ML081370200
ML081370200 | |
Person / Time | |
---|---|
Site: | Browns Ferry |
Issue date: | 04/08/2008 |
From: | NRC/RGN-II |
To: | Tennessee Valley Authority |
References | |
50-259/08-301 | |
Download: ML081370200 (103) | |
See also: IR 05000259/2008301
Text
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XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
60 or 6E Core S ra
1. VERIFY OPEN the following valves:
3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV
3-FCV-75-11 , CORE SPRAY PUMP 3C SUPPR POOL SUCT VLV
3-FCV-75-23, CORE SPRAY SYS I OUTSD INJECT VALVE.
2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST VALVE.
3. VERIFY CS Pump 3A and/or 3C RUNNING .
4. WHEN .*. RPV pressure is below 450 psig, THEN .*. THROTTLE 3*FCV-
75-25, CORE SPRAY SYS IINBO INJECT VALVE, as necessary to control
injection at or below 4000 gpm per pump.
5. MONITOR Core Spray Pump NPSH using Attachment 1.
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XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
1. IF ..... Adequate core cooling is assured AND It becomes necessary to
bypass LPCI Injection Valve Timers to control injection, THEN ... EXECUTE
EOI Appendix 16F concurrently with this procedure
2. VERIFY OPEN 3-FCV-74-1 , RHR PUMP 3A SUPPR POOL SUCT VLV.
3. VERIFY OPEN 3-FCV-74-12 , RHR PUMP 3C SUPPR POOL SUCT VLV.
4. VERIFY CLOSED the follow ing valves :
3-FCV-74-61 , RHR SYS I DW SPRAY INBD VLV
3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV
3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV
3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE
3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VLV.
5. VERIFY RHR Pump 3A and/or 3C running.
6. WHEN ... RPV pressure is below 450 psig, THEN ... VERIFY OPEN 3-FCV-
74-53, RHR SYS I LPCIINBD INJECT VALVE.
7. IF ..... RPV pressure is below 230 psig, THEN ... VERIFY CLOSED 3-FCV-
68-79, RECIRC PUMP 3B DISCHARGE VALVE.
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XII. Crew Critical Tasks
1) Manually isolate HPCI before 2 areas exceed Maximum Safe Radiation or Temperature
levels.
2) Emergency depressurizes RPV based upon not being able to maintain reactor water level
above -162, but before reaching - 200"
3) Restores I maintains water level above -162" after ED
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XIII. SCENARIO REVIEW CHECKLIST
(
SCENARIO NUMBER HLTS-3-2
~ Total Malfunctions Inserted; List: (4-8)
1) HPCI steam line break
2) RBCCW 3A pump trips
3) 3A Recirc. high vibration
4) 3A Recirc pump suction valve fails open and will not close
5) Failure of ADS/SRV 1-22
6) Drywell Leak
7) CRD pump 3B fails to start
8) CRD pump 3A trips
9) RCIC 71-8 fails to open
~ Malfunctions That Occur After EOI Entry; List: (1-4)
1) CRD pump 3B fails to start
2) CRD pump 3A trips
3) RCIC 71-8 fails to open
L Abnormal Events; List: (1-3)
1) SRV fails open
..£.. Major Transients; List: (1-2)
1) Loss of all high pressure makeup
2) Drywell Leak
.a, EOls used; List: (1-3)
1) EOI-1
2) EOI-2
3) EOI-3
.z. EOI Contingencies Used; List: (0-3)
1) C1
2) C2
90 Run Time (minutes)
45 EOI Run Time (minutes); 50 % of Scenario EOI Run Time
~ Crew Critical Tasks (2-5)
Yes Technical Specifications Exercised (yes/no) - Technical Requirements Manual
( XIV. Shift Turnover Information
Equipment out of service/LCOs: 3C RHR Pump is out of service . T.S 3.5.1.A.1!
3.6.2.3, 3.6.2.4, 3.6.2.5 have been entered . Unit 2 is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> into a seven day LCO.
Appendix R LCO addressed and in LCO tracking .
Operation/Maintenance for the Shift: Unit 3 is at 79% power, Alternate EHC Pumps per section
of 01 47A. Increase reactor power to 85% using Recirc flow (GOI-100-12 ,step 5.132) with no
pre-conditioning limitations. Reactor Engineering will evaluate any further power changes.
Continue with 3-SR-3.5 .1.7 which is in progress and is complete up to Step 7.11 (HPCI Main and
Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure) .
Loop I( RHR has been placed in Torus cooling and 3-SR-3.6.2.1.1 needs to be started 5 minutes
before starting HPCI. Units 1 & 2 are at 100% power,.
Unusual Conditions/Problem Areas: 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of
3-SR-3 .5.1.7
AppendixD Scenario Outline Form ES-D-l
Facility: BFN Scenario Number: HLTS-3-3 Op-Test Number: HLT0610
(
Examiners: Operators:
Initial Conditions:
The HPCI system is tagged out for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to repair the Auxiliary Oil Pump. It is expected back in 3
hours. Flow indicator 3-78B is out of service . Instrument Mechanics are looking for a new transmitter.
The Main Generator voltage regulator has been placed in Manual for PMs on the Automatic voltage
regulator. The spare RBCCW pump in service to Unit 2.
Turnover:
Reduce power to 95% using recirculation flow due to low system load requirements. PMs on the
voltage regulator are complete. Return the Main Generator voltage regulator to Automatic operation.
Event Malfunction Event Event
Number Number Type* Description
la N/A R-ATC The ATC operator will reduce reactor power to 95% using
R-SRO recirc flow using 3-01-68.
Ib N/A N-BOP The BOP operator will return the Main Generator voltage
N-SRO regulator to Automatic using 3-01-47.
2 ior zdihs7542a C-BOP The crew will recognize and respond to an inadvertent start of
start C-SRO the 3D Core Spray pump .
TS-SRO The SRO will address Tech Specs.
3 imf rd0718-35 C-ATC The crew will recognize and respond to a control rod drifting
C-SRO into the core using 3-AOI-85-5.
TS-SRO The SRO will address Tech Specs. .
4 bat NRC/ C-ATC The crew will recognize and respond to a recirc pump trip,
HLTSI0-1 C-SRO power oscillations, scram and ATWS .
C-BOP
5 Timed out from M The crew will recognize and respond to a fuel failure during
batch file All the ATWS recovery actions.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
(
AppendixD Scenario Outline Form ES-D-l
Facility: BFN Scenario Number: HLTS-3-3 Op-Test Number: HLT0610
('
Examiners: Operators:
Initial Conditions:
The HPCI system is tagged out for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to repair the Auxiliary Oil Pump. It is expected back in 3
hours. Flow indicator 3-78B is out of service. Instrument Mechanics are looking for a new transmitter.
The Main Generator voltage regulator has been placed in Manual for PMs on the Automatic voltage
regulator. The spare RBCCW pump in service to Unit 2.
Turnover:
Reduce power to 95% using recirculation flow due to low system load requirements. PMs on the
voltage regulator are complete. Return the Main Generator voltage regulator to Automatic operation.
Event Malfunction Event Event
Number Number Type* Description
l ti., N/A R-ATC The ATC operator will reduce reactor power to 95% using
R-SRO recirc flow using 3-01-68.
1b N/A N-BOP The BOP operator will return the Main Generator voltage
N-SRO regulator to Automatic using 3-01-47.
2 ior zdihs7542a C-BOP The crew will recognize and respond to an inadvertent start of
start C-SRO the 3D Core Spray pump.
TS-SRO The SRO will address Tech Specs.
3 imf rd0718-35 C-ATC The crew will recognize and respond to a control rod drifting
C-SRO into the core using 3-AOI-85-5.
TS-SRO The SRO will address Tech Specs.
4 bat NRC/ C-ATC The crew will recognize and respond to a recirc pump trip,
HLTSI0-l C-SRO power oscillations, scram and ATWS .
C-BOP
5 Timed out from M The crew will recognize and respond to a fuel failure during
batch file All the ATWS recovery actions .
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (Mjajor
(
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(
SIMULATOR EXERCISE GUIDE
TITLE POWER REDUCTION, CORE SPRAY 3D PUMP INADVERTANT START,
RECIRCULATION PUMP TRIP, REACTOR POWER OSCILLATIONS, ATWS WITH
MSIVS OPEN
REVISION o
DATE January 20, 2008
PROGRAM BFN Operator Training - HLT
PREPARED BY:
REVIEWED BY:
(Operations Superintendent or Designee)
(Required Exam Scenarios only)
VALIDATION
BY:
e'
(Operations SRcr (Required for Exam Scenarios only)
c/7 /0 g
Date
(
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(
NUCLEAR TRAINING
REVISIONISROAGE LOG
REVISION DESCRIPTION OF DATE PAGES REVIEWED BY
NUMBER REVISION AFFECTED
0 INITIAL 01/20108 All csf
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( I. PROGRAM: BFN Operator Training
II. COURSE: Examination Guide
III. TITLE : POWER REDUCTION,CORE SPRAY SR FAILURE, RECIRCULATION PUMP
TRIP, REACTOR POWER OSCILLATIONS, ATWS WITH MSIVS OPEN
IV. LENGTH OF LESSON: 1 to 1 % hours
V. Training Objectives
A. Terminal Objective
1. Perform routine shift turnover , plant assessment and routine shift operation in
accordance with BFN procedures.
2. Given uncertain or degrading conditions , the operating crew will use team skills to
conduct proper diagnostics and make conservative operational decisions to remove
equipment/unit from operation. (SOER 94-1 and SOER 96-01)
3. Given abnormal conditions, the operating crew will place the unit in a stabilized
condition per normal, abnormal, annunciator, and emergency procedures.
B. Enabling Objectives
1. The operating crew will recognize and respond to an inadvertent start of a Core
Spray pump and determine required actions per Technical Specifications.
2. The operating crew will recognize and respond to a recirculation pump trip with
reactor power oscillations in accordance with 3-AOI-68-1 .
3. The operating crew will recognize and respond to CRD pump 3A trip per 3-AOI-
85-3.
4. The operating crew will recognize and respond to an ATWS in accordance with
EOI-1 and C-5.
5. The operating crew will recognize and respond to high radiation in accordance
with EOI-3.
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( VI. References: The procedures used in the simulator are controlled copies and are used in development
and performance of simulator scenarios. Scenarios are validated prior to use, and any
procedure differences will be corrected using the procedure revision level present in the
simulator. Any procedure differences noted during presentation will be corrected in the
same manner. As such, it is expected that the references listed in this section need only
contain the reference material which is not available in the simulator.
VII. Training Materials: (If needed, otherwise disregard)
A. Calculator
B. Control Rod Insertion Sheet
C. Stopwatch
D. Hold Order I Caution tags
E. Annunciator window covers
F. Steam tables
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( IX. Console Operation Instructions
A. Scenario File Summary
1. File: bat HLTS3-3
MF/RF/IOR DESCRIPTION
1) imffw26b 0 'B' FW flow failure
2) bat tohpci Tags out HPCI
3) imfth23 (e3 0) 2.515:00 Fuel failure
4) imf rp08a RPS A1 scram failure
5) imf rp08b RPS A2 scram failure
6) trg e1 CSD Set trigger e1 to file CSD
7) trg e2 CSDHS Set trigger e2 to file CSDHS
8) trg e3 MODESW Set trigger e3 to file MODESW
9) trg e1= dor zdihs7542a Trigger e1 initiates command
10) trg e2= ior zloil7542 on Trigger e2 initiates command
11) imftc020 Fails Bypass valves closed
2. File: bat HLTS3-3-1
MF/RF/IOR DESCRIPTION
1) imf th03a (none 10:00) Trips 3A Recirc. pump
2) imfth03b Trips 3B Recirc. pump
3) imf cr02a 65 10:00 Power Oscillations
4) batatws90 90% Hydraulic ATWS
5) Imf tc01 (e35:00) Fail bypass valves closed 5 min after
mode sw
3. File bat tohpci
MF/RF/IOR DESCRIPTION
1) ior ypomtrglesh fail_cn_po Tag gland seal exhauster
ior ypovfcv733a close 73-3 close
2) ior ypovfcv733 fail_now Tag FCV73-3
ior ypovfcv7316 fail_now Tag FCV 73-16
3) ior ypovfcv7381 fail_now Tag FCV 73-81
4) ior zdihs7347a ptl Tag HPCI Aux oil pump
5) ior zohs7347a[1] off
6) imf hp05 HPCI trip
4. File bat HLTS3-3-4
MF/RF/IOR DESCRIPTION
1) trg e4 RODDRIFT Stops drifting rod motion at notch 42.
trg e4 = dmf rd07r2627
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( IX. Console Operation Instructions
A. Scenario File Summary
5. File bat app01f
MF/RF/IOR DESCRIPTION
1) mrf rp13a byp Bypasses automatic scrams
2) mrf rp13b byp (Appendix 1F)
6. File batapp02
MF/RF/IOR DESCRIPTION
1) mrf rp12a test Bypasses ARI
2) mrf rp12b test (Appendix 2)
7. File batapp08ae
MF/RF/IOR DESCRIPTION
1) mrf rp06a byp Bypasses MSIV isolation on low
2) mrf rp06b byp RPV water level (Appendix 8A)
3) mrf rp06c byp
4) mrf rp06d byp
5) mrf rp14a byp Bypasses Rx Bldg ventilation
6) mrf rp14b byp isolation on low RPV level
8. File bat atws90east
MF/RF/IOR DESCRIPTION
1) imf rd17a SDV level switch failure
2) imf rd09a 90 90% hydraulic ATWS East SDV
9. File bat sdvtd
MF/RF/IOR DESCRIPTION
a) dmf rd17a Deletes SDV level switch failure
b) dmf rd17b
c) imf rd17a (none 7:00) Inserts level switch failure after 7
minutes
d) imf rd17a (none 7:00)
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( IX. Console Operation Instructions
8. Console Operator Manipulations
ELAP TIME PFK DESCRIPTION/ACTION
Sim.Setup reset 28 100% MOC
Sim. Setup restorepref HLTS3-3 Establishes Function Keys
Sim. Setup setup Verify Function Keys
Sim. Setup esc Clears Function Key Popup
Sim.Setup F3 See scenario file summary (bat HLTS3-3)
Sim.Setup manual Tag out HPCI. Hang out of service cover
on "8" FW Flow Indicator
Sim.Setup manual HPCI AOP and SPE pumps in PTL. Place
Main Generator Voltage Regulator in
Manual
ELAP TIME PFK DESCRIPTION/ACTION
2 minutes after Unit at 95% power F4 Core Spray pump 3D start
ior zdihs7542a start
When CS "0" Starts: bat CSO bat CSO
If lockout light does not illuminate when CS F5 Illuminates lockout light
pump stopped, then lor zloil7542 on
2 minutes after Tech Specs addressed for F6 Control Rod 26-27 drifting in.
CS pump imf rd072627 in
bat HLTS3-3-4 Assigns trg e4 to stop rod motion at notch
42.
ROLE PLAY: As AUO at HCU 18-35, REPORT - The scram inlet riser is hot to the touch.
ROLE PLAY: As AUO at HCU 18-35, REPORT - 3-SHV-85-588 valve is closed.
ROLE PLAY: Respond as needed as AUO at HCU and as Operator at pn19-16 in AUX INST ROOM.
ROLE PLAY: As AUO at HCU 18-35, REPORT - solenoids operating normally (no chattering) and the valve
stems indicate closed. Also, when directed, REPORT - 3-SHV-85-588 is open .
.!,MORE FOLLOWS.!,
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( IX. Console Operation Instructions
B. Console Operator Manipulations
ELAPTIME DESCRIPTION/ACTION
When directed by Chief Examiner: <shift>F2 Initiates Recirc pump trips and power
bat HLTS3-3-1 oscillations. ATWS
After scram inserted <shift>F3 SDV switches enabled
bat sdv
When appendix 2 requested, wait 3 minutes <shift>F4 Bypass ATWS/ARI circuit
batapp02
When requested to perform appendix 1F, wait <shift>F5 Jumper out scram logic
5 minutes bat app01f
When requested to perform Appendix 8A and <shift> F6 Allows restart of Reactor/Refuel zone
8E, wait 5 minutes batapp08ae ventilation
When scram is reset <shift> F7 SDV switches enabled
bat sdvtd
If requested to close 3-FCV-85-586, wait 5 <shift> F8 Provides drive water pressure for rod
minutes mrf rd06 close insertion
If requested to open 3-FCV-85-586, wait 1 <shift> F9 Pressurizes charging water header
minute mrf rd06 open
nd
When Reactor is manually scrammed (2 <shift>F3 SDV switches enabled
time) batsdv
nd
When Reactor is scram reset (2 time) <shift> F7 SDV switches enabled
bat sdvtd
<shift> F10 Removes power oscillations
dmf cr02a
<shift> F11 Deletes ATWS
bat atws-1
Terminate the scenario when the following conditions are satisfied or upon request of the Chief Examiner:
1. All rods fully inserted .
2. RPVwater level +2" to +51."
3. Reporting requirements made .
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(
IX. SCENARIO SUMMARY:
The unit is operating at 100% power with a 5% power reduction scheduled. HPCI is tagged out
for maintenance on the Auxiliary Oil Pump and is expected to be returned to service within the
next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. It has been out of service for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
The Main Generator voltage regulator was placed in Manual to allow PMs on the Automatic
regulator. PMs are complete and the voltage regulator can be returned to Automatic.
Core Spray 3D pump inadvertent start is received and the Crew must consult Tech Specs to
determine required actions.
Control Rod 26-27 drifts inadvertently into the core and stops at Notch 42.
38 Recirc pump trips, resulting in power oscillations with some fuel failure. While responding to
the power oscillations per AOI-68-1, 3A Recirc pump trips and a manual scram must be inserted.
The crew will experience a hydraulic ATWS and respond per 3-EOI-1. The SDV will fail to drain
totally, thus requiring two additional reactor scrams to insert control rods.
(
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( x. Information to Evaluators :
A. Ensure recorders are inking and recording and ICS is active and updating.
B. Assign Crew Positions based on the required rotation.
1. SRO: Unit Supervisor
2. ATC: Board Unit Operator
3. BOP: Desk Unit Operator
C. Conduct a shift turnover with the Shift Manager and provide the Shift Manager with a copy of the
Shift Turnover.
D. Direct the shift crew to review the control board and take note of present conditions, alarms , etc.
E. Terminate the scenario when the following conditions are satisfied are at the request of the
floor/lead instructor/evaluator.
1. All rods inserted
2. Water level +2" to +51"
3. Reporting requirements have been made
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( XI. Simulator Event Guide
Event 1a: POWER REDUCTION
TIME POSITION EXPECTED ACTIONS
ATC educes reactor ower in accordance with 3-GOI-100-12 and 3-01-6
[1] IF NOT in single loop operation, THEN
ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-
HS-96-15A(158)/LOWER SLOW(MEDIUM) 3-HS-96-17A(178), push-
buttons, to achieve balanced jet pump flows. AND/OR ADJUST
Recirc Pump speed 3B using, RAISE SLOW (MEDIUM), 3-HS-96-
6A(16B) /LOWER SLOW(MEDIUM) 3-HS-96-18A(18B), pushbuttons, to
achieve balanced jet pump flows.
[2] WHEN desired to control Recirc Pumps 3A and/or 3B speed with the
RECIRC MASTER CONTROL, THEN
ADJUST Recirc Pump speed 3A & 38 using the following push
buttons as required:
RAISE SLOW, 3-HS-96-31
RAISE MEDIUM, 3-HS-96-32
LOWER SLOW, 3-HS-96-33
LOWER MEDIUM, 3-HS-96-34
LOWER FAST, 3-HS-96-35
BOP Peer checks during power reduction
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( XI. Simulator Event Gu ide
Event 1b: VOLTAGE REGULATOR TO AUTOMATIC
POSITION EXPECTED ACTIONS
BOP VERIFY VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, is in
MAN.
PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-
57-26, to RAISE UNTIL the upper limit is reached (red light
illuminated).
PLACE GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 32-HS-
57-26, to LOWER UNTIL the lower limit is reached (green light
illuminated).
ADJUST GENERATOR FIELD VOLTAGE AUTO ADJUST (90P), 3-HS-
57-26, UNTIL GEN TRANSFER VOLTS, 2-EI-57-41, indicates zero.
PLACE VOLTAGE REGULATOR MAN/AUTO SEL, 3-HS-57-27, in
AUTO.
VERIFY GEN VOLT REGULATOR TRIP TO MAN,
3-EA-57-132 (3-XA-55-8A, window 3) alarms.
RESET GEN VOLT REGULATOR TRIP TO MAN,
3-EA-57-132 (3-XA-55-8A, window 3).
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( XI. Simulator Event Guide
Event 2: SPURIOUS START OF 3D CORE SPRAY PUMP
POSITION EXPECTED ACTIONS
BOP Reports start of 3D Core Spray pump and verifies no valid
automatic start signal.
SRO Directs trip of 3D Core Spray pump
BOP Trips 3D Core Spray pump. Informs SRO that Lockout indicator
for 3D Core Spray Pump is illuminated indicating the pump will
not start automatically if needed.
SRO Consults Tech Spec 3.5.1 determines that 3.5.1.A is a 7 day
Action Statement for 3D Core Spray pump and 3.5.1.D is a 72
hour Action Statement in effect with HPCI and one (1) Low
Pressure ECCS system inoperable.
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XI. Simulator Event Guide
Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
ATC Announces "Rod Drift" alarm 3-ARP-9-SA window 28
A. DETERMINE which rod is drifting from Full Core Display.
Identifies rod 26-27 as drifting in.
B. F rod driftin in THEN REFER TO 3-AOI-85-5.
C. IF rod drifting out, THEN REFER TO 3-AOI-85-6.
D. REFER TO Tech Spec Section 3.1.3, 3.10.8.
ATC Recognizes that Rod 26-27 stops moving at Notch 42.
SRO irects actions er 3-AOI-8S-5
SRO Directs rod be continuously inserted to 00
(
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XI. Simulator Event Guide
Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
ATC 3-AOI-85
Immediate Actions
[1] IF multiple rods are drifting into core, THEN
NA MANUALLY SCRAM Reactor. REFER TO 3-AOI-100-1.
Subsequent Actions
[1] IF the Control Rod travels greater than two notches from its
intended position, THEN INSERT Control Rod to position 00 using
CONTINUOUS IN. (otherwise N/A)
ATC [2] NOTIFY Reactor Engineer.
ATC [3] CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).
[4] ADJUST control rod pattern as directed by Reactor Engineer
and CHECK Thermal Limits on ICS (RUN OFFICIAL 3D).
(
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XI. Simulator Event Guide
Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
[5] IF CRD Cooling Water Header DP is excessive and causing
the control rod drift, THEN ALTERNATELY ADJUST tape setpoint of
CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, and position of CRD
DRIVE WATER PRESS CONTROL VLV, 3-HS-85-23A, to establish
the following conditions (otherwise N/A):
o CRD CLG WTR HDR DP, 3-PDI-85-18A, of about 20 psid, and
o CRD DRIVE WTR HDR DP, 3-PDI-85-17A, between 250 and 270 psid,
and
o CRD SYSTEM FLOW CONTROL, 3-FIC-85-11, between 40 and 65
gpm .
ATC Directs AUO to check the following per 3-AOI-85-5:
[6] VER IFY scram pilot air header aligned to scram inlet and
outlet valves.
[7] CHECK CRD SCRAM OUTLET VALVE, 3-FCV-085-39B, for
leakage as indicated by the following :
o Scram riser for affected HCU has higher than normal Temperature
o CRD SCRAM OUTLET VALVE , 3-FCV-085-39B, producing flow noise
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( XI. Simulator Event Guide
Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
ATC [8] CHECK CRD SCRAM INLET VALVE , 3-FCV-085-39A, for
leakage as follows:
[8.1] CHECK insert riser for affected HCU for higher than
normal temperature.
ATC Directs AUO to perform the following;
[8.2] CLOSE CHARGING WATER SOV, 3-SHV-085-588 and
OBSERVE CRD ACCUMULATOR NITROGEN SIDE
PRESS, 3-PI-085-034, for lowering trend.
SRO Declares accumulator inoperable per Tech Spec 3.1.5.A and
addresses actions (when charging water is isolated)
EXAMINER NOTE: With charging water isolated to the HCU, the
control rod no longer satisfies the OPERABILITY requirement that
the control rod is capable of being scrammed even if the rod is fully
inserted.
ATC After report from AUO thart scram inlet valve is leaking, Directs
scramming of affected rod from panel 9-16 in Aux.lnst. Room
(
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Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
ATC [9] IF either Scram Inlet or Outlet Valve is found to be leaking,
THEN PERFORM the following to scram the control rod (otherwise
N/A):
[9.1] ESTABLISH communications between Control Room and the
folloWing locations:
o Hydraulic control unit affected, elevation 565, Reactor Building
o Panel 3-9-16 in Auxiliary Instrument Room, elevation 593, Control
Bay
[9.2] VERIFY CLOSED CHARGING WATER SOV, 3-SHV-085-588.
ATC [9.3] INITIATE individual rod scram by actuating selected rod
scram switch on Panel 3-9-16 to its scram (DOWN) position.
[9.4] VERIFY control rod has reached FULL IN on Panel 3-9-5.
[9.5] IF attempting to reseat scram valves, THEN RETURN rod scram
switch for associated control rod to its normal (UP) position at
Panel 3-9-16,.
[9.6] CHECK solenoid operation of CRD SCRAM INLET and OUTLET
VALVEs 3-FCV-85-39A and 3-FCV-85-39B, (they should function
normally without chatter or abnormal buzzing .)
[9.7] CHECK stem travel indicators on CRD SCRAM INLET and OUTLET
VALVEs 3-FCV-85-39A and 3-FCV-85-39B. IF either scram valve
indicates OPEN, THEN NOTIFY control room .
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Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
ATC [9.8] CHECK blue Scram indicator light on Full Core Display
extinguished.
[9.9] RESET Rod Drift Alarm and CHECK DRIFT indicator light on
Full Core Display extinguished. (N/A if rod is still drifting in)
[9.10] CHECK annunciator CONTROL ROD DRIFT (3-XA-55-5A,
Window 28) reset. (N/A if rod is still drifting in)
ATC Have AUO perform the following;
[9.11] SLOWLY OPEN CHARGING WATER SOY, 3-SHV-085-588.
ATC [9.12] CHECK amber ACCUM indicator light on Full Core Display
extinguished.
[9.13] CHECK red indicating light for associated HCU extinguished on
local Panel 3-28-4(3-25-22).
[9.14] NOTIFY Site Engineering.
[9.15] INITIATE a work order.
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Event 3: CONTROL ROD DRIFT IN
POSITION EXPECTED ACTIONS
[10] IF insert directional control valve is suspected of leaking, THEN
ATTEMPT to reseat valve as follows (otherwise N/A):
[10.1] INSERT control rod one notch.
[10.2] NOTIFY Site Engineering.
[10.3] INITIATE a work order.
[11] IF attempts to stop control rod drifting are unsuccessful, THEN
PERFORM the following (otherwise N/A):
[11.1] VERIFY control rod drive is at position 00 or "FULL IN".
[11.2] REMOVE associated HCU from service.
REFER TO 3-01-85 and Tech Spec 3.1.3.
ATC Reports to SRO rod settles to 00 position
SRO Initiates actions to determine CR operability and suggests actions
including maintenance and inspection.
ATC De-selects and re-selects Rod 26-27 to clear RBM DOWNSCALE 3-
ARP-9-5A (W 31).
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Event 4 : RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS
POSITION EXPECTED ACTIONS
ATC Recognizes B Recirculation pump trip
SRO irects 3-AOI-68-1 ent
Contacts Rx Engr to place APRM's in SLO mode (If time permits)
ATC/BOP [1] IF both Recirc Pumps are tripped in modes 1 or 2, THEN
(Otherwise N/A),
A. SCRAM the Reactor.
[2] IF Region I or II of the Power to Flow Map (Illustration 1) is
entered, THEN (Otherwise N/A)
IMMEDIATELY take actions to INSERT control rods to less than
95.2% load line. Refer to 0-TI-464, Reactivity Control Plan
Development and Implementation.
[3] RAISE core flow to greater than 45%. Refer to 3-01-68.
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XI. Simulator Event Guide
Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS
POSITION EXPECTED ACTIONS
[4] INSERT control rods to exit regions if not already exited. Refer
to 0-TI-464, Reactivity Control Plan Development and
Implementation.
Inserts rods on emergency shove sheet ~
[5] CLOSE tripped Recirc Pump discharge valve 3-FCV-68-79.
[6] MAINTAIN operating Recirc pump flow less than 46,600 gpm.
Refer to 3-01-68.
Verifies flow on A Recirc pump < 46,600 gpm
[7] [NERlC] WHEN plant conditions allow, THEN, (Otherwise N/A)
MAINTAIN operating jet pump loop flow greater than 41 x 106 Ibm/hr
(3-FI-68-46 or 3-FI-68-48). [GE SIL 517]
Verifies jet pump flow> 41,100 Ibm/hr
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Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS
POSITION EXPECTED ACTIONS
[10] [NERlC] WHEN the Recirc Pump discharge valve has been
closed for at least five minutes (to prevent reverse rotation of the
pump) [GE SIL-517], THEN (N/A if Recirc Pump was isolated in
Step 4.2[8]) OPEN Recirc Pump discharge valve as necessary to
maintain Recirc Loop in thermal equilibrium.
ATC Recognizes power oscillations
ATC/BOP Notices failure to Scram ~ or anticipates trip and
inserts a manual scram ~
SRO Directs manual reactor scram ~
ATC Inserts manual scram
Places Mode switch in shutdown
Recognizes hydraulic ATWS
Provides scram report
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Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS
TIME POSITION EXPECTED ACTIONS
SRO nters EQI-1/C-5 and verifie
Verifies Mode switch to shutdown
ARI initiated
Directs ADS inhibited ~
BOP Contacts AUO to perform outside portions of App 1F & 2
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XI. Simulator Event Guide
Event 4: RECIRCULATION PUMP TRIP/POWER OSCILLATIONS/ATWS
TIME POSITION EXPECTED ACTIONS
ATC 1. VERIFY at least one CRD pump in service.
2. IF ..... Reactor Scram or ARI CANNOT be reset,
THEN ..* DISPATCH personnel to CLOSE 3-SHV-085-o586,
CHARGING WATER SOV (RB NE, EI565 ft).
Dispatches AUO to close 3-SHV-85-586.
3. VERIFY REACTOR MODE SWITCH in SHUTDOWN.
4. BYPASS Rod Worth Minimizer.
5. REFER to Attachment 2 and INSERT control rods in the area of
highest power ~
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN
POSITION EXPECTED ACTIONS
BOP Recognizes 3A Recirc pump trip, if not tripped by ATC Operator
due to ATWS
Crew Recognize and reports
"OG Pretreatment Radiation High"
"OG Annual Release Limit Exceeded"
"Turbine Building High Radiation"
Notifies RadCon, and Chemistry
Evacuates appropriate area of Turb. Bldg.
SRO Directs RPV pressure be maintained 800-1000 psig
BOP Controls RPV pressure between 800-1000 psig with SRVs
(
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
Directs Appendix 8A and 8E be performed
Reports SAE 1.2-5
ATC 1. PREVENT injection to RPV from the following systems in
any order as required: (Critical Task)
a. HPCI
1) IF HPCI Turbine is NOT at zero speed, THEN PRESS and HOLD
3-HS-73-18A, HPCI TURBINE TRIP push-button.
2) WHEN ..*.HPCI Turbine is at zero speed, THEN ....PLACE 3-HS-73-
47A, HPCI AUXILIARY OIL PUMP control switch in PULL TO LOCK
and
RELEASE 3-HS-73-18A, HPCI TURBINE TRIP push-button.
1) IF DIRECTED by SRO to allow RCIC injection, THEN EXIT step
1.b.
2) PRESS 3-HS-71-9A, RCIC TURBINE TRIP push-button to trip RCIC
Turbine.
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XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
BOP c. CORE SPRAY
NOTE: Following receipt of an automatic initiation signal, it is NOT
necessary to wait until the pump actually starts before performing the
next step.
Following an initiation signal, PLACE ALL Core Spray pump control
switches in STOP .
PREVENT injection by EITHER of the following methods:
Following automatic pump start, PLACE RHR SYSTEM I pump control
switches in STOP.
BEFORE RPV pressure drops below 450 psig,
1) VERIFY Appendix 16F has been performed, AND
2) VERIFY CLOSED 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT
VALVE.
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
PREVENT injection by EITHER of the following methods:
Following automatic pump start , PLACE RHR SYSTEM II pump control
switches in STOP.
BEFORE RPV pressure drops below 450 psig,
1) VERIFY Appendix 16G has been performed, AND
2) VERIFY CLOSED 3-FCV-74-66, RHR SYS II LPCI OUTBD INJECT
VALVE.
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
ATC f. CONDENSATE and FEEDWATER
1) LOWER RFPT 3A(3B)(3C) speed to minimum setting
(approximately 600 rpm) using ANY of the following methods on Panel 3-9-
5:
Using 3-L1C-46-5, REACTOR WATER LEVEL CONTROL PDS, in
MANUAL AND individuaI3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED
CONTROL PDS in AUTO,
Using individuaI3-SIC-46-8(9)(10), RFPT 3A(3B)(3C) SPEED CONTROL
PDS in MANUAL,
Using individuaI3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT
RAISE/LOWER switch in MANUAL GOVERNOR.
2) CLOSE the following valves BEFORE RPV pressure drops below 450
psig:
3-FCV-3-19, RFP 3A DISCHARGE VALVE
3-FCV-3-12, RFP 3B DISCHARGE VALVE
3-FCV-3-5, RFP 3C DISCHARGE VALVE
3-LCV-3-53, RFW START-UP LEVEL CONTROL.
3) TRIP RFPTs as necessary to prevent injection by DEPRESSING the
following push-buttons:
3-HS-3-125A, RFPT 3A TRIP
3-HS-3-151A, RFPT 3B TRIP
3-HS-3-176A, RFPT 3C TRIP.
(
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XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
Crew Monitors suppression pool temperature
8A&8E
ATC After Appendix 1F and 2 complete resets scram and drains SDV
ATC ~ 1
2. WHEN ... RPS Logic has been defeated, THEN ..* RESET Reactor
3. VERIFY OPEN Scram Discharge Volume vent and drain valves .
4. DRAIN SOV UNTIL the following annunciators clear on Panel 3-9-4:
o WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM
(3-XA-55-4A, Window 1)
o EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM
(3-XA-55-4A, Window 29).
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
ATC Continues to insert control rods per Appendix1 D
BOP Maintains water level as directed with RFP I RCIC
BOP Maintains Pressure control using the following appendices:
11D Main Steam line Drains
11F RFPT
11ASRV's
2. VERIFY hotwel! pressure below -7 in. Hg.
3. CONTROL RPV pressure with Main Steam line drains as follows:
a. VERIFY PCIS reset.
b. OPEN the following valves (Panel 3-9-3):
o 3-FCV-1-55, MN STM LINE DRAIN INBD ISOLATION VLV
o 3-FCV-1-56, MN STM LINE DRAIN OUTBD ISOLATION VLV
o 3-FCV-1-58, UPSTREAM MSL DRAIN TO CONDENSER
4. THROTTLE 3-FCV-1-59, DOWNSTREAM MSL DRAIN TO
CONDENSER, as necessary to control cooldown rate.
(
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XI. Simulator Event Guide
Event 6: ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN
POSITION EXPECTED ACTIONS
2. VERIFY MSIVs open.
3. VERIFY Hotwell Pressure at or below -7 in. Hg.
4. PLACE RFPTs in service as follows:
a. VERIFY the following:
1) At least one condensate pump running.
2) At least one condensate booster pump running.
3) Condensate System aligned to supply suction to RFPs .
b. VERIFY Main Oil Pump running for EACH RFPT to be started .
c. VERIFY CLOSED 3-FCV-3-19(12)(5), RFP 3A(3B)(3C)
DISCHARGE VALVE.
d. DEPRESS 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED CONT
RAISE/LOWER, and VERIFY amber light is
illuminated.
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN
POSITION EXPECTED ACTIONS
BOP e. DEPRESS 3-HS-3-124A(150A)(175A), RFPT 3A(3B)(3C)
TRIP RESET.
f. PLACE 3-HS-46-112A(138A)(163A), RFPT 3A(3B)(3C)
START/LOCAL ENABLE, in START.
g. CHECK RFPT 3A(3B)(3C) speed increases to approximately 600 rpm.
h. VERIFY OPEN 3-FCV-3-20(13)(6), RFP 3A(3B)(3C) MIN
FLOW VALVE .
i. PLACE 3-HS-46-8A(9A)(10A), RFPT 3A(3B)(3C) SPEED
CONT RAISE/LOWER in RAISE to raise RFPT speed,
maintaining discharge pressure less than 1250 psig.
(
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
BOP A 11A1
2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE
MSRVs and CONTROL RPV pressure using other options.
3. OPEN MSRVs using the following sequence to control RPV
pressure as directed by SRO:
a. 1 3-PCV-1-179 MN STM LINE A RELIEF VALVE.
b. 2 3-PCV-1-180 MN STM LINE 0 RELIEF VALVE.
c. 3 3-PCV-1-4 MN STM LINE A RELIEF VALVE.
d. 4 3-PCV-1-31 MN STM LINE C RELIEF VALVE.
e. 5 3-PCV-1-23 MN STM LINE B RELIEF VALVE.
f. 6 3-PCV-1-42 MN STM LINE 0 RELIEF VALVE.
g. 7 3-PCV-1-30 MN STM LINE C RELIEF VALVE.
h. 8 3-PCV-1-19 MN STM LINE B RELIEF VALVE.
i. 9 3-PCV-1-5 MN STM LINE A RELIEF VALVE.
j. 10 3-PCV-1-41 MN STM LINE 0 RELIEF VALVE.
k. 11 3-PCV-1-22 MN STM LINE B RELIEF VALVE.
I. 12 3-PCV-1-18 MN STM LINE B RELIEF VALVE.
m. 13 3-PCV-1-34 MN STM LINE C RELIEF VALVE.
(
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XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
ATC When alarms
WEST CRD DISCH VOL WTR LVL HIGH HALF SCRAM
(3-XA-55-4A, Window 1)
EAST CRD DISCH VOL WTR LVL HIGH HALF SCRAM
(3-XA-55-4A, Window 29).
Are clear, directs 3-85-586 re-opened and after accumulator alarms
are clear, Inserts manual scram (Critical Task)
Crew Recognizes some control rod movement, but all control rods not in
SRO Directs reactor reset, drain SDV, and re-scram ~
Directs SLC injection if Torus temperature approaches 110 deg.
ntel'S EQI-2 on Torus wa er leyel
Directs placing H20 2 monitors in service
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
1. VERIFY at least one SGTS train in service.
2. VERIFY CLOSED the following valves (Panel 3-9-3 or Panel 3-9-54):
3-FCV-64-31, DRYWELL INBOARD ISOLATION VLV,
3-FCV-64-29, DRYWELL VENT INBD ISOL VALVE,
3-FCV-64-34, SUPPR CHBR INBOARD ISOLATION VLV,
3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE.
3. IF ... While executing this procedure to vent the Suppression Chamber,
Suppression Pool water level can not be determined to be below 20 ft, THEN
. PERFORM step 13 to secure the vent path and reenter this procedure if
further venting is required .
4. IF ... While executing this procedure, the desired vent path is lost or can
not be established, THEN . PERFORM step 13 to secure the vent path and
reenter this procedure if further venting is required.
(
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
BOP 5. IF ... While executing this procedure, CAD addition per SAMG-2, Step G-4
OR G-9, is to begin , THEN. BEFORE CAD is initiated, PERFORM Step 13
to secure the vent path .
NOTE: Venting may be accomplished using EITHER:
o3-FIC-84-19, PATH B VENT FLOW CONT, OR
o3-FIC-84-20, PATH A VENT FLOW CONT.
NOTE : Unless the TSC recommends otherwise, venting the Drywell
DIRECTLY should be performed ONLY if the Suppression Chamber can
NOT be vented.
6. IF ... ANY of the following exists:
Suppression Pool water level can not be determined to be below 20 ft, OR
Suppression Chamber can NOT be vented , OR
SRO orders DIRECT drywell venting,
THEN CONTINUE in this procedure at:
Step 10 to vent the Drywell through 3-FCV-84-19, OR
Step 11 to vent the Drywell through 3-FCV-84-20.
7. CONTINUE in this procedure at:
Step 8 to vent the Suppression Chamber through 3-FCV-84-19, OR
Step 9 to vent the Suppression Chamber through 3-FCV-84-20.
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XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
BOP 8. VENT the Suppression Chamber using 3-FIC-84-19, PATH B VENT
FLOW CONT, as follows:
a. PLACE keylock switch 3-HS-84-35, DW/SUPPR CHBR VENT ISOL
BYP SELECT, to SUPPR-CHBR position (Panel 3-9-54).
b. VERIFY OPEN 3-FCV-64-32, SUPPR CHBR VENT INBD ISOL VALVE
(Panel 3-9-54).
c. PLACE 3-FIC-84-19, PATH B VENT FLOW CONT, in AUTO with
setpoint at 100 scfm (Panel 3-9-55).
d. PLACE keylock switch 3-HS-84-19, 3-FCV-84-19 CONTROL, in OPEN
(Panel 3-9-55).
e. VERIFY 3-FIC-84-19, PATH B VENT FLOW CONT, is indicating
approximately 100 scfm .
f. CONTINUE in this procedure at step 12.
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XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
BOP 12. ADJUST 3-FIC-84-19, PATH 8 VENT FLOW CONT, or 3-FIC-84-20,
PATH A VENT FLOW CONT, as applicable, to maintain ALL of the
following:
Stable flow as indicated on controller, AND
3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND
Release rates as determined below:
i. IF. . .PRIMARY CONTAINMENT FLOODING per C-1 , Alternate Level
Control, is in progress THEN ..MAINTAIN release rates below those
specified in Attachment 2.
ii. IF. . .Severe Accident Management Guidelines are being executed, THEN .
.MAINTAIN release rates below those specified by the TSC SAM Team.
iii. IF...Venting for ANY other reason than items i or ii above, THEN.
.MAINTAIN release rates below Stack release rate of 1.4 x 107 ~Ci/s
AND 0-S1-4.8.8.1.a.1 release fraction of 1.
BOP Contacts LOG AUO to monitor release rates
(
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( XI. Simulator Event Guide
Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
ATC Maintains water level as directed to control power
ATC After SDV drained and after accumula~d, scrams
reactor again and verifies all rods in ~
SRO Directs level be restored +2" to +51" (Critical Task)
SRO Directs SLC stopped (if injected)
Crew Recognize RM-90-29A Rx Bldg High Radiation (cond itional)
BOP Evacuates Reactor Building
SRO radiation and directs ventilation
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN
POSITION EXPECTED ACTIONS
1. VERIFY PCIS Reset.
2. PLACE Refuel Zone Ventilation in service as follows (Panel 3-9-25):
a. VERIFY 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS,
control switch is in OFF .
b. PLACE 3-HS-64-3A, REFUEL ZONE FANS AND DAMPERS,
control switch to SLOW A (SLOW B).
c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-3A, REFUEL
ZONE FANS AND DAMPERS, control switch extinguish and two SPLY/EXH
A(B) red lights illuminate.
d. VERIFY OPEN the following dampers:
- 3-FC0-64-5, REFUEL ZONE SPLY OUTBD ISOL DMPR
- 3-FCO-64-6, REFUEL ZONE SPLY INBD ISOL DMPR
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDV TO DRAIN
POSITION EXPECTED ACTIONS
3. PLACE Reactor Zone Ventilation in service as follows (Panel 3-9-25):
a. VERIFY 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS,
control switch is in OFF.
b. PLACE 3-HS-64-11A, REACTOR ZONE FANS AND DAMPERS,
control switch in SLOW A ( SLOW B).
c. CHECK two SPLY/EXH A(B) green lights above 3-HS-64-11A, REACTOR
ZONE FANS AND DAMPERS, control switch
extinguish and two SPLY/EXH A(B) red lights illuminate.
d. VERIFY OPEN the following dampers:
3-FCO-64-13, REACTOR ZONE SPLY OUTBD ISOL DMPR
- 3-FCO-64-14, REACTOR ZONE SPLY INBD ISOL DMPR
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Event 5: ATWS WITH FUEL FAILURE/FAILURE OF SDVTO DRAIN
POSITION EXPECTED ACTIONS
ATC/BOP Announces MAIN STEAM LINE RADIATION HIGH-HIGH
Annunciator 3-ARP-9-3A window 27 (if received)
A. VERIFY alarm on 3-RM-90-136 thru 137 on Panel 3-9-10.
B. CONFIRM main steam line radiation level on recorder 3-RR-90-135,
Panel 3-9-2.
C. IF alarm is VALID and scram has NOT occurred, THEN PERFORM the
following:
IF core flow is above 60%, THEN
1. LOWER core flow to between 50-60%.
2. MANUALLY SCRAM the Reactor.
3. REFER TO 3-AOI-100-1.
D. IF plant conditions DO NOT require the execution of 3-C-5,
Power/Level Control, THEN VERIFY the MSIV's CLOSED.
E. NOTIFY RADCON.
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( XII. Crew Critical Tasks (CCT)
SAT/UNSAT
1. Manual scram due to Scram failure of OPRM Trip within one minute.
2. Prevent ADS actuation.
3. Controls power by :
- Inserting control rods per RC/Q-21 .
- Lowering reactor water level per EOI-C-5.
4. Maintains RPV water level above -180" with rods out
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XIII. Scenario Verification Data
1. Control Rod Drift 201002A2.02 3.2 3.3
2. APRM Failure 215005A2.03 3.6 3.7
2.1 .12 2.9 4.0
3. Recirculation Pump Trip/Power Oscillations/ATWS 295001 3.3 3.4
295025 3.8 3.9
295037 3.9 4.0
(
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( SCENARIO REVIEW CHECKLIST
SCENARIO NUMBER HLTS-3-3
7 Total malfunctions Inserted; List: (4-8)
1. Recirc Trip
2. Power Oscillations
3. ATWS
4. Fuel Failure
5. Core Spray pump 3D trip
6. Control Rod Drift
2 Malfunctions That Occur After EOI Entry; List: (1-4)
1) ATWS
2) Fuel Failure
2 Abnormal Events; List: (1-3)
1) Control Rod Drift
2) Recirc Trip
2 Major Transients; List: (1-2)
1) ATWS
2) Fuel Failure
3 EOls used; List: (1-3)
1) EOI-1
2) EOI-2
3) EOI-3
1 EOI Contingencies Used; List: (0-3)
1) C5
75 Run Time (minutes)
35 EOI Run Time (minutes); 50 % of Scenario EOI Run Time
4 Crew Critical Tasks (2-5)
Yes Technical Specifications Exercised (yes/no)
(
XV. SHIFT TURNOVER INFORMATION
( Equipment out of service/LCOs: HPCI tagged out for 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> to repair Aux iliary Oil Pump. Expected
back in 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> . Flow indicator 3-78B out of service, 1M's are looking for a new transm itter. Main
Generator voltage regulator in manual for PMs on Automatic voltage regulator. Spare RBCCW pump in
service to Unit 2.
Operation/Maintenance for the Shift: Reduce power to 95% with recirculation flow due to high river water
temperature. PMs on voltage regUlator complete, return voltage regulator to automatic.
Unusual Cond itions/P roblem Areas: _---!.,;N!..l::o~n~e _
AppendixD Scenario Outline Form ES-D-l
Facility: BFN Scenario Number: HLTS-3-4 Op-Test Number: HLT0610
(
Examiners: Operators:
Initial Conditions:
The unit is starting up following a refuel outage. Reactor power is at - 9%. "An RFP is uncoupled for
performance of turbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.
Turnover:
The 3A RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine
overspeed. Currently at step 5.76.8 of3-GOI-100-IA and at step 5.6 [18] 00-01-3 for warming 3B
RFP.
Event Malfunction Event Event
Number Number Type* Description
I none R-ATC Crew will continue to pull rods to increase power and start
N-BOP warming up 2B RFP
R-SRO
2 imf rd l 4a I-ATC Crew will respond to a RWM failure.
I-SRO SRO references Tech Specs.
TS-SRO
3 imfrdOla C-ATC Crew will respond to a trip of 3A CRD pump .
C-SRO
4 imf sw02a trip C-BOP Crew will respond to a RBCCW pump trip
7048FfC C-SRO Crew manually closes 70-48 after fails to auto close
5 ior zdihs468a C-BOP Crew will respond to feedwater controller malfunction which
imfth235 C-SRO results in cold water irijection
6 imfth235 M Crew responds to fuel failure after cold water injection
All
7 imf cu0425 M Crew responds to a RWCU line break and scrams reactor
ior zdihs691 All before any area reaches max safe value.
null
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
(
Appendix D Scenario Outline Form ES-D-l
Facility: BFN Scenario Number: HLTS-3-4 Op-Test Number: HLT0610
(
Examiners: Operators:
Initial Conditions:
'\ ~A"
The unit is starting up following a refuel outage. Reactor power is at - )6/0. I RFP is uncoupled for
performance of turbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.
Turnover:
~
The 3Sl RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine
overspeed. Currently at step 5.76.8 of3-GOI-IOO-IA and at step 5.6.~ of 3-01-3 for warming 3B RFP.
t(&i
Event Malfunction Event Event
Number Number Type* Description
1 none R-ATC Crew will continue to pull rods to increase power and start
N-BOP warming up 2B RFP
R-SRO
2 irnfrd14a I-ATC Crew will respond to a RWM failure.
I-SRO SRO references Tech Specs.
TS-SRO
3 irnfrdOla C-ATC Crew will respond to a trip of 3A CRD pump.
C-SRO
4 irnf sw02a trip C-BOP Crew will respond to a RBCCW pump trip
7048FTC C-SRO Crew manually closes 70-48 after fails to auto close
5 ior zdihs468a C-BOP Crew will respond to feedwater controller malfunction which
irnfth235 C-SRO results in cold water injection
6 irnfth235 M Crew responds to fuel failure after cold water injection
All
7 irnf cu0425 M Crew responds to a RWCU line break and scrams reactor
ior zdihs69 1 All before any area reaches max safe value.
null
- (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
AppendixD Scenario Outline Form ES-D-l
Facility: BFN Scenario Nwnber: HLTS-3-4 Op-Test Nwnber: HLT06I0
Examiners: Operators:
Initial Conditions:
The unit is starting up following a refuel outage. Reactor power is at - 1%. "C" RFP is uncoupled for
performance of turbine overspeed testing. Currently at step 5.76.8 of3-GOI-IOO-IA.
Turnover:
The 3C RFP is uncoupled and the suction and discharge valves are tagged for performance of turbine
overspeed. Currently at step 5.76.8 of3-GOI-100-lA and at step 5.6.13 of3-0I-3 for warming 3B RFP.
Event Malfunction Event Event
Number Number Type* Description
I none R-ATC Crew will continue to pull rods to increase power and start
N-BOP warming up 2B RFP
R-SRO
2 irnfrd14a I-ATC Crew will respond to a RWM failure.
I-SRO SRO references Tech Specs.
TS-SRO
3 irnfrdOla C-ATC Crew will respond to a trip of 3A CRD pump.
C-SRO
4 irnf sw02a trip C-BOP Crew will respond to a RBCCW pump trip
7048FTC C-SRO Crew manually closes 70-48 after fails to auto close
5 ior zdihs468a C-BOP Crew will respond to feedwater controller malfunction which
irnfth235 C-SRO results in cold water injection
6 irnfth235 M Crew responds to fuel failure after cold water injection
All
7 irnf cu0425 M Crew responds to a RWCU line break and scrams reactor
ior zdihs69 1 All before any area reaches max safe value .
null
- (N)onnal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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SIMULATOR EVALUATION GUIDE
TITLE RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP, FEED
PUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE
BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE
WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION
LEVELS
REVISION o
DATE January 20, 2008
PROGRAM BFN Operator Training - HLT
PROVIDE COPY OF 3-GOI-100-1A TO EXAMINEES
PREPAREDBy:Q~ ~
/
REVIEWED BY: i..I2t.J-~
(Operations Training Manager or Designee)
~/d
/-~-t---
Date
CONCURRED D-RsJ) ~
(Operations Superif1t8i1dent or Designee)
Z-joo-=J
Date
VALIDATION : ----l......::.......lf--+-----:>l~- /
BY (Operation 0 : Required for Exam Scenarios Only)
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NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION DESCRIPTION DATE PAGES REVIEWED BY
NUMBER OF AFFECTED
REVISION
0 INITIAL 2/5/2008 All R.M. Spadoni
(
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I. Program: BFN Operator Training
II. Course: Examination Guide
III. Title : RWM FAILURE, CRD PUMP TRIP, RBCCW PUMP TRIP,
FEEDPUMP CONTROL FAILURE, FUEL FAILURE, RWCU LINE
BREAK WITH FAILURE TO ISOLATE, RAPIDLY DEPRESSURIZE
WITH 2 AREAS APPROACHING MAXIMUM SAFE RADIATION
LEVELS AND EMERGENCY DEPRESSURIZE AFTER 2 AREAS
REACH MAXIMUM SAFE RADIATION LEVELS
IV. Length of Scenario: 1 to 1 % hours
V. Examination Objectives:
A. Terminal Objective
1. Perform routine shift turnover, plant assessment and routine shift
operation in accordance with BFN procedures.
2. Given uncertain or degrading conditions, the operating crew will
use team skills to conduct proper diagnostics and make
conservative operational decisions to remove equipmenUunit from
operation. (SOER 94-1 and SOER 96-01)
3. Given abnormal conditions, the operating crew will place the unit in
a stabilized condition per normal, annunciator, abnormal, and
emergency procedures.
B. Enabling Objectives:
1. The operating crew will start and warm-up "B" RFP In accordance
with 01-6 section 5.7.
2. The operating crew will recognize and respond to a failure of RWM
in accordance with 3-01-85-5 and Tech. Specs.
3. The operating crew will recognize and respond to a CRD pump trip
in accordance with 3-AOI-85-3.
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4. The operating crew will recognize and respond to a RBCCW pump
trip in accordance with 3-AOI-70-1 .
5. The operating crew will recognize and respond to Feedpump
control failure in accordance with 3-AOI-3-1.
6. The operating crew will recognize and respond to a fuel failure in
accordance with ARPs and EOI-3.
7. The operating crew will recognize and respond to a break in the
RWCU system and rapidly depressurize the RPV.
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VI. References: The procedures used in the simulator are controlled copies and are
used in development and performance of simulator scenarios.
Scenarios are validated prior to use, and any procedure differences
will be corrected using the procedure revision level present in the
simulator. Any procedure differences noted during presentation will
be corrected in the same manner. As such, it is expected that the
references listed in this section need only contain the reference
material which is not available in the simulator.
VII. Training Materials: (If needed, otherwise disregard)
A. Calculator
B. Control Rod Insertion Sheet
C. Stopwatch
D. Hold Order I Caution tags
E. Annunciator window covers
F. Steam tables
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VIII . Console Operator Instructions
A. Scenario File Summary
1. File: bat HLTS3-4
MF/RF/lOR# Description
a.) ior zdihs691 null Fails 69-1 to close
b.) imf cu04 25 RWCU suction line break
c.) imf cu06
d.) bat 7048FTC fail 70-48 to not auto close
2. File: bat HLTS3-4-1
MF/RF/lOR# Description
a.) imf rm10g 10005:00 Fails rm14 upscale
b.) imf rm10e 1000 10:00 Fails rm09 upscale
3. File: bat 7048ftc
MF/RF/IOR# Description
a.) ior zlohs7048a[2] on Override red light on
b.) ior ypovfcv7048 fail-power_now Fails power to valve
c.) trg e1=bat 7048-1 Set trigger to 70-48 HS
d.) Imffw10c Fail 3C RFP auto trips
4. File: bat 7048-1
MF/RF/IOR# Description
a.) dor zlohs7048a[2] Delete Override on red
light
b.) dor ypovfcv7048 Restore power to valve
5. File: bat HLTS3-4-4
MF/RF/lOR# Description
a.) imf fw30c (none 0) 60 30 50 Run up and stop 3C RFP
controller in manual
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VIII. Console Operator Instructions
B. Console Operator Manipulations
ELAPTIME DESCRIPTION/ACTION
Sim. Setup Reset IC 9 -9% power, MOC
Sim. Setup Manual Place Hold Order Tags on A RFP
suction and discharge valves
Sim . Setup Manual Ensure RWM is latched with no Insert
or Withdrawal blocks and comp/prog
lights reset, rod group 39 - 06-47
selected
Sim. Setup Manual Verify 3A RFP suct & disch valve lights
extinguished. If not, bat 3arfptag
Sim Setup <Shift F1> Set 70-48 to not close on low pressure
bat7048ftc and fail 3C RFP auto trips
After RFP warmed and F3 Fails RWM (imf rd14a)
When requested by
Examiner
ROLE PLAY: If asked, have not performed a startup with RWM
bypassed within last calendar quarter
ROLE PLAY: If requested to verify open 3-1-155 and 3-1-156, report that they
are open
After Tech Specs imf rd01a Trips 3A CRD Pump.
addressed for RWM
ROLE PLAY: When sent to investigate the trip of 3A CRD Pump, report that
the breaker is tripped on over-current.
After the crew starts 38
CRD pump and with Lead F8 Trips A R8CCW pump
Examiners concurrence: (imf sw02a)
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VIII. Console Operator Instructions (continued)
B. Console Operator Manipulations
If requested to align spare Aligns spare RBCCW pump to Unit 3
RBCCW pump to Unit 3 F9 (mrf sw02 align)
Wait 3 minutes
If requested to reset local F12 mrf an01e reset
RWCU panel alarms
After spare RBCCW pump <Shift F3> Fails RFP governor in raise direction in
aligned and RWCU Bat HLTS3-4-4 manual for 30 sec
returned to service
Two (2) Minutes after F6 fuel failure
Feedpump governor (imf th23 5 15:00)
problem
When directed by examiner F7 RWCU line break with failure to isolate
(bat HLTS3-4)
ROLE PLAY: If requested to attempt to close 69-1 locally at the breaker, wait
5 minutes and report it will not close
ROLE PLAY: If requested to check Aux Inst rm, report 835 A&C and 835
B&D reading 90 deg F and fairly steady
After attempts to close 69-1 F10 Causes Rad monitors to reach max
are made (bat HLTS3-4-1)
Terminate the scenario when the following conditions are satisfied or when requested
by Chief Examiner:
1. Reactor Water level restored between +2 to +51"
2. RPV rapidly depressurized
3. RPV emergency depressurized
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IX. Scenario Summary
The plant is at approximately 9% power withdrawing control rods to open
sufficient bypass valves to roll the main turbine. "B" RFP needs to be started
and warmed in preparation for water level control.
During the control rod withdrawal, the RWM will experience a program fault
which will block rod movement. Tech. Specs will be addressed and control rod
withdrawal will continue when a second licensed operator is present to ensure
withdrawal is in accordance with the BPWS.
A CRD pump will trip causing the crew to start the standby CRD pump.
An RBCCW pump will trip causing RWCU to be secured and the spare RBCCW
pump aligned to Unit 3 and the RWCU system returned to service.
The In-service RFP will experience a governor fault causing it to inject cold water
into the RPV causing a power spike and some fuel failure. Later the RWCU
system develops and leak and fails to isolate requiring entry into EOI-3 and
subsequent rapid depressurization due to 2 areas approaching max safe
radiation levels.
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x. Information to Evaluators:
A. Ensure recorders are inking and recording and ICS is active and updating.
B. Assign Crew Positions based on the required rotation.
1. SRO
2. ATC
3. BOP
C. Conduct a shift turnover with the Shift Manager and provide the Shift
Manager with a copy of the Shift Turnover.
D. Direct the shift crew to review the control board and take note of present
conditions, alarms, etc.
E. Terminate the scenario when the following conditions are satisfied are at
the request of the floor/lead instructor/evaluator.
1. Reactor water level restored at +2" to +51"
2. RPV rapidly depressurized
3. RPV emergency depressurized when 2 areas are above max safe
values.
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XI. Simulator Event Guide
EVENT 1: Warming up second RFP
TIME POSITION EXPECTED ACTIONS
SRO irects warmin u B RFP in accordance with 3-01-
BOP Warms up "B" RFP utilizing section 5.6 of 3-01-3.
3-ARP-9-6C window 32
A. VERIFY reactor Feedpump flow on Panel 3-9-6.
B. REFER TO 3-01-3, Section 8.7.
C. IF annunciation is caused by RFW Control System
malfunction, THEN REQUEST assistance from Site
Engineering and IMs.
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XI. Simulator Event Guide
EVENT 1: Warming up second RFP
TIME POSITION EXPECTED ACTIONS
BOP Place in auto and verify open RFP min flow valve 3-FCV-
3-13
Place 38 start/local enable 3-HS-46-138A in start and
observe RFP accelerates to 600 rpm
Verify no abnormal rubbing or vibration is observed
Raise speed to -1000 rpm using 3-HS-46-9A
Place TG motor 3-HS-3-127A in Auto
Depress 38 trip 3-HS-3-127A and verify HP and LP stop
valves close
Verify TG auto engages or RFP rolling on min flow
Depress 38 trip reset 3-HS-3-150A and verify blue light
extinguishes and HP and LP stop valves open
Place 38 start/local enable 3-HS-46-138A in start and
observe RFPT speed increases to - 600 rpm
(
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XI: Simulator Event Guide
EVENT 2: RWM FAILURE
TIME POSITION EXPECTED ACTIONS
ATC Announces "RWM ROD BLOCK" 3-XA-55-5B window
35 alarm and refers to ARP.
A. CHECK RWM panel for error.
B. CHECK rod position and COMPARE it with Control Rod
Movement Data Sheet (3-SI-4.3.B.1.a) (3-SR-3.1.3.5(A)).
C. IF RWM becomes inop, THEN REFER TO 3-01-85 and
Tech Spec 3.1, 3.3, Table 3.3.2.1-1.
SRO Directs ATC to bass RWM er 01-85
Refers to T.S. 3.1 3.3 table 3.3.2.1-1
Contacts Rx Engineer
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XI: Simulator Event Guide
EVENT 2: RWM FAILURE
TIME POSITION EXPECTED ACTIONS
ATC -01-85 section 8.1
[1] VERIFY the following initial conditions are satisfied :
- The Shift Manager/Reactor Engineer has directed the Rod
Worth Minimizer to be bypassed .
- A second licensed operator is available to verify control
rod position.
[2] REVIEW all Precautions and Limitations in Section
3.4.
[3] PLACE RWM SWITCH PANEL, 3-XS-85-9025, in
BYPASS.
[4] CHECK the Manual Bypass light is illuminated .
[5] CHECK all other indications on the Rod Worth Minimizer
Operator's Panel are extinguished.
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XI: Simulator Event Guide
EVENT 2: RWM FAILURE
TIME POSITION EXPECTED ACTIONS
ATC [6] CHECK the Blue Rod Out Permit light above 3-HS-85-48
is illuminated.
[7] RESET CONTROL ROD WITHDRAWAL BLOCK
annunciator (3-XA-55-5A, Window 7).
SRO Determines T.S. 3.3.2.1 condition C.2.1-1 & 2.2 applies.
Greater than 12 rods withdrawn and 2nd person to verify
compliance with BPWS.
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XI. Simulator Event Guide
EVENT 3: CRD PUMP 3A TRIP
TIME POSITION EXPECTED ACTIONS
ATC Recognize annunciator MOTOR TRIPOUT 3-ARP-9-8c (W
33) is in alarm.
Acknowledges and resets MOTOR TRIPOUT annunciator.
4.1 Immediate Actions
[1] IF operating CRD PUMP has TRIPPED AND
STANDBY CRD PUMP is AVAILABLE, THEN
(Otherwise N/A)
PERFORM the following at Panel 3-9-5:
[1.1] PLACE CRD SYSTEM FLOW CONTROL, 3-FIC-
85-11 , in MAN at minimum setting .
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XI. Simulator Event Guide
EVENT 3: CRD PUMP 3A TRIP
TIME POSITION EXPECTED ACTIONS
ATC [1.2] START associated standby CRD Pump using one of
the following:
- CRD PUMP 3B, using 3-HS-85-2A
- CRD Pump 3A, using 3-HS-85-1A
[1.3] ADJUST CRD SYSTEM FLOW CONTROL, 3-FIC-
85-11, to establish the following conditions:
CRD CLG WTR HDR DP, 3-PDI-85-18A,
approximately 20 psid.
CRD SYSTEM FLOW CONTROL, 3-FIC-85-11,
between 40 and 65 gpm.
[1.4] BALANCE CRD SYSTEM FLOW CONTROL, 3-FIC-
85-11, and PLACE in AUTO or BALANCE.
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
BOP Responds to loss of RBCCW pump 3A trip and
attempts to restart 3A RBCCW pump and reports it
failed to start.
3-ARP-9-4C window 12
A. VERIFY 3-FCV-70-48 CLOSING/CLOSED.
Reports that the 3-FCV-70-48 sectionalizing valve failed
to close.
B. VERIFY RBCCW pumps A and B in service.
C. VERIFY RBCCW surge tank low level alarm is reset.
D. DISPATCH personnel to check the following:
o RBCCW surge tank level locally.
o RBCCW pumps for proper operation.
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
BOP Immediate Actions
[1] IF RBCCW Pump(s) has tripped, THEN: ATTEMPT to
restart tripped pump(s).
[2] IF RBCCW Pump(s) cannot be restarted, THEN:
(Otherwise N/A) SHUT DOWN RWCU System Pumps.
(Reference TRM 3.4.1)
Secures RWCU pumps and reports that the 3-FCV-70-48
sectionalizing valve failed to close.
N/A IF Reactor is at power AND Drywell Cooling cannot be
immediately restored, AND core flow is above 60%,THEN:
(Otherwise N/A):
N/A REDUCE core flow to between 50-60% .
N/A MANUALLY SCRAM the Reactor and PLACE Mode Switch to
SHUTDOWN. REFER TO 3-AOI-100-1.
N/A SHUT DOWN both Recirc Pumps.
N/A o DEPRESS RECIRC DRIVE 3A SHUTDOWN, 3-HS-96-19.
N/A o DEPRESS RECIRC DRIVE 3B SHUTDOWN, 3-HS-96-20.
N/A INITIATE a 90°F/HR cooldown rate. REFER TO 3-AOI-100-
1.
N/A IF any EOI entry condition is met, THEN: (Otherwise N/A)
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
[3] IF unable to restart a tripped pump, THEN:
Otherwise N/A PLACE Spare RBCCW Pump in service.
REFER TO 3-01-70.
REQUEST Unit 1 to place the spare RBCCW pump in
service to support Unit 3 operation. (REFER TO 1-01-70).
Contacted U1 Operator to place the spare pump in
service to Unit 3.
ack to 3-AOI-70-1
[4] IF RBCCW flow was restored to two pump operation
THEN: (Otherwise N/A)
[4.1] REOPEN RBCCW SECTIONALIZING VLV, 3--HS--70-
48A. After Spare RBCCW pump placed in service,
(conditional, SRO may not direct valve to be opened
after failure to auto close and if so, will NOT place
RWCU in service.)
[4.2] ESTORE the RWCU s stem to 0
iTO 3-01-69J.
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
BOP -01-69 section 5.1 8
RWCU Pump Startup
[1] REVIEW precautions and limitations in Section 3.0.
[2] VERIFY RWCU prestartup requirements in Section 4.0
have been completed.
[3] VERIFY RESET the RWCU Group 3 isolation using PCIS
DIV I RESET, 3-HS-64-16A-S32 and PCIS DIV II RESET, 3-
HS-64-16A-S33 at Panel 3-9-4.
[4] IF a condition exists which could have caused 3-FCV-069-
0094 to isolate, THEN VERIFY OPEN 3-FCV-069-0094,
RWCU SYSTEM APP R FLOW CONTROL VLV, locally. (Unit
3 Rx Bldg, EI 593' R-17 S-Line).
[5] VERIFY RWCU HEAT EXCHANGERS RBCCW FLOW
CONTROL, 3-TIC-069-0010A is in MANUAL, and FULL
OPEN demand is on 3-TCV-70-49. (REFER TO Illustration
5)[BFPER 03-000348-000]
[6] VERIFY CLOSED the following:
o RWCU BLOWDOWN PRESS CONTROL VLV, using 3-HC-
69-15
o RWCU BLOWDOWN TO MAIN CNDR, using 3-HS-69-16A
o RWCU BLOWDOWN TO RADWASTE, using 3-HS-69-17A
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
[7] IF a Caution Order is present on the control room hand
switch for RWCU PUMP 3A(3B) informing operator that 3-
SHV-070-0573A(0573B) is closed, THEN PERFORM the
following:
[7.1] OPEN 3-SHV-070-0573A(0573B), RWCU PUMP A(B)
CLG WTR INLET.
[7.2] REMOVE Caution Order from the control room hand
switch for RWCU PUMP 3A(3B) informing operator that 3-
SHV-070-0573A(0573B) is CLOSED.
[8] NOTIFY chemistry RWCU is being placed in service
and to check the durability monitor.
[9] VERIFY OPEN the following valves:
- RWCU DEMIN BYPASS VALVE, 3-FCV-69-8
[10] OPEN 3-FCV-069-0012 by one of the two methods
described below.
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
BOP * PLACE 3-HS-69-12A in the OPEN position, THEN
RETURN 3-HS-69-12A to the NORM position when
intermediate position (red and green light) is indicated.
- PLACE 3-HS-69-12A in the OPEN position, THEN
RETURN 3-HS-69-12A to the NORM position when
FULL OPEN position (red light only) is indicated.
N/A [11] PLACE seal purge in operation to pump(s) to be
placed in service. REFER TO Section 8.2.
[12] START RWCU RECIRC PUMP 3A(3B) using control
switch 3-HS-69-4A(4B)-A, and A RISE flow, using
RWCU RETURN ISOLATION VALVE, 3-HS-69-12A, to
prevent low flow trip.
[13] IF two pump operation is desired, THEN START
the second RWCU RECIRC PUMP 3B(3A) using control
switch 3-HS-69-4B(4A)-A, and A RISE flow using RWCU
RETURN ISOLATION VALVE, 3-HS-69-12A, to prevent
low flow trip.
[14] IF the RWCU filter-demineralizers is to be placed
in service, THEN REFER TO Section 6.2.
(all local actions except Operator closing 3-FCV-69-8
valve as AUO rolls demins in service)
(
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XI. Simulator Event Guide
EVENT 4: LOSS OF 3A RBCCW pump
TIME POSITION EXPECTED ACTIONS
3-ARP-9-4B window 24
A. DISPATCH personnel to local Panel 25-3, to determine
cause of alarm.
B. IF alarm is valid, THEN REFER TO 3-ARP-25-3 for
appropriate operator action.
C. IF this alarm meets the requirements AND the Shift Manager
desires the annunciator to be disabled, THEN REFER TO OPDP-
4.
BOP Coordinates with AUO to roll demins in service
SRO Dispatches personnel to investigate pump loss
May contact Rx Engineer about heat balance
Contacts Chemistry
Reviews TRM LCO 3.4.1 and verify it does not apply
whether RWCU is placed in service or not.
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XI. Simulator Event Guide
EVENT 5: FEEDWATER CONTROLLER FAILURE
TIME POSITION EXPECTED ACTIONS
ATC Observes period rise by meter or annunciator and
checks for cause of reactivity addition
ATC Ranges IRMs as necessary to prevent a reactor scram
BOP Attempts to take control of A RFP by adjusting 3-HS-46-
8C and reports that "C" RFP cannot be controlled
IF Feedwater Control System has failed, THEN
PERFORM the following:
PLACE individual RFPT Speed Control Raise/Lower
switches in MANUAL GOVERNOR (depressed position
with amber light illuminated).
ADJUST RFP Discharge flows with RFPT Speed Control
Raise/Lower switches as necessary to maintain level.
IF level continues to rise, THEN TRIP a RFP, as
necessary.
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XI. Simulator Event Guide
EVENT 5: FEEDWATER CONTROLLER FAILURE
TIME POSITION EXPECTED ACTIONS
SRO Directs t~ P and using "B" RFP for RPV level
control ~
BOP Trips "C" RFP by depressing 3-HS3-125C and raises "B"
RFP speed by using 3-HS-46-9B (Critical Task)
BOP Opens "B" RFP discharge valve 3-HS-3-12B when "B"
RFP discharge pressure is within 250 Ibs of reactor
pressure.
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XI. Simulator Event Guide
EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION
POSITION EXPECTED ACTIONS
BOP Announces "TURBINE BUILDING HIGH RADIATION"
3-ARP-9-3A window 27
DETERMINE area with high radiation level on Panel 3-9-11.
(Alarm on Panel 3-9-11 will automatically reset if radiation
level lowers below setpoint.)
IF the TSC is NOT manned, THEN USE public address system
to evacuate area where high airborne conditions exist.
N/A IF the TSC is manned, THEN REQUEST the TSC to evacuate
non-essential personnel from affected areas.
NOTIFY RADCON.
MONITOR other parameters providing input to this annunciator
frequently as these parameters will be masked from alarming
while this alarm is sealed in.
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XI. Simulator Event Guide
EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION
POSITION EXPECTED ACTIONS
BOP Announces "RX BLDG HIGH RADIATION" and determines
which area and evacuates that area. North and South RWCU
area.
DETERMINE area with high radiation level on Panel 3-9-11.
(Alarm on Panel 3-9-11 will automatically reset if radiation
N/A level lowers below setpoint.)
IF the alarm is from the HPCI Room while Flow testing is being
performed, THEN REQUEST personnel at the HPCI Quad to
validate conditions
NOTIFY RADCON.
IF the TSC is NOT manned and a "VALID" radiological
condition exists., THEN USE public address system to
evacuate area where high airborne conditions exist
MONITOR other parameters providing input to this
annunciator frequently as these parameters will be masked
from alarming while this alarm is sealed in.
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XI. Simulator Event Guide
EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION
POSITION EXPECTED ACTIONS
BOP Announces "OFF-GAS ANNUAL RELEASE LIMIT
EXCEEDED" 3-ARP-9-4C window 27
To determine if the Off Gas Annual Release Rate Limit is
exceeded, PERFORM the following :
VERIFY alarm condition on the following:
- OFFGAS PRETREATMENT RADIATION recorder, 3-RR-90-157
on Panel 3-9-2
- OG PRETREATMENT RAD MON RTMR radiation monitor,
3-RM-90-157 on Panel 3-9-10
CHECK off-gas flow and monitor sample flow normal.
NOTIFY RADCON.
BOP/SRO Notifies Chemistry to perform analysis and Radcon
SRO Declares a NOUE on a valid OG pretreatment rad alarm.
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XI. Simulator Event Guide
EVENT 6: FUEL FAILURE DUE TO COLD WATER INJECTION
POSITION EXPECTED ACTIONS
BOP REQUEST Chemistry perform radiochemical analysis to
determine source.
N/A WITH OPS MGT and Shift Manager's permission, PLACE
charcoal beds in parallel with another unit. REFER TO 3-01-
66.
IF fuel damage is suspected, THEN REFER TO 3-SI-4.6.B.5 (3-
SR-3.4.6.1) for dose equivalent iodine -131 determination.
REFER TO O-SI-4.8.B.1.a.1 and 3-51-4.6.B.6 (3-SR-3.4.6.1-a)
for ODCM compliance and to determine if power level
reduction is required.
IF directed by Shift Manager or Unit Supervisor, THEN
REDUCE reactor power to maintain off-gas radiation within
ODCM limits.
REFER TO EPIP-1.
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XI. Simulator Event Guide
EVENT?: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
BOP Reports on RWCU leak detection alarms 3-ARP-9-3D window
17
N/A
IF this alarm is received in conjunction with RWCU ISOL
LOGIC CHANNEL A TEMP HIGH [3-XA-55-5B, window 32]
and RWCU ISOL LOGIC CHANNEL B TEMP HIGH [3-XA-55-
5B, window 33], THEN EXIT this procedure and GO TO 3-
ARP-9-5B. Otherwise,
CHECK RWCU Leak Detection System temperatures on Panel
3-9-21 and Panels 9-83,9-84,9-85 and 9-86 in the auxiliary
instrument room. . The 834 and 835 Temp Loops are also displayed
on ICS under 'HPTURB' for Main Steam Tunnel and 'RWCU' for the
Pipe Trench.
IF high temperature is indicated on TS69-290, E, F, G or H or TIS
69-835A, B, C, or 0, THEN ENTER 3-EOI-3 Flowchart.
CHECK Rx Bldg. RWCU system ARMs, 3-RI-90-13A and 14A on
Panel 3-9-11, and Rx Zone Exhaust Rad Monitor, 3-RR-90-142 on
Panel 3-9-2.
DISPATCH personnel to investigate the affected area.
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XI. Simulator Event Guide
EVENT?: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
ATC Recognizes that 69-1 failed to isolate and attempts to
manually close
Crew Directs outside personnel to attempt to close 69-1 locally at
the breaker.
SRO Directs Rx Scram before any area temp is above the
maximum safe operating temperature.
ATC Scrams reactor and provides scram report
SRO Directs ATC to erform actions of 3-AOI-100-1
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
SRO/BOP Continue to monitor and trend secondary area temps and radiation
levels
BOP Reports that 2 areas are approaching maximum safe radiation
levels
SRO Directs rapid depressurization ot the RPV using BPVs
BOP Opens all BPVs using the Jack
BOP/ATC Coordinate level control during depressurization to prevent flooding
the RPV
BOP Determines that 2 areas are above max safe radiation values
SRO Determine~ncy Depressurization is Required and
entersC2 ~
Directs BOP to open all ADS valves (Critical Task)
BOP Opens all ADS valves (Critical Task)
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
Reports Main Steam Line Radiation High - High
3-ARP-9-3A window 27
A. VERIFY the alarm on 2-RM-90-136and 2-RM-90-137 on
Panel 2-9-10.
B. CONFIRM main steam line radiation level on recorder 2-RR-90-
135, Panel 2-9-2.
C. IF alarm is valid and Reactor Scram has not occurred, THEN
PERFORM the following:
1. IF core flow is above 60% THEN LOWER core flow to between
50-60% ..
2. MANUALLY SCRAM the Reactor.
3. REFER to 2-AOI-100-1 .
D. IF plant conditions DO NOT require execution of 2-C-5, THEN
VERIFY the MSIV's closed.
E. NOTIFY RADCON.
F. VERIFY actions of 2-ARP-9-3A Window 7 have been completed.
G. IF Technical Specification limits are exceeded, THEN
REFER TO EPIP-1.
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
3-ARP-9-3A window 7
A. CHECK following radiation recorders:
1. MAIN STEAM LINE RADIATION monitor, 2-RR-90-135 on
Panel 2-9-2.
2. OFFGAS PRETREATMENT RADIATION, 2-RR-90-157 on
Panel 2-9-2.
3. OFFGAS RADIATION, 2-RR-90-160 on Panel 2-9-2.
4. OFFGAS POST-TREATMENT RADIATION, 2-RR-90-265 on
Panel 2-9-2 .
5. STACK GAS RADIATION, O-RR-90-147 on Panel 1-9-2.
B. NOTIFY RADCON.
C. [NRC/C) NOTIFY Chemistry to perform radiochemical analysis of
primary coolant. [NCO 940247001]
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
SRO Directs Rx water level be maintained +2 - +51 using
Condensate, Core Spray, or RHR
6A Condensat
1. VERIFY CLOSED the following Feedwater heater return
valves :
3-FCV-3-71, HP HTR 3A1 LONG CYCLE TO CNDR
3-FCV-3-72, HP HTR 3B1 LONG CYCLE TO CNDR
3-FCV-3-73, HP HTR 3C1 LONG CYCLE TO CNDR.
2. VERIFY CLOSED the following RFP discharge valves:
3-FCV-3-19, RFP 3A DISCHARGE VALVE
3-FCV-3-12, RFP 3B DISCHARGE VALVE
3-FCV-3-5, RFP 3C DISCHARGE VALVE.
3. VERIFY OPEN the following drain cooler inlet valves:
3-FCV-2-72, DRAIN COOLER 3A5 CNDS INLET ISOL VLV
3-FCV-2-84, DRAIN COOLER 3B5 CNDS INLET ISOL VLV
3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
4. VERIFY OPEN the following heater outlet valves:
3-FCV-2-124, LP HEATER 3A3 CNDS OUTL ISOL VLV
3-FCV-2-125, LP HEATER 3B3 CNDS OUTL ISOL VLV
3-FCV-2-126, LP HEATER 3C3 CNDS OUTL ISOL VLV.
5. VERIFY OPEN the following heater isolation valves:
3-FCV-3-38, HP HTR 3A2 FW INLET ISOL VLV
3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VLV
3-FCV-3-24, HP HTR 3C2 FW INLET ISOL VLV
3-FCV-3-75, HP HTR 3A1 FW OUTLET ISOL VLV
3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VLV
3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
6. VERIFY OPEN the following RFP suction valves:
3-FCV-2-83, RFP 3A SUCTION VALVE
3-FCV-2-95, RFP 3B SUCTION VALVE
3-FCV-2-108, RFP 3C SUCTION VALVE.
7. VERIFY at least one condensate pump running .
8. VERIFY at least one condensate booster pump running.
9. ADJUST 3-L1C-3-53, RFW START-UP LEVEL CONTROL, to
control injection (Panel 3-9-5).
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
1. VERIFY OPEN the following valves:
3-FCV-75-2, CORE SPRAY PUMP 3A SUPPR POOL SUCT VLV
3-FCV-75-11, CORE SPRAY PUMP 3C SUPPR POOL SUCTVLV
3-FCV-75-23, CORE SPRAY SYS I OUTBD INJECT VALVE.
2. VERIFY CLOSED 3-FCV-75-22, CORE SPRAY SYS I TEST
VALVE.
3. VERIFY CS Pump 3A and/or 3C RUNNING .
4. WHEN ... RPV pressure is below 450 psig, THEN ...
THROTTLE 3-FCV-75-25, CORE SPRAY SYS IINBD INJECT
VALVE, as necessary to control injection at or below 4000 gpm
per pump.
5. MONITOR Core Spray Pump NPSH using Attachment 1.
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
1. IF ..... Adequate core cooling is assured AND It becomes
necessary to bypass LPCllnjection Valve Timers to control injection,
THEN ... EXECUTE EOI Appendix 16F concurrently with this
procedure.
2. VERIFY OPEN 3-FCV-74-1, RHR PUMP 3A SUPPR POOL SUCT
VLV.
3. VERIFY OPEN 3-FCV-74-12, RHR PUMP 3C SUPPR POOL
SUCTVLV.
4. VERIFY CLOSED the following valves:
3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV
3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV
3-FCV-74-57, RHR SYS I SUPPR CHBRIPOOL ISOL VLV
3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE
3-FCV-74-59, RHR SYS I SUPPR POOL CLGfTEST VLV.
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XI. Simulator Event Guide
EVENT 7: RWCU LINE SUCTION BREAK
POSITION EXPECTED ACTIONS
5. VERIFY RHR Pump 3A and/or 3C running.
6. WHEN ... RPV pressure is below 450 psig, THEN ... VERIFY
OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE.
7. IF ..... RPV pressure is below 230 psig, THEN ... VERIFY
CLOSED 3-FCV-68-79, RECIRC PUMP 3B DISCHARGE VALVE.
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XII. Crew Critical Tasks
TASKS SAT/UNSAT
1. Trips "C" RFP prior to reaching Main
Steam Lines (120" on 3-55 level
instrument)
2. Emergency Depressurize when 2 areas
reach maximum safe values. (Within 5
minutes)
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XIII. Scenario Verification Data
EVENT TASK NUMBER KIA RO SR CONTROL
0 MANIPULATION
1. Warm up RFP 259001 3.9 3.7
A4.02
2. RWM Failure 201006 3.2 3.4
A4.01
3. CRD Pump Trip 201001 3.2 3.3
A2.01
4. RBCCW Pump 295018
Trip AK3.03 3.1 3.4
AA1.01 3.3 3.4
AK3.04 3.3 3.3
5. RFP Governor 259001 A2.07 3.7 3.8
failure 295008 AA1.08 3.5 3.5
6. Fuel Failure 295014 AA1.05 3.9 3.9
AA1.07 4.0 4.1
7. RWCU Line Break 295033 EA1.05 3.9 4.0
EK3.01 3.3 3.5
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SCENARIO REVIEW CHECKLIST
SCENARIO NUMBER HLTS-3-4
7 Total Malfunctions Inserted; List: (5-8)
1) RWM Failure
2) CRD Pump trip
3) RFP controller failure
4) Fuel Damage
5) RWCU line break
6) "A" RBCCW pump trip
7) Failure of 69-1 to close
8) Failure of RFPs to trip on Hi level
_1_ Malfunctions That Occur After EOI Entry; List: (1-2)
1) RWCU line Break
..L Abnormal Events; List: (2-4)
1) RFP control failure
2) CRD Pump trip
3) RBCCW pump trip
_1_ Major Transients; List: (1-2)
1) RWCU line break (small LOCA)
~ EOls used; List: (1-2)
1) EOI-1
2) EOI-3
L EOI Contingencies Used; List: (0-2)
1) C2
63 Run Time (minutes)
52 EOI Run Time (minutes); 83 % of Scenario EOI Run Time
L Crew Critical Tasks (2-3)
Yes Technical Specifications Exercised (yes/no)
(
SHIFT TURNOVER SHEET
Equipment Out of Service/LCOs 3A RFP is uncoupled and awaiting overspeed testing.
Suction, Discharge and Minimum Flow valves are tagged.
Operations/Maintenance For the Shift: Continue with reactor startup at step 5.69.8 of
3-GOI-100-1A. Continue with warm-up of uB" RFP per 01-3 at step 5.6.[181. Thrust
bearing/ Overspeed/ Stop Valve and Control Valve tests are complete for "B" RFP.
Place 3B RFP 100 psig below reactor pressure.
Unusual Conditions/Problem Areas: Power System Alert in effect for the next 36
Hours.
(