ML081370192
| ML081370192 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/08/2008 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-259/08-301 50-259/08-301 | |
| Download: ML081370192 (103) | |
See also: IR 05000259/2008301
Text
Draft Submittal
(Pink Paper)
SIMULATOR SCENARIOS
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Appendix D Scenario Outline Form ES-D-l
FINAL
Facility: BFN Scenario Number: HLTS-3-1 Op-Test Number: HLT0610
Examiners: Operators: _
Initial Conditions:
Unit 3 has been operating for 192 days. Unit 2 has been operating for 56 days. Unit 1 has been
operating for 274 days. 3ED Diesel Generator is tagged for water jacket leakage repair. Day 2
of the LCO. Expected to be returned to service this shift. Fuelleakers on U3 are currently at
RFI 60,000. Thunderstorms are passing through the region, but no watches are in effect for the
immediate area. The 3C RFP was oscillating approximating 30 RPM during last shift, but is
now working properly and being monitored. The 3C RFP Pump is operating in automatic
in order to collect data for the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A trouble shooting plan is being developed.
Turnover:
Support scheduled maintenance and testing activities. Alternate Stator Cooling Water Pumps per 3-01-
35A, Sect 6.4 per scheduled OPA.
Event Malfunction Event Event
Number Number Type* Description
1a mrf anO1b reset N-ATC The crew will alternate Stator Cooling Water Pumps using 3-
N-BOP 01-35A.
N-SRO
1b N/A TS-SRO The US will respond to a HPCI Rupture Diaphragm pressure
switch PS-73-20B failure.
2 imffw05b 100 R-ATC The crew will respond to a 3B HP FW heater isolation using
8:00 C-BOP 3-AOI-6-1.
R-SRO The crew will reduce power to --91% using a recirc flow
reduction.
The crew will isolate feedwater to the 3B FW heater string.
The crew will further reduce power to <79% using a recirc
flow reduction.
3 imfsw10a C-ATC The crew will respond to a trip of the 3A Fuel Pool Cooling
C-SRO pump using 3-AOI-78-1.
TS-SRO
4 imffw13b C-ATC The crew will respond to a trip of the 3B Reactor Feedwater
C-BOP Pump (RFP) using 3-AOI-3-1 and 3-01-3.
C-SRO
5 bat rfpactrip M The crew will respond to a total loss of feedwater and reactor
All scram.
6 bat M The crew will respond to a RCIC steam leak into secondary
HLTS3-1 All containment and a HPCI 120V AC power failure.
The crew will anticipate Emergency Depressurization or
perform Emergency Depressurization due to secondary
containment high radiation.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor
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SIMULATOR EXERCISE GUIDE
TITLE SLOW LOSS OF HP FEEDWATER HEATING ON B STRING, 3A FPC PUMP TRIP, RFP
TRIP, LOSS OF ALL FEEDWATER, UNISOLABLE RCIC STEAM LINE BREAK,
2 OR MORE AREA RAD LEVELS ABOVE MAX SAFE.
~EVISION o
DATE January 19, 2008
P'ROGRAM BFN Hot License Training
PREPARED BY: --Jooc~---T-----::tI'-------_\ Zy 65
rrate
0
REVIEWED BY: _~~
(0 rations Training Manager or Designee)
\d 7j f
Date
CONCURRED:
~... 1*b~
-===
(Operations Superintendent or Designee) (Required for Exam Scenarios only) Date
'\
)
VALIDATION / ....
BY: (R '-, uired for Exam Scenarios only)
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NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION DESCRIPTION DATE PAGES REVIEWED
NUMBER I OF CHANGES I I AFFECTED I BY
0 Initial 01/19/2008 All csf
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I. PROGRAM: BFN Licensed Operator Requalification Training
II. COURSE: License Requalification Training (Simulator Exercise Guide)
III. TITLE: SLOW LOSS OF HP FEEDWATER HEATING ON B STRING, FPC PUMP TRIP, RFP
TRIP, LOSS OF ALL FEEDWATER, UNISOLABLE RCIC STEAM LINE BREAK,
2 OR MORE AREA RAD LEVELS ABOVE MAX SAFE.
IV. LENGHT OF LESSON: 1 % to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
V. Training Objectives
A. Terminal Objectives
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)
3. Given abnormal conditions, the operating crew will place the unit in a stabilized condition
per normal, annunciator, abnormal, and emergency procedures.
4. Use step text procedural compliance.
B. Enabling Objectives
1. The operating crew will alternate stator coolant pumps as directed by 3-01-35A
section 6.4.
2. The operating crew will recognize and respond to a high pressure heater string
isolation as directed by 3-ARP-9-6A and 3-AOI-6-1A.
3. The operating crew will recognize and respond to a spurious FPC system trip and
will place the 3B pump I/S in accordance with 3-ARP-94 win 1 and 3-AOI-78-1.
4. The operating crew will recognize and respond to a RFP Trip with 3-AOI-3-1.
5. The operating crew will recognize and respond to a loss of feedwater event and
RxSCRAM.
6. The operating crew will recognize and respond to unisolable RCIC steam line break, 2 or
more area rad levels above max safe requiring Emergency Depressurization.
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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.
A. SOER 94-01
B. SOER 96-01
VII. Training Materials:
A. Calculator (If required)
B. Control Rod Insertion Sheet (If required)
C. Stopwatch (If required)
D. Hold Order / Caution tags (If required)
E. Annunciator window covers (If required)
F. Steam tables (If required)
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VIII. Console Operator Instructions
A. Scenario File Summary
1. File: bat HLTS3-1
MF/RF/IOR# Description
a) ior zlofcv712[2] on Fails 71-2 and 71-3 open
b) ior zlofcv713[2] on
c) ior zlohs712a[2] on
d) ior zlohs713a[2] on
e) ior ypovfcv712 fail_now
f) ior ypovfcv713 fail_now
g) imf rm10h (e1 :25) 30 HCU-East rad ~ 30 mr/hr
h) imf rm10j (e1 :25) 25 HCU-West rad ~ 25 mr/hr
i) imf rm10p (e1 2:00) 50 CS/RCIC area rad 50mr/hr
j) imf DG01D D DIG Fails to Start
k) imf DG02D D DIG Trip Protective Relay Operation
I) ior zI03hS2113ed10a[1] OFF 1836 Green Light Off
m) mrf DG01 D open Opens logic breaker
n) imf rp08a Auto scram failure
0) imf rp08b Auto scram failure
p) imf rp14b Bypass valve failure
q) ior zdihs47130b null BPV jack null
2. File: bat HLTS3-1-1
MF/RF/IOR# Description
a) mmf rm10p 1000 6:00 RCIC rad to max in 6 mins.
b) mmf rm10h 1000 13:00 HCU-West to Max in 13 mins.
c) mmf rm10j 1000 14:00 HCU- East to Max in 14 mins.
d) imf rc09 100 7:00 RCIC steam leak
e) imf ad01b 0 MSRV 1-19 fails closed
f) imf ad01f 0 MSRV 1-34 fails closed
g) Imf ad03b MSRV 1-19 Stuck Closed
h) Imf ad03f MSRV 1-34 Stuck Closed
3. File: bat HLTS3-1-2
MF/RF/IOR# Description
i) imffw08b 30 RFP 3B Discharge Check Valve Sticks
j) imf fw13b (none, :10) 3B RFPT trips on Thrust Brng Wear
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IX. Console Operator Instructions
8. Console Operators Manipulations
ELAP TIME PFK DESCRIPTION/ACTION
Sim. Setup rst 28 1000/0 power MOC
Sim. Setup restorepref Establishes Preference Keys
HLTS3-1
Sim. Setup setup Verify Preference Keys
Sim. Setup esc Clears Popup Window
Sim. Setup F3 trg e1 MODESW Assigns trigger
Sim. Setup F4 bat HLTS3-1 see file summary
Sim. Setup manual Tag D D/G with Hold notices
ROLE PLAY:
- 3-PI-035-0064 is reading 47 psig.
- 3-HS-035-0040 selected for "A-RES" Stator Coolant pump on panel 25-114.
When requested to reset local Stator F5 mrf an01b reset Allows resetting MCR alarm
Coolant panel alarm then:
ROLE PLAY: As an 1M report that HPCI rupture diaphragm pressure switch PS-73-20B has failed low.
When directed from the Floor then: F6 imf fw05b 100 8:00 '8' HP heater string isolation
ROLE PLAY: If sent to investigate which valve is open, wait 2 minutes and report 3-LCV-22B light is out
(B2 high level dump)
ROLE PLAY: At ~ 79% power, as the Reactor Engineer, recommend inserting the first group of
Emergency Insert Control Rods.
If asked to reset local Cond Demin F7 mrf an01d reset allows reset of control room alarm
alarm
After conditions stabilized or as directed F8 imf sw10a Trips 3A FPC pump
by Floor Instr.
ROLE PLAY: (If asked) As AUO, report 3-78-506, 511, & crosstie 507 are open & 3-78-510 (B hx outlet) is
closed
ROLE PLAY: (If asked) As RW UO, 3-FRC-78-24 is in manual & set to 0%
If asked to throttle 3-FCV-78-66 F9 ior zlohs7866a[2] on
If asked to close 3-FCV-78-66 F10 dor zlohs7866a[2]
ROLE PLAY: (If asked) As Rx Bldg AUO, report 3B pump discharge pressure is 140 psig (PI-78-16 on 9-
25-16)
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ROLE PLAY: If sent to inspect breaker on 3A FPC pump, report bkr was found tripped and will not test
After FPC restored and as directed by F11 bat HLTS3-1-2 Trips 38 RFP on thrust brng
Floor Instr. wear with check valve failure at 30 % *
ROLE PLAY: If sent to check 38 RFP report that there is no apparent cause but you will continue to
check
NOTE: Mark the time when RPV level reaches +2 inches to ensure Critical Task completion of
inserting a manual scram within 60 seconds of reaching +2 inches.
When directed by Lead Examiner F12 imf fw13a Trips 3A RFP on thrust brng wear
If doesn't start on low level <shift>F1 imf rc02 Start of RCIC
After HPCI is in manual control and <shift>F2 imf hp07 HPCI 120V failure
injecting up to -50" or directed by Lead
Examiner then:
After 10 minutes of RCIC operations or <shift>F4 bat HLTS3-1-1 Max. Rad (2 areas in 13 mins.)
directed by Lead Examiner then:
ROLE PLAY: If directed to close RCIC valves 71-2 & 3 locally, respond that you are waiting on RadCon
to enter the Reactor building.
If decided to attempt to close valves mrf rc05k emer 71-2 to emerg
locally: mrf rc05s emer 71-3 to emerg
To return transfer switch to normal mrf rc05k norm 71-2 to norm
mrf rc05s norm 71-3 to norm
Terminates the scenario when the following conditions are satisfied or upon request of the Lead Examiner:
1. All rods are fully inserted.
2. Reactor water level is in the normal band.
3. Emergency Depressurization has been completed.
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X. Scenario Summary
With the unit operating at 100%, the crew will alternate Stator Cooling Water Pumps per 3-01-
35A. Then the operating crew will experience a slow loss of FW HTR level control on the 8 high
pressure heater string. Once the heater is isolated and power reduced, a trip of 3A FPC pump will
require the operator to start 38 FPC pump per 3-01-78. When plant conditions are stable the 38
Reactor Feedwater Pump will trip, the crew will respond per 3-AOI-3-1. After conditions stabilize,
The crew will experience a loss of the remaining RFPs which will require the crew to scram and
utilize RCIC for level control. The reactor will NOT scram automatically. When RCIC is initiated it
develops a steam leak which cannot be isolated forcing the crew to emergency depressurize
based on 2 Area Rad Monitors above maximum safe. If HPCI is used for water level control the
crew will experience a problem with the flow controller to respond in automatic. Eventually, HPCI
will experience a failure of the 120V AC power supply and HPCI will no longer function.
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x. Information to Floor Instructors:
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. Terminate the scenario when the following conditions are satisfied or at the direction of the
Lead Examiner:
1. All rods fully inserted
2. Reactor Water level normal
3. Emergency Depressurize on 2 area RADS above max safe value
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XI. Simulator Event Guide
( Event 1a: NORMAL OPERATIONS
POSITION EXPECTED ACTIONS
ATC/BOP ~Ite rn a e Stator Coolin Pum slAW 3-OI-35A sect. 6.4
[1] START the Standby Stator Cooling Water Pump A(B) by placing
GEN STATOR CLG WATER PUMP 3A(B), 3-HS-35-35A(36A) on Panel 3-
9-8 to START.
[2] STOP the Stator Cooling Water Pump B(A) by placing GEN
STATOR CLG WATER PUMP 3B(A), 3-HS-35-36A(35A) on Panel 3-9-8
to STOP.
[3] VERIFY the STATOR COOLING WATER GEN INLET FLOW, 3-FIS-
035-0065, indicates Min. 595 to Max. 732 gpm on Panel 25-114.
[4] VERIFY the STATOR COOLING WATER GEN INLET PRESS, 3-PI-
035-0064, indicates 42 (22 psig and 20 psig head) to 52 psig on Panel 25-
114.
[5] VERIFY the pump control switch for the stator cooling water pump
stopped in Step [2] above , (3A), is returned to AUTO on Panel 3-9-8 .
[6] SELECT STATOR COOLING WATER PUMPS SEL,
3-HS-035-0040 (A-RES-CO-B-RES) on Panel 25-114 to the non-
operating pump.
ATC/BOP Identify the improper lens configuration on Stator Cooling Water pumps and
swap the lenses or informs the SRO.
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XI. Simulator Event Guide
Event 1b: HPCI PRESSURE SWITCH FAILURE
POSITION EXPECTED ACTIONS
ATC/BOP Responds to Report by IMs of HPCI rupture diaphragm pressure switch failure (3-
PS-73-20B), by relaying information to SRO.
SRO Consults Tech Spec 3.3.6.1 Function 3c and determines only three pressure
switches are required.
SRO Determines an INFORMATION ONLY LCO must be written for HPCI pressure
switch 3-PS-73-20B.
(
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XI. Simulator Event Guide
( Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON "B" STRING
POSITION EXPECTED ACTIONS
ATC/BOP Announces "BYPASS VALVE TO CONDENSER NOT CLOSED" and refers to
3-ARP-9-6A, win 18.
ATC/BOP A. CHECK heater high or low level or moisture separator high or low level alarm
window illuminated on Panel 3-9-6 or 3-9-7 to identify which bypass valve is
opening.
B. DISPATCH personnel to check which valve's light is extinguished on
junction box 34-21, Col T-13 J-LINE, elevation 565'.
SRO Direct an Upper Power Runback due to RFP speed above 5050 rpm.
ATC Initiates an Upper Power Runback of Recirc Pumps.
ATC/BOP Announces "HEATER B2 LEVEL HIGH" and refers to 3-ARP-9-6A, win 9.
VERIFY Automatic action - Drain valve to condenser 3-LCV-6-22B opens.
A. CHECK the following indications:
- Condensate flow recorder 2-29, Panel 3-9-6. Rising flow is a possible
indication of a tube leak.
- Heater B2 shell pressure, 3-PI-5-22 and drain cooler B5 flow, 3-FI-6-34,
Panel 3-9-6. High or rising shell pressure or drain cooler flow is possible
indication of a tube leak.
(
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XI. Simulator Event Guide
( Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON "B" STRING
TIME POSITION EXPECTED ACTIONS
ATC/BOP B. CHECK drain valve 3-FCV-6-95 open.
C. CHECK level on ICS screen, FEEDWATER HEATER
LEVEL(FWHL).
- IF the 3B2 heater indicates HIGH (Yellow), THEN VERIFY proper
operation of the Drain and Dump valves.
- DISPATCH personnel to local PaneI3-LPNL-925-562C to VERIFY
and MANUALLY control the level.
D. IF a valid HIGH HIGH level is received, THEN
GO TO 3-AOI-6-1A or 3-AOI-6-1C.
ATC/BOP Announces B1 and B2 HP htr. Extraction isolation
SRO IRECTS Crew to enter 3-AOI-6-1
Contacts Reactor Engineer
(
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XI. Simulator Event Guide
( Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON "8" STRING
TIME POSITION EXPECTED ACTIONS
ATC/BOP 3-AOI-6-1~
Performs immediate actions;
REDUCE Core Thermal Power to e 5% below initial power level to maintain
thermal margin.
ATC/BOP Performs subsequent actions
1 REFER TO 3-01-6 for turbine/heater load restrictions.
[2] REQUEST Reactor Engineer EVALUATE and ADJUST
thermal limits, as required.
[3] ADJUST reactor power and flow as directed by Reactor
Engineer/Unit Supervisor to stay within required thermal and
feedwater temperature limits. REFER TO 3-GOI-100-12 or
3-GOI-100-12A for the power reduction.
SRO Directs isolating FW to 8 HP heater string
Directs power reduction to < 79% power (Mid-power run back) per 3-01-6,
1111 HEATERS OUT (Tube and Shell Side)** One HP string 920 MWe (79%)
nters 3-GOI-100-12 Power Maneuvering
Notifies Rx Eng. And ODS of Feedwater Heater isolation and power
reduction
(
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XI. Simulator Event Guide
Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON "B" STRING
TIME POSITION EXPECTED ACTIONS
ATC/BOP Closes the following FW valves (Attachment 1)
3-FCV-3-31, HP HTR 3B2 FW INLET ISOL VALVE
3-FCV-3-76, HP HTR 3B1 FW OUTLET ISOL VALVE
Performs a mid-power runback -79%
ATC/BOP [4] ISOLATE heater drain flow from the feedwater heater string that isolated by
closing the appropriate FEEDWATER HEATER A-2(B-2) or (C-2) DRAIN TO HTR
A-3(B-3) or (C-3), 3-FCV-6-94(95) or (96). (Closes 3-FCV-6-95)
[5] VERIFY automatic actions occur. REFER TO Attachment 1.
VERIFY automatic actions
The High Pressure Heater Extraction Isolation Valves and Moisture Separator Level
Control Isolation valves close.
3-FCV-5-9, HP HEATER 3B1 EXTR ISOL VLV
3-FCV-5-21, HP HEATER 3B2 EXTR ISOL VLV
3-FCV-6-74, MOISTURE SEP LC RES B1 ISOL VLV
3-FCV-6-172, MOISTURE SEP LC RES B21S0L VLV
(
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XI. Simulator Event Guide
( Event 2: SLOW LOSS OF HP FEEDWATER HEATING ON "B" STRING
POSITION EXPECTED ACTIONS
Crew [6] MONITOR TURB THRUST BEARING TEMPERATURE,
3-TR-47-23, for rises in metal temperature and possible
active/passive plate reversal.
[7] DETERMINE cause which required heater isolation and PERFORM
necessary corrective action. i.e. Recognizes HTR level lowers as a result of
isolating the Condensate side of 3B HP HTR string (i.e. tube leak)
SRO Direct ATC to insert the first group of control rods on the Emergency Shove
Sheet per Reactor Engineer recommendation.
ATC Insert the first group of rods on the Emergency Shove Sheet using a peer check
as directed by Rx Engineer & Unit Supervisor
(
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XI. Simulator Event Guide
Event 3: Trip of 3A FPC pump
TIME POSITION EXPECTED ACTIONS
Crew Recognizes 3A FPC pump trip, responds per the ARP
ATC/BOP Resets MOTOR TRIPOUT 3-ARP-9-8C (W33)
ATC/BOP Performs the following:
Responds to alarm FPC system abnormal 3-ARP-9-4C (W 1)
A. DISPATCH personnel to Panels 25-15 and 25-16 to determine the
cause of the alarm.
H. IF Fuel Pool Cooling System failure has occurred, THEN
REFER TO 3-AOI-78-1.
Enters 3-AOI-78-1 to start the standb
Immediate Actions - None
Subsequent actions
4.2[3] IF fuel pool cooling system failure is from loss of cooling, THEN:
(Otherwise N/A) PERFORM the following:
[3.1] START idle FUEL POOL COOLING PUMP 3B(3A).
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XI. Simulator Event Guide
( Event 3: Trip of 3A FPC pump
POSITION EXPECTED ACTIONS
Coordinates with Rx Bldg AUO and Radwaste UO to start 3B FPC
pump
Verifies discharge pressure >120 psig with AUO
Directs RW UO and Rx Bldg AUO to place demin in service
SRO/BOP Dispatch AUO/EMs to check breaker for 3A FPC pump
SRO Directs restoration of system after cause is determined
SRO valuate Tech. Sec. TRM 3.9.213.9.3
SRO Determine TRM 3.9.2 Action (A) applies to maintain FP temperature
below 150°F.
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XI. Simulator Event Guide
( Event 4: 3B RFPT Trip
TIME POSITION EXPECTED ACTIONS
ATC/BOP Announces "RFPT " Abnormal" alarm" and trip of RFPT 'B'.
ATC/BOP Recognize that RFPT "B" speed still indicates -4000 rpm after the trip.
ATC/BOP Recognize that RFPT "A" and "C" are running at the upper speed limiter.
ATC/BOP Diagnose the possibility that the discharge check valve on RFPT "B" has not
SRO closed.
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XI. Simulator Event Guide
( Event 4: 3B RFPT Trip
TIME POSITION EXPECTED ACTIONS
ATC/BOP Refers to ARP 9-6C and take required action
A. VERIFY reactor power is within the capacity of operating RFPs.
B. CHECK core limits.
C. WHEN RFPT coasts down to zero speed, unless RFPT is rolling on minimum flow,
THEN VERIFY turning gear motor starts and engages.
D. EFER TO 3-AOI-3-1 or 3-01-3, Section 8.1.
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XI. Simulator Event Guide
( Event 4: 3B RFPT Trip
TIME POSITION EXPECTED ACTIONS
ATC/BOP nters 3-AOI-3-1
[1] VERIFY applicable automatic actions.
C. Recirc Pumps receive run back signal to 75% speed at 27" (normal range) if the
discharge flow of a RFP is less than 889,000 Ib/hr 19% (rated flow).
[2] IF level OR Feedwater flow is lowering due to loss of Condensate,
Condensate Booster, or Feedwater Pump(s), THEN REDUCE Recirc flow as
required to avoid scram on low level.
(
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XI. Simulator Event Guide
( Event 4: 3B RFPT Trip
TIME POSITION EXPECTED ACTIONS
[9] IF RFPs are in automatic control, THEN
VERIFY 3-L1C-46-5 raises flow of operating RFPs.
[12] IF a RFPT has tripped and is NOT re uired to maintain level, THEN
SECURE tripped RFPT. EFER TO 3-01-3
[14] IF unit remains on-line, THEN
RETURN Reactor water level to normal operating level of 33" (normal
range).
SRO Dispatches AUO to RFP to determine cause of trip
ATC/BOP Verifies that unit stable
Verifies Rx Thermal limits
SRO Contacts maintenance to check reason for RFPT trip
NOTE: LEAD EXAMINER notify Console Instructor when ready to trip the next RFP (i.e. next event)
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XI. Simulator Event Guide
( Event 5: 3A and 3C RFP Trip
POSITION EXPECTED ACTION
ATC/BOP Recognizes 3A RFP trip and need for reactor scram
ATC/BOP ~to scram failure (If not manually scrammed prior)
SRO Directs Reactor scram (Critical Task)
ATC anuall scrams the reactor and gerforms 3-AOI-100-1 actions
-mode switch in SID
-checks power lowering
-reports all rods in
-recognizes trip of 3C RFP and informs SRO all RFP's are tripped
BOP Trip Turbine / verify isolations
SRO Enters 3-EOI-1 on low reactor water leve
Directs level be controlled by:
-RCIC
-CRD
-HPCI
-Enter AOI-100-1
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XI. Simulator Event Guide
C" EventS: 3A and 3C RFP Trip
TIME POSITION EXPECTED ACTION
ATC/BOP Utilizes RCIC for reactor water level control
1. IF ..... BOTH of the following exist:
RPV Pressure is at or below 50 psig, AND
Bypass of RCIC low RPV pressure isolation interlocks is necessary, THEN ...
EXECUTE EOI Appendix 16A concurrently with this procedure.
2. IF .... . BOTH of the following exist:
High temperature exists in the RCIC area, AND
SRO directs bypass of RCIC High temperature Isolation interlocks, THEN ...
PERFORM the following:
a. EXECUTE EOI Appendix 16K concurrently with this procedure.
b. RESET auto isolation logic using RCIC AUTO*ISOL LOGIC A(B) RESET
3-XS-71-S1A(B) pushbuttons.
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XI. Simulator Event Guide
( Event 5: 3A and 3C RFP Trip
TIME POSITION EXPECTED ACTION
BOP 3. VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE
RESET.
4. VERIFY 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller in
AUTO with setpoint at 600 gpm.
5. OPEN the following valves:
3-FCV-71-39, RCIC PUMP INJECTION VALVE
3-FCV-71-34, RCIC PUMP MIN FLOW VALVE
3-FCV-71-25, RCIC LUBE OIL COOLING WTR VLV.
6. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.
7. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC
Turbine.
(
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XI. Simulator Event Guide
( Event 5: 3A and 3C RFP Trip
TIME POSITION EXPECTED ACTION
8. CHECK proper RCIC operation by observing the following :
a. RCIC Turbine speed accelerates above 2100 rpm.
b. RCIC flow to RPV stabilizes and is controlled automatically at 600 gpm.
c. 3-FCV-71-40, RCIC Testable Check Vlv, opens by observing 3-ZI-71-40A,
DISC POSITION , red light illuminated.
d. 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE, closes as flow rises above
120 gpm .
SRO nters 3-EOI-3 on Rx Bid Hi Rad
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XI. Simulator Event Guide
(
Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP If HPCI is used, recognizes auto control failure and places HPCI
controller in manual
ATC/BOP Recognizes and reports high area temperature for RCIC room
Recognizes RCIC failure to isolate and attempts to manually isolate it
SRO Directs RCIC be isolated locally
Crew Monitors area radiation levels
SRO Determines has two area radiation levels above max safe lAW 3-EOI-3
and directs emergency depressurization by opening 6 ADS valves (C2)
(Critical Task)
EXAMINER NOTE: Of the 6 ADS valves, 2 will fail to open and the candidate will have to open
additional valves (any two) until six are open.
ATC/BOP Opens 6 ADS valv~izes 2 valves failed to open and opens 2
additional valves ~
Verifies RFP discharge valves closed before uncontrolled injection on
lowering Rx pressure
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
SRO Directs RPV level be maintained between +2" and +51"
with one or more of the following: (After emergency depressurization.)
(Critical Task)
-LPCI
-Core Spray
-Condensate
ATC/BOP After emergency depressurization maintains RPV water level TAF and
restores level +2" to +51" with one or more of the following:
(Critical Task)
-LPCI
-Core Spray
-Condensate
ARR 6A Condensate
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.
(
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
POSITION EXPECTED ACTIONS
ATC/BOP 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
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 (SOL VLV.
(
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XI. Simulator Event Guide
( Event 5: RCIC STEAM LEAK/LOSS OF HPCI
POSITION EXPECTED ACTIONS
ATC/BOP 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-3-75, HP HTR 3B1 FW OUTLET ISOL VLV
3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV
5. 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 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP ~.........._.::=:."""""""",,,",,::::.r"::'O=:~;;:iJ:"'=-=-,~..:..-~.:..:.:==~
- .::
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 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 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP ~c.c..=~~~...:..L::=d:-:.:'-===".
- ..:
1. IF *.*.* Adequate core cooling is assured AND It becomes necessary to
bypass LPCllnjection Valve Timers to control inj ect io n, 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 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 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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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP 8. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, as
necessary to control injection.
9. MONITOR RHR Pump NPSH using Attachment 1.
10. PLACE RHRSW pumps in service as soon as possible on ANY RHR
Heat Exchangers discharging to the RPV.
11. THROTTLE the following in-service RHRSW outlet valves to maintain
flow between 1350 and 4500 gpm:
3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV
3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV.
12. NOTIFY Chemistry that RHRSW is aligned to in-service
RHR heat exchangers.
(
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
SRO After -EOI-2 entered on hi h SP water level or tem erature
directs the following:
- H20 2 analyzers placed in service
ATC/BOP Places H20 2 analyzers in service
SRO Directs all available Suppression Pool cooling be placed into service due
to Suppression Pool water temperature
ATC/BOP
1. IF ..*.. Adequate core cooling is assured, THEN ... BYPASS LPCI
Injection Valve Timers as necessary using EOI Appendices 16F and 16G.
Calls for App 16F&G
2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:
a. VERIFY at least one RHRSW pump supplying each EECW header.
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
POSITION EXPECTED ACTIONS
ATC/BOP b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).
c. THROTTLE the following in-service RHRSW outlet valves to obtain
between 1350 and 4500 gpm RHRSW flow:
3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV
3-FCV-23-46, RHR HX 38 RHRSW OUTLET VLV
3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV
3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.
d. IF ..... Directed by SRO, THEN ... PLACE the following key lock switches
in MANUAL OVERRIDE:
3-XS-74-122, RHR SYS I LPCI2/3 CORE HEIGHT OVRD.
3-XS-74-130, RHR SYS II LPCI2/3 CORE HEIGHT OVRD.
e.IF ..... LPCIINITIATION Signal exists, THEN ... MOMENTARILY PLACE
the following in select:
3-XS-74-121, RHR SYS I CTMT SPRAY/CLG VLV SELECT.
3-XS-74-129, RHR SYS II CTMT SPRAY/CLG VLV SELECT.
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP f. IF ..... 3-FCV-74-53(67), RHR SYS I(II} LPCIINBD INJECT VALVE, is
OPEN, THEN ... VERIFY CLOSED 3-FCV-74-52(66}, RHR SYS I(II} LPCI
OUTBD INJECT VALVE.
g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBRJPOOL ISOL VLV.
h. VERIFY desired RHR pump(s} for Suppression Pool Cooling are operating.
i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLGITEST
VLV, to maintain EITHER of the following as indicated on 3-FI-74-50(64),
RHR SYS 1(11) FLOW:
Between 7,000 and 10,000 gpm for one-pump
operation. OR
At or below 13,000 gpm for two-pump operation.
(
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XI. Simulator Event Guide
( Event 6: RCIC STEAM LEAK/LOSS OF HPCI
TIME POSITION EXPECTED ACTIONS
ATC/BOP j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE
(VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E) ,
Compartment 4E(4E), if required).
k. MONITOR RHR Pump NPSH using Attachment 1.
I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat
Exchangers.
m. IF ..... Additional Suppression Pool Cooling flow is necessary, THEN ...
PLACE additional RHR and RHRSW pumps in service using Steps 2.b
through 2.1.
Terminate scenario when emergency depressurization has occurred and Rx water level is under control.
(
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XII. Crew Critical Tasks (If an evaluated scenario)
( SAT/UNSAT
1. Maintains reactor water level above TAF
2. Emergency depressurize based on 2 areas radiation
above maximum safe with a primary system
discharging to secondary containment (within 5
minutes)
3. Recognize auto scram failure within one minute. (If
not manually scrammed)
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XIII . Scenario Verification Data
( EVENT TASK# RO SR CONTROL MANIPULATION
o
1. Loss of HP Feedwater Heating 295014 3.7 3.9 B17
U-068-NO-10
U-006-AB-01
S-006-AB-01
T-000-AD-17
2. 3A FPC pump trip
3. RFPs Trip 295001A2.01 3.7 3.7 B3
U-003-AB-01
S-003-AB-01
U-003-NO-08 295001A4.02 3.9 3.7
295009G12 3.8 4.4
T-000-AD-17
4. HPCI Pressure Switch Failure U-073-AL-19 206000A2.09 3.5 3.7 B5
S-000-AD-27 2.1.12 2.9 4.0
5. RCIC LeaklMSL Leak U-000-EM-10 295033 3.6 3.9 A7,B14,A12 ,
U-000-EM-11 B15,14,120
S-000-EM-10 295032 3.5 3.6
S-000-EM-12
U-000-EM-01 3.8 4.4
U-000-EM-02
U-000-EM-03 3.6 4.2
S-000-EM-01 3.5 4.1
S-000-EM-02 3.9 4.5
S-000-EM-03 3.9 4.5
U-000-EM-14 2.4.38 2.2 4.0
S-000-EM-15 295026 3.6 3.8
S-000-EM-24
T-000-AD-04
T-000-EM-09
T-000-EM-11
T-000-EM-16
(
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SCENARIO REVIEW CHECKLIST
(
SCENARIO NUMBER HLTS 3-1
§.... Total Malfunctions Inserted; List: (4-8)
1) High Pressure Heater Isolation
2) 3A FPC pump trip
3) RFPT trip
4) RCIC steam leak
5) RCIC failure to isolate (auto or manual)
6) HPCI 120V Failure
8) BPV Failure
9) ARI Automatic Failure
~ Malfunctions That Occur After EOI Entry; List: (1-4)
1) RCIC steam leak
2) RCIC isolation failure (auto or manual)
3) Two ADS valve failures
~ Abnormal Events; List (1-3)
2) 3A FPC pump trip. (AOI & ARP)
_1_ Major Transients; List: (1-2)
1) RCIC Steam Line Break
.a, EOls used; List: (1-3)
1) EOI-1
2) EOI-2
3) EOI-3
_1_ EOI Contingencies Used; List: (0-3)
1) C2
90 Run Time (minutes)
29 EOI Run Time (minutes) ; 30 % of Scenario EOI Run Time
L Crew Critical Tasks
yes Technical Specifications Exercised (yes/no)
(
XIV. SHIFT TURNOVER INFORMATION
Equipment out of service/LCOs: Unit 3 has been operating for 193 days, Unit 2 has been operating
for 56 days. Unit 1 has been operating for 290 days.
3ED Diesel Generator is tagged for water jacket leakage repair. Day 2 of LCO. will be returned to service
this shift.
Operation/Maintenance for the Shift: Support scheduled maintenance and testing activities
Alternate Stator Cooling Water Pumps per 3-01-35A. Sect 6.4 for scheduled maintenance on 3A Stator
Cooling Water Pump . HPCI SR in progress for rupture disk pressure switches by 1M's.
Unusual Conditions/Problem Areas : Fuelleakers on U3 are currently @ RFI 60,000.
Storms passing through the region, No Watches in effect for the immediate area.
3C RFP was oscillating approximately 30 RPM during the last shift, but currently working properly and
being monitored . 3C RFP is operating in automatic to collect data for next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A trouble shooting
plan is being developed .
AppendixD Scenario Outline Form ES-D-l
FINAL
Facility: BFN Scenario Number: HLTS-3-2 Op-Test Number: HLT0610
Examiners: Operators:
Initial Conditions:
Unit 3 is at 79% power. 3C RHR Pump is out of service. T.S 3.5.l.A.l, 3.6.2.3, 3.6.2.4, 3.6.2.5
have been entered. Unit 3 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. Loop II ofRHR has been vented within the hour in preparation for placing Torus cooling
in service. Valve 3-FCV-73-36 seal-in circuit has been disabled per step 7.6 of 3-SR-3.5.1.7
Turnover:
Continue with 3-SR-3.5.1.7 which is in progress and is complete up to Step 7.11 (HPCr Main and
Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure).
Alternate EHC Pumps per section 6.3 of3-01-47A. Increase reactor power to 85% using Recirc flow (3-
G01-100-12, step 5.132) with no pre-conditioning limitations. Reactor Engineering will evaluate further
Event Malfunction Event Event
Number Number Type* Description
1 N/A N-BOP The crew will alternate EHC pumps using 3-01-47A.
N-SRO
2 N/A R-ATC The crew will continue with power ascension using 3-G01-l2
R-SRO and 3-01-68.
3 irnfhp08 C-BOP The crew will recognize and respond to a HPCr steam line
C-SRO break. HPCr will fail to auto isolate and must be manually
TS-SRO isolated.
The SRO will enter and execute E01-3.
4 irnf adOlg 40 C-ATC The crew will recognize and respond to a stuck open SRV
C-SRO using 3-A01-l-1.
TS-SRO
5. batRRPAVIB M The crew will recognize and respond to a recirc pump high
irnf cr02a 75 All vibration, dual seal failure , trip, core power oscillations and
3:00 scram.
The crew will carry out actions using E01 -l & 2 and 3-A01-
100-1.
6 irnf 002 100 M The crew will recognize and respond to a Msrv Closure and
1:30 All LOCA using E01-l & 2.
The crew will monitor and control primary containment until
reactor water level approaches TAF.
The crew will transition to EOr C-l and perform Emergency
Depressurization to enable level restoration using low pressure
systems.
- (N)ormal, (R)eactivity, (Ijnstrument, (C)omponent, (M)ajor
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( SIMULATOR EVALUATION GUIDE
TITLE HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP, DRYWELL LEAK,
EMERGENCY DEPRESSURIZATION ON LEVEL (C1)
REVISION o
DATE January 19, 2008
PROGRAM BFN Operator Training - Hot License
PREPARED BY:
\~ ate
REVIEWED BY: \ ~6& Date
CONCURRED : \ z.- ? t:>~
Date
VALIDATION BY: \ 2/1/oP
Date
Requires copy of 3-SR-3 .5.1.7 (current rev.) completed up to step 7.11 to be provided to crew at turnover
HLTS-3-2
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NUCLEAR TRAINING
REVISION/USAGE LOG
REVISION DESCRIPTION OF DATE PAGES REVIEWED BY
NUMBER REVISION AFFECTED
0 INITIAL 1/19/08 All csf
(
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( Program : BFN Operator Training
I.
II. Course: Hot License Training
III. Title: HPCI STEAMLINE BREAK, SRV FAILURE, RECIRC PUMP TRIP , DRYWELL
LEAK , EMERGENCY DEPRESSURIZATION ON LEVEL (C1)
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 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 alternate EHC pumps.
2. The operating crew will continue power ascension from", 79% power.
3. The operating crew will experience a HPCI steam line break during performance of 3-SR-
3.5.1.7 HPCI Flow Rate, with a failure of HPCI to auto isolate.
I
4. The operating crew will recognize and respond to a safety-relief valve failed open.
5. The operating crew will recognize and respond to a high vibration and trip of 3A Recirc
pump .
6. The operating crew will recogn ize and respond to reactor power oscillations by scramming
the reactor.
7. The operating crew will recognize and respond to a high drywell pressure condition.
8. The operating crew will Emergency De-pressurize when in C1 before reactor water level
reaches -180".
(
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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:
A. Calculator
B. Control Rod Insertion Sheet
C. Stopwatch
D. Hold Order/Caution tags
E. Annunciator window covers
F. Steam tables
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( VIII. Console Operators Instructions
A. Scenario File Summary
1. File: bat HLTS3-2
MF/RF/10R# Description
a) trg e1 MODESW Sets trigger
b) trg e2 adssrv1-22 Sets trigger
c) ior zlohs7416a[1] off Tag Out 3C RHR
d) imf rh01c 3C RHR Pump trip
e) ior ypobkrpmpcrh faiLpower Control power for RHR 3C breaker
f) mrf hw01 fast Advances all charts
g) imf th33b (e1 0) 1 2:00 B MSL break in DW
h) imf th21 (e1 5:00) 0.5 10:00 Recirc. line break
i) imf rd01a (e1 10:00) 3ACRDP trip
j) imf rd01b 3B CRDP trip
k) imf hp09 Failure of HPCI to auto isolate
I) lor zdihs718a close Fails RCIC
m) ior ypovfcv718 fail-power Keeps the 71-8 valve closed
n) imf rp11 (e1 1:00) MSIV logic fuse failure
2. File: bat RRPAVIB
MF/RF/10R# Description
1) imf th12a Inserts Vibration Alarm
2) imf th1 Oa (none 1: ) Fails Recirc Pump A Inboard Seal
3) imf th11a (none 2: ) Fails Recirc Pump A Outboard Seal)
4) ior zdihs681 open Prevents Recirc Pump A Suction Valve Closure
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( B. Console Operators Manipulations
ELAP. TIME PFK# DESCRIPTION/ACTION
Simulator setup rst 28 "" 78 O/OPower MOC, use mid-power runback push button
Simulator setup restorepref Establishes Function Keys
HLTS3-2
Simulator setup setup Verify Function Keys
Simulator setup esc Clears Function Key Popup
Simulator setup F3 bat HLTS3-2 See Scenario File Summary
Simulator setup manual Place suppression pool cooling in service (Loop II)
Simulator setup manual Place HO tags on '3C' RHR pump
Simulator setup manual Place TESTING/MAINT frames on Panel9-3F, Windows 5,11,
26 for HPCI 3-SR-3.5.1.7 complete up to step 7.11
Simulator setup manual Provide a copy of 3-SR-3.6.2.1.1, Suppression Chamber Water
Temperature Checks.
Simulator setup manual Verify lens covers on EHC pumps are correct
~OLE PLAY: When asked for local EHC pressure, (3-PI-047-0001(0002>> indicates 1625 psig. (3-01-47A section 6.3
step [4].
ROLE PLAY: When asked, EHC pump 38 EHC PUMP SUCTION FILTER and EHC AUX PUMP SUCTION FILTERS,
indicate CLEAN, (3-01-47A section 6.3 step [11].
ROLE PLAY: When asked, MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at 2.0 turns clockwise. (3-01-47A
section 6.3 step [12].
ROLE PLAY: If asked, state that the anti-rotation collar markings are aligned.
When HPCI is at rated pressure and F4 imf hp08 Steam leak into HPCI room
flow
ROLE PLAY: AUO at HPCI quad. Reports a large steam leak on HPCI and present location is elev. 565 Rx.8Idg.
When directed by Lead Instructor F6 imf ad01c 40 Fails SRV-1-22 open
When RO cycles SRV then: F7 dmf ad01c SRV-1-22 closes
When directed by Lead Instructor F8 bat RRPAVIB Recirc Pump A high vibration, seal failure,
suction valve fails to close and power
oscillations.
ROLE PLAY: When dispatched to check 3A Recirc Vibration, wait 2 minutes and report back swinging 10 to 14
mils.
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( C. Console Operators Manipulations
ELAP. TIME PFK# DESCRIPTION/ACTION
When 'A' Recirc trips F9 dmf th12a Deletes vibration high alarm
4 min. after 3A recirc. pump trip F10 imf cr02a 75 3:00 Core power oscillations
then: and
F11 imfth22 (none 1:30) 100 Bottom head leak
When requested, wait 3 minutes F12 bat app16fg Defeats RHR injection valve timers
Terminate the scenario when the following conditions are satisfied are at the direction of the Lead Examiner.
1. RPV water level +2" to +51"
2. Drywell sprayed
3. Emergency Depressurizarion completed
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IX. Scenario Summary
( Given Unit 3 at 79% power, the crew will alternate EHC pumps and resume power ascension to 100%. As 3-
SR-3.5.1.7, HPCI Flow Rate, is continued the crew will experience a ruptured HPCI steam line with a failure of
HPCI to automatically isolate . Manual HPCI isolation will be possible . As power ascension is continued, an
SRV fails open but can be closed as steps of 3-AOI-1-1 are performed. The crew experiences high vibration
with a subsequent trip and seal leakage on the 3A Recirc Pump resulting in high drywell pressure. When the
diesel generators automatically start the 3ED diesel generator fails to auto start but can be manually started.
Finally , the crew will Emergency Depressurizes before reactor water level reaches -200" .
HLTS-3-2
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x. Information to Floor Instructors:
( 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 Unit Supervisor.
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 floorzlead
instructor/evaluator.
1. RPV water level +2" to +51"
2. Emergency Depressurizarion completed
HLTS-3-2
REVO
PAGE 10 OF 63
XI. Simulator Event Guide
( Event 1: Alternate EHC Pumps
TIME POSITION EXPECTED ACTION(S)
ATC/BOP Receive crew briefing and walk boards down
SRO Directs BOP to alternate EHC pumps
BOP ~Ite rn ates EHC Pum s in accordance with 3-01-47A section 6.3
[1] VERIFY EHC Sys is in service. REFER TO Section 5.1.
[2] REVIEW Precautions & Limitations listed in Section 3.0.
[3] START the non-operating EHC PUMP 3B(3A) using EHC HYD FLUID
PUMP 3B(3A), 3-HS-47-2A(1A).
[4] CHECK the started EHC pump EHC HYD PUMP A(B) DISCH PRESS , 3-PI-
047-0001(0002), indicates between 1550 psig and 1750 psig, locally at the EHC
skid . (AUO reports 1625 psig)
[5] IF the started EHC pump discharge pressure is NOT between 1550 psig and
1750 psig, THEN ADJUST the pressure compensator for the started EHC pump
to adjust pump discharge pressure. REFER TO Step 8.6[1].
[6] STOP EHC PUMP 3A(3B) using EHC HYD FLUID
PUMP 3A(3B), 3-HS-47-1A(2A).
(
HLTS-3-2
REVO
PAGE 11 OF 63
XI. Simulator Event Guide
(
Event 1: Alternate EHC Pumps
TIME POSITION EXPECTED ACTION(S)
[7] CHECK EHC HEADER PRESSURE, 3-PI-47-7, indicates between 1550 psig
and 1650 psig.
[8] IF EHC header pressure is NOT between 1550 psig
and 1650 psig, THEN ADJUST the pressure compensator for the operating
EHC pump to adjust EHC header pressure. REFER TO Step 8.6[2].
[9] IF there are any disagreement flags, THEN
RESET disagreement flags by placing the operating pump handswitch, EHC
HYD FLUID PUMP 3A(3B) , 3-HS-47-1A(2A), to START .
[10] CHECK the started EHC PUMP 3B(3A) MTR AMPS,
3-EI-47-2(1), indicates less than 140 amps.
[11] VERIFY EHC Pump 3B(3A) , EHC PUMP SUCTION FILTER and EHC AUX
PUMP SUCTION FILTERS, indicate CLEAN, locally at the EHC skid.
[12] [NERlC] VERIFY MANUAL FLOW CONTROL VALVE, 3-047-0588, is set at
2.0 turns clockwise. [INPO SOER 84-006]
BOP Swaps lens covers for EHC pumps based on new lineup
(
HLTS-3-2
REVO
PAGE 12 OF 63
XI. Simulator Event Guide (Continued)
(
Event 2: Power Ascension
POSITION EXPECTED ACTION(S)
SRO irects ower ascension er 3-GOI-1 00-12 ste 6.2 and 3-01-68
ATC Raises reactor power in accordance with 3-GOI-100-12 and 3-01-68
[1] IF NOT in single loop operation, THEN
ADJUST Recirc Pump speeds 3A using, RAISE SLOW (MEDIUM), 3-HS-96-
15A(15B)/LOWER SLOW(MEDIUM) 3-HS-96-17A(17B), 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 & 3B 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 Performs as peer checker for recirc flow changes
(
HLTS-3-2
REVO
PAGE 13 OF63
XI. Simulator Event Guide (Continued)
( Event 3a: HPCI Surveillence
POSITION EXPECTED ACTION(S)
SRO irects BO~ to continue with 3~R-3.5.1.1 at step.1 11
BOP [11] ALIGN HPCI System for a manual start by performing the following steps:
[11.1] CHECK HPCI SYSTEM FLOW/CONTROL 3-FIC-73-33 is in AUTO and
SET to control at 500 (5,000 gpm) .
IF required, THEN DEPRESS AUTO operation mode transfer switch and
ADJUST setpoint using Setpoint up/down keys.
[11.2] PLACE HPCI STEAM PACKING EXHAUSTER by placing 3-HS-73-10A
to START.
[11.3] VERIFY 3-FCV-73-36, using HPCI/RCIC CST TEST VLV 3-HS-73-36A,
is OPEN.
[11.4] OPEN 3-FCV-73-35, using HPCI PUMP CST TEST VLV, 3-HS-73-35A.
[12] START the HPCI turbine by performing the following:
[12.1] [NER] VERIFY communication is established with Operations personnel
in HPCI Room. [IE 93-67]
[12.2) [NER) REQUEST Operations personnel in HPCI Room, to ensure that all
unnecessary personnel have exited HPCI Room. [IE 93-67)
[12.3] [NER] ANNOUNCE HPCI turbine startup over plant public address
system. [IE 93-67]
HLTS-3-2
REVO
PAGE 14 OF63
XI. Simulator Event Guide (Continued)
( Event 3a: HPCI Surveillence
POSITION EXPECTED ACTION(S)
BOP [12.4] PLACE HPCI AUXILIARY OIL PUMP 3-HS-73-47A to START.
[12.5] OPEN 3-FCV-73-30, using HPCI PUMP MIN FLOW
VALVE,3-HS-73-30A.
[12.6] ENSURE personnel are ready to monitor 3-FCV-73-18 for smooth
operation. AND NOTIFY the personnel monitoring that the next step will open
3-FCV-73-18.
[12.7] OPEN 3-FCV-73-16, using HPCI TURBINE STEAM SUPPLY VLV, 3-
HS-73-16A.
[12.8] OBSERVE that the following actions occurs:
o HPCI AUXILIARY OIL PUMP starts .
o [NRC/C] HPCI TURBINE STOP VALVE 3-FCV-73-18 opens by observing 3-
ZI-73-18 position indicating lights . [Appendix R]
o HPCI TURBINE CONTROL VALVE 3-FCV-73-19 partially or fully opens by
observing 3-ZI-73-19 position indicating lights.
HLTS-3-2
REVO
PAGE 15 OF 63
XI. Simulator Event Guide (Continued)
( Event 3a: HPCI Surveillence
POSITION EXPECTED ACTION(S)
o [NRC/C] HPCI PUMP MIN FLOW VALVE 3-FCV-73-30 closes when HPCI
SYSTEM FLOW/CONTROL 3-FIC-73-33 indicates approximately ~ 125 (~1250
gpm) flow. [Appendix R]
o HPCI turbine speed rises to greater than 2400 rpm as indicated on HPCI
TURBINE SPEED 3-SI-73-51 .
o HPCI STM LINE CNDS INBD/OUTBD DR VLVS 3-FCV-73-6A and 3-FCV-73-
6B close by observing 3-ZI-73-6A and 3-ZI-73-6B position indicating lights.
o HPCI AUXILIARY OIL PUMP stops as turbine speed rises.
[12.9] VERIFY Smooth operation of 3-FCV-73-18 and mark results below.
Yes _ No _
o IF the Answer above is "NO", THEN NOTIFY System Engineer to initiate a
WO and proceed with test. (Otherwise N/A)
[12.10] VERIFY RESET the following annunciators:
o HPCI PUMP DISCH FLOW LOW 3-FA-73-33
(3-XA-55-3F, window 5)
o HPCI TURBINE TRIPPED 3-ZA-73-18 (3-XA-55-3F, window 11)
o HPCI TURBINE GLAND SEAL DRAIN PRESSURE
HIGH 3-PA-73-46 (3-XA-55-3F, window 14)
o HPCI TURBINE BEARING OIL PRESSURE LOW
3-PA-73-47 (3-XA-55-3F, window 19)
[12.11] VERIFY system flow, discharge pressure, and turbine speed are stable
prior to performing the next step.
(
HLTS-3-2
REVO
PAGE 16 OF63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTIONeS)
BOP Responds to Reactor Bldg Hi Rad alarm per 3-ARP-9-3A window 22
A. 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.)
Determines HPCI area source of hi rad
B. IF the alarm is from the HPCI Room while Flow testing is being performed ,
THEN REQUEST personnel at the HPCI Quad to validate conditions.
C. NOTIFY RADCON.
D. 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
E. IF the TSC is manned and a "VALID" radiological condition exists, THEN
REQUEST the TSC to evacuate non-essential personnel from affected areas.
HLTS-3-2
REV 0
PAGE 17 OF 63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTION(S)
F. MONITOR other parameters providing input to this annunciator frequently as
these parameters will be masked from alarming while this alarm is sealed in.
G. IF a CREV initiation is received, THEN
1. VERIFY CREV A(B) Flow is ~ 2700 CFM, and s 3300 CFM as indicated on 0-
FI-031-7214(7213) within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of the CREV initiation . [BFPER 03-017922]
2. IF CREV A(B) Flow is NOT ~ 2700 CFM, and s 3300 CFM as indicated on 0-
FI-031-7214(7213) THEN
PERFORM the following: (Otherwise N/A) [BFPER 03-017922]
a. STOP the operating CREV per 0-01-31.
b. START the standby CREV per 0-01-31 .
HLTS-3-2
REV 0
PAGE 18 OF63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTIONeS)
BOP Responds to HPCI Leak Detection Temp Hi alarm per 3-ARP-9-3F window 10
A. CHECK HPCI temperature switches on LEAK DETECTION SYSTEM
TEMPERATURE, 3-TI-69-29 on Panel 3-9-21.
B. IF high temperature is confirmed, THEN NTER 3-EOI-3 Flowchart
C. CHECK following on Panel 3-9-11 and NOTIFY RADCON if rising radiation
levels are observed:
1. HPCI ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-24A.
2. RHR WEST ROOM EL 519 RX BLDG radiation indicator, 3-RI-90-25A.
D. DISPATCH personnel to investigate for leaks consistent with ALARA
considerations in HPCI Turbine Area (EI 519) and HPCI Steam Supply Area
(EI550).
Recognizes HPCI not isolated when isolation lights are illuminated
Notifies Unit Supervisor HPCI failed to isolate and 3-FCV-73-2 and 3-FCV-
73-3 are still open.
HLTS-3-2
REV a
PAGE 19 OF63
XI. Simulator Event Guide (Continued)
Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTION(S)
SRO Directs HPCI manually isolated (Critical step)
BOP Mam~HPCI steam supply by closing 3-FCV-73-2 and 3-FCV-
73-3 ~
ATC Receives EOI-3 entry on flood level in HPCI room 3-ARP-9-4c window 10
A. DISPATCH personnel to VISUALLY CHECK the HPCI room.
B. IF possible, THEN
DETERMINE the source of the leak and the leak rate.
SRO Re-enters EOI-3 on flood level
BOP Notifies Rad Con and Fire Protection
Monitors for lowering temperature and radiation levels in HPCI area (after
successful isolation)
HLTS-3-2
REV 0
PAGE 20 OF63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTION(S)
SRO into 3-AQI-6~*2B
BOP Immediate Actions
[1] VERIFY automatic actions occur .
HPCI Turbine TRIPS .
HPCI STEAM LINE INBD ISOL VALVE, 3-FCV-73-2 CLOSES.
HPCI STEAM LINE OUTBD ISOL VALVE, 3-FCV-73-3 CLOSES.
HPCI STEAM LINE WARM-UP VALVE, 3-FCV-73-81 CLOSES.
HPCI PUMP MIN FLOW VALVE, 3-FCV-73-30 CLOSES.
HPCI SUPPR POOL INBD SUCT VLV, 3-FCV-73-26 CLOSES .
HPCI SUPPR POOL OUTBD SUCT VLV, 3-FCV-73-27 CLOSES.
HPCI TURBINE STOP VALVE, 3-FCV-73-18 CLOSES.
HLTS-3-2
REV 0
PAGE 21 OF 63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTION(S)
BOP SUbsequent Actions
[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s).
[2] DISPATCH an operator to the HPCI Turbine room to investigate.
[3] CHECK the following monitors for a rise in activity or area temperature:
AREA RADIATION, 3-RR-90-1, Point 23 (RM-90-24), Panel 3-9-2
AIR PARTICULATE RAD MON, 3-MON-90-50, Address 024 (3-RM-90-58),
Panel 3-9-2
RB & TB REFUELING ZONE EXH RAD MONITOR, 0-CONS-90-362, Address
08, 3-RM-90-250, Panel 1-9-44
LEAK DET SYS, TI-69-29, Panel 3-9-21, DEPRESS pushbutton to read TS-
73-55A through 550.
(
HLTS-3-2
REVO
PAGE 22 OF 63
XI. Simulator Event Guide (Continued)
( Event 3b: HPCI Steam Line Break
POSITION EXPECTED ACTION(S)
BOP [4] VERIFY the following valves OPEN to drain the HPCI steam lines.
MN STM LINE DRAIN INBD VLV, 3-FCV-1-55
OUTBD ISOLATION VLV, 3-FCV-1- -56,
[5] IF the HPCI TURBINE EXH DRAIN POT LEVEL HIGH 3-LA-73-8 (3-XA-55-
3F, Window 33) annunciator is in alarm, THEN PERFORM the following:
[5.1] OPEN the HPCI TURB EXH CNDS POT LCV, 3-LCV-73-8.
[5.2] WHEN the annunciator HPCI TURBINE EXH DRAIN POT LEVEL HIGH
resets, THEN CLOSE the HPCI TURB EXH CNDS POT LCV, 3-LCV-73-8.
SRO Determines unit in 14 day LCO (TS 3.5.1.C - HPCI inop. Verify RCIC
OPERABLE by administrative means)
Determines unit in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO (TS 3.5.1.0 - HPCI and C RHR Inop)
Tech. Specs. 3.6.1.3.B.1, on FCV 73-2 or 73-3 when tagged (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to
close and de-activate)
EXAMINER NOTE: When the valves are closed they are now considered
OPERABLE because they are in the required position following an
isolation signal, however the isolation logic is still INOPERATIVE.
HLTS-3-2
REV a
PAGE 23 OF63
XI. Simulator Event Guide (Continued)
( Event 4: SRV-1-22 Fails Open
POSITION EXPECTED ACTIONeS)
CREW Recognizes SRV open
- Main Steam Relief Valve Open alarm
- lowering generator output
BOP Immediate Action
[1] IDENTIFY stuck open relief valve by OBSERVING the following:
SRV TAILPIPE FLOW MONITOR, 3-FMT-1-4, on Panel 3-9-3, OR
MSRV DISCHARGE TAILPIPE TEMPERATURE, 3-TR-1-1 on Panel 3-9-47.
Determines SRV-1-22 from acoustic monitor
[2] WHILE OBSERVING the indications for the affected Relief valve on the
Acoustic Monitor; CYCLE the affected relief valve control switch several times
as required:
CLOSE to OPEN to CLOSE positions
Cycles relief valve and reports SRV closed
[3] IF all SRVs are CLOSED, THEN CONTINUE at Step 4.2.3. (Otherwise N/A)
(
HLTS-3-2
REV 0
PAGE240F63
XI. Simulator Event Guide (Continued)
(
Event 4: SRV-1-22 Fails Open (continued)
TIME POSITION EXPECTED ACTION(S)
BOP 4.2.3 Other Actions and Documentation
[1] IF ANY EOI entry condition is met, THEN ENTER the appropriate EOI(s).
[2] REFER TO Technical Specifications Sections 3.5.1 and 3.4.3 for
Automatic Depressurization System and relief valve operability
requirements.
[3] INITIATE suppression pool cooling as necessary to maintain suppression
pool temperature less than 95°F.
[4] IF the relief valve can NOT be closed AND suppression pool temperature
Can NOT be maintained less than or equal to 95°F, THEN PLACE the reactor
Mode 4 in accordance with 3-GOI-100-12A.
[5] DOCUMENT actions taken and INITIATE Work Order for the valve.
SRO Evaluates Tech Spec operability of ADS valve lAW TS 3.5.1(H) and
3.4.3(A). Determines valve operable and 3.5.1.H is not applicable, but
requests Eng. evaluation. (Functional evaluation)
HLTS-3-2
REV 0
PAGE 25 OF 63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram
POSITION EXPECTED ACTIONS
ATC Announces Recirc "3A" high vibration alarm 3*ARP*9-4A window 20
A. CHECK temperatures for RECIRC PMP MTR 3A WINDING AND BRG
TEMP recorder, 3-TR-68-58 on Panel 3-9-21 are below those listed for 3-XA-
55-4A, Window 13.
B. CHECK for a rise in Drywell equip sump pumpout rate due to seal leakage.
C. DISPATCH personnel to 3*LPNL*925*0412 (Vibration Mon. System) on EL
565' (S-R17) and REPORT the Vibration Data for Pump A to the Unit Operator
and any other alarm indications. The person shall advise the Unit Operator of
any changes in the vibration values.
D. IF alarm seals in, THEN ADJUST pump speed slightly to try reset the
alarm.
E. IF unable to reset alarm, THEN CONSULT with Shift Manager, and with
his concurrence, SHUTDOWN the Recirc pump and REFER TO 3*AOI-68*
1A or 3*AOI-68*1B.
F. IF pump operation continues, THEN RECORD pump 3A seal parameters
hourly on Attachment 1, Page 22 of this ARP.
HLTS-3-2
REV 0
PAGE 26 OF63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram
POSITION EXPECTED ACTIONS
SRO Contacts Reactor Engineer
ATC Announces Recirc A Seal Leakage Alarm 3-ARP-9-4A window 25
A. DETERMINE initiating cause by comparing NO.1 and 2 seal cavity pressure
indicators on Panel 3-9-4 or ICS.
Plugging of No. 1 RO - NO.2 seal cavity pressure indicator drops toward zero,
and control leakage lowers to ~ 0.5 gpm.
Plugging of NO.2 RO - NO.2 seal pressure approaches no. 1 seal pressure
and control leakage lowers to ~ 0.5 gpm .
Failure of No. 1 seal - NO.2 seal pressure is greater than 50% of the pressure
of NO.1 . The controlled leakage will be ~ 0.9 gpm.
Failure of NO.2 seal - no. 2 seal pressure is less than 50% of the NO.1 seal.
(
HLTS-3-2
REV 0
PAGE 27 OF 63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage , Power Oscillations and Scram
POSITION EXPECTED ACTIONS
ATC Identifies Seal Failure via Instrumentation
Recognizes lowering pressure on Recirc Pump A #1 seal
B. RECORD pump seal parameters hourly on Attachment 1, Page 28 of this
procedure, unless other acceptable compensatory methods for recording these
parameters is evaluated and approved by Engineering .
C. IF single seal failure is indicated, THEN INITIATE seal replacement as soon
as possible . Continued operation is permissible if Drywelileakrate is within T.S.
limits .
SRO Directs crew to watch for signs of increased leakage
ATC Acknowledges Recirc Pump A seal leakoff high alarm; 3-ARP-9-4A
window 18, informs SRO.
Recognizes lowering pressure on Recirc Pump A outboard seal; informs
Monitors drywell parameters; notes pressure and temperature increasing;
informs SRO
(
HLTS-3-2
REV 0
PAGE 28 OF63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram
POSITION EXPECTED ACTIONS
SRO When vibration report received or dual seal failure is reported, directs
'A' Recirc Pump tripped
ATC C. IF dual seal failure is indicated, THEN
1. SHUTDOWN Recirc Pump 3A by depressing RECIRC DRIVE 3A
SHUTDOWN,3-HS-96-19.
2. VERIFY TRIPPED, RECIRC DRIVE 3A NORMAL FEEDER, 3-HS-57-17.
3. VERIFY TRIPPED, RECIRC DRIVE 3A ALTERNATE FEEDER, 3-HS-57-15.
4. CLOSE Recirculation Pump 3A suction valve.
- REPORT to SRO of failure of suction valve to close.
Directs AUO to close Recirc Pump suction valve locally at Board.
5. CLOSE Recirculation Pump 3A discharge valve.
6. EFER TO 3-AOI-68-1A or 3-AOI-68-1B AND 3-01~8 .
7. DISPATCH personnel to secure Recirculation Pump 3A seal water.
(
HLTS-3-2
REV 0
PAGE 29 OF 63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
ATC [2] Checks Power to flow map to verify in region 1 or 2
Informs SRO of being in region 1
Checks APRMs and LPRMs for indication of power oscillations
Informs SRO of Power Oscillations
SRO Directs inserting emergency shove sheet control rods
BOP Keeps SRO informed as drywell pressure approaches 2.45 psig
HLTS-3-2
REV 0
PAGE 30 OF63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
SRO irects ventin er 3-AOI-64-1
EXAMINER NOTE: Venting may not be performed based on Drywell
pressure.
[3] VENT Drywell as follows :
[3.1] CLOSE SUPPR CHBR INBD ISOLATION VLV 3-FCV-64-34 (Panel 3-9-
3).
[3.2] VERIFY OPEN , DRYWELL INBD ISOLATION VLV, 3-FCV-64-31 (Panel 3-
9-3).
[3.3] VERIFY 3-FIC-84-20 is in AUTO and SET at 100 scfm (Panel 3-9-55) .
[3.4] VERIFY Running, required Standby Gas Treatment Fan(s) SGTS Train(s)
A, B, C (Panel 3-9-25) .
[3.5] IF required, THEN REQUEST Unit 1 Operator to START Standby Gas
Treatment Fan(s) SGTS Train(s) A, B. (Otherwise N/A)
HLTS-3-2
REVO
PAGE 31 OF 63
XI. Simulator Event Guide (Continued)
(
Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
[3.6] IF required , THEN RECORD venting data in 3-SI-4.7.A.2.a (Otherwise
N/A)
[3.7] PLACE 3-FCV-84-20 CONTROL DW/SUPPR CHBR
VENT, 3-HS-64-35, in OPEN (Panel 3-9-3).
[3.8] MONITOR stack release rates to prevent exceeding ODCM limits.
Directs Logs person to monitor release rates
SRO Directs manual reactor scram prior to reaching 2.45psig DW pressure
HLTS-3-2
REV 0
PAGE 32 OF 63
XI. Simulator Event Guide (Continued)
Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
SRO irects 3-AOI-100-1
ATC Carry out actions of 3-AOI-100-1
SRO irects ventin
BOP 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.
HLTS-3-2
REVO
PAGE 33 OF63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
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.
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:
3-FIC-84-19, PATH B VENT FLOW CO NT, OR
3-FIC-84-20, PATH A VENT FLOW CO NT.
NOTE: Unless the TSC recommends otherwise, venting the Drywell DIRECTLY
should be performed ONLY if the Suppression Chamber can NOT be vented .
(
HLTS-3-2
REV 0
PAGE 34 OF63
XI. Simulator Event Guide (Continued)
( Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
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.
HLTS-3-2
REV 0
PAGE 35 OF 63
XI. Simulator Event Guide (Continued)
(
Event 5: Recirc Vibration , Seal Leakage , Power Oscillations and Scram (Continued)
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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PAGE 36 OF 63
XI. Simulator Event Guide (Continued)
(
Event 5: Recirc Vibration, Seal Leakage, Power Oscillations and Scram (Continued)
POSITION EXPECTED ACTIONS
BOP 12. ADJUST 3-FIC-84-19, PATH 8 VENT FLOW CONT, or 3-FIC-84-20, PATH
A VENT FLOW CO NT, as applicable, to maintain ALL of the following:
o Stable flow as indicated on controller, AND
o 3-PA-84-21, VENT PRESS TO SGT HIGH, alarm light extinguished, AND
o 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 00 Stack release rate of 1.4 x 107 J.lCi/s
AND 0-SI-4.8.8.1.a.1 release fraction of 1.
BOP Contacts LOG AUO to monitor release rates
(
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PAGE 37 OF63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA
TIME POSITION EXPECTED ACTION(S)
SRO - Directs RPV pressure controlled 800 to 1000 psig with one or more of
the following :
- Directs RPV level be maintained between +2" to +51" with one or more
of the following:
-RCIC (App 5C) (will not work)
-CRD (App 56)
60P Controls pressure 800 to 1000 psig with one or more of the following:
1. IF ..... Drywell Control Air is NOT available, THEN ... EXECUTE EOI
Appendix aG, CROSSTIE CAD TO DRYWELL CONTROL AIR,
CONCURRENTLY with this procedure.
2. IF ..... Suppression Pool level is at or below 5.5 ft, THEN ... CLOSE MSRVs
and CONTROL RPV pressure using other options.
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PAGE 38 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA
POSITION EXPECTED ACTIONS
BOP 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 D 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 D 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 D 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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PAGE 39 OF63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA
POSITION EXPECTED ACTIONS
BOP Recognizes MSIV closures and reports to SRO.
BOP Controls RPV level +2 to +51 with one or more of the following:
1. IF ..... Maximum injection flow is NOT required, THEN ... VERIFY CRD
aligned as follows:
a. VERIFY at least one CRD pump in service and aligned to Unit 3 CRD system.
b. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, as necessary to
obtain flow rate of 65 to 85 gpm.
c. THROTTLE 3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV, to
maintain 250 to 350 psid drive water header pressure differential.
d. EXIT this procedure.
(
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PAGE 40 OF 63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA
POSITION EXPECTED ACTIONS
2. IF ... .. BOTH of the following exist:
CRD is NOT required for rod insertion, AND Maximum injection flow is required,
THEN ... LINE UP ALL available CRD pumps to the RPV as follows:
a. IF ..... CRD Pump 3A is available, THEN ... VERIFY RUNNING CRD Pump
3A or 3B.
b. IF .... . CRD Pump 3B is available, THEN ... VERIFY RUNNING CRD Pump
3A or 3B.
c. OPEN the following valves to increase CRD flow to the RPV:
3-PCV-85-23, CRD DRIVE WATER PRESS CONTROL VLV
3-PCV-85-27, CRD CLG WATER PRESS CONTROL VLV
3-FCV-85-50, CRD EXH RTN LINE SHUTOFF VALVE.
BOP Reports 38 CRD pump tripped
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PAGE 41 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTIONS
BOP d. ADJUST 3-FIC-85-11, CRD SYSTEM FLOW CONTROL, on Panel 9-5 to
control injection WHILE maintaining 3-PI-85-13A, CRD ACCUM CHG WTR
HDR PRESS, above 1450 psig, if possible.
e. IF Additional flow is necessary to prevent or mitigate core damage,
THEN DISPATCH personnel to fully open the following valves as required:
o 3-THV-085-0527, CRD PUMP DISCH THROTTLING (RB NE, e1565')
o 3-BYV-085-0551 , CRD PUMP TEST BYPASS (RB NE, el 565').
SRO Directs determining the cause of the isolation
Directs H20 2 Analyzers placed in service
BOP Places H2 0 2 Analyzers in service
1. Place Analyzer isolation bypass keylock switches to bypass.
2. Select OW or Supp Chmbr and momentarily pull out select switch
handle to start sample pumps.
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PAGE 42 OF63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTIONeS)
SRO Directs SP coolin be laced in service Rer A R 17~
BOP Places SP cooling in service per App 17A
2. PLACE RHR SYSTEM 1(11) in Suppression Pool Cooling as follows:
a. VERIFY at least one RHRSW pump supplying each EECW header.
b. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).
c. THROTTLE the following in-service RHRSW outlet valves to obtain
between 1350 and 4500 gpm RHRSW flow:
3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV
3-FCV-23-46, RHR HX 38 RHRSW OUTLET VLV
3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV
3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.
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PAGE430F63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
d. IF ..... Directed by SRO, THEN ... PLACE the following keylock switches
in MANUAL OVERRIDE:
3-XS-74-122, RHR SYS I LPCI2/3 CORE HEIGHT OVRD.
3-XS-74-130, RHR SYS II LPCI2/3 CORE HEIGHT OVRD.
e. IF ..... LPCIINITIATION Signal exists, THEN ... MOMENTARILY PLACE
the following in select:
3-XS-74-121, RHR SYS I CTMT SPRAY/CLG VLV SELECT.
3-XS-74-129, RHR SYS II CTMT SPRAY/CLG VLV SELECT.
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PAGE 44 OF 63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTIONeS)
BOP f. IF 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN ,
THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)
g. OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL ISOL VLV.
h. VERIFY desired RHR pump(s) for Suppression Pool Cooling are operating.
i. THROTTLE 3-FCV-74-59(73), RHR SYS 1(11) SUPPR POOL CLGITEST VLV,
to maintain EITHER of the following as indicated on 3-FI-74-50(64), RHR
SYS 1(11) FLOW:
Between 7,000 and 10,000 gpm for one-pump Operation. OR
At or below 13,000 gpm for two-pump operation.
j. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE
(VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),
Compartment 4E(4E), if required).
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PAGE 45 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
k. MONITOR RHR Pump NPSH using Attachment 1.
I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat
Exchangers.
m. IF ..... Additional Suppression Pool Cooling flow is necessary, THEN ...
PLACE additional RHR and RHRSW pumps in service using Steps 2.b through
2.1.
ATC/BOP Monitors containment parameters
SRO nters EOI-2 on OW Rressul'e and re-enters EOI-1 and directs the
following:
Verify all available DW coolers in service
SRO Directs cooldown
ATC/BOP Verify all available DW coolers in service
ATC/BOP Commences a cooldown as directed
SRO Determines cannot maintain suppression chamber pressure less than
12 psig and directs suppression chamber sprayed
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PAGE 46 OF63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
BOP ression chamber 17Q
1. BEFORE Suppression Chamber pressure drops below 0 psig, CONTINUE in
this procedure at Step 6.
2. IF ..... Adequate core cooling is assured, OR Directed by EOI-2 to spray the
Suppression Chamber irrespective of adequate core cooling , THEN ... BYPASS
LPCllnjection Valve Timers as necessary using EOI Appendices 16F and
16G.
3. IF .. ... Directed by SRO to spray the Suppression Chamber using Standby
Coolant Supply, THEN ... CONTINUE in this procedure at Step 7.
4. IF ... .. Directed by SRO to spray the Suppression Chamber using Fire
Protection, THEN ... CONTINUE in this procedure at Step 8.
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PAGE 47 OF 63
XI. Simulator Event Guide (Continued)
(
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
5. INITIATE Suppression Chamber Sprays as follows:
a. VERIFY at least one RHRSW pump supplying each EECW header.
b. IF..... EITHER of the following exists :
. LPCllnitiation signal is NOT present, OR
Directed by SRO, THEN ... PLACE keylock switch 3-XS-74-122(130), RHR
SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.
c. MOMENTARILY PLACE 3-XS-74-121 (129), RHR SYS 1(11) CTMT
SPRAY/CLG VLV SELECT, switch in SELECT.
d. IF 3-FCV-74-53(67), RHR SYS 1(11) INBD INJECT VALVE, is OPEN ,
THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11) OUTBD INJECT
VALVE.
e. VERIFY OPERATING the desired RHR System 1(11) pump(s) for Suppression
Chamber Spray.
f. VERIFY OPEN 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL (SOL
VLV.
g. OPEN 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.
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PAGE 48 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
BOP h. IF..... RHR System 1(11) is operating ONLY in Suppression Chamber Spray
mode, THEN... CONTINUE in this procedure at Step 5.k.
i. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE
(VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),
Compartment 4E(4E), if required).
[, RAISE system flow by placing the second RHR System 1(11) pump in
service as necessary.
k. MONITOR RHR Pump NPSH using Attachment 2.
I. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).
m. THROTTLE the following in-service RHRSW outlet valves to obtain
between 1,350 and 4,500 gpm flow:
. 3-FCV-23-34, RHR HX 3A RHRSW OUTLET VLV
. 3-FCV-23-46, RHR HX 38 RHRSW OUTLET VLV
3-FCV-23-40, RHR HX 3C RHRSW OUTLET VLV
3-FCV-23-52, RHR HX 3D RHRSW OUTLET VLV.
n. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat
Exchangers.
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PAGE 49 OF63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
BOP 6. WHEN ... EITHER of the following exists:
Before Suppression Pool pressure drops below 0 psig, OR
Directed by SRO to stop Suppression Chamber Sprays, THEN ... STOP
Suppression Chamber Sprays as follows:
a. CLOSE 3-FCV-74-58(72), RHR SYS 1(11) SUPPR CHBR SPRAY VALVE.
b. VERIFY CLOSED 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE
c. IF..... RHR operation is desired in ANY other mode, THEN... EXIT this EOI
Appendix .
d. STOP RHR Pumps 3A and 3C (3B and 3D).
e. CLOSE 3-FCV-74-57(71), RHR SYS 1(11) SUPPR CHBR/POOL ISOL VLV.
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PAGE 50 OF63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
SRO When SC pressure exceeds 12 psig or if SRO determines cannot
maintain OW temp. <280 then directs the following:
- Ensures Recirc. pumps shutdown
- OW blowers secured
17B
ATC Trips Recirc. pumps
BOP Secures OW blowers
Requests 16F & 16G be performed
Sprays the DW using RHR per App 17B
1. BEFORE Drywell pressure drops below 0 psig, CONTINUE in this procedure
at Step 7.
2. IF ..... Adequate core cooling is assured, OR Directed to spray the Drywell
irrespective of adequate core cooling, THEN ... BYPASS LPCllnjection Valve
Timers as necessary using EOI Appendices 16F and 16G.
(
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PAGE 51 OF 63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
BOP 3. VERIFY Recirc Pumps and Drywell Blowers shutdown.
4. IF Directed by SRO to spray the Drywell using Standby Coolant supply,
THEN CONTINUE in this procedure at Step 8.
5. IF ..... Directed by SRO to spray the Drywell using Fire Protection , THEN ...
CONTINUE in this procedure at Step 9.
6. INITIATE Drywell Sprays as follows:
a. VERIFY at least one RHRSW pump supplying each EECW header.
b. IF..... EITHER of the following exists:
LPCI Initiation signal is NOT present, OR
. Directed by SRO, THEN ... PLACE keylock switch 3-XS-74-122(130), RHR
SYS 1(11) LPCI 2/3 CORE HEIGHT OVRD, in MANUAL OVERRIDE.
c. MOMENTARILY PLACE 3-XS-74-121 (129), RHR SYS 1(11) CTMT
SPRAY/CLG VLV SELECT, switch in SELECT.
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PAGE 52 OF 63
XI. Simulator Event Gu ide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
d. IF 3-FCV-74-53(67), RHR SYS 1(11) LPCIINBD INJECT VALVE, is OPEN,
THEN VERIFY CLOSED 3-FCV-74-52(66), RHR SYS 1(11)
e. VERIFY OPERATING the desired System 1(11) RHR pump(s) for Drywell
Spray.
f. OPEN the following valves:
. 3-FCV-74-60(74), RHR SYS 1(11) OW SPRAY OUTBO VLV
. 3-FCV-74-61(75), RHR SYS 1(11) OW SPRAY INBO VLV.
g. VERIFY CLOSED 3-FCV-74-7(30), RHR SYSTEM 1(11) MIN FLOW VALVE
(VERIFY CLOSED 3-BKR-074-0007(0030) on 480V RMOV Board 3D(3E),
Compartment 4E(4E), if requ ired) .
(
HLTS-3-2
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PAGE 53 OF63
XI. Simulator Event Guide (Continued)
( EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
BOP h. IF..... Additional Drywell Spray flow is necessary, THEN *.. PLACE the
second System 1(11) RHR Pump in service.
i. MONITOR RHR Pump NPSH using Attachment 2.
j. VERIFY RHRSW pump supplying desired RHR Heat Exchanger(s).
k. THROTTLE the following in-service RHRSW outlet valves to obtain
between 1,350 and 4,500 gpm RHRSW flow:
I. NOTIFY Chemistry that RHRSW is aligned to in-service RHR Heat
Exchangers.
(
HLTS-3-2
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PAGE 54 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA(continued)
TIME POSITION EXPECTED ACTION(S)
SRO Directs OW sprays/SC sprays be stopped when that area reaches 0
psig
BOP Stops DW/SC sprays when that area reaches 0 psig
Monitors containment parameters
SRO Monitors RPV water level, determines level is lowering. Re-enters EOI-1 at
+2" RPV level
Directs performance of App 7B (SLC)
ATC Calls Rx Bldg AUO to perform App 7B
Crew Monitors Drywelll PSC I and RPV water level
SRO nters C1 at A:I -100" to - 122u
Directs ADS inhibited
ATC Closes RFP discharge valves
Reports 3A CROP tripped
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PAGE 55 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
SRO After entering C1 align all available injection systems for injection.
-Containment sprays terminated
When water level reaches TAF (-162") and before - 200 directs the
following:
Enters C2 (Critical step)
Six ADS valves opened (Critical step)
RPV level returned +2" to +51"
BOP When directed by US terminates Containment Sprays and lines up
RHRforLPCI
BOP Opens and verifies open 6 ADS valves Critical ste )
SRO Directs restoring Rx level with Condensate, Core Spray, or RHR
(Critical step)
SRO Classifies event as Site Area Emergency (1.1-81)
ATC/BOP Restores RPV water level +2" to +51" using: (Critical step)
-RHR
-Core Spray
-Condensate
(
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PAGE 56 OF 63
( XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
'A 6A Condensate
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 381 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 38 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 385 CNDS INLET ISOL VLV
3-FCV-2-96, DRAIN COOLER 3C5 CNDS INLET ISOL VLV
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PAGE 57 OF 63
( XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSURE/LOCA (continued)
TIME POSITION EXPECTED ACTION(S)
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 383 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 382 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 381 FW OUTLET ISOL VLV
3-FCV-3-77, HP HTR 3C1 FW OUTLET ISOL VLV
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PAGE 58 OF 63
XI. Simulator Event Guide (Continued)
EVENT 6: MSIV CLOSUREILOCA (continued)
TIME POSITION EXPECTED ACTION(S)
6. VERIFY OPEN the following RFP suction valves:
3-FCV-2-83 , RFP 3A SUCTION VALVE
3-FCV-2-95, RFP 38 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-LIC-3-53, RFW START-UP LEVEL CONTROL, to control
injection (Panel 3-9-5).
(