
................
................
................
................
p6$qt&Jfi
................
Removal of 1A-A MDAFW pump from service.
-..
LIS Tagging A l l 0 enters Control Room
with two Hold Order Tags for tagging
out 1A-A MB AFW pump. Reports to
Unit Supervisor that Operations
Superintendent has requested an
immediate clearance to be placed on
damage to pump. The data taken
pump during Surveillance run last
shift, ~ f review
l by Engineering,
indicates action required due to high
vibrations.
-
US Refers to Tech Specs, declares the
?A-A pump inoperable, and enters TS
3.9.5 Condition B "Restore Operable
Status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days
from discovery to meet the LCO."
US 3irects the CRO to place IA-A
MDAFW pump in stop and pull to lock
for placing hold order tags.
US Zontacts SM and informs the SM of
condition of the unit and may request
Licensing group assistance in Tech Spec
directed actions and may request
evaluating risk using TI-124 "Equipment q
Scenario 1
Appendix 5 Operator Actions Rev. 0
Page 22 of 39
Scenario 1
Appendix D Operator Actions Rev. Q
Page 23 of 39
OP Test No: -Scenario NO.: 1 Event No.: 3 Page __ 1 of ~
2
Event Chem Lab report of small steam generator tube leak (10 gpd) on
- Description:
....................................
SG #I ~
-
a -
-
.............................................
?Jm& .P
.......... . .. . ..... ..........._.......
us implements AQI-33 Steam
- Generator Tube beak.
OAC Checks Pzr level and charging flow
determines that Pzr level is STABLE
and charging Row 1s STABLE
US GO PO Appendix A, Enhanced Leak
Rate Monitoring for a 10 gallday leak
on #I S/G.
CRO Monitors 1-RE-90-119 operable and
determines that count rate is rising.
CRW E Monitors leak rate USING
Chem 7 screen for I-RE-90-
1 19 Response/ Leak Rate
Conversion.
e Checks Vacuum pump
exhaust and SG Elowdown
monitors.
CREW 3etermines leakage rate-of-change
at least once per 30 min using the
difference in leak rate divided by the
change in time.
OAC Uonitors PZFlevel STABLE.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 24 of 39
QP Test No: - Scenario No.: I Event No.: 3 Page - 2 of ~ 2
Event Chem Lab report of small steam generator tube leak ( I O gpd) on
- Description:
...................................................
..iw
.................
____e
SG #I.
-
.::...:......M ...
US Evaluates leakage using Appendix E3
& C, SG Tube Leak Shutdown
Criteria, and determines that
increased monitoring is required
(greater than or equal to 5 gpd but
less than 30 gpd).
US Directs CWO to monitor radiation monitor
readings hourly until stable per Appendix
A.
US Contacts Chemistry to adjust
radiation monitors 1-WM-113, -120,-
121 setpoints to provide prompt
indication of leakage rise.
US Notifies RADCQN to survey
US Notifies Shift Manager concerning
CREW Makes PA announcement to plant
concerning SG tube leak.
-
Scenario 1
Appendix D Operator Actions Rev. 0
Page 25 of 39
OP Test No: - Scenario No.: 1 Event No.: 4 Page - I of - 2
Main steam header pressure transmitter, 1-PT-1-33 fails HIGH
Event
Description: which causes Main FW pump speed to raise which requires the
operator to take manual control.
Phis failure will cause elevated feedwater flow and SG levels will
begin to rise until the operator takes manual control and Bowers
- flow.
.........
CRQ Respond to annunciators and recognize
Failure of PT 1-33. Informs crew of
Failure. May lower pump speed.
Indications:
- Feedwater flow rising
SIG levels rising
Alarms:
- #I HEATERS FW SUPPLY
PRESS HI (57-8)
Computer alarms: FW pump
suction pressure low; MFP l A & I B
discharge pressure high
US Implements AOI-16, section 3.7 and
jirects action of the CRO.
CRO 'laces main feed pump speed
- ontroller (master) in MANUAL. (May
ower pump speed to lower discharge
xessure).
OAC Zhecks rod control in MANUAL.
-Znsure Tavg-Tref are within 3°F.
I
QAC
Scenario 1
Appendix B Operator Actions Rev. 0
Page 26 of 39
OP Test No: - Scenario No.: 1 Event No.: 4 Page - 2 of - 2
Event Main steam header pressure transmitter, 1-PT-1-33 fails HIGH
Description: which causes Main FW pump speed to raise which requires the
operator to take manual control.
This failure will cause elevated feedwater flow and SG levels will
begin to rise until the operator takes manual control and lowers
flow.
C RQ Adjusts speed control to maintain Feed
Pump discharge pressure on
PROGRAM and return S16 levels to
PROGRAM.
CRO Checks Steam Dump mode in Tavg B Auto Control of
Dosition. Steam Dumps in
Pressure Mode not
available (will work in
manual).
us Notifies Work Control to initiate repairs. B Feed pump speed
requires manuai
control.
OAC If desired to place control rods in auto, VOTE: Auto rod control
Then ensure Tavg and Tref within I" 3ut of service due to
and place control rods to auto. (Leaves iNork in logic cabinet.
rod control in manual)
Scenario 1
Appendix D Operator Actions Rev. 0
Page 27 of 39
OQ Test No: - Scenario No.: 1 Event No.: 5 Page - 1 of -4
Event Controlling PZR level transmitter 1-LT-68-339 fails LOW.
-
Description:
................
................
................
................
................
................
................
................
F&$lfl6Ki
................
__I
OAC Recognize PZR level channel I failure
and informs crew.
Channel I level indication fails L o w .
PZW level alarms:
0 PZR LEVEL HllLO [92-A]
PZR LEVEL LO-HTRS OFF &
LETDOWN CLOSED [92-C]
OAC Recognizes letdown isolation and should Expected response to
isolate charging. (1-HS-62-9QA& I-HS- solate charging if
62-91A). inventory problem does
not exist.
us Implement 801-20 Malfunction of
Pressurizer Level Control System and
directs the actions of the crew.
Checks PZR level program signal
NORMAL, recorder 1-LR-68-339. (green
Pen)
Scenario 1
Appendix D Operator Actions Rev. 0
Page 28 of 39
OP Test No: -Scenario No.: 1 Event Ne.: 5 Page - 2 of - 4
Event Controlling PZR level transmitter 1-LT-68-339 fails LOW.
Description:
..........
m
..........
..........
........... .....-
................
................
................
................
.......... i5glrt6g
gfsg ................
...
.......... ................
. . . .
................
QAC Determines that I-XS-68-339E is
selected to FAILED channel.
-
QAC
failure is LOW.
OAC Piaces charging valve controller 1-HIC-
62-93A in Manual, and cioses l-FCV-62-
89.
QAC Maintains RCP seal flow between 8 and
13 gpm with charging valve controller 1-
HIC-62-93A.
OAC Selects operable channel for controlling
channel using 1-XS-68-339E (selects LI-
68-335 8320).
Ensure operable channel selected for
recording with 1-XS-68-3395. (Channel
339 not selected.)
I
Scenario
Appendix B Operator Actions Rev. 0
Page 29 of 39
-
OP Test No: ~ Scenario No.: 1 Event No.: 5 Page - 3 of - 4
Event Controlling PZR level transmitter 1-bT-68-339 fails LOW.
-
Description:
................
................
................
................
r663tTggi
................
.................
............
QAC Establishes normal charging and
letdown per attachment 1 of AOI-20
Closes I-FCV-62-89.
Ensures Charging Pump running.
Openskheck open 1-FCV-62-90
and 1-FCV-62-91.
Ensures 1-FCV-62-85 or -86 open
Adjusts 1-FCV-62-93 to maintain 8-
13 gprn seal flow.
Ensure letdown isolation valves oper
1-FCV-62-69, 1-FCV-62-70 and 1-
FCV-62-77.
Place Letdown Hx temperature
control valve (1-HIC-62-78A) in
MANUAL at 25% open.
Places letdown pressure control (1- !0-30% open if 45 gpm
HIC-62-81A) in MANUAL at 40-50% xifice used.
open.
Establish charging flow 75 gpm or
greater & 8-13 gpm seal injection
flow to each RCP.
Open letdown orifices as needed.
4-FCV-62-73 or 74, or 72 or 76.
Adjust letdown pressure (1-HIC-62-
81A) to -32Opsig and place in
AUTO.
Place I-HIC-62-78A, letdown hx
outlet temp TCVJO-192 cntl, in
AUTO.
Returns Pzr level to program
Return l-HlC-62-93A, charging Row
pzr level control, to AUTO.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 30 of 39
--
OP Pest No: Scenario No.: 1 Event No.: 5 Page - 4 of ~
4
Event Controlling PfR level transmitter 1-LT-68-339 fails LOW.
Description:
OAC Restores Pzr level control to normal:
MAINTAIN regen hx letdown temp
<380 "F.
Controls charging and letdown to
return Pzr level to program.
8 Ensures Pzr control heater bank D
red light lit.
Momentarily places 1-HS-68-941H
Pnr backup heater bank C HS to
OFF. Will probably restore
- Checks Pzr program level normal on level to program before
1-LR-68-339 (green pen). placing in auto.
Returns charging valve controller, 1-
HIC-62-93A to AUTO.
us Notifies work control to remove failed
channel from service.
US Evaluates Tech Specs and enters LCOs
3.3.1.9 Condition X and 3.3.3 Condition
A.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 31 of 39
-
QP Test No: Scenario No.: - 1 Event No.: 6, 7, 8 Page- 1 of -
6
Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
Description: valves to auto close.
CREW Recognize SG tube leak by
indications and alarms:
Indications:
Rising vacuum pump exhaust and
SG blowdown radiation Dropping
PZR level, rising charging.
- Dropping PZR pressure
Reduced feedwater flow to #I SG
Alarms:
PZRPRESSLOBACKLJPHTRS
ON
PZR LEVEL HllbO
LIS Returns to section 3.0 of AOI-33 and
directs crew actions.
QAC Establishes maximum charging
flow. Opens 1-FCV-62-33 and -
89.
Monitors PZR level and Way take several
determines that pressurizer level is ninutes for this
still dropping even with maximum determination.
charging.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 32 of 39
OP Test No: Scenario No.: - 1 Event No.: 6, 7, 8 Page- 2 of -6
Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
- Description:
..................................................
........................................
rrmg;
valves to auto ciose.
- ..........
.... ......
CRQ Places dumpback to CST in MANUAL.
and closes 1-LCV-2-3 using 1-[SIC-2-3.
-
CRO Monitors condenser level 1-bR-2-12
on scale.
US Notifies Radcon and Chemistry to
survey secondary plant and
sample SGs for high activity.
- Makes plant announcement to
warn personnel.
US Directs reactor trip and safety injection
initiation based on inability of charging
to maintain pressurizer level.
OAC Initiates manual reactor trip. Verifies
Initiates manual Safety Injection.
OAC May determine that Auto SI did not
actuate as required. Manually initiates
safety injection or places in service at EVENT 7
ieast one full train of ESF equipment
before transition from E-0.
US Implements E-0 Reactor Trip end
Safety Injection and directs crew
actions.
Scenario 1
Appendix I Operator Actions Rev. 0
Page 33 of 39
OP Test No: Scenario No.: ~ 1 Event No.: 6, 7, 8 Page__3 of -6
Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
Description: valves lo auto close.
.. ii............
?????E?
..........
................
........
rf*&;
i&A&&Li P
GREW Performs immediate actions of E-0.
OAC Ensures reactor trip and safety EVENT 8
injection.
- Manually closes VCT Outlet
Valves 1-LCV-62-132 & 4 33.
CRO Ensures turbine trip.
0 Ensures shutdown boards
energized.
CRO Ensures AFW pump operation:
running
CRO Znsures MFW isolation:
MFW isolation valves closed
MFW bypass isolations closed
MFW reg and bypass reg vaives
closed
MFWPT A and B tripped
a Standby MFWP stopped
- Cond demin pumps tripped
Cond booster pumps tripped
Scenario 1
Appendix 5 Operator Actions Rev. 0
Page 34 of 39
OP Test No: Scenario No.: - 1 Event no^: 6, 7, 8 Page__4 of __ 6
Event SG #? Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
Description: valves to auto close.
P
CRO Evaluates support systems: See Attachment for
copy of Appendix A & B
0 SI support systems using 3, 3f E-0 in back of this
Appendix A. guide.
Phase B Pipe Break
Contingencies using E-0,
Appendix B.
~~
US Announces reactor trip and SI.
OAC 0 Monitors ECCS actuation by
checking pumps running and
alignments. Manually CLOSE K T outlet valves may
VCT outlet valves 1-LCV-62-132 7ave been closed
8 133. sarlier.
Ensures cntmt isolations by
checking Phase A. and CVl on
status panels.
0 Checks cntmt pressure 2.8 psig
CRQ Ensures secondary heat sink by 3 e w may take prudent
checking AFW flow > 410 gpm or SG 3perator action (after
levels 9 10% NR. step I 2 of E-O), swap
steam supply for TD
1DW pump to #4 SG,
m d isoiate FW to #I
Scenario 1
Appendix D Operator Actions Rev. 0
Page 35 of 39
Scenario 1
Appendix D Operator Actions Rev. 0
Page 36 of 39
OP Test No: Scenario No.: - 1 Event No.: 6 , 7, 8 Page- 5 of -6
Event SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
Description: valves to auto ckose.
? . .?. . .=
. . .v??-
...............
............
..........
. . . . . ... .. . ..
Positiorr.
OAC e Monitors Tavg stable or trending
557°F.
Checks excess letdown valves
closed.
e Checks Pmr PORVs closed
Checks Pzr safety valves closed
by tailpipe temp or acoustic
monitor.
Checks Pzr sprays closed.
Determines that RCPs should be
on
CRO e Checks SG pressures controlled or
rising
e Determines that secondary
radiation is NOT normal.
US Transitions to E-3 "Steam Generator
Tube Rupture" and directs crew
actions.
Note: Console Operator insert #I
SG Steam Line break at this point.
CREW Commences monitoring of Status
Trees
US Refers to EPBP-1 or notifies the SM to
refer to REP.
QAC Determines that RCPs should remain
in service. If RCS oressure I1500
Scenario 1
Appendix 5 Operator Actions Rev. 0
Page 37 of 39
n I psig, then RCPs are stopped.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 38 of 39
SG #I Tube Rupture. Failure of Auto SI. Failure of VCT Outlet
eription: valves to auto close.
CREW Identifies #I SG as ruptured.
CRO Ensure #I SG PORV set at 90% and
in P-AUTO
CRO Ensure #I SG PORV set at 90% and
in P-AUTO (may have been
performed previously)
CRO Ensures SG #I blowdown isolated.
CRO Isolates ruptured #I SG:
Criticai Task
Isolates AFW to #1 (may have
been done previously)
Close #I SG Main Steam Isolation
Valve (MSRV).
CRO 0 Controls #1 SG > 10% NR.
CREW Determines that containment pressure
is rising and the ruptured SG is now
faulted to containment.
Indications:
Lowering SG levels
Lowering SG #I Steam Flow
Alarms
KCS LOOSE PARTS DETECTED
ICE CONB INLET DOOR OPEN
CNTMT MOISTURE HI
Scenario 1
Appendix D Operator Actions Rev. 0
Page 39 of 39
OP Best No: Scenario No.: - 1 Event No.: 9 Page- 1 of -6
Event SG #I Ruptured and Faulted inside containment
Description:
CRQ Determines #I S/G pressure dropping
in uncontrolled manner.
us Transitions to E 9 Faulted Steam
Generator isolation if any SG
pressure Bow or dropping uncontrolled
AND has not been isolated. Direct
crew actions.
QAC Reports that CNTMT pressure > 2.8
psig. Phase B has initiated. Verifies
containment spray fiow, stops RCPs.
CREW Identifies ORANGE path FR-Z.1 High
Containment Pressure.
us Transition to FR-2.2 based on Status
Trees Response to High High
Containment Pressure.
Scenario 1
Appendix B Operator Actions Rev. 0
Page 48 of 39
Scenario 1
Appendix B Operator Actions Rev. 0
Page 41 of 39
OP Best No: Scenario No.: __1 Event No.: 9 Page__2 of 6
Event SG #IRuptured and Faulted inside containment
Description:
....... . .. . . . ..
CROIOAC Implement actions of FR-Z.l "High
Containment Pressure" as directed
Determines both Cntmt Spray
pumps running.
There is Cntmt Spray Flow both
trains
isolations.
Ensures MSlVs and Bypasses
CLOSED.
Placeslchecks steam dump
controls in OFF
Ensures all four WCPs
STOPPED.
RUNNING.
Monitors air return fan start 10
minutes adter Phase B initiation.
-
CRO Checks SIG Pressures. Isolates #I
SIG:
Ensures AFW to # I SI6 isolated
Ensures MFW isolated to # I SI6
US Transitions back to E-3 and directs
crew actions.
~
Scenario 1
Appendix D Operator Actions Rev. 0
Page 42 of 39
P P
OP Test No: Scenario No.: - I Event No.: 9 Page__3 of 6
Event SG #IRuptured and Faulted inside containment
Description:
P
.
I..
...
.. ...............................
us Determines that SG #I should not be
supplied feedwater (SG #I also
faulted inside containment).
CRQ * Places dumpback to CST in
manual and closed (may have
been performed previously)
Maintains condenser Bevel on scale
e Checks Cond Dl Bypass valve 1-
FCV-14-3 OPEN.
US e Ensure Radcon dispatched to
survey secondary plant
- Notifies Chemistry to sample SGs
Notifies plant personnel of
potential releases
OAC Monitors Pzr PORVs and safeties
closed.
CRO Check SG #2, #3, and #4 pressure
controlled or rising.
CRQ Verifies at least 1 intact SIG available.
- 2, #3, and #4 SlGs are intact.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 43 of 39
Scenario 2
Appendix D Operator Actions Rev. 0
Page 44 of 39
SG # I Ruptured and Faulted inside containment
OAC Resets SI, Phase A, Phase B and stops
RHR Pumps.
I
I
!
Establishes Cntmt air by opening 1-
FCV-32-80 and 1-FCV-32-102.
CRO Monitors all AC buses energized by
!
offsite power.
I I CRo
Ensures #I
SG isolated from intact
pressure 680 psig.
ir-I us
us
1 Transitions to ECA-3.1
Implements ECA-3.1 SGTR and
LOCA - Subcooled Recovery and
---+--- QAC
directs crew actions.
Dispatches personnel to restore
power to RHR suction valve from
RWST. (Appendix A of ECA9.1)
/I I OAC
Resets SI, Phase A, and Phase 5.
(should have been performed earlier)
Ensures cntmt ais in service. (should
Scenario 1
Appendix B Operator Actions Rev. 0
Page 45 of 39
8_ __ -
OP Test No: - Scenario No.: 1 Event No.: 9 Page - 5 of __6
Event SG #I Ruptured and Faulted inside containment
Description:
-
- .........
....................................
.......................
............ ...
- .Em:@
aiiiijij.
Monitors all AC buses energized by
Dffsite power.
OAC Checks RHR pumps not required and
shutdown in A-AUTO
-
OAC Determines that Cntmt Spray not
required.
Resets CS signal, stops and
places in A-AUTO both CS
pumps.
GfO§e§ their respective Cntmt
Spray Discharge Valves 1-
FCV-72-2 and 1-FCV-72-39.
(May have been performed
earlier)
CREW Maintain feedwater isolated to SG #I.
(Ruptured & Faulted)
us Notifies Chemistry of event status and
plant conditions.
us May direct STNSM to evaluate plant
equipment evaluation Appendix D of
ECA3.1.
Scenario 1
Appendix D Operator Actions Rev. 0
Page 46 of 39
- P
OP Test No: -Scenario No.: 1 Event No.: 9 Page - 6 of -6
Event SG #I Ruptured and Faulted inside containment
-
~
Description:
.......... ....................
.......................
.......... ....._._.._._.___
.......... ......................
.......... ....................................
...-
..........
if$@ .........................
...............
....................
CROJUS Evaluates plant equipment status
using Appendix D of ECA-3.1.
CRO Checks SG pressures
controlled or rising
Monitors SG #2, #3, & #4
levels >25% but less than 50%
and controlled.
CRO Controls intact SG #2, #3, and #4
between 25% and 50%.
-
us Contact SM/STA to refer to I-SI-0-10
for Shutdown margin.
Crew nitiates RCS cooldown to cold
Critical Task
- hutdown maintaining T-cold cooldown
ess than 100 O F in one hour. (or if
- ooldown rate has been exceeded
letermines when cooldown can be
- tasted.
TERMINATE THE EXERCISE WHEN
CREW HAS INITIATED COOLDOWN
OR DETERMINED WHEN THEY
Scenario 1
Appendix D Operator Actions Rev. 0
Page 47 of 39
APPENDIX B
SHIFT TURNOVER CHECKLIST
Page 1 of 2
SHIFT TURNOVER CHECKLIST
'
a
0
US/MCR
uo
Unit
Unit
Station
STAISTA Function)
-
s_
- ' Off-goinq- Natne
Qwomina - Name
>art 1 - Completed by off-going shiWReviewed by on-coming shift: RCS Cb _____
= 951
Abnormal noihment lineuo/conditions:
SI/Test in progresdpianned: (including need for new brief)
-
None in progress see schsdule
Major ActivitiesIProcefJures in progresdplanned:
-. .-.Cind Startup
1) .. in p r o y r e s s ' o h o ~shutdowr, .for
-. seconcrdry =.
.. repet .-. GO-4. Section 5 1 S:e@5
.. __
2) :tiirned;ately iebunie power esLJlwon .. lo 100%
.- .- wnde ..-. . .. in target .band
mamain931 .-. .__
Radiological changes in plant during shift:
None
'art 2 - Performed bv on-comino shift
~ ~ ~ _ _ _
A review of the Operating Log since last held shift or 3 days, whichever is less (N/A for AUOs)
A rsview of the Rounds sheets/Abnwmal readings (AUOs only)
Review the foilowing programs for changes since last shift turnover:
67
Sanding Orders
Immediate required reading 13
LCO(s) in actions (N/A for ALIOS)
TACF (N/A for AUOs -
'aft 3 - Performed by both off-going and on-coming shift
P -
I? A waikdown of the MCR control boards (N/A for AUOs)
Relief Time: Relief Date:
TVA 40741 (03-20011 Page 1 of 1 BPBP-1-1 [03-?4-200ll
APPENDlX B
SHIFT TURNOVER CHECKLIST
Page 2 of 2
SHIFT TURNOVER CHECKLIST
Page -of -
0 USiMCR Unit - _ I
a uo Unit - Off-aoing - NKmB
0 AUO Station - _ I
STA (STA Function) On-comino - Name
-
Part 1 - Completed by off-going shiftlReviewed by en-coming shift RCS Cb = 951
Abnormal equipment lineuplconditins:
1) Maintenance is troubleshooting AUTO rod control circuit. Control rods in MANUAL.
SliTest in progresslplanned: (including need for new brief)
None in progress -see schedule
Major ActivitisslProcedures in pmgressiplanned:
1) Unit Startup in progress following shutdown for secondaly repairs. GO-4, Section 5.1 Step 35
2) Pie Conditioned power level is 100%.
3) Sol-62.02 Appendix E target boron for load escalation is 938 ppm
4) Sol-62.02 Appendix D states that 794 gallons of primary makeup needed to obtain 100% with
Control bank 'D' at 220 steps.
Radiological changes in plant during shift
-- - - -
- -
'art 2 Performed by on-coming shift
8__ -
A review of the Operating Log since last held shift or 3 days, whichever is less (NIA for AUOs)
A review of the Rounds sheetsIAbnorrnal readings (AUOs only)
Review the following programs for changes since last shift turnover:
Standing Orders LCO(s) in actions (NlA for AUOs)
0 Immediate required reading
- TACF (N/A for AUQs
-
'art 3 - Performed by both off-going and on-coming shift
-
0 A walkdown of the MCR control boards (NlA for AUOs)
Relief Time: Relief Date:
TVA 40741 [03-ZOOI] Page 1 of 1 OPW-1-1 [03-14-2001]