ML20205C567

Simulator Four-Yr Certification Rept

ML20205C567
Person / Time
Site:	Quad Cities
Issue date:	03/19/1999
From:	David Decker, Symonds C, Tsakeres F COMMONWEALTH EDISON CO.
To:
Shared Package
ML20205C559	List: ML20205C567 SVP-99-054, Forwards Quad Cities Simulator Four-Yr Certification Rept, IAW 10CFR55.45,Section (b)(5)(ii).Rept Summarizes Simulator Testing Performed Since Last Certification Rept Submitted on 950310
References
NUDOCS 9904010265
Download: ML20205C567 (12)

Text

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• - ATTACIIMENT A Quad Cities Simulator Four-Year Certification Report SVP-99-054

, , (Page 1 of 5)

I. Introduction I

The Quad Cities Simulator is used to conduct NRC licensing examinations and is therefore required to meet criteria established in 10 CFR 55.45. A report identifying the simulator testing status must be submitted to the commission every 1 four years on the anniversary of the simulator certification. The Quad Cities j Simulator was certified on March 26,1991.

i The Quad Cities Simulator is owned and operated by Comed and MidAmerican Energy Companies for the training and testing of Quad Cities Nuclear Power Plant operators. The Quad Cities Simulator models Quad Cities Unit One with Unit One being considered the reference plant. The simulator was constructed by i

Link-Miles Simulation Corporation and was declared ready for training in April,

1990.

1 i This repon summarizes the simulator testing performed since the last certification j l report submitted to the NRC on March 10,1995. A full report including test data l for any certification year is available upon request. For the purpose of tids repon, a certification year stans on March 18 of a year and ends on March 18 of the

-following year. Based on the certification reports for the Quad Cities Simulator, j l Quad Cities Nuclear Power Station meets the requirements of 10 CFR 55.45.  !

l i II. References l

Title 10, Code of Federal Regulations, Part 55, " Operator Licensee," Subpart E, Section 45.

U.S. Nuclear Regulatory Guide 1.149, " Nuclear Power Plant Simulation Facilities for Use in Operator License Examinations."

ANSI /ANS 3.51993," Nuclear Power Plant Simulators for Use in Operator Training."

III. Reporting Requirements The requirements for tids report, as outlined in 10 CFR 55.45, are:

A. Paragraph 55.45 (b)(5)(ii): Identify any uncorrected perfonnance test failures, and submit a schedule for correction of such perfonnance test

, failures, if any.

l l B. Paragraph 55.45 (b)(5)(vi): A description of performance testing completed for the simulation facility.

9904010265 990325 PDR ADOCK 05000254 R PDR

I ATTACHMENT A' Qurd Cities Simulator Four-Yecr Certificztion Report SVP-99-054 k (Page 2 of 5)

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C. Paragraph 55.45 (b)(5)(vi): A description of the performance tests, if )

different, to be conducted on the siinulation facility during the subsequent I four-year period.

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D. Paragraph 55.45 (b)(5)(vi): A schedule for the conduct of approximately j 25 percent of the performance tests per year for the subsequent four years.

IV. Implementation:

A. Identify any uncorrected performance test failures, and submit a schedule for correction of such performance test failures, if any.

1. The 75% power steady state test showed point Cl27 (Tota'. Recire Flow to the Flow converters) to be out of tolerance in the 1998-1999 certification year. This is a non-critical parameter and visible to the operator only through the process computer. This point value will be part of the new thermal hydraulics model that has been developed in the Simulator Rehost Project, mentioned in section IV.C.2. Therefore, the point out-of-tolerance is scheduled to be corrected in August of 1999. (Simulator Work Request 19-99) This has little or no impact on operator train:.ng.

2. The 100% power steady state test showed points C121 and C122 (Reactor Water Cleanup Demin Flows) to be out of tolerance. At the time of the data collection, the reference plant showed a higher than normal Reactor Water Cleanup Demin Flow. The simulator remote functions for adjusting these flows will be corrected as part of the new Instructor Station, which is being developed in the Simulator Rehost Project mentioned in section IV.C.2. The simulator remote functions are scheduled to be completed in August of 1999. (Simulator Work Request 20-99) This has little or no impact on operator training.

B. Provide a description of performance testing completed for the simulation j facility. l

1. Computer Real Time Test I

This test verifies that the simulator computer remains in "Real Time" while doing complicated calculations. This test was performed armually and has tested satisfactorily each year from 1996 through 1999.

ATTACHMENT A Quad Cities Simulator Four-Tear Certification Report SVP-99-654 (Page 3 of 5)

2. Steady State Test The Steady State Test is divided into two parts: (1) a one-hour stability test and, (2) full and interim power tests. The stability test verifies the computed values do not deviate more than two percent in an hour's time.

The power test compares simulator computed data to actual plant data over the power range. These tests are perfonned annually and have tested I satisfactorily each year from 1996 through 1999.

3. Nonnal Operations Tests Normal Operations Tests, specified in ANSI /ANS-3.51993, section 3.1.1.,

are perfonned on the simulator as a test to ensure the procedures can be performed using only operator actions nonnal to the reference plant operation. The evolutions consist of startups, shutdowns, power operations and surveillance tests. These tests were perfonned over the four-year certification period and tested satisfactorily.

4. Transient Tests Transient Tests, as specified in ANSI /ANS-3.51993, Appendix B, were performed, plotted and then evaluated to be consistent to actual plant transients, UFSAR or expert panel best esthnate. These tests are performed annually and have tested satisfactorily each year from 1996 through 1999.

5. Malfunction Tests ,

1 Malfunction Tests were perfonned using Acceptance Test Procedures at a l rate of about 25% per year. Since the last NRC repon, all malfunctions i have been tested and any noted discrepancies have been corrected. l C. A description of the performance tests, if different, to be conducted on the j shnulation facility during the subsequent four-year period.

1. Refer to section IV.D. for a complete listing of perfbrmance testing to be completed in the next four year period.

2. Quad Cities Station is in the process ofinstalling a new Simulator Rehost Pmject. This project includes new PC based simulation computers, a new PC based Instructor Station, a new neutronics and thennal hydraulics model, a new containment model, and a new radiation propagation model.

Additional testing will include a Ported Model Test, a Factory Acceptance Test, an Instructor Station Test, and a Final Acceptance Test ccmducted by Comed and the vendor, RNI Technologies. This testing is ongoing and is

s ATTACHMENT A-Quad Cities Simulator Four-Year Certification Report

, SVP-99-054 l .

(Page 4 of 5) scheduled for completion in August of 1999, at which time the simulator will be recertified.

l l D. Pmvide a schedule for the conduct of approximately 25 percent of the l performance tests per year for the subsequent four years, i

! 1. Unless otherwise noted, the following tests will be perfonned annually:

a. Computer Real Time Test

5. Steady State Tests at full power and interim power levels at which valid reference plant data is available.

c. 100% Power One Hour Stability Test

d. Transient Tests: )

-Manual reactor trip

-Simultaneous trip of All Reactor Feed Pumps

-Simultaneous Closure of all MSIV's

-Simultaneous Trip of All Recirculation Pumps

-Single Recirculation Pump Trip

-Main Turbine trip (Maximum power that does not result in an inunediate reactor trip) 4

-Maximum rate power ramp l

-Maximum size LOCA combined with a loss of offsite power  !

-Maximum size unisolable steam line rupture

-Simultaneous closure of all MSIV's combined with a single stuck open safety / relief valve (inhibit high pressure ECCS pumps)

e. Normal Operations Tests

-Normal Reactor Stanup to full power conditions in the 1999-2000 certification year

-SCRAM recovery and cooldown in the 2000-2001 certification year

-Surveillance tests covered by the criteria:

1) Safety Related System

2) Required Frequency of unnthly or less

3) Have Observable results on control board indicators in the 2001-2002 certification year

-Nonnal Reactor shutdown to cold conditions in the 2002- 2003 certification year

-Any other nonnal operations test that warrants inunediate testing to validate perfonnance due to reference plant undifications or pmcedure changes

f. Malfunction Testing Malfunction testing will be done at a rate of 25% per year. See the attached list for the testing schedule.

O irriCnuturi O Q:id Cities Similr.t:r Feur Yerr Certificatin Report SVP-99-054 (Page 5 of 5)

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Chris Symondf Operations Training ' Superintendent

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i ATTACHMENT B

, Simul: tor Milfuncti:n Test Schedule SVP 99-054 (Page 1 of 7)

ANNUALTESTING PERIOD i MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-

! NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 l l

AD01 Relief Valve Setpoint Drift X AD02 Relief Valve ADS Solenoid Fail X AD03 ADS 110 Second Timer Fails To Start X l AD07 k lief Valve Sticks X l CR01 - Fuel Element Failure X CR02 Gross Fuel Element Failure X CS01 Core Spray Pump Trip X CS02 Core Spray Pump Reduced Capacity X CS03 Core Spray injection Valve Fails To Auto Open X l CSO4 Core Spray Logic Fails To Initiate X I CS07 Core Spray Injection Valve Binding X l CU01 RWCU Pump Trip X CUO3 RWCU System Leak At Regen Heat l Exchanger Inlet X l

DG01 Diesel Gen Trips and Locks Out X  !

DG02 Diesel Gen Output Breaker Trip X DG03 Diesel Engine Fails To Start X DG04 Diesel Engine Auto Start Failure X ED01 345 KV Switchyard Breaker Trip X ED02 Loss Of Reserve Auxiliary Transformer X ED03 4.16 KV BUS Failure X ED04 4.16 KV Breaker Fails to Close X ED05 480 VAC BUS Failure X ED06 480 VAC Breaker Fails To Close X ED07 480 VAC BUS Tie Breaker Trip X ED09 120/240 VAC Instrument BUS Failure X ED10 120/240 VAC Essential Service BUS Failure X ED12 250 VDC MCC Failure X ED13 125 VDC BUS Failure X EDl4 48/24 VDC BUS Failure X ,

l EG01 Main Generator Trip X EGO'2 Main Generatc r Lockup Relay l Fails To Trip X l EG04 Main Generator Stator Coolant  ;

Runback Failure X )

EG05 Main Generator Stator Coolant Pump Trip X l

l l

t L

ATTACHMENT B

i. Simulat:r Mdfuncti:n Test Schedule SVP-99-054 (Page 2 of 7)

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ANNUALTESTING PERIOD MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-l NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 FP01 Diesel Fire Pump Trip X FWOI Reactor Feed Pump Trip X FWO2 Standby Reactor Feed Pump Auto Start Failure X FWO3_ Reactor Feed Pump Faile To Auto Trip X FWO4 Reactor Feed Pump Reduced Capacity X FWO6 Reactor Feed Pump Flow Transmitter Failure X FWO7 Feedwater Level Control Valve Failure X FWO8 Feedwater Level Control Valve Lock Up X FWO9 FW Line Rupture Inside The Drywell Before The Check Valve X FW10 FW Line Rupture Inside The Drywell After The Check Valve X FW11 FW Line Rupture Outside The Drywell In The SteamTunnel X FW12 FW Line Rupture Outside Drywell At FW Reg Valve Inlet X FW14 LP FW Heater Al Tube Rupture X FW15 LP FW Heater B Tube Rupture X FW16 HP FW Ileater D Tube Rupture X FW17 Condensate / Condensate Booster Pump Trip X FW18 Condensate Booster Pump Reduced Capacity X FW19 Condensate Pump Reduced Capacity X FW21 Hotwell Makeup Control Valve Failure X FW22 Hotwell Reject Control Valve Failure X HP01 HPCI Turbine Trip X HP02 HPCI Turbine Fails To Auto Trip X HP03 HPCI Main Pump Reduced Capacity X HP04 HPCI Minimum Flow Valve Fails To Auto Open X HP09 HPCI Flow Controller Failure X HP10 Inadvertent HPCI Initiation X HP11 HPCI Failure to initiate X

)

I V

ATTACHMENT B

, Simulat:r Malfunctirn Test Schedule SVP 99-054 (Page 3 of 7)

ANNUAL TESTING PERIOD MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 ,

HP13 HPCI Steamline Rupture Inside The HPCI Room X l HPl4 Group Four Isolation Actuation X HP15 Group Four Isolation Fails  !

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( To Actuate X IIP 16 Safe Shutdown Pump Trip X l

i IIP 17 HPCI lajection Valve Binding X l

l HV01 Reactor Building Ventilation Fails To Auto Isolate X

'IA01 Instrunent Air Compressor Trip X l IA02 Reactor Building Instrunent Air System Rupture X  ;

IA03 Service AirToInstrunent Air  !

Backup Failure X IA04 Turbine Building Instrunent Air System Rupture X l IA05 Scram Air Header Leak X I IA07 Drywell Nitrogen Compressor Trip X I IA08 Drywell Nitrogen System Leak inside The Drywell X l MC01 Circulating Water Pump Trip X MC02 Circulating Water Pump Discharge Valve Fails To Open X MC03 Circulating Water Pump Discharge Valve Fails To Close X l MC04 Main Condenser Tube Sheet Blockage X MC07 . Main Condenser Tube Leak X <

MC08 Main Condenser Air Inleakage X I l MC09 SJAE Regulator Failure X l MC10 SJAE Suction Valve Fails Closed X '

MCI 1 SJAE Suction Valve Fails To Auto l Close X l

MS01 Main Steamisolation Valve Closure X l MS02 Main Steam lsolation Valve Fails i To Close X l MS03 Main Steamisolation Valve Slow Closure Time X MS05 Main Steamline Breakinside Drywell After Restrictor X MS06 Relief Valve Seat Eroded X l

, ATTACHMENT B

. Simulator Malfuncti::n Test Schedule SVP-99-054 (Page 4 of 7)

ANNUALTESTING PERIOD MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 MSO9 Main Steamline Break In The Steam .

l Tunnel X l l MS10 Main Steam Leak In The Turbine Building l

l X

l MS12 Loss Of Extraction SteamTo LP l FW Heater B .

X )

l MS13 Loss Of Extraction SteamTo LP  !

l FW Heater C X ]

MS14 Loss Of Extraction SteamTo HP i FW Heater D X MS16 Relief Valve Tailpipe Break In The Suppression Chamber X 1

NM01 SRM Channel Failure X NM02 Flow Converter Failure X NM03 SRM Detector Stuck X NM05 IRM Channel Failure X NM06 1RM Channel Out Of Calibration X NM07 IRM Detector Stuck X ,

I NM08 APRM Channel Failure X NM10 RBM Channel Failure X NM14 LPRM Detector Failure X PC01 Drywell Cooler Blower Trip X PC04 Drywell Vacuum Breaker Fails Open X l X

PC07 Suppression Pool Flange Leak PCOS Standby Gas Treatment Fan Trip X PC09 Standby Gas Treatment Fan Fails To Auto Start X PC11 Standby Gas Treatnrnt Flow Connoller Failure X RC01 RCIC Turbine Mechanical Trip X RC02 RCIC Turbine Electrica] Trip X RC04 RCIC Turbine Failure To Auto Start X RC05 RCIC Pump Reduced Capacity X RC06 RCIC FMw Controller Failure X 4 RC07 RCIC Lijection Valve Fails To Auto Open X RC10 RCIC lsolation Valve Binding X RCI1 RCIC Steamline Rupaire At Turbine Inlet X l

s

ATTACIIMENT B

, Simulatir Malfunction Test Schedule i SVP-99-054 l (Page 5 of 7)

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l ANNUALTESTING PERIOD l MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 RCl". Group Five Isolation Actuation X RCl3 Group Five Isolation Fails To Actuate X RCl4 RCIC Injection Valve Binding X RD01 Control Rod Uncoupled X RD02 Control Rod Stuck X RD03 Control Rod Drift In X RD04 Control Rod Drift Out X RDOS Control Rod Scram X RD06 Control Rod Accumulator Trouble X RD07 CRD Hydraulic Pump Trip X RD08 CRD Hydraulic Pump Reduced Capacity X RD13 Scram Disch Volume Hydraulic Lock X RD22 Manual Alternate Rod Insert 4 Circuit Failure X l RD23 Scram Disch Volume Drain Valves j Stick Open X )

RH01 RHR Pump Trip X  !

RH02 RHR Pump Reduced Capacity X RH03 RHR Inboard injection Valve Fails To Auto Open X RH06 RHR Logic Fails To Initiate X RH07 RHR Injection Valve Binding X RH08 RHR Minimum Flow Valve Binding X RM01 Area Radiation Monitor Failure X RM02 Process Radiation Monitor Failure X RP02 Auto Scram Circuit Failure X RP03 Manual Scram Circuit Failure X RPO4 RPS MG Set Trip X RP05 Group One Isolation Actuation X RP06 Group One Isolation Fails To Actuate X RP07 Group Two Isolation Actuation X RP08 Group Two Isolation Fails To Actuate X RP09 Group Three Isolation Actuation X RP10 Group Three Isolation Fails To Actuate X

^ ATTACIIMENT B

, Simulat:r M:lfuncti:n Test Schedule l SVP-99-054 l (Page 6 of 7)

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ANNUALTESTING PERIOD MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 RROI Recire Pump Drive Motor Breaker Trip X .

RR02 Recire Pump Field Breaker Trip X RR04 Recire Puny Reduced Capacity X RR06 Recire Pump inboard Seal Failure X RR07 Recirc Pump Outboard Seal Failure X j RR08 Master Recirc Flow Controller Failure X '

RR09 Recire Pung Speed Signal Failure X RRIO Recire Loop Suction Pipe Rupture X RRil Recire Loop Discharge Pipe Rupture X RR12 Reference Leg Pipe Rupture A RPV Nozzle X RR13 Variable Leg Pipe Rupture At RPV Nozzle X RR14 Recire Loop Flow Transmitter Failure X RRIS FW Level Control Level l Transmitter Failure X RR16 FW liigh Level Trip Level Instrument Failure X RR17 Analog Trip System Level Transmitter Failure X RR18 ECCS Level Instrument Failure X RR19 ATWS Level Transmitter Failure X RR20 Fuel Zone Level Transmitter Failure X RR21 ATWS Pressure Transmitter Failure X RR23 RX Level Press Compensator Press Transmitter Failure X RR25 RilR 100 psig Interlock Fails Low X RR26 RIIR 100 psig Interlock Fails liigh X SLO 1 SBLC Pump Trip X SLO 2 SBLC Pung Disch Line Relief Valve Fails Open X SWOI Service Water Puny Trip X SWO3 Recire MG Set Oil Cooler Service Water Flow Blockage X SWO4 RilR Service Water Pump Trip X SWO5 RiiR Service Water Pump Reduced Capacity X SWO6 RBCCW Pung Trip X SWO7 RBCCW Pump Reduced Capacity X SW11 TBCCW Pump Trip X SW12 TBCCW Pump Reduced Capacity X l

l l

l

l ATTACHMENT B l," Simulator Mrlfuncti n Test Schedule l SVP-99-054 (Page 7 of 7) l ANNUALTESTING PERIOD MALF MALFUNCTION 3/1999- 3/2000- 3/2001- 3/2002-NO. DESCRIPTION 3/2000 3/2001 3/2002 3/2003 SW15 Diesel Generator Cooling Water Pump Trip X l TC01 Main Turbine Trip X TC02 Main Turbine Auto Trip Logic Fails To Actuate X TC05 EHC Pump Trip X TC06 Main Turbine Stop Valve Fails Open X TC07 Main Turbine Stop Valve Fails Closed X TC08 Main Turbine Control Vahe Failure X TC09 Main Turbine Bypass Valve Failure X TCl1 EHC Pressure Regulator Failure X TUO1 Main Turbine Journal Bearing High Tenperature X TUO2 Main Turbine Journal Bearing High Vibration X TUO4 Main Turbine AC Oil Pump Trip X TUO5 Main Turbine AC Oil Pump Fails To Auto Start X TUO6 Main Turbine DC Oil Pump Trip X TUO7 Main Turbine DC Oil Pump Fails To Auto Start X

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