ML20077M827

Simulator Four-Yr Certification Rept

ML20077M827
Person / Time
Site:	Calvert Cliffs
Issue date:	01/10/1995
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20077M815	List: ML20077M811 ML20077M827
References
NUDOCS 9501130185
Download: ML20077M827 (18)

Text

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ENCLOSURE (1)

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CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATOR FOUR-YEAR CERTIFICATION REPORT L

INTRODUCTION.

He Calven Cliffs Nuclear Power Plant Simulator four-year Certification Repon is a supplement to the Simulation Certification form (NRC Fc. m-474), the Simulator Annual Certification Report, and Simulator Support Unit Procedures. This repat briefly provides a description of the simulator, the Certification Resubmittal checklist and a current status of simulator configuration modifications. Additional information concerning specific tests is available upon request. The last report was submitted January 11,1991.

II.

SIMULATOR INFORMATION Simulator type:

Reference Plant Simulator Manufacturer:

Combustion Engineering Owner / Operator:

Baltimore Oas and Electric Company (BGE)

Reference Plant:

Calvert Cliffs Unit One Plant Location:

Lusby, Maryland Plant Type:

Pressurized Water Reactor Plant Rating:

2700 Mwth Date Available for Training:

January,1985 Original Certification Date:

January 11,1991 Type of Report:

Four-Year Certification Applicable Str.ndards:

Design / Testing:

ANSI /ANS 3.8-1985 (Reference 2)

NRC RO 1.149-1987 (Reference 3)

III.

SIMULATOR PROCEDURES ne Simulator is controlled, operated, tested and modified using the following Calvert Cliffs procedures:

TI 15 " Administrative Control of Changes to Training Programs."

TI16 " Simulator Issue Reports."

i TI19 "Calvert Cliffs Simulator Facility Configuration Management."

IV.

SIMULATOR DATABASE Controlled drawings and procedures are used as a basis for handler logic and system flow i

calculations. The plant setpoird file is also used as an input to the simulator data base. Plant or j

Simulator Support Unit logs are:used whenever possible to compare initial condition values. Plant or Engineering data is used when necessary to ensure the simulator data base closely models the plant. Feedback from plant operators, using the Simulator Issue Repon (SIR) process, is an essential part of maintaining the simulator current with the plant.

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'c ENCLOSURE (1) t CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATOR FOUR-YEAR CERTIFICATION REPORT V.

DEVIATIONS SINCE LAST REPORT Missing three Year One Annual Test hard copies. Documentation of the runs are contained in the Year One Annual Report. All annual tests were completed with satisfactory results.

Missed the performance of ANS 3.8 paragraph C.4 " Hot Standby to Minimum Load" in Year i

Two. The simulator was subsequently exercised with satisfactory results under the 100% Trip and Recovery test performed in 1994. This test was performed on January 6,1995, with satisfactory j

results.

l ANS 3.8 C.5 " Turbine Startup and Synchronization" and C.6 " Minimum Load to 100 Percent l

Power" were delayed two months to allow testing of new input / output (I/0) placed on the simulator I

l in December 1992.

t Missed the performance of Year Two Malfunction 165 during 1992. It was run with satisfactory f

results in 1991. This test was performed on January 5,1995, with satisfactory results.

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No additional major difTerences exist between the simulator and the reference plant.

VI.

MAJOR CII ANGES SINCE TIIE LAST REPORT f

Inclusion of the Digital Feedwater Control System and Lovejoy in the Reference Plant and the l

Simulator eliminates the "Feedwater Panel" EXCEPTION in the original submittal.

l Changed Malfunction 59 [ Power Operated Relief Valve (PORV) Leakage] to Malfunction 66 i

(PORV Leakage) to allow the option for either PORV to be affected.

f There were no discrepancies under the " MAJOR Simulator Fidelity" category.

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VII.

MAJOR CIIANGE MILESTONES OCCURRING WITIIIN Tif E NEXT YEAR f

Host and I/O Computer replacement Instructor Station replacement including workstations Possible ability to perform Cetification Testing off-line Furniture replacement in the plant and on the simulator Station Blackout Emergency Diecel Generator panel installation (Per Operations Request, the Simulator Installation will lead Plant Installation to facilitate training.)

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ENCLOSURE (I)

CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATOR FOUR-YEAR CERTIFICATION REPORT VIII. OUTSTANDING ITEMS FROM LAST SUBMITTAL j

The following discrepancies have not been corrected:

SIR No.

Discrepancy Corrective Actions S1700 During 100% Power Trip & Recovery, at Pending. Modifications were made to th, 20% Reactor Power the transfer from software to reflect plant design. Rese First Stage Pressure Feedback Out to changes caused major difTerences in other First Stage Pressure Feedback In caused indications. After this attempt failed, the enough penurbations to cause a Reactor First Stage Pressure Feedback failed in the Trip.

plant causing plant operations in First Stage Pressure Feedback OUT only, except for valve testing.

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S1879 During the 75% Power Steady State Test Pending. With the simulator matching MWE output was too high.

plant conditions (summer time) the MWE

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fell into specification, but other indications t

fell out of specification.

IX.

CERTIFICATION TESTING CHECKLIST The attached Calven Clifts Nuclear Power Plant Simulator Cenification Report Checkoff Sheet

[ Attachment (1)] indicates the audit completed to maintain simulator certification. Specific data is available upon request.

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Certification tests are divided into three groups:

Performed each year (Certification file on the simulator) i Annual Tests Performed over a four-year period (Certification file on the simulator)

Performance Tests Malfunction Tests 25% per year in accordance with the testing schedule (Certification file on the simulator)

X.

ADDITIONAL TESTING SPIN Testing: Every time a " SPIN" (new training load) occurs, we run an integration test to ensure the changes are incorporated and that the changes do not detract from training. His testing includes l

ANS 3.8 2i " Main Steam Line Break" and 2h "LOCA with Loss of Offsite Power" because these tests i

exercise most of the computer models. Affected malfunction tests may also be used. Credit for this testing is not considered in the Cenification Testing.

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The computer replacement project included BENCHMARK testing to ensure the continued certification of l

the Calvert Cliffs Simulator. This testing included taking the simulator from "100% to Cold Shutdown,"

" Mass / Energy Balance" testing, " Simultaneous Trip of Both Steam Generator Feed Pumps,"

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATOR FOUR-YEAR CERTIFICATION REPORT

" Simultaneous Closure of Both Main Steam Isolation Valves," " Reactor Trip and Recovery from 100 Percent Power" and selected Malfunctions from Year Four.

The following MALFUNCTIONS were developed, tested and added to our test plan for the 1995-1998 Certification cycle:

Malfunction 5 Wide Range Nuclear Instrument Failure Yr3 Malfunction 52 Switchyard Breaker Fails to Trip Yr3 Malfunction 63 Pressurizer Pressure Safety Channel Failure Yr1 Malfunction 74 Tube Leak in the Non-Regenerative Heat Exchanger Yr3 Malfunction 97 Digital Feedwater Control System Central Processing Unit Yr4 Failure Malfunction 106 Loss of Steam Flow Input to Digital Feedwater Control System Yr3 Malfunction 107 Feed Flow Element F11II A/l121 A Failure Yr2 Malfunction 152 Steam Generator Blowdown Fails to Isolate on High Radiation Yr2 Signal Malftmetion 187 Low Pressure Safety Injection (LPSI) Pump Suction Break Yr4 Malfunction 195 Low Level in the Safety Injection Tank Yr 1 Malfunction 214 Service Water Leak in Auxiliaiy Building Yr1 Malfunction 215 Service Water Leak in Turbine Building Yr2 Malfunction 217 Saltwater System Leak Yr3 Malfunction 218 Area Radiation Monitor Failure Yr1 Malfunction 231 Component Cooling Water Leak in Containment Yr4 Malfunction 240 Main Steam Isolation Valve (MSIV) Fails to Shut on Yr1 Engineered Safety Feature Actuation Signal Malfunction 241 Automatic Containment Isolation Signal (CIS) Fails to Actuate Yr2 Malftmetion 242 Manual CIS Fails to Actuate Yr3 Malfunction 243 Automatic Steam Generator Isolation Signal (SGIS) Fails to Yr4 Actuate Malfunction 244 Spurious SGIS Actuation Yr2-Malfunction 245 Containment Radiation Monitor Failure Yr4 Malfunction 246 Failure of Shutdown Sequencer (SDS) Bus 11 to Unblock Yr1 Malfunction 247 Failure of SDS Bus 14 to Unblock Yr2 Malfunction 248 Failure of Loss-of-Coolant Incident Sequencer (LOCIS)

Yr3 Bus 11 to Unblock Malfunction 249 Failure of LOCIS Bus 14 to Unblock Yr4 Malfunction 250 Steam Generator Wide Range Level Transmitters Fail Yr3 Malfunction 251 Failure of No.12 Steam Generator Pressure Transmitters Yr4 Malfunction 252 Failure of No.12 Steam Generator Protection Level Yr1 Transmitters Malfunction 253 Blockage of Salt Water Components Yr4 i

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT SIMULATOR FOUR-YEAR CERTIFICATION REPORT i

XI.

REFERENCES l

1.

Title 10, Code of Federal Regulations, Part 55, " Operators' Licenses."

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ANSI /ANS 3.8-1985 American Nuclear Society " Nuclear Power Plant Simulators for Use

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in Operator Training i

3.

United States Nuclear Regulatory Guide 1.149 " Nuclear Power Plant Simulation Facilities 3

for Use in Operator License Exams" April 1987.

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ATTACIIMENT (1)

CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR -- CilECKOFF SIIEET INIT / DATE 1.

Review SPIN and Annual Reports and list major changes since the last report.

/ ///a/r List these under Section VI.

_z 2.

Review SPIN and Annual Reports for any changes to the simulator environment (lighting, painting, etc.) List these under Section VI.

/ //o/ff 3.

Review SPIN and Annual Reports for any major model changes, or model

/ r//o/Y changes on SIRS which had " MAJOR Simulator Fidelity" checked. List these e

under Section VI.

4.

List all FCRs which were incorporated on the simulator since the last report.

Ilave this list available for review.

<[ / /30/97 5.

List any outstanding items to be completed within the next year. List these under Section VII.

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6.

Verify Certification Documentation:

a.

List all tests from last report and include the dates they were run,

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Simulator Issue Reports written and resolution.

d / /,/ e /F r b.

Verify testing was performed in accordance with the testing schedule last

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submitted or reasons for deviation documented in Section V.

d / //o/fr M / //g/9f-c.

List additional testing performed including SPIN tests.

f 7.

Give up to date evaluation of the simulator:

a.

llave differences list available for review.

[ / </e/fr b.

List any major differences between the reference plant and the simulator concerning panels, conununications, furniture and plant computer. If differences exist which were not addressed in the original submittal, include them in Section V.

[ / e / o /f r c.

List all of the initial conditions. Ensure conditions under the original submittal are still being met.

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IIave SIR list available for review.

ed[/f// hf e.

Attach the test plan for the next four years. [ Attachment (2)]

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List any additional exceptions to the standard.

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Review Examiners conunents from exams performed including our reply.

llave these available for review.

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List any deviations from the standard. Include these in Section V.

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List the qualifications of persons who performed, reviewed or approved testing over the last four years:

j Charles Andrews Former Licensed SRO (CCNPP)

Richard Best Attached Edmund Chrzanowski Licensed SRO (CCNPP)

James Macklin Licensed SRO (CCNPP)

Patrick Murphy Former Licensed RO (CCNPP)

[ /,/q/pr Douglas Tilton Attached f

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ATTACIIMENT (2) i CALVERT CLIFFS UNIT ONE-REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR ANNUAL TEST PLAN i

ANS 3.8-Id 100% Power Drift Check Operability Check of Real Time Simulation ANS 3.8-la 25% Power Energy / Mass Balance ANS 3.8-lb

- 50 ANS 3.8-l% Power Energy / Mass Balance ANS 3.8-Ic 75% Power Energy / Mass Balance ANS 3.8-Id 100% Power Energy / Mass Balance l

ANS 3.8-2a Manual Reactor Trip l

ANS 3.8-2b Trip of 11 & 12 Steam Generator Feedwater Pumps ANS 3.8-2c Closure of11 & 12 MSIVs ANS 3.8-2d Trip of All Reactor Coolant Pumps (RCPs)

ANS 3.8-2c Trip of 12A RCP at 80% Power ANS 3.8-2f Main Turbine Trip at 12% Power ANS 3.8-2g Maximum Power Ramp 100% - 75% - 100% Power ANS 3.8-2g Large Break Loss-of-Coolant Accident with Loss of Offsite Power ANS 3.8-2i Main Steam Line Rupture ANS 3.8-2j Slow Reactor Coolant System Depressurization with Engineered Safety Feature Actuation System failed l

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ATTACHMENT (2)

CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR

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DUAL UNIT SIMULATOR YEAR ONE TEST PLAN I.

PROCEDURES l

Cold Shutdown to Hot Standby Operation in Hot Standby IL MALFUNCTIONS i

002 Wide Range Nuclear Instrumentation Channel High Voltage Power Supply Failure 012 Power Range Subchannel Linear Amplifier Fails High 016 Reactor Protective System (RPS) Channel B Bistable Trip Relay Contact Fails to Open on Trip 019 Failure of Manual Reactor Trip 027 Uncoupled Control Element Assembly (CEA) 033 Individual CEA Reed Switch Position Indication Fails 035 Reactor Trip 036 Loss of Control Element Drive Mechanism Motor Generator Set 048 Failure of RCP First Stage Seal 063 Pressurizer Pressure Safety Channel Failure 073 Loss of Normal Letdown Due to 1-CVC-516 Failing Closed 082 Failure of Boric Acid Pump 083 Volume Control Tank Level Transmitter Fails Hi/Lo 093 MSIV Stuck at 90% of Full Open 094 MSIV Fails Closed 103 Turbine Bypass Valve's Fail Open (Any Combination) 108 Failure ofTurbine Bypass Valve Control Loop From IPIC-4056 109 Turbine Bypass Valve Controller Fails in Automatic Mode 110 Failure of Steam Flow Transmitter Hi/Lo 112 Atmospheric Dump Valve Controller Fails while in Automatic Mode 137 Main Generator Trip 140 Main Generator Automatic Voltage Regulator Misoperation 141 Loss ofStator Liquid Cooling 147 Loss of Unit Two Vital Instmment Bus 157 Loss of Pressurizer Heater Motor Control Centers l

160 Loss of 250 VDC Emergency DC Bus 161 Failure of Emergency Diesel Generator to Start i

171 Feedwater Regulating Valve Fails Full Open or Closed in Automatic Control 186 Failure of Auxiliary Feedwater Actuation System to Actuate D1 High Pressure Safety Injection (HPSI) Valves Fail-as-is

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195 Low Levelin Safety Injection Tank

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203 Failure of Recirculation Actuation Signal to Actuate on Automatic Demand 207 Failure of Containment Cooling Fans 214 Service Water Leak in the Auxiliary Building 218 Area Radiation Monitor Failure 2

ATTACHMENT (2)

I CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR 223 Iess of Component Cooling Pump 224 Loss of Service Water Pump i

225 Loss of Salt Water Pump

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234 Loss of Motor Driven Auxiliary Feed Pump 239 Core Exit Thermocouple Detector Failure 240 Failure of MSIV to Close on SGIS 246 Failure of SDS Bus 1I to Unblock 252 Failure of No.12 Steam Generator Protection Level Transmitters e

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ATTACHMENT (3)

CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR l

l YEAR TWO TEST PLAN I.

PROCEDURES Hot Standby to 10% Power Turbine Startup and Generator Synchronization 10% to 100% Power II.

MALFUNCTIONS 003 Wide Range Nuclear Instrumentation Channel Pre-amp Output Fails Low 008 Power Range Safety or Control Channel Detector Output Fails Low 011 Power Range Safety or Control Channel Output From Power Summer Fails Low 017 Failure of RPS Logie Matrix Relay AB-1 020 RPS Logie Matrix Power Supply Failure 028 CEAs Fail to Move on Demand (Manual) i 029 Control Pulses Sent But CEA Doesn't Move. CEA is Trippable 030 Stuck CEA. Will Not Trip 037 Inadvertent Opening ofIndividual Reactor Trip Breakers 049 Failure of RCP Second Stage Seal 050 Failure of RCP Third Stage Seal 070 Loss of Flow From Charging Pump 077 Volume Control Tank Level Transmitter LT-227 Fails Hi/Lo 091 Steam Generator Tube Leakage 096 Steam Generator Level Transmitter For Protection Channels Fails Hi/Lo 102 Inadvertent Slow Closure of MSIV 105 Steam Line Rupture Outside Containment 107 Feed Flow Element F1111 A/l121 A Failure i15 Failure of Automatic Turbine Trips. Manual Trip Will Function 131 Variable High Vibration on Main Turbine 135 Moisture Separator Relief Valve Fails Open 152 Failure of Steam Generator Blowdown to Isolate on RMS Alarm i

153 Loss of 4 KV Bus 154 Loss of 480 V Bus 155 Loss of 480 V Reactor Motor Control Center 163 Loss of Condenser Vacuum 164 Hotwell Level Control Problems 166 Loss of Condensate Pump 167 Loss of Condensate Booster Pump 170 Steam Generator Feed Pump Trip 174 Feedwater Regulating Valve Differential Pressure Transmitter Fails Hi/ Low 180 Loss of Heater Drain Pump 183 Loss of Auxiliary Feedwater Pump 189 Failure of LPSI Pump 190 Failure of Containment Spray Pump 4

ATTACllMENT (2)

CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR 215 Service Water Leak in the Turbine Building 241 Failure of Automatic CIS Actuation 244 Spurious SGIS Actuation 247 Failure ofSDS Bus 14 to Unblock t

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ATTACliMENT (2) 1 CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR l

DUAL UNIT SIMULATOR YEAR TIIREE TEST PLAN L

PROCEDURES i

100% Power to Cold Shutdown II.

MALFUNCTIONS l

t 005 Wide Range Nuclear Instrumentation Failure l

010 Power Range Safety or Control Channel Output From Power Summer Fails High 018 Failun. of Automatic Reactor Trip 021 Failure of CEA Withdrawal Interlocks to Block Outward CEA Motion 023 Uncontrolled Withdrawal ofIndividual CEA or Group of CEAs 025 Uncontrolled Withdrawal of a Single CEA 026 Uncontrolled Insertion of a Single CE 4 032 Dropped CEA 038 Loop 12B Double-ended Rupture of RCS Cold Leg 042 Failure of Reactor Vessel Level Detector 043 RCP Trip 047 Failure of RCP Lift Pump to Reach Operating Pressure When Running 052 Switchyard Breaker Fails to Trip 054 Pressurizer Spray Valve 100E Fails Open 062 Pressurizer Pressure Control Fails Hi/Lo 064 Low Range Pressurizer Pressure Transmitters Fail Hi/Lo i

065 Pressurizer Level Control Fails Hi/Lo 7

074 Tube Rupture in Non-Regenerative Heat Exchanger 075 Loss of Component Cooling to the Non-Regenerative Heat Exchager 078 Failure of the Boronometer 079 Inadvenent Boration 098 Steam Generator Pressure Transmitters Fail Hi/Lo 104 Steam Line Rupture Inside Containment 106 Steam Flow Input to Digital Feedwater Control System Failure 113 Main Steam Safety Valve's Fail Open 114 Turbine Trip 116 Turbine Control Valve Fails Open 150 Loss of 13 KV Service Transformer 151 Loss of 13 KV Bus 156 Loss of a Turbine Motor Control Center 162 Loss of 125 Vital DC Bus 165 Gross Condenser Tube Leakage 172 Feedwater Regulating Valve Mechanical Failure 177 Feed Line Rupture Outside of the Containment 185 Auxiliary Feedwater Pipe Rupture i

188 Failure ofIIPSI Pump 204 Failure of the Diverse Scram System (DDS) to open 217 Salt Water System Leak l

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ATTACHMENT (2)

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CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR i

DUAL UNIT SIMULATOR

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219 High Radiation Alarms on Process Radiation Monitors 221 Intake Structure Traveling Screens Obstructed

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226 Loss of Senice Water to Turbine Building -

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248 Failure of LOCIS Bus 11 to Unblock 250 Steam Generator Wide Range Level Transmitters Fail l

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ATTACllMENT (2) i CALVERT CLIFFS UNIT ONE - REFERENCE PLANT SIMULATOR DUAL UNIT SIMULATOR YEAR FOUR TEST PLAN I.

PROCEDURES i

100% Power Reactor Trip and Recovery to 100% Power i

II.

MALFUNCTIONS 004 Wide Range Nuclear Instrumentation Channel Stanup Rate Degradation 024 Uncontrolled Insertion ofIndividual CEA or Group of CEAs i

031 Stuck CEA. WillTrip 034 Rupture of Control Element Drive Mechanism Housing (CEA #1) 039 RCS Leak into Containment l

045 Locked Rotor on RCP 1IB 060 PORV Minor Leakage l

061 Pressurizer Safety Vaive Leakage

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066 Major Leakage of PORVs (Previously Malfunction 59) l 068 Leak in Letdown Line Inside Containment (Between Check Valve & 1-TE-221) 069 Leak in Letdown Line in Penetration Room 086 Leakage Through Letdown Line Relief Valves 087 Charging Pump Primary Packing Leak 092 Steam Generator Gross Tube Failure 097 Digital Feedwater Control System Central Processing Unit Failure i

100 Steam Generator Differential Pressure Transmitter Fails Hi/Lo 138 Load Rejection 149 Loss of Off-site Power 158 Loss of Non-Vital 120/208 VAC Instrument Bus 159 Loss of120 VAC VitalInstrument Bus 173 Erratic Operation of Feedwater Regulating Valv:

175 Fee hvater Line Rupture Inside the Containment; Before Check Valve 176 Feedwater Line Rupture Inside the Containment; ARer Check Valve i

181 Feedwater Flow Transmitter Input to Control Channel Fails l

187 LPSI Pump Suetion Break 196 Failure of Safety Injection Actuation Signal (SIAS) to Actuate on Automatic Demand 197 Failure of SIAS Manual Initiation 199 Failure of Containment Spray Actuation Signal (CSAS) to Actuate on Automatic Demand i

200 Failure of CSAS ManualInitiation 205 Spurious CIS j

213 Failed Fuel Equivalent to 1 Fuel Pin i

216 Accidental Release of Gaseous Waste i

227 Loss ofInstrument Air 228 Loss ofInstrument Air in Containment 231 Component Cooling Water Leak in Containment 233 Loss of Component Cooling Water to Containment 238 Core Exit Hermocouple Meter Failure 243 Failure of Automatic SGIS Actuation f

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ATTACHMENT (2)

CALVERT CLIFFS UNIT ONE - REFERENCE PI ANT SIMULATOR DUAL UNIT SIMULATOR I

245 Containment Radiation Monitor Failure 249 Failure of LOCIS Bus 14 to Unblock 251 Failure of No.12 Steam Generator Pressure Transmitters 253 Blockage of Salt Water Components i

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i RICHARD L BEST Instructor EDUCATION US Navy Nuclear Power School LICENSE AND NRC Reactor Operator License, Salem 1 and 2 CERTIFICATIONS Senior Reactor Operators Certification, Salem 1 and 2 WORK EXPERIENCE NPS Technical Services 1993-PRESENT Mr. Best is assigned to the Procedures Upgrade Project, revising Abnormal Operating Procedures by verifying them

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against the latest revisions of plant drawings and reference materials.

1992-1993 Etatral Physics Carporation Mr. Best was assigned to the Operations Training Unit at Calvert Cliffs, working for the Simulator Support Group. He conducted ANSI 3.5 testing to maintain simulator certification, verified Simulator Modification Requests and tested software modifications prior to inclusion into training loads.

1980 - 1992 Public Service Electric & Gas. Salem 1 and 2 As the Salem Simulator Configuration Engineer, Mr. Best's responsibilities included tracking of Design Changes for applicability on the simulator and design of the work package to implement and test the changes. During this period the Salem Simulator gained NRC Certification under his supervision. Mr. Best maintained his SRO and Instructor Certification by teaching a minimum of five sessions per quarter.

As the Lead Simulator Instructor, Mr. Best was responsible j

for the development of the initial training materials used on the simulator for New Licensed and Requalification Training.

During this period he assisted in the development of Salem Emergency Operating Procedures and their subsequent verification and validation in accordance with Westinghouse Emergency Response Guidelines. He also developed the operations portions of the plant Emergency Response drills.

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l GENERAL PHYSICS CORPORATION DOUGLAS R. TILTON Car #

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EDUCATION B.S., Nuclear Engineering Technology, Thomas Edison State College LICENSES AND Ucensed Senior Reactor Operator, Seabrook Station CERTIFICATIONS Ucensed Reactor Operator, Salem Nuclear Generating Station Certified Classroom and Simulator Instructor, Calvert Cliffs EXPERIENCE 5/89 - Present General Physics Corporation Mr.Tilton was assigned to the Calvert Cliffs Nuclear Power Plant supporting the Initial Operator Training Unit. He conducts classroom and simulator training in all areas including theory, plant systems, integrated operations and transients. He also served as the simulator operator during numerous NRC Ucense examinations.

As a member of the Ucense Operator Requalification Tralidng Unit, he conducted both classroom and simulator training. He served as a utility representative for three NRC Requal Exams and was also responsible for validation of NRC requalification exam and Emergency Plan simulator scenarios. He is also responsible for writing and reviewing simulator issue reports and malfunction testing.

6/85 - 5/89 New Hamnshire Yankee. Seabrook Stati9n

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As a Senior Simulator Instructor, Mr. Tilton provided simulator training for licensed and non-licensed operators. He was also responsible for modifi Mon and malfunction testing of the simulator. After a co

.nodel upgrade he validated the new model and tested core response prior to releasing the model for training.

Mr. Tilton developed the simulator instructor station operating procedures. He acted as Technical Assistant to the Emergency Operations Manager during Emergency Plan activation.

i 10/81 - 6/85 Public Service Electric and Gas Company. Salem Nuclear Generatine Station As a Nuclear Control Operator, Mr. Tilton was licensed on both Units. He was responsible for 10 equipment and utility operators.

l He participated in normal plant operations, surveillance testing and several refueling outages. Mr. Tilton w9s part of a team that l

validated the response of the Salem sinmlator after initial delivery.

OP4F40 (9/E6)

t RICHARD L. BEST Instructor EDUCATION US Navy Nuclear Power School LICENSE AND NRC Reactor Operator License, Salem 1 and 2 CERTIFICATIONS Senior Reactor Operators Certification, Salem 1 and 2 WORK EXPERIENCE NPS Technical Services 1993-PRESENT Mr. Best is assigned to the Procedures Upgrade Project, revising Abnormal Operating Procedures by verifying them against the latest revisions of plant drawings and reference materials.

1992-1993 General Physics Cornoration Mr. Best was assigned to the Operations Training Unit at Calvert Cliffs, working for the Simulator Support Group. He conducted ANSI 3.5 testing to maintain simulator certification, verified Simulator. Modification Requests and tested software modifications prior to inclusion into training loads.

1980 - 1992 Public Service Electric & Gas. Salem 1 and 2 As the Salem Simulator Configuration Engineer, Mr. Best's responsibilities included tracking of Design Changes for applicability on the simulator and design of the work package to implement and test the changes. During this period the Salem Simulator gained NRC Certification under his supervision. Mr. Best maintained his SRO and Instructor Certification by teaching a minimum of five sessions per quarter.

As the Ixad Simulator Instructor, Mr. Best was responsible for the development of the initial training materials used on the simulator for New Licensed and Requalification Training.

During this period he assisted in the development of Salem Emergency Operating Procedures and their subsequent verification and validation in accordance with Westinghouse Emergency Response Guidelines. He also developed the operations portions of the plant Emergency Response drills.

RICHARD L. BEST As Training Supervisor, Mr. Best acted as the Plant / Trainer liaison to the vendor during the last nine months of the simulator construction at the factory. In this capacity he t

oversaw the merge of the simulation models and Integrated Operations testing, and conducted the on site Acceptance Test once the simulator was delivered to the training center.

As Training Specialist, Mr. Best developed the T11eory and Instrument & Controls portion of the New Licensed Operator training program. He taught both Licensed and Non-1 Licensed operator courses. He also received his NRC 1

Reactor Operator License during this period.

1973-1980 U.S. Navy While stationed at the Nuclear Power Training Unit, Windsor, Ct., Mr. Best held the position of Crew Training Coordinator and was a member of the Staff Training Group.

He qualified as Reactor Operator, Engineering Watch e

Supervisor, and Engineciing Officer of the Watch.

Mr. Best was stationed on board the USS George Bancroft, and qualified as Reactor Operator and Engineering Watch Supervisor.

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GENERAL PHYSICS CORPORATION DOUGLAS R. TILTON Lwl EDUCATION B.S., Nuclear Engineering Technology, Thomas Edison State College LICENSES AND Ucensed Senior Reactor Operator, Seabrook Station CERTIFICATIONS Ucensed Reactor Operator, Salem Nuclear Generating Station Certified Classroom and Simulator Instructor, Calvert Cliffs EXPERIENCE 5/89 - Present General Physics Cornoration Mr. Tilton was assigned to the Calvert Cliffs Nuclear Power Plant supporting the Initial Operator Training Unit. He conducts classroom and simulator training in all areas including theory, plant systems, integrated operations and transients. He also served as the simulator operator during numerous NRC Ucense examinations.

As a member of the Ucense Operator Requalification Training Unit, IT conducted both classroom and simulator training. He served as a utility representative for three NRC Requal Exams and was also responsible for validation of NRC requalification exam and Emergency Plan simulator scenarios. He is also responsible for writing and reviewing simulator issue reports and malfunction testing.

6/85 - 5/89 New Homoshire Yankee. Seabrook Station As a Senior Simulator Instructor, Mr. Tilton provided simulator training for licensed and non-licensed operators. He was also responsible for modification and malfunction testing of the simulator. After a core model upgrade he validated the new model and tested core response prior to releasing the model for training.

Mr. Tilton developed the simulator instructor station operating procedures. He acted as Technical Assistant to the Emergency Operations Manager during Emergency Plan activation.

10/81 - 6/85 Public Service Electric and Gas Comoany. Salem Nuclear J

Generating Station As a Nuclear Control Operator, Mr. Tilton was licensed on both Units. He was responsible for 10 equipment and utility operators.

He participated in normal plant operations, surveillance testing and several refueling outages. Mr. Tilton was part of a team that validated the response of the Salem simulator after initial delivery, i

GP-sP-40 (9/86)

,