ML18038B575
| ML18038B575 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/13/1995 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18038B574 | List: |
| References | |
| NUDOCS 9512180209 | |
| Download: ML18038B575 (25) | |
Text
ENCLOSURE TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS Iq 2 q AND 3 SIMULATOR FOUR YEAR TEST REPORT TAB E OF CON ENTS I. Introduction II. General Discussion III. Description of Performance Tests Completed A.
B.
C.
D.
E.
F.
G.
Steady State Test Drift Test Transient Test Procedures Test Malfunction Test Real Time Test Simulator Fidelity IV. Uncorrected Test Performance Deficiencies and Correction Schedule A.
B.
C.
D.
E.
Steady State Test Transient Test Procedures Test Malfunction Test Spare Time Test V. Description of Test Differences VI. Simulator Test Schedule TABLES Table 1
Table 2
Table 3
Table 4
Table 5
Table 6
Table 7
Table 8
Table 9
Steady State Test Critical Parameters Steady State Non-Critical Parameters Simulator Transient Test Description
- Transient Parameters Normal and Abnormal Operating Plant Instructions Test Description and Schedule Malfunction List and Certification Test Schedule Simulator Certification Testing Schedule Simulator Exceptions
- Simulator Limitations
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INTRODUCTION This test report is required by 10 CFR 55.45(b)(5)(ii), to be submitted to NRC every four years on the anniversary of the initial certification report.
The four year NRC Form-474 date for certification is December 13, 1995.
Initial Simulator test schedules were given in the certification letter submitted in December 1991 to NRC.
Tests were completed as required by American National Standards Institute (ANSI) 3.5-1985 and were performed each year as outlined in the initial proposed schedule.
This report outlines the methods and the unresolved deficiencies for each test.
ZZ GENERAL DISCUSSION Since the initial certification, the BFN simulator has been used continually for various training at BFN.
The simulator has been maintained in accordance with ANSI-3.5, and additional self-imposed requirements.
Modifications and tuning adjustments are routinely made as plant data is made available, thus, simulation models are maintained as close to the referenced plant as practical.
ZIZZ DESCRIPTZON OF PERFORMANCE TESTS COMPLETED The following is a summary of the tests completed on the BFN simulator over the past four years.
Test results are maintained in the BFN Simulator Services Section.
They are maintained per the requirements of 10 CFR 55.45(b)(5)(iii).
Any parameter failing these tests had a Simulator Discrepancy Report (SDR) written to correct the simulation calculation of the failed parameter.
Any uncorrected test deficiencies are listed in the Uncorrected Test Performance Deficiencies and Correction
- Schedule,Section IV of this report.
A.
Steady State Test Each year the steady state tests were performed on the simulator at three power levels.
Plant critical and non-critical parameters (Tables 1 and 2) were compared to the simulator values at each power level.
The differences were calculated automatically for both critical and non-critical parameters.
Acceptable differences were calculated based on + 2 percent of span for critical and
+ 10 percent of span for non-critical parameters for each individual instrument.
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B. Drift Test The drift test was performed each year for the past four years.
The simulator was reset to a 100 percent power initial condition and data was collected for an hour for each of the critical parameters at a rate of one sample per second.
Plots were made with this data and checked for stability.
A parameter would fail the test if it drifted beyond
+
2 percent of the initial value any time during the hour test.
C.
Transient Test The required ANSI-3.5 transient tests, listed in Table 3, were performed each year for four years.
Test results were compared to the initial certification transients.
Data was collected for each of the required parameters listed in Table 4 at a rate of four samples per second.
These results were then plotted and compared with the previous year responses.
Problems identified were documented by the initiation of a SDR.
Simulation model changes, as a result of corrected simulator problems and plant modifications implemented on the simulator, were taken into account for each transient performed to ensure proper plant behavior.
D.
Procedures Test Approximately 25 percent of the procedure tests were performed each year for four years (Table 5).
The 25 percent represents the approximate amount of actual work time to perform the test.
The following is a summary of the tests performed:
Year 1-General Operating Instructions (GOIs)
Year 2-Surveillance Instructions (SIs)
Year 3-Emergency Operating Instructions (EOIs)
Year 4-Abnormal Operating Instructions (AOIs)
The tests used the latest revision of the BFN Unit 2 plant controlled procedures.
Problems encountered during the procedures tests were documented on a SDR.
E.
Malfunction Test Approximately 25 percent of the certified malfunctions were tested each year for four years.
Prior to each
- test, the Malfunction Cause and Effects document was reviewed by test personnel to identify anticipated simulator responses and to consider appropriate operator actions.
The simulator was then initialized E-3
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to an appropriate Initial Condition and the malfunction was inserted.
Test personnel observed the simulator responses and took appropriate actions.
See Table 6
for BFN simulator's certified malfunctions.
F.
Real Time Test G.
The simulator executive used a frame-based scheduling algorithm in which each second of real time was equally divided into a number of smaller units of time called frames.
The simulator executive collects frame timing and copies this data to a global region.
A non-simulator task collects the global data to a file which is processed later by an offline program which produces plots and tables indicating real time usage.
Simulator Fidelity When modifications were initiated in the plant, the design changes were reviewed by the simulator staff for simulator impact and if applicable, were incorporated into the simulator.
In addition, plant and simulator control room photographs were made of all simulated panels after major control room modifications and were compared.
Differences were reconciled based on training impact.
The photographs helped to capture any additional changes made to the plant that were not detected through the normal design change review process.
Major differences in hardware and software fidelity that remain and are not planned to be corrected, are tracked as Exception Reports.
The initial certification identified 14 Exceptions.
During the past four years, one exception was closed.
See Table 8
for the current list of Simulator Exceptions.
The BFN Simulator imposes six limits of simulation.
Since the exact response of the plant would be unknown beyond these limits, the simulation is stopped automatically or "frozen."
This protects the students from negative training.
The limits of simulation are listed in Table 9.
IV+
UNCORRECTED TEST PERFORMANCE DEFICIENCIES AND CORRECTION 8CHEDULE The following is a summary of the uncorrected performance test deficiencies encountered during simulator certification testing over the last four years.
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Steady State Test Deficiencies:
DR-2751 Simulator recirculation pump flows were outside the acceptance criteria.
The planned correction date for DR-275 is December 13, 1996.
DR-2953 Simulator feedwater temperatures were outside the acceptance criteria.
The planned correction date for DR-2953 is December 13, 1996.
Transient Testing Deficiencies:
DR-2951 Slight change in reactor power response between 1994/1995 dual recirculation pump trip.
The planned correction date for DR-2952 is December 13, 1996.
DR-2952 Slight change in reactor pressure and feedwater flow response between 1994/1995 for main steam line break.
The planned correction date for DR-2952 is December 13, 1996.
Procedures test Deficiencies:
There are no uncorrected performance deficiencies for procedure tests.
Malfunction Test Deficiencies There are no uncorrected performance deficiencies for malfunction tests.
Spare Time Deficiencies DR-2754 During Loss of Offsite power with 100 percent LOCA the simulator will run non-real time momentarily.
The planned correction date for DR-2754 is December 13, 1996.
DESCRIPTION OP TEST DIPPERENCES For the next four years all tests will be performed in the same manner as the previous test period.
There will be minor changes made to the parameters collected for the Steady State and the Transient tests which are summarized below.
The Steady State parameter list was changed to show actual Integrated Computer System (ICS) parameters collected.
ICS parameters are used in order to enable a direct comparison between plant and simulator data.
The Transient parameter list was changed from three separate lists to one common list of parameters.
This simplified the transient data collection process and E-5
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enhanced the evaluation and validation of the transient plots.
A list of the Transient parameters is shown in Table 4.
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SIMULATOR TEST SCHEDULE The next four year test schedule is shown in Table 7.
Annual Test Periods 1 through 4 are for years 1996 through 1999 which comprise the next four year simulator certification cycle.
Table 5 lists the procedures to be tested for each year.
Table 6 lists the malfunctions to be tested for each year.
The Steady State, Drift, Transient, and Real Time tests will be performed each year.
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Table 1 STEADY STATE TEST CRITICAL PARAMETERS PARAMETER CALC002 3-59 CALC025 3-54 68-49 APRMA APRMB APRMC APRMD APRME APRMF 3-48A 3-50A CALC041 68-5A 68-81B CALC040 1-81 2-1 2-5 2-8 68-15A 68-25 A 68-38A 68-7A 68-45 68-47 3-53/60 85-11C 85-7-1 LOW 850 100
-15 HIGH 1050 1300 1500 120 125 125 125 125 125 125 430 430 70 70 16 755 80 80 60 100 600 UNITS PSIG MWE PSIG MLB/HR
% POWER
% POWER
% POWER
% POWER
% POWER
% POWER DEGF DEGF MLB/HR KGPM KGPM MLB/HR PSIG INHGA INHGA INHGA MLB/HR MLB/HR MLB/HR MLB/HR MLB/HR MLB/HR INCHES GPM DEGF DESCRIPTION REACTOR POWER NSSS CALCULATED RX PRESSURE-NARROWRANGE REACTOR POWER ELECTRICAL RX PRESSURE-WIDE RANGE TOTALCORE FLOW APRM CHANNELA APRM CHANNELB APRM CHANNELC APRM CHANNELD APRM CHANNELE APRM CHANNELF RFW LINE A TEMP RFW LINE B TEMP MN STM LEAVINGREACTOR RECIRC PUMP A FLOW RECIRC PUMP B FLOW RFW FLOW TO REACTOR FIRST STAGE PRESSURE GOV END CNDR A HOTWELLPRESSURE (ABS)
CNDR B HOTWELL PRESSURE (ABS)
CNDR C HOTWELLPRESSURE (ABS)
RECIRC JET PUMP //1 FLOW RECIRC JET PUMP S6 FLOW RECIRC JET PUMP 011 FLOW RECIRC JET PUMP //1 6 FLOW RECIRC JET PUMP LOOP FLOW A RECIRC JET PUMP LOOP FLOW B RX LEVEL-NORMALCONTROL RANGE CONTROL ROD DRIVE FLOW CONTROL ROD 02-43 DRIVE TEMP E-7
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Table 2
STEADY STATE NON-CRITICAL PARAMETERS PARAMETER 2-29A 2-17 2-48 2-70 2-105 3-20 3-13 3-8 3-16 3-9 3-2 3-115A 3-141 A 3-166A 5-6 5-'IO 5-'I4 5-18 5-22 5-26 5-40 5-53 5-68 5-33 5-48 5-59 5-29 5-42 5-55 3-45 2-3 2-2 69-358 69-608 89-BA 69-6D LOW
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-16
-15
-15
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-15 HIGH 15 150 150 500 1500 1500 1500 8000 8000 250 250 250 150 150 150 100 100 50 50 60 1600 80 150 600 800 UNITS MLB/HR PSIG PSIG PSIG PSIG MLB/HR MLB/HR ML8/HR PSIG PSIG PSIG RPM RPM RPM PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG PSIG INCHES DEGF GPM GPM DEGF DEGF DESCRIPTION CNDS PMP DISCH HDR FLOW CNDS PMP DISCH HDR PRESS CNDS BSTR PMP SUCT HDR PRESS CNDS BSTR PMP DISCH HDR PRESS RFP SUCTION HEADER PRESSURE RFP A FLOW RFP 8 FLOW RFP C FLOW RFP A DISCH PRESS RFP 8 DISCH PRESS RFP C DISCH PRESS RFPT A SPEED RFPT 8 SPEED RFPT C SPEED HTR A1 SHELL STEAM PRESSURE HTR 81 SHELL STEAM PRESSURE HTR C1 SHELL STEAM PRESSURE HTR A2 SHELL STEAM PRESSURE HTR 82 SHELL STEAM PRESSURE HTR C2 SHELL STEAM PRESSURE HTR A3 SHELL STEAM PRESSURE HTR 83 SHELL STEAM PRESSURE HTR C3 SHELL STEAM PRESSURE HTR A4 SHELL STEAM PRESSURE HTR 84 SHELL STEAM PRESSURE HTR C4 SHELL STEAM PRESSURE HTS A5 SHELL STEAM PRESSURE HTR 85 SHELL STEAM PRESSURE HTR C5 SHELL STEAM PRESSURE RFW PRESSURE TO REACTOR CNDR A HOTWELL LEVEL CNDR A HOTWELLTEMP RWCU DEMIN 2A FLOW RWCU DEMIN 28 FLOW RWCU LOOP INLETTEMP RWCU LOOP OUTLET TEMP E-8
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Table 3 SIMULATOR TRANSIENT TEST DESCRIPTION Test Number Test Description InitiatingEvents'est Duration Manual Scram.
Simultaneous trip of all feedwater pumps.
Simultaneous closure of all Main Steam Isolation Valves.
Simultaneous trip of all recirculation pumps.
Single recirculation pump trip.
Main turbine trip (maximum power, level which does not result In immediate reactor scram).
Maximum rate power ramp (master recirculation flow oontroller In "manual" )
down to approximately 75% and back up to 100%.
Depressing both manual scram pushbuttons Malfunctions FW13A-C "Spurious RFPT Excessive Thrust Bearing Wear Trip" Malfunction RP11 "Inadvertent MSIV Isolation" Malfunctions TH03AKB"Recirc Pump Tnp" Malfunction TH03A Reciro Pump Trip" Malfunction TC01 "Turbine Trip" Manually rampad master recirc controller PIC-98-1 to 75% power demand and let set approximately 2 minutes end then ramped back to the 100% power demand.
10 minutes 20 minutes 10 minutes 10 minutes 10 minutes 10 minutes 10 minutes Maximum size reactor coolant system rupture combined with loss of ell offsite power.
Malfunctions TH21 "Recirc Pump Suction, 10 minutes Une Break" et 100% severity and ED01 "Loss of all Offsite Power" 10 Maximum size unisolable main steam line rupture.
Simultaneous closure of all Main Steam Isolation Valves combined with single stuck open safety/relief valve. (Inhibit activation of high pressure Emergency Core Cooling Systems).
Malfunction TH33A "Main Steam Une Break Inside Containment" Malfunctions RP11 "Inadvertent MSIV Isolation" and AD01A Relief Value Failure (PCV-1-5)" with RCIC and HPCI disabled.
10 minutes 10 minutes NOTE: 'Initiating events may be changed at the discretion of the test team to accomplish test objective.
Table 4 Transient Parameters PARAMETER APRM A-METER APRM B-METER APRM C-METER APRM D-METER APRM E-METER APRM F-METER EI-57-50 FI-68-46 FI-68-48 Fl-74-50 Fl-74-64 Fl-75-21 FI-75-49 FIC-71-36A FIC-73-33 FR-46-5 (FT-3-78)
FR-46-5 (PT-1-78)
FR-68-5 (FT-68-5A)
FR-68-5 (FT-68-81 B)
LI-3-52 LI-3-53 LI-3-58A PR-3-53 (PT-3-59)
PR-3-53 (PT-3-53)
Tl-64-1 61 XR-3-53 (FT-3-78)
XR-64-50B XR-64-52 (TE-64-52)
XR-64-50 (TE-64-50)
FR-68-50 (FT-3-78)
-e98
-268
-155 850 30
-15 HIGH 125 125 125 125 125 125 1300 25000 25000 10000 700 6000 16 16 70000 70000 32 eo eo 1500
'050 230 16 e5 400 400 12 UNITS
% POWER
% POWER
% POWER
% POWER
% POWER
% POWER MLB/HR MLB/HR GPM GPM GPM GPM GPM GPM MLB/HR MLB/HR GPM GPM INCHES INCHES INCHES PSIG PSIG DEGF MLB/HR PSIG DEGF DEGF ML8/HR DESCRIPTION APRM CHANNELA APRM CHANNELB APRM CHANNELC APRM CHANNELD APRM CHANNELE APRM CHANNELF MEGAWATTSELECTRIC NO 11 THRU NO 20 JET PMP FLOW NO 1 THRU NO 10 JET PMP FLOW RHR SYSTEM I TOTALFLOW RHR SYSTEM II TOTALFLOW CS SYS I FLOW TO REACTOR CS SYS II FLOW TO REACTOR RCIC SYSTEM FLOW HPCI SYSTEM FLOW TOTALSTEAM FLOW TURBINE STEAM FLOW RECIRC PUMP A DISCH FLOW RECIRC PUMP B DISCH FLOW RX WATER LEVEL POST ACCIDENT RANGE NARROW RANGE REACTOR LEVEL WIDE RANGE REACTOR LEVEL NARROW RANGE REACTOR PRESSURE WIDE RANGE REACTOR PRESSURE SUPPRESSION POOL BULKTEMPERATURE TOTALFEEDWATER FLOW DRYWELLPRESSURE SUPPRESSION POOL TEMPERATURE DRYWELLTEMPERATURE CORE FLOW E-10
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Table 5 - NORMAL AND ABNORMAL OPERATING PLANT INSTRUCTIONS TEST DESCRIPTION AND SCHEDULE Test Number Annual Test Period 1st yr.
2nd yr.
3rd yr.
4th yr.
Test Description Plant start up from cold shutdown to 100% power and plant shutdown from 100% power, using the BFNP Unit 2 General Operating Instructions (GOls).
Perform the BFNP Unit 2 Surveillance Instructions (Sls).
Perform the BFNP Unit 2 Emergency Operating Instruct(ons (EO!s) including appendicies.
Perform the BFNP Unit 2 Abnormal Operating Instructions (AOls).
Test Date Planned Start 11/199B 11/1 997 11/1998 10/1999
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Table 6
MALFUNCTION LIST AND CERTIFICATION TEST SCHEDULE Annual Test Period Item Number 9
10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31
.32 33 34 35 36 37 38 39 Malfunction Doser(Ption Malfunction Definition MAINSTEAM LINE BREAK INSIDE CONTAINMENT RWCU SYSTEM SUCTION LINE BREAK RECIRC PUMP SUCTION LINE BREAK COOLANT LEAKINSIDE DRYWELL RELIEF VALVEFAILURES LOSS OF CONTROL AIR DG TRIP LOSS OF OFFSITE POWER LOSS OF 4KV SHUTDOWN BOARD LOSS OF 250V BATTERYBOARD 2 LOSS OF UNIT PREFERRED RECIRC PUMP TRIP LOSS OF CONDENSER VACUUM CONDENSER HOTWELLLEVELAUTOMATICMAKEUP FAILURE RCW PUMP TRIP PARTIALLOSS OF PLANT PREFERRED SYSTEM FAILTHE FOLLOWING PRESS INSTRUMENTS LOSS OF RBCCW FLOW TO THE DRYWELL CONDENSATE PUMP TRIP SPURIOUS RFPT LOW SUCTION PRESS TRIP RCIC LOW SUCTION PRESS TURBINETRIP RPS CHANNELMG SET FAILURE DRIFT ANYCONTROL ROD OUT UNCOUPLE ANYCONTROL ROD STICK ANYCONTROL ROD DRIFT ANYCONTROL ROD IN RMCS TIMER FAILURE FUEL CLADDINGDAMAGE TURBINETRIP GENERATOR LOCKOUT DUE TO TRANSFORMER FAULTS RECIRC SYSTEM SPEED DEMANDFAILURE APRM FAILURE FEEDWATER UNE BREAK IN STEAMTUNNEL IRM FAILURE MASTER FEEDWATER LEVEL CONTROLLER AUTO FAILURE PRESSURE REGULATOR FAILS OPEN (DEPRESSURIZATION)
CORE SPRAY LOGIC POWER FAILURE RCIC LOGIC POWER LOSS AUTO SCRAM CHANNELS FAIL(MANUALSTILLFUNCTIONAL)
TURBINE BYPASS VALVESCONTROL UNIT FAILURE Malf Name TH33 CU04 TH21 TH22 AD01 IA01 DG02 ED01 ED09 ED17 ED19 TH03 OG02 FW20 SW04 SW06 TH31 SW01 FW01 FW22 RC03 RP01 RD04 RD05 RD06 RD07 RD13 TH23 TC01 EG01 TH15 NM09 FW19 NM05 FW03 TC06 CS04 RC07 RP06 TC02 ANS 3.5 Section 3.1.2 Reference 3.1.2(1b,20) 3.1.2(lb) 3.1.2(1c) 3.1.2(1c) 3.1.2(1d) 3.1.2(2) 3.1.2(3) 3.1.2(3) 3.1.2(3) 3.1.2(3) 3.1.2(3) 3.1.2(4) 3.1.2(5) 3.1.2(5) 3.1.2(6) 3.1.2(6) 3.1.2(7) 3.1.2(8) 3.1.2(9) 3.1.2(10) 3.1.2(10) 3.1.2(11) 3.1.2(1 2) 3.1.2(1 2) 3.1.2(12,13) 3.1.2(1 2) 3.1.2(13) 3.1.2(14) 3.1.2(1 5) 3.1.2(16) 3.1.2(17) 3.1.2(19,21) 3.1.2(20) 3.1.2(21) 3.1.2(22) 3.1.2(22,25) 3.1.2(23) 3.1.2(23)
,3.'1.2(24) 3.1.2(25)
Test Data Planned Start 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1996 9/1997 9/1997 9/1997 9/1997 9/1997 9/1997 9/1997 9/1997 9/1997 9/1997 9/1998 9/1998 9/1998 9/1998 9/1998 9/1998 9/1998 9/1998 9/1998 9/1 998 9/1999 9/1999 9/1999 9/1999 9/1999 9/1 999 9/1 999 9/1999 9/1 999
Table 7 SIMULATOR CERTIFICATION TESTING SCHEDULE Four-Year Test Schedule Dece ber 6 December 13 1999 Annual Test Period Test Description A) Simulator Steady State Test.
B) Simulator Normal and Abnormal Operating Plant (GOls)
C) Simulator Transient Performance Tests.
D) Simulator Malfunction Tests.
Test Date Planned Start 08/01/98 07/01/98 10/01/98 09/01/98 A) Simulator Steady State Test.
B) Simulator Normal and Abnormal Operating Plant (Sls)
C) Simulator Transient Performance Tests.
D) Simulator Malfunction Tests.
A) Simulator Steady State Test.
B) Simulator Normal and Abnormal Operating Plant (EOls)
C) Simulator Transient Performance Tests.
D) Simulator Malfunction Tests.
08/01/97 07/01/97 10/01/97 09/01/97 08/01/98 07/01/98 10/01/98 09/01/98 A) Simulator Steady State Test.
B) Simulator Normal and Abnormal Operating Plant (AOls)
C) Simulator Transient Performance Tests.
D) Simulator Malfunction Tests.
08/01/99 07/01/99 10/01/99 09/01/99 E-13
Table 8
SIMULATOR EXCEPTIONS Exception Number 10 12 13 14 Open Date 11/22/91 11/22/91 11/23/91 11/23/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 12/03/91 Close Date 11/09/95 Exception Description No camera equipment mounted at top of panels or ceiling at plant.
Simulator room lighting does not match the plant.
Side panels 2-9-2, 2-9-10, 2-9-11, 2-9-12, 2-9-13, 2-9-14, 2-9-53, 2-9-54, 2-9-55, 2-9-21, 2-9-20, 1-9-20, 0-9-23-2, 0-9-23-4, 0-9-23-3, 0-9-23-4, 0-9-23-5, 0-9-23-6, 0-9-23-7, 0-9-23-8 and 2-9-22A are located on the opposite sides of the room in respect to Unit 2 horseshoe.
Panel 2-9-47 is only partially simulated.
Panel 0-9-56 is not simulated.
Panel 2-9-9 is not simulated.
Panel 2-9-46 is not simulated.
Panel 2-9-24 is not simulated.
Panel 2-9-44 is not simulated.
Panel 2-9-59 is not simulated.
Panel 2-9-22 ls not simulated.
Electrical operator typer is not simulated.
Drywall TV Monitor is not simulated.
Panel 2-9-54 has additional instruments.
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Table 9
SIMULATOR LIMITATIONS The followingsimulator limitations have been imposed to prevent training from occurring when the simulator is operating beyond the planned scope of simulation.
1.
Drywell pressure exceeds design limit(,( -2 pslg or ) 63 psig).
2.
Fuel clad temperatures exceed clad malt point f2200 deg F).
3.
Reactor vessel pressure exceeds design limit(1375 psig).
4.
Water entering steam turbines.
5.
Suppression pool temperature exceeds boiling point.
6.
Core average void fraction > 90% and water level < -400 inches If any above limitis reached, the simulator willfreeze and the Instructor station willdisplay a "SIMULATOROUT OF BOUNDS" popup explaining the limit.
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