ML19209C876
| ML19209C876 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/10/1979 |
| From: | David Jones MEMPHIS STATE UNIV., MEMPHIS, TN |
| To: | Haas P OAK RIDGE NATIONAL LABORATORY |
| Shared Package | |
| ML19209C834 | List: |
| References | |
| TASK-TF, TASK-TMR NUDOCS 7910180424 | |
| Download: ML19209C876 (21) | |
Text
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MEMPHIS STATE UNIVERSITY
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MEMPHIS.TESNESSEE 3S!!:
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e 5,.L,,, U July 10, 1979 v
Ccwr for Vw lear brunsen O..r-e ou r hc ihrec one
< ~ ;, m.sa Dr. Pc.ul Haas Engineering Physics Division Oak Ridge flational Laboratory P.O. Box X Oak Ridge, TN 37830
Dear Paul,
SUSJECT-If TER!M REP 0DT 0" SIM'JLATOR SURVEY Attached herewith are summaries of the data we have collected thus far on simulatcr capabilities, systems simulated, and preprogrammed mal-functions. This data and its documentation is not sufficiently complete to afford a comprehensive report at this time; however, points to which we were requested to assign priority in our initial survey were address-ed. Pertinent information follows:
A.
C*?ASILITY OF SIMULATOR 3 TO FAIL SELECTED COM?0NENTS Tables 1 and 2 identify those malfunctions of specific comocnents which have been preprogrammed to simulators in operation and under con-s t ruct i on. Additional data collected on other pertinent simulator features is presented in Table 3.
This data provides a preliminary comparision between early and late mode.1 simulators.
In reoard to the number of initializaticn conditions availabla, there is not significant difference between old and new simulators. The number of preprogrammed malfunctions has, however, incrcased by 43'; in the case of BWR simulators and 185L in tne case of PWR simulators over the last decade. The capability of the comouters used in the simulators has increased dramatically.
B.
CAPABILITY FOR MULTIPLE FAILURES All simulators have the capability to simulate selected malfunctions simutaneously or in rapid saquence and to initialize malfunctions on the board to a greater or lesser extent. The state of the art isimprovingandmorespecificattentionisbeingpaidtosimulati{on of multiple events in the newer simulators.
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?24 The Natson's first Reguanal Center for Nuclear Manpower Development An Equal Opportuntry Univenty
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7 91018 0 4 2_. q-
Dr. P6ul Haas Pace 2 Juiy 10,1979 C.
ABILITV TO SIMULATE SATURATED CONDITIONS Because BWR's operate normally under saturated conditions in the primary loop, the survey was directed towards CWR simulators only. A review of the malfunctions listed in Tables 1 and 2 reveal no specific malfunction aimed at saturated conditions in the primary system, as might arise from an abnormal condition that would ::roduce bubbles. To date, simulator modeling has assumed that protective systems would shut the reactor down and effort has been directed toward simulation of those system responses.
Surveys.of utility simulators indicate that modeling of saturated conditions in the primary loop is being considered, and mest of the operating simulators are atteroting to include simulation of saturated conditions in their training program to the extent allowed by current modeling in their facility. Modeling of saturated conditions is fea-sible and could be routinely incorporated into the next generation of simulators.
D.
TRAINING ON CONTROL OF PRESSURIZER LEVEL Operators are routinely trained to recognize and interpret condi-tions which involve the pressurizer lev 0 and to maniculate the appro-priate controls necessary to correct excess trends in the pressurizer level. However, CNS surveys have not identified any training programs specifically directed toward normal control of pressurizer parameters.
E.
TRAINING ON ACTIVE AND PASSIVE FAILURES GM
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6 involve both active and passive failures are routinely included in
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Surveys of simulators facilities indicate that malfunctions which c
,g,p' training programs.
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TRAINING ON ACHIEVING NATURAL CIRCULATION y u~.' -
Surveys of training facilities indicate that training on natural o~
circulation has not been included as a primary purpose of drills and J.,.
ext rcises. Natural circulation is, however, considered in various
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exarcises which involve the primary system. Simulation of natural circulation has not been emphasized in modeling except as necessary to support drills and exercises aimed at other purposes. Specific
-e' modeling of natural circulation is within the current state of tecn-
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nology.
In regard to a work plan listing objectives, plans, and schedules for subsequent phases, please refer to attachment B which provides a summary of detailed tasks proposed during tne fourth cuarter of Federal fiscal year 1979. Principal objectives proposed ir.cluce:
B f) C 3 ^i c
[J
Dr. Paul haas Page 3 July 10, 1979 a.
Field collection of information and data pertinent to the identification of key elements of skill and knowledge im-portant in required coerator response to safety related events and psychological traits / characteristics which play a role in the ability of the operator tc perfom.
Milestones in the achievement of this goal include:
1.
Definition of Field objectives.
2.
Development of Methodology and Procedures for data collection.
3.
data collection at nuclear power plants, reviews of records and studies in other industries which docunent safety related events, and a review of cther studias in progress.
4.
Analysis of date to extract key elements of skill arc knosledge which are important to required operator resp.nse and relevan: psychological trai ts/cha racteristics.
b.
Initial development of methodology and planning simu-lator calibration experiments in which a ;orrelation between operator response during actual plant emergenc-ies and simulated emergencies will be sought for the planning of simulator studies of operator response in events not documented.
Completion of all surveys needed to fully realize the goals establisned may require extension of the propcsed work into Federal fiscal year 1980; however-a full report on tasks accomplished will be made on September 30, 1979. Monthly interim reports will also be submitted.
If further infomation is needed, please call.
Sincerely, D. W. Jones, Director bj Attachments cc: File 30-4201/79-09 86,-
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TABLE 1 BWR SYSTEMS Ari MALFUt:CTI0t S SI'i'JLATED l
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SYSTEM e
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SYSTEM /MALFUt;;TICt 5 CROSS di ["/ g/ g;l/
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x REFEREf;CE
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REACTC? C0t;TRCL Control Rod Drif t X
X X
X Control Rod Dropped X
Rod Over Travel X
Inccmolete Scram X
Roc Stuck X
X X
X Low Pressure X
X X
CR0 Water Pumo X
X X
Position Indicator X
X Scram Discharge X
Volume Higr. Level Pattern Control System X
f;UCLEAR II;STRUMEt TATIO::
SR Full /Cown Scale X
X X
X SFJi Stuck Chamber X
X X
X IRM Full /Down Scale X
X X
X IFJi Failure to Retract X
X X
X LPPJi Fuli/Down Scale X
X X
X EPTCi Failure to Switcn X
AP?fi Full /Down Scale X
X X
X REAUCR COOLAliT Recirc Pump Failure X
X X
X Recirc Pump Suction Valve Recirc Pump Control Valve X
X Flow Control Actuator X
X X
Main Flow Control Valve Feedwater X
Recirc Pum;: Line H/L Flow X
X Recirc Pump Seal Leak X
X X
X R. P. Seal Temp. High RWCU Influent Conduct.
RWCU Effluent Concuct.
Pressure Relief Valve X
x x
PRV Fails Open X
X X
High PRV Line Temperature PRV Does flot Open Manual Recirc Pump Trouble X
X
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TABLE 1 BWR SYSTEMS AND MALFUNCTIONS SIMULATED xl l
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i SYSTEM U
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SYSTEM / MALFUNCTIONS CROSS 8/
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REFERENCE Et $/ U/ Ol N/ El E! E! 3i 31 & cl Cl m/ ml 2/ Ll
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._j CONTAINME.';T Pressure Control Flow Low X
X Annulus Exhaust Flcw Low Fuel Bldg. Pressure Control Steam Line Break X
X Water Line Break X
X LEAKAGE DETECTIGN RV Flange Inner Seal X
X T. B. Main Stean Line X
Steam Tunnel MS Line X
X X
X RWCU Rcom Water Leak Aux. Blog. Exhaust Radiation Raawaste Sieg. Raciation MCR Intake Radiation MAIN STEAM & TUR3INE MSIV Fails Closed X
IHC Governor Control X
X X
M. S. Pressure Oscillation X
X X
Hign Vibration X
X X
X High Eccentricity X
X LPT Exhaust Hood Temp.
X X
X X
Bearing Oil Temoerature X
X Bearing Metal Temperature Bearing Heater Oil Pressure X
X X
X Oil Tank Level Low X
X Stop Valve Failure X
Bypass Valve Stuck X
X X
Pressure Regulator Failure X
X X
X Tur::ine Trip X
X X
X Control Valve Fails X
X Bypass Valve Fails X
Thrust Bearing Wear Acceleration Control X
X X
X Gland Seal Regulator X
X X
X CONDENSER / CONDENSATE Main Air Ejector Failure X
X X
Vacuum Breaker Leakage Flow Controller X
X Condensate Booster Pump X
X X
X Hotwell level High X
X Hotwell Level Low X
X Condensate Conductivity Cond. Demin. Effluent Cond.
X X
X 865 '20
a TAELE 1 BWR SYSTEMS AND MALFUNCTICNS SIMULATED
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SYSTEM / MALFUNCTIONS CRJ55 8/e
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REFERENCE h/ v! =- e W'!'
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FEEDWATER LPFW Heater Level Low X
HFFW Heater Level High X
HPFW Heater Level Hi-Hi X
X Feedwater Pumo X
X X
X Total FW Flow Reactor Cool ant X
X Main Flow Control Valve Reactor Cool ant X
X CLOSED COOLING WATER Loss of Main Circulator X
X
. ir Binding in Main Condenser X
CCW F1ow Less CCW Flcw to RWCU HX X
X CCW Flow to Drywell f) [ I
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TABLE 1 BWR SYSTEMS A!;0 MALFUf;CTIO!iS SIMULATED
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SYSTEM SYSTEM /MALFU!;CTIO:;S CROSS
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REFERE;CE Si cl c.l ~/
1 SERV:CE WATER f;SSS SW Header SDP SW Header Crywell Chilled Water Temo.
C. B. Chilled Water Temp.
Fuei Pool Cooling Temp.
OFFSAS Glycol Solution Temp.,
Drier Discharge Humidity Steam Flow Low ECCS HPCS Leg Fili Pumo LPCS Leg Fill Pumo HPCS Pump Suction HPCS Pumo Run Light X
LPCS Pump Run Light LOCA-Low Water X
X LOCA-L. W. & Drywell Pressure X
HPCS Pump Discharge Pressure LPCS Pumo Distnarge Pressure HPCS Testacle Stop Check Valve LPCS Testable Stop Check Valve X
X HPCS Puro Running or Trip X
X LPCS Puma Running or Trip RCIC Turoine Trouble X
X RCIC Governor Valve RCIC Isolation Sicnal X
X RCIC Pump Discharge Flow RES! DUAL HEAT RE?iOVAL RHR Leg Fill Pump RHR Pump Run Lignt RHR Pump Discharge Pressure RHR Pump Running or Trip X
X X
X RHR HX Tube to Shell Pressure RHR HX Service Water Flow RHR HX Level Controller X
X RHR Steam Mode Press. Reducer X
X RHR HX RC Conductivity MAI:1 GE!;ERATOR & ELECTRICAL Loss of Power to Essential Bus.
X X
X X
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TABLE 1 BWR SYSTEMS AND MALFUNCTIONS SIMULATED x/
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SYSTEM SYSTEM / MALFUNCTIONS CRCSS C/ g/ #j g /
REFERENCE
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Loss of DC to Lockout X
X Potential Transfomer X
X X
Exciter Field Overload Stator Cooling System X
X X
Gas Purity Low X
X Gas Temperature Hich X
X Hycrogen Seal Oil Pump X
X Isolated Phase Bus Temp.
X X
X Loss of 125Vdc Vital _ Bus.
X X
X DIESEL GENERATOR DG Start Failure D3 shutdown X
X Control Power Failure X
Local Annuciator Fails to Sychronize in Auto X
X X
X MISCELLANEOUS Process Computer Output Unit Standby Liquid Control Tank Fire Protection System Alarm Instrument Air Header X
X X
Standby Gas Charcoal Temp.
X X
X PROCESS RADIATION MONITORING Main Steam Line Hi-Hi M. S. Line Down Scale X
X M. S. Line High X
X X
Off-Gas Pretreatment Hi X
X Off-Gas Posttreatment Hi-Hi X
X Off-Gas Vent Pipe Hi X
Liquid Effluent Hi CCW Liquid Hi Service Water Hi X
X 865 T
TABLE 1 BWR SYSTE.S AND MALFUNCTIONS SIMULATE 3
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REFERENCE pi n /g g/ e/ c&lg/ el jr/
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Carbon Bed Vault Hi Cont. Vent. Exnaust Hi Cont. Vent Discharge Mi AREA RADIATION MONITORING Reactor Building X
X Turbine Building X
Rad.a:te Buildina Auxiliary Building Fuel Building Monitor-Down Scale X
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TABLE 2 Pk:R SYSTEMS AND MALFUNCTIONS SIMULATED i
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SYSTEM h.
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SYSTEMS / MALFUNCTIONS CROSS M/
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REFERENCE u
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REACTOR C00' ANT X
X X
X X
X SG Tube Rup.ture X
X X
X X
RC Pipe Ruoture Leak into Containment X
X X
X X
X X
X RV Head Flange Leak RC Pumo Shaft Shear X
X X
X RCP High Oil Level X
X RCP Flow Degradation X
X RCP Seal Failure X
X X
X X
X X
RCP Rotor Locked X
X X
X X
X X
X Loss of RC Flow X
X X
X X
X X
RCP High Vibration X
X X
X RTD Failure in Hot Leg NI X
X X
X X
X RTD Failure in Cold Leg NI X
X X
X X
X PIR Pressure Control-High X
X X
X X
PZR Pressure Control-Low X
X X
X PZR Level Control-High X
X X
X X
X PZR Level Control-Low X
X X
X X
X PIR Relief Valve Leak X
X X
X X
X X
PZR Spray Valves Fail-Closed X
X X
X X
X X
PZR Spray Valves Fail-Open X
X X
X X
X X
PZR Heaters Fail On X
X X
X X
X X
PZR Heaters Fail Off Fuel Leaks-Variable X
X X
X X
X RCP Electrical Failure Electrical X
X X
X COMPONENT COOLING WATER Loss of CCW to RCP RC X
X X
X X
X X
X Loss of CCW Pumps X
X X
X X
X X
X PEACTOR BUILDING COOLING RB Spray Pump Failure X
RB Cooler Failure X
CHEMICAL AND VOLUME CONTROL Letdown Line Leak X
X X
X X
Loss of Nomal Letdown X
X X
X Makeup Control Failure X
X Leak in Charging Line X
X X
X X
X X
Loss of Charging Pump CCW X
X X
X X
X X
m77
.JJ
TABLE 2 PWR SYSTEMS A!!D MALFUt!CTIO!;S SIMULATED l'
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SYSTEM
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&l Lij ?l k';' 3l Ci 5 Loss of CCW to SW HX CCW X
X X
X X
Hign 1.; Across RC Filter X
RC Dilution-Refueling X
RC Dilution-Startuo RC Dilution-Power X
X Letdcwn Valve to VC Tank X
X X
X X
VC Tank Low Level X
X X
X X
X Letdown Control Valve X
X X
X X
X REACTOR C0t; TROL Uncontrolled Rod Withdrawal X
X X
X X
X Uncontrolled Rod Insertion X
X X
X X
X X
X X
X Misalignment of Rods Control Rod Dropped X
X X
X X
X X
X X
X Rod Rejection Rods Fail to Move X
X X
X X
X Position Indicator Failure X
X X
X X
X Failure to Scram X
X X
X X
Failure of Rod Stops X
X X
X X
Loss of Speed Control X
X X
X X
Loss of Movement Control X
X X
X X
Failure to Trip on Manual X
X X
X ELECTRICAL Loss of All offsite Power X
X X
X X
X X
Loss of Station Transfomers X
X X
X Loss of Emergency Bus X
X X
X X
X X
Loss of 12SV DC Bus X
X X
X Main Generator Trip X
X X
X X
Voltage Regulator Failure X
X X
X X
X RCP Electrical Failure X
X X
X Diesel Generator RC Loss of Diesel Generator X
X X
X X
Loss of Bearing Cooling X
MAIN STEAM & TURBIT;E Turbine Trip X
X X
X X X Turbine Lube Oil Loss X
X X
Pressure Transmitter Failure X
X X
X X
Failure of Turbine Trip X
X X
Failure of EHC System X
X X
X X
Turbine Governor Valve X
X X
X X
Turbine Stoo Valve X
X Turbine High V1bration X
X X
X X
Turbine Lube Oil Pressure X
X 865
':V
TAELE 2 PWR SYSTEMS AND MALFUNCTIONS SIMULATED l2l l
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SYSTEMS /"ALFUNCTIONS CROSS m/ u,/ jf/ s./
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! REFERENCE
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@&l El ?l &l 5l Cl El Turbine Driven Lube Oil Pump X
X X
Loss of EH Fluid Pumo X
X X
Turcine Lube Oil Tercerature X
Tur:ine Auto Run Eack X
X X
Turoine Overspeed X
M.S. Trio Valve Fails Shut X
X X M.S. Line Rupture Inside Containment
'X X
X X
X X M.S. Line Rupture After MSIV X
X X
X X
5.G. Level Control-High X
X X
X X X
X X
X X X 5.G. Level Control-Low.
X X
X X
X X Failure of Auto Steam Dumo Steam Header Press Control X
X X
X X
Gland Seal Regulator X
X X
X Atmospheric Relief Valve X
X M.S. Trip Valve Failure X
M.S. Safety Valve X
X Extraction Steam Valve X
X CONDENSER / CONDENSATE Hotwell level Hign X
X X
X X Hotwell Level Low X
X X
X X Loss of Condensate Pumo X
X X
X X
Concensate Recirc Valve X
Condensate Line Leak X
X High Cor. denser Recirc. Temp.
X High Cendensate Conductivity X
X fiain Condenser Tube Leak X
X X
X X
X X X FEEDWATER Feedwater Enthalpy X
X X
X X
X X
X Low Lube Oil Pressure Feed Pump X
X Main FW Regulating Valve X
X X
X Main FW Retirc. Valve X
X X
X X
X X
Aux. 5. G. Feed Pump X
X X
X X X Aux. S. G. Turbine Feed Pumo X
X X FW High Conductivity X
X FW Heater Failure X
X X
Low Canal Level X
B65 '3L
O TABLE 2 PWR SYSTEMS AND MALFUNCTIONS SIMULATED
/
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SYSTEM O
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SYSTEMS / MALFUNCTIONS CROSS 9/ M E 5/
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mt t;UCLEAR INSTRUMENTATION X
X X
X X-X SRM Failure-Hich X
X X
X X
X SRT' Failure-Los X
X X
X X
X PEM Failure-High X
X X
X X
X PRM Failure-Low X
X X
X X
IRM Failure to Allow Manual X
X X
X SRM Slugcish Indication X
X X
X IRM Overcompensated X
X X
X IRM Failure-Hich X
X X
X X
IRM Failure-Low X
X X
Loss of Power to PRM X
X Axial Flux Tilt X
X Radial Flux Tilt RTD Failure in Hot Lee RC X
X X
X X
X RTD Failure in Cold Leg RC X
X X
X X
X X
X X
Axial Xenon Oscillation RESIDUAL HEAT REMOVAL X
X X
X X
Loss of RHR Pump X
X X
RHR System Temperature X
X X
RHR System Flow Loss of CCW to RHR HX CCW X
X X
X 2RON RECOVERY SYSTEM Boric Acid Transfer Pumo X
X X
X Boric Acid Tank Heaters X
X Eoric Acid Heat Tracing WASTE DISPOSAL X
X Accidental Liquid Release Accidental Gaseous Release X
X X
RADIATION MONITORING Area Monitor Failure X
X X
X Area Monitor Increase X
X X
X Process Monitor Failure X
X X
X Process Monitor Increase X
X X
CCt:TAIUMEtiT False Actuation of Isolation X
X X
Increase in Containment Pressure X_
865 'M
TABLE 2 PWR SYSTEMS AND MALFUNCTIONS SIMULATED l-lLt WI i
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i fi!S CELLANE005 Instrument Air System X
X X
X Charging Pu o Service Water X
Process Computer Failure X
X X
False Alarc on Annunciator X
X Failure of Annunciator X
X Loss of Control Air X
X X
X Loss of Service Air X
SIS Sycter Leakage X
X X
UHI Aw..:ulator Low Pressure X
UHI Accumulator High Pressure X
SIS Accumulator Low Pressure X
X X
X SIS Accumulator High Pressure X
S!S Accumulator Low Level X
X X
X SIS Accumulator High Level X
SIS at Power X
X EGTS Failure X
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- 77
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TABLE 3 SIMillATOR SufftARY SYSTEMS MALFullCTI0flS INITIAL TRAltililG Sil!ULATOR Sif!ULATED I'REPROGRNFlED CONIllT 10flS C0fIPlfTER TI AliiRiS B&W, NPPS 27 73/fil ill ill til VEPCO, Surry fli 231/NI 21/30, SEL 32/55 NI Duke, McGuire NI 247/NI 10/t!'
PDP 1135 til TVA, Sequoyali 32 140/150 21/30 SD. 32/55 9
CE, Calvert Cliffs NI 100/NI 20/NI PDP 1135 til WEC, Zion ill 81/NI 16/19 Per 1135
'til APS, Palo Verde 29 150/200 21/30 (2) SEL 32/55 11 GE, Dresden 2 33 107/HI 21/fil GEPAC 4020 17 TVA, Browns Ferry 62 109/150 19/30 SEL 32/55 NI 9
GE,llartsville 45 142/178 26/35 SEL 32/55 NI 12 GE, Black Fox 45 142/178 26/35 SCL 32/55 NI 12 a_-
n (T
ua C2 NS: Not Selected NI:
Indicates no information available at the time the report was prepared.
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WORK RREAKDOWN STRUCTURE TASK:
FIELD DATA COLLECTIO!1 ACTIVITY:
SAFETY RELATED OPERATOR ACTI0tl5 MILESTONES SUDTASK/SECOfJDARY SUDTASK FY 191H FY 1970 FY 19110 UEYOf1D l
2 3
4 1
2 3 4 1
2 3 4 FY 1980 METif0DS AfiD PROCEDURES:
2.1 Characterize events to identi fy cottinon types of error and levels of stress.
2.2 Identify spect fic objectives for field survey (interview) of operators.
2.3 Develop procedure for review of plant documenta tion.
2.4 Develop procedure for interview with nuclear plant operators involved in events.
2.5 Perform preliminary validation of psychological interview format with Cils staf f and cooperating plants.
2.6 Determine extent of interviews neces-sary in other industries.
cc 2.7 Develop plan for analysis of data and Ch its ingorous and quantitative correla-U' tion with data from other industries.
2.8 Develop methods for integrating fic1d
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data with simulator data.
2.9 Establish preliminary data anslysis fonna t.
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WORK llREAKDOWN STRUCTUllE SAFETY RELA 7ED OPERATOR ACTI0fl5 TASK:
flELD DATA COLLECTI0ff ACTIVITY:
MILESTOtJES SUDTASK/ SECONDARY SUBTASK F Y 19 /11 FY 1979 FY 191!U BE YOf10 1
2 3 4
1 2
3 4 1
2 3
1 FY 19110 FIELD DATA AllALYSIS:
P 4.1 Analyze field data in terms of specified objectives developed in task 2.2.
4.2 Correlate field data on nuclear plant events with similar events in other in-dustries.
4.3 Correlate field data with current research being performed on nuclear plant simulators.
4.4 Correlate field data wi th research per-forned on simulators in other industries.
4.5 Establish correlations between field data and simulator research for use in planning simulator calibration experiments.
4.6 lbentify specific job-related stress fac-tors which should be addressed in operator screening programs.
4.7 Identify other specific safety-related CD aptitudes which should be addressed in operator screening programs.
(..n 4.8 Correlate field data and results derived g
in analyses with operator training programs y
to identify areas of weakness.
4.9 Prepare reconnendations for improvement of screening and training programs.
.