ML20078S050
| ML20078S050 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/12/1994 |
| From: | Mueller J NEBRASKA PUBLIC POWER DISTRICT |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NLS940121, NUDOCS 9412280067 | |
| Download: ML20078S050 (23) | |
Text
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P.O. DOX B L EB SKA 68321 i
Nebraska Public Power District "ES W" 1
NLS940121 December 12,1994 l
Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555-0001
Subject:
Cooper Nuclear Station Simulator Certification Report NRC Docket No. 50-298, DPR 46
Reference:
(1) NLS9000537 dated November 30,1990, G. R. Horn to the Office of Nuclear Reactor Regulation, Cooper Nuclear Station Simulator Initial Certification Report
Dear Sir:
The Nebraska Public Power District is submitting the 1994 Cooper Nuclear Station Simulator Certification Report and NRC Form 474, Simulation Facility Certification. This report is submitted as required by 10CFR55.45 on the fourth. anniversary of the initla! certification of the Cooper Nuclear Station Simulator (reference 1).
j The enclosed report describes performance tests conducted from 1991 to 1994, discusses performance test discrepancies from 1991 to 1994, and provides a revised Performance Test Schedule for 1995 through 1998. This report also discusses exceptions to the ANSl/ANS-3.5-1985 Standard.
NRC Form 474 is enclosed due to changes in the Performance Test Schedule.
If you have any questions regarding this submittal, please contact my office.
Sincerely, IJ)$L ohn H. Mueller Site Manager tinclosure l
cc:
Regional Administrator USNRC Region IV NRC Resident Inspector Cooper Nuclear Station 9412200067 941212 fDR ADOCK 05000298 i
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g November 30,1994 Cooper Nuclear Station Simulator 199LCAFLtlficatLaiLRnonit introduction The Cooper Nuclear Station 1994 Simulator Certification Report is required to be submitted to the Nuclear Regulatory Commission in accordance with 10CFR55.45 on the fourth anniversary of the initial certification of the Cooper Nuclear Station Simulator (November 30,1990). This report is a supplement to the 1994 Simulator Annual Certification Report.
This report describes performance tests conducted from 1991 to 1994, discusses performance test discrepancies from 1991 to 1994, and provides a revised Performance Test Schedule for 1995 through 1998. This report also discusses exceptions to the ANSI /ANS-3.5-1985 Standard.
The owner / operator of the Simulator is the Nebraska Public Power District Cooper Nuclear Station (CNS) located near Brownvulo, Nebraska. The Simulator vendor was S3 Technologies of Columbia, Maryland. CNS is a General Electric Bolling Water Reactor (BWR/4) rated at 2381 MWTh.
The Simulator was available for training on June 4,1990.
Additional information regarding the 1994 CNS Simulator Certification Report is available upon request.
Performance Tests Conducted 1991-1994 The CNS Simulator completed all annual and quadrennial performance tests for the years 1991 through 1994 as scheduled in the initial certification report.
Performance Test Discreoancies 1991-1994 Dist:repancies documented during conduct of performance tests from 1991 through 1993 have been corrected to date.
Twenty seven performance test discrepancies were documented during the conduct of the 1994 performance tests. These discrepancies are attributed to one malfunction (ED11), Critical 120 VAC Power Panel Falure, with ten generic power supply panel malfunctions (ED11 A - ED11J). These discrepancies are associated with incorrect or non-existent power supply boolean checks for various simulated components. These discrepancies are minor in nature and do not contribute to a performance test failure for this malfunction. These discrepancies are documented on Training Work Requests as priority work items.
Performance Test Schedule 1995-1998 The content of the Performance Test Schedule for 1995 through 1998 is identical to the original schedule in the initial certification report with the exception of tests which have been added to the scope of simulation and/or meet the criteria of ANSI /ANS-3.5-1985, Section 3.1.2, Plant Malfunctions. Changes to the Performance Test Schedule are enclosed as attachment 1. The revised annual Performance Test Schedules for 1995 through 1998 are enclosed as attachments 2 through 5.
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Cooper Nudear Station Simulator
.1994 Certification Report -
November 30,1994 Page 2 of 3 i
Mainr Chanaam Since I amt Reoort An intenelve effort to perform an initial upgrade to the CNS Simulator was completed in 1991. This upgrade included all reference plant modifications from the Simulator procurement contract data freeze date of May,1988 through the plant refueling outage of 1990.
Initial procurement contract warranty discrepancies were corrected since the last report.
The stimuisted plant process computer system was upgraded to reflect the configuration of the reference plant.
All applicable outage modifications to reference plant systems have been evaluated and implemented in the Simulator to date. Minor modifications have been implemented within one year of initial review of modifications i
An audio / visual system was installed in the Simulator for use in the performance evaluation process by licensed operations personnel, trainees, and instructors.
An intensive physical fidelity audit was performed to ensure the Simulator environment matches the reference plant main control room as close as is reasonable and practical. Differences noted between the Simulator and Main Control Room are maintained in a configuration database.
Exceotions to the ANSl/ANS-3.5-1985 Standard Reference 1, section 4.1(4) states that 'The calculated values of noncriticalparameters pertinent e
to plant operation, that are included on the simulator control room panels, shall agree within t 10% of the reference plant parameters and shall not detract from training '
The intent of this requirement is met by visually ensuring various power plant parameters are maintained within the CNS accepted operating range of indicating instruments on the Simulator panels.
j Reference 1, Section B1.2 specifies data to be recorded simultaneously versus time with a e
resolution of 0.5 seconds or less while monitoring parameters for transient testing.
CNS meets the intent of this requirement by verifying that parameters required to be recorded are monitored during the execution of transient tests on a time scale of two minutes to achieve a resolution of.5 seconds on a monitored parameter trend display. Once the transient test is completed, the time scale is adjusted in order to capture the transient data on a readable plot, typically ten to twenty minutes in duration. The hardcopy data that is maintained in the certification reports reflect a resolution of greater than 0.5 seconds.
Cooper Nuclear Station Simulator 1994 Certification Report November 30,1994 Page 3 of 3 Reference 1, section 3.1.1, Normal Plant Evolutions, states that 'The simulator shall be capable e.
of simulee%g continuoualy, and in real time, plant operations of the reference plant.'
- CNS takes credit for various normal plant evolutions based on presentation of training material in i
the Simulator.
Reference 1, section 3.1.1(4), Normal Plant Evolutions, states that 'the simulator shall be e
capable of performing, using only operator action normal to the reference plant; Reactor trip followed by recovery to rated power.'
Recovery to rated power from a reactor trip is not practiced at CNS within the short time interval as implied by this requirement. CNS takes exception to this requirement since training is not provided in a restart of the reactor within a short timo interval following a reactor trip.
Referenc? 1,4pendit B, section B t.1 specifies various data to be recorded during Steady e
State Performance Testing.
a.
Control Rod Drive Hyirsulic System Flow b.
Control Rod Drive Hydraulic System Temperature c.
Reactor Water Cleanup System Inlet and Return Flows d.
Reactor Water Cleanup Retum Temperature CNS did not record the data listed above during the Simulator steady state performance tests in the initial (1990) and 1991 Simulator Certification Reports. CNS noted this discrepancy during the 1991 Certification proce' The data listed above were subsequently recorded in the 1992, 1993 and 1994 Simulator stc@ state tests.
The CNS Simulator takes no further weptions to the standard other than those reported in the initial certification.
End of Reoort i
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Cooper Nuclear Station Simulator 1994 Certincation neport Test Schedule Chanees November 30,1994 Page 1 of 2 Malfunction Title Schedule Changes AD08A Reactor Safety Valve 70A Spurious Opening Addition AD08B Reactor Safety Valve 70B Spurious Opening Addition AD08C Reactor Safety Valve 70C Spurious Opening Addition AD09 Leak on Drywell Pneumatic Header Addition EG02A Main Transformer A Loss of Cooling Addition EG02B Main Transformer B Loss of Cooling Addition EG02C Main Transformer C Loss of Cooling Addition EG06 Loss of Generator Exciter Cooling Addition EG07 Loss of GeneratorIlydrogen Cooling Addition IM17 Condensate Pump Suction Boot Rupture Addition HP05 HPCIInadvertant Initiation Addition HP09 FailureofHPCI AutoIsolation Addition MC04A SJAE Steam Supply PCV-77A Failure Addition MC04B SJAE Steam Supply PCV-77B Failure Addition MS05 Steam Seal Pressure Regulator Failure Addition RC04 RCIC Flow Controller Failure Addition RC05 RCIC Inadvertant Initiation Addition RC07 Failure of RCIC Auto Isolation Addition RD04A CRD Flow Control Valve 19A Failure Addition RD04B CRD Flow Control Valve 19B Failure Addition RM01A Service Water Rad Monitor Failure Addition RM01B REC Rad Monitor Failure Addition RM01C Liquid Radwaste Efiluent Monitor Failure Addition RM02A-Q Gaseous Radiation Monitor Failure AWtion RM04A MSL Rad Monitor 251 A Fails Inoperative Addition RM04B MSL Rad Monitor 251B Fails Inoperative Addition RM04C MSL Rad Monitor 251C Fails Inoperative Addition RM04D MSL Rad Monitor 251D Fails Inoperative Addition RPl2 Group 3 Isolation Failure Addition RR06A RR Pump 1 A Control Signal Failure Addition RR06B RR Pump IB Control Signal Failure Addition RR14A RR Loop Flow Transmitter 110A Failure Addition
Cooper Nuclear Station Simulator 1994 Certincation neport Test Schedule Changes November 30,1994 Attachancat 1 Page 2 of 2 Malfunction Title Schedule Changes RRl4B RRImp Flow Transmitter 110B Failure Addition RR14C RRImp Flow Transmitter 1IOC Failure Addiuon RRl4D RR Loop Flow Transmitter 110D Failure Addition RR24A RPT Fails to Trip RR Pump 1 A Addition RR24B RIrr Fails to Trip RR Pump IB Addition SWO3A Class ! Isolation (SW-PS-364A)
Addition SWO3B Class I Isolation (SW-PS-346B)
Addition SW13A RECIIX 1 A Cooling Water Blockage Addition SW13B REC IIX IB Cooling Water Blockage Addition TC05 DEH Computer Failure Addition
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I Cooper Nuclear Station Simulator 1994 Certific.dion Report tiovamber so,1994 1995 Performance Tests Pay 1of4 l
Test Title Malfunction CR01 Fuel Clad Failure Malfunction CS01A Core Spray Pump 1 A Trip Malfunction CS01B Core Spray Pump IB Trip Malfunction DG01 A Diesel Generatu 1 Fails to Start Malfunction DG01B Diesel Generator 2 Falls to Start Malfunction DG02A Diesel Generator 1 Trip Malfunctica DG02B Diesel Generator 2 Trip Malfunction ED03A 4160V Bus I A Auto Transfer Failure Malfunction ED03B 4160V Bus IB Auto Transfer Failure Malfunction ED03C 4160V Bus 1E Auto Transfer Failure Malfunction ED03D 4160V Bus IF Auto Transfer Failure Malfunction ED03E 4160V Bus 1G Auto Transfer Failure Malfunction ED08A 4160V Bus I A Power Failure Malfunction ED08B 4160V Bus IB Power Failure Malfunction ED08C 4160V Bus IC Power Failure Malfunction ED08D 4160V Bus 1D Power Failure Malfunction ED08E 4160V Bus IE Power Failure Malfunction ED08F 4160V Bus IF Power Failure Mall'anction ED080 4160V Bus 1G Power Failure Malfunction ED12A less of 125VDC HPCI Starter Rack Malfunction ED12B Loss of125VDC RCIC Starter Rack Malfunction ED12C Loss of 125VDC Reactor Building Starter Rack Malfunction ED12D Loss of 125VDC Distribution Panel A
!,'alfunction ED12E Loss of 125VDC Distribution Panel B Malfunction ED12F Loss of 125VDC Starter Rack B Malfunction EDl5 Loss of 12.5KV Power Malfunction FWOI A Reactor Feedwater Pump I A Trip Malfunction FWolB Reactor Feedwater Pump IB Tsip Malfunction FWO5A RFP 1 A Individual M/A Station Controller Failure Malfunction FWO5B RFP IB Individual M/A Station Controller Failure
Cooper Nuclear Station Simulator
' 1994 Certification Report November 30,1994 1995 Performance Tests Attacheneet 2 Page 2 of 4 Test Title Malfunction FW17 Condensate Pump Suction Boot Rupture Malfunction HP01 HPCI System Failure to Auto Start Malfunction HP05 HPCIInadvertant laitiation Malfunction IA01 Instrument Air System Depressurizes Malfunction MCol Main Condenser AirIn Leakage Malfunction MC04A SJAB Steam Supply PCV-77A Failure Malfunction MC04B SJAE Steam Supply PCV-77B Failure Malfunction MSol A MSL-A Steam Leakage inside Primary Containment Malfunction MS01B MSL-B Steam Leakage Inside Primary Containment Malfunction MS01C MSL-C Steam Leakage Inside Primary Containment Malfunction MS01D MSL-D Steam Leakage Inside Primary Containment Malfunction MS02A MSL-A Line Rupture Inside Primary Containment Malfunction MS02B MSL-B Line Rupture Inside Primary Containment Malfunction MS02C MSL-C Line Rupture Inside Primary Containment Malfunction MS02D MSL-D Line Rupture Inside Primary Containment Malfunction MS05 Steam Seal Pressure Regulator Failure Malfunction NM01 A Rod Block Monitor A Failure Malfunction NM01B Rod Block Monitor B Failure Malfunction NM02A SRM Channel A Failure Malfunction NM02B SRM Channel B Failure Malfunction NM02C SRM Channel C Failure Malfunction NM02D SRM Channel D Failure Malfunc6en NM03 A SRM Channel A Retract Permit Failure Malfunction N$03B SRM Channel B Retract Permit Failure Malfunction NM03C SRM Channel C Retract Permit Failure Malfunction NM03D SRM Chamiel D Retract Permit Failure Malfunction NM04A SRM Channel A Detector Stuck Malfunction NM04B SRM Channel B Detecior Stuck Malfunction NM04C SRM Channel C Detector Stuck Malfunction NM04D SRM ChannelIl Detector Stuck
Cooper Naclear Station Simialator 1994 Certification Report neve,,ser so,1994 1995 Performance Tests Attachement 2 Page 3 of 4 Test Title Malfunction RC04 RCIC Flow Controller Failure Malfunction RC05 RCIC laadvertant initiation Malfunction RC07 Failure of RCIC Auto Isolation Malfunction RD02 ATWS Malfunction RD04A CRD Flow Control Valve 19A Failure Malfunction RD04B CRD Flow Control Valve 19B Failure Malfunction RD06 CRD Drive Water Filter Clogging Malfunction RII01 A RIIR Pump 1 A Trip Malfunction RII0lB RIIR Pump IB Trip Malfunction R1101C RIIR Pump 1C Trip Malfunction R1101D RiiR Pump ID Trip Malfunction RP01 A Group 1 Scram Pilot Solenoids Fail to De-energize Malfunction RP01B Group 2 Scram Pilot Solenoids Fail to De-energize Malfunction RP01C Group 3 Scram Pilot Solenoids Fail to De-energize Malfunction RPOID Group 4 Scram Pilot Solenoids Fail to De-energize Malfunction RP02 Reactor Scram Malfunction RR04A Recirc Pump Drive Motor Breaker ICS Trip Malfunction RR04B Recire Pump Drive Motor Breaker ICN Trip Malfunction RR04C Recire Pump Drive Motor Breaker IDS Trip Malfunction RR04D Recirc Pump Drive Motor Breaker IDN Trip Malfunction RR05A Recire Pump i A Field Breaker Trip Malfunction RR05B Recirc Pump IB Field B:r.aker Trip Malfunction RR06A RR Pump 1 A Control Signal Failure Malfunction RR06B RR Pump IB Control Signal Failure Malfunction SWOI A Senice Water Pump 1 A Trip Malfunction SWolB Senice Water Pump IB Trip MalAmetion SWOIC Senice Water Pump IC Trip
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Malfunction SWOID Senice Water Pump ID Trip Malfunction SWO4A RIIR Senice Water Booster Pump 1 A Trip Malfunction SWO4B Ri!R Senice Water Booster Pump 1B Trip J
Cooper Nuclear Station Sinsulator 1994 Certification Repor1t November 30,1994 1995 Performance Tests Attarkw 2 Fase 4 of 4 Test Title Malfunction SWO4C RilR Service Water Booster Pump IC Trip Malfunction SWO4D RIIR Service Water Booster Pump ID Trip Malfunction TC01 Main Turbine Trip Transient 1 Manual Scram from 100% Power Transient 2 Simultaneous Trip of Both Feedwater Pumps Transient 3 Simult.meous Closure of all MSIVs Transient 4 Simultaneous Trip of Both Recirc Pumps Transient 5 Single Recirc Pump Trip Transient 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp Transient 8 Reactor Coolant System Rupture with Loss of all AC Transient 9 Unisolable Main Steam Line Rupture Transient 10 Closure of all MSIVs with Single Stuck Open Relief Valve Steady State Test 25%,75%,100% Steady State Operations Realtime Computer Real Time Test Normal Operations Normal Operations Tests i
oper Nuclear Station Simulator 4 n4 cenancation nepen November 3o, nest i996 Performance Tests Attachement 3.
Page 1 of'4 Test Title Malfunction AD08A Reactor Safety Valve 70A Spurious Opening i
Malfunction AD08B Reactor Safety Valve 70B Spurious Opening Malfunction AD08C Reactor Safety Valve 70C Spurious Opening Malfunction AD09 Leak on Dr>well Pneumatic Header i
Malfunction CS02A Core Spray Iq)cction Valve 12A Fails to Auto Open i
Malfunction CS02B Core Spray injection Valve 12B Fails to Auto Open r
Malfunction DG03A Diesel Generator Breaker EGI Fails to Auto Close Malfunction DG03B Diesel Generator Break;r EG2 Fails to Auto Close Malfunction ED04 Loss of All AC Power Malfunction ED09A 480V Bus 1 A Power Failure Malfunction ED09B 480V Bus IB Power Failure Malfunction ED09C 480V Bus IE Power Failure Malfunction ED09D 480V Bus IF Power Failure Malfunction ED09E 480V Bus 1G Power Failure Malfunction EDl3A Loss of 250VDC HPCI Starter Rack Malfunction EDl3B Loss of 250VDC RCIC Starter Rack Malfunction EDl3C Loss of 250VDC DIV-1 Starter Rack Malfunction ED13D Loss of 250VDC DIV-2 Starter Rack Malfunction ED13E Loss of 250VDC Turbine Building Starter Rack Malfunction ED13F Loss of 250VDC Starter Rack B Malfunction ED14A Loss of 24VDC Power Panet DC-A Malfunction EDl4B f oss of 24VDC Power Panel DC-B Malfunction ED16A 425VDC Battery Charger I A Failure Malfunction EDl6B 125VDC Battery Charger 1B Failure Malfunction ED16C 125VDC Battery Charger IC Failure Malfunction EG02A Main Transformer A Loss of Cooling Malfunction EG02B Main Transformer B Loss of Cooling Malfunction EG02C Main Transformer C Loss of Cooling Malfunction EG06 Loss of Generator Exciter Cooling Malfunction EG07 Loss of Generator Hydrogen Cooling
i Ceeper Nuclear Staties Simulator 1994 Certificaties Iteport November so, sss4 1996 Performance Tests Page 2 of 4 Test Title f
Malfunction FWO9 RFP Master Controller Failure MalAmetion FW11 A Feedwater Flow Signal Failure to RVLC System - 50A Malfunction FW1IB Feedwater Fbw Signal Failure to RVLC System - 50B Malfunction FW13A Steam Flow Signal Failure to RVLC System - 51 A Malfunction FW13B Steam Flow Signal Failure to RVLC System - SIB Malfunction FW13C Steam Flow Signal Failure to RVLC System - 51C Malfunction IW13D Steam Flow Signal Failure to RVLC System - SID Malfunction HPO4 IIPCI Flow Controller Failure Malfunction HP09 FailureofIIPCI Autoisolation Malfunction MS03A MSL-A Line Rupture Outside Primary Containment Malfunction MS03B MSL B Line Ruptute Outside Primary Containment Malfunction MS03C MSL-C Line Rupture Outside Primary Containment Malfunction MS03D MSL D Line Rupture Outside Primary Containment Malfunction NM05A IRM Channel A Failure Malfunction NM05B IRM Channel B Failure Malfunction NM05C IRM Channel C Failure Malfunction NM05D 1RM Channel D Failure Malfunction NM05E IRM Channel E Failure Malfunction NM05F IRM Channel F Failure Malfunction NM0$G IRM Channel G Failure Malfunction NM0511 IRM Channel H Failure Malfunction NM06A IRM Channel A Detector Stuck Malfunction NM0(S IRM Channel B Detector Stuck Malfunction NM06C IRM Channel C Detector Stuck Malfunction NM06D IRM Channel D Detector Stuck Malfunction NM06E IRM Channel E Detector Stuck Malfunction NM06F IRM Channel F Detector Stuck Malfunction NM06G IRM Channel G Detector Stuck i
Malfunction NMD611 IRM Channel H Detector Stuck Malfunction NM07A IRM Channel A Retract Permit Failure
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l Cooper Nuclear Station Simulator 1994 Certification Report Neveanber 30,1994
'I996 Perforntance Tests Attachement 3 Page 3 of 4 Test Title Malfunction NM07B IRM Channel B Retract Permit Failure Malfunction NM07C 1RM Channel C Retract Permit Failure Malfunction NM07D IRM Channel D Retract Permit Failure Malfunction NM07E IRM Channel E Retract Permit Failure Malfunction NM07F IRM Channel F Retract Permit Failure Malfunction NM07G IRM Channel G Retract Permit Failure Malfunction NM0711 IRM Channel 11 Retract Permit Failure Malfunction NM08 (1-124)
LPRM Failure Malfunction PC04 Instrument Line Break Malfunction RD09 (1 137)
Control Rod Drin in Malfunction RD10 (1-137)
Control Rod Drin Out Malfunction RD12 (1-137)
Control Rod Stuck Malfunction RDl3 (1 137)
Control Rod Uncoupled Malfunction R1104A LPCI INBD Injection Valve 25A Failed Closed Malfunction RiiO4B L.PCI INBD Injection Valve 25B Failed Closed Malfunction RPO4 Group 1 Isolation Failure Malfunction RP05 Group 21 solation Failure Malfunction RR16 Recirc Master Flow Controller Failure Malfunction SWO5A Loss of REC to RR Pump 1 A Malfunction SWO5B Loss of REC to RR Pump 1B Malfunction SWO7A TEC Pump I A Trip Malfunction SWO7B TEC Pump 1B Trip Malfunction SWO7C TEC Pump IC Trip Tmnsicct i Manual Scram from 100% Power Trarisient 2 Simultaneous Trip of Both Feedwater Pumps Transient 3 Simultaneous Closme of all MSIVs Transient 4 Simultaneous Trip of Both Recire Pumps Transient 5 Single Recirc Pump Trip Transient 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp Transient 8 Reactor Coolant System Rupture with Loss of all AC
Cooper Nuclear Station Simesister 1994 Certification Report Neveanber 30,1994 1996 Performance Tests Attachenest 3 Page 4 of 4 Test Title Transient 9 Unisolable Main Steam Line Rupture Transient 10 Closure of all MSIVs with Single Stuck Open Relief Valve Steady State Test 25%,75%,100% Steady State Operations Realtime Computer Realtime Test Normal Operations Normal Operations Tests i
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l Ceeper Nuclear Station Simulator 1994 Certificaties Repost l
Ne m serso,s994 1997 Performance Tests Page 1 of 3 l
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Test Title Malfunction CR03 Gross Fuel Cladding Failure
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Malfunction ED05 IAss of Startup Transformer 1
Malfunction ED06 Loss of Emergency Transformer Malfunction ED10A MCC-A Failure Malfunction ED10B MCC-F Failure
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Malfunction ED10C MCC-LX Failure Malfunction ED10D MCC-TX Failure Malfunction ED10E MCC K Failure 1
Malfunction ED10F MCC-L Failure Malfunction ED100 MCC-S Failure Malfunction ED10H MCC-T Failure j
Malfunction ED17 Loss of NBPP #1
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Malfunction FW16A Ilotwell Level Controller Auto Failure (LIC-2A)
Malfunction FW16B llotwell Level Controller Auto Failure (LIC 2B)
Malfunction FWl8A Feedwater A Line Break Inside Containment Malfunction FW18B Feedwater B Line Break Inside Containment Malfunction FW19A Feedwater A Line Break Outside Containment Malfunction FW19B Feedwater B Line Break Outside Containment Malfunction FW20A Feedwater Heater 1-A 5 Level Control Failure Malfunction FW20B Feedwater Heater 1 B-5 Level Control Failure Malfunction IA03 Non-Critical Instrument Air System Leak Malfunction MS08A DEH Pressure Transmitter 81 A Failure Malfunction MS08B DEH Pressure Transmitter 81B Failure Malfunction NM09A APRM Channel A Signal Failure Malfunction NM09B APRM Channel B Signal Failure Malfunction NM09C APRM Channel C Signal Failure Malfunction NM09D APRM Channel D Signal Failure Malfunction NM09E APRM Channel E Signal Failure Malfunction NM09F APRM Channel F Signal Failure Malfunction NM12A SRM Channel A Inop
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~ Ceeper Maclear Station Simulator 1994 Certincation Report l
l non herse,ised 1997 Performance Tests l
- Attacheneet 4 Page 2 et 3 Test Title Malfunction NM12B SRM Channel B Inop Malfunction NM12C SRM Channel C Inop Malfbaction NM12D SRM Channel D Inop Malfunction RD20 RPIS Failure - Total Malfunction RM01 A Service Water Rad Monitor Failure Malfunction RM01B REC Rad Monitor Failure Malfunction RMolC Liquid Radwaste Elliuent Monitor Failure Malfunction RM02A-Q Gascous Radiation Monitor Failure Malfunction RM04A MSL Rad Monitor 251 A Fails Inoperative Malfunction RM04B MSL Rad Monitor 251B Fails Inoperative Malfunction RM04C MSL Rad Monitor 251C Fails Inoperative Malfunction RM04D MSL Rad Monitor 251D Fails Inoperative Malfunction RP06 Group 3 Reactor Low Level Isolation Failure l
Malfunction RP07 Group 6 Iligh Rad Isolation Failure Malfunction RP12 Group 3 Isolation Failure Malfunction RR14 A RR Loop Flow Transmitter 110A Failure Malfunction RR14B RR Loop Flow Transmitter 110B Failure Malfunction RRl4C RR Loop Flow Transmitter 110C Failure Malfunction RR14D RR Loop Flow Transmitter 110D Failure Malfunction RR17A Recirc Pump 1 A hVA Flow Controller Failure Malfunction RR17B Recire Pump IB hVA Flow Controller Failure Malfunction RR20A RR Loop A Coolant Leak Inside Primasy Containment Malfunction RR20B RR Loop B Coolant Leak Inside Primary Containment i
Malfunction SWO9A REC Line Break 1 A Malfunction SWO9B REC Line Break IB l
l Malfunction SW10 TEC Line Break l
Malfunction SWil A REC Pump i A Trip 1
Malfunction SW1IB REC Pump IB Trip Malfunction SWilC REC Pump IC Trip Malfunction SWllD REC Pump ID Trip
Cooper Nuclear Station Sinsulator 1994 Certification Report Neveseber 30,1994 1997 Performance Tests Attaciudent 4 Page 3 of 3 Test Title Malfunction TC07A Bypass Valve #1 Failure Malfunction TC07B Bypass Valve #2 Failure Malfunction TC07C Bypass Valve #3 Failure Malfunction TC09A C9ntro! Valve #1 Failure Malfunction TC09B Control Vahr #2 Failure Malfunction TC09C Control Valve #3 Failure Malfunction TC09D Control Valve #4 Failure Transient i Manual Scram from 100% Power Transient 2 Simultaneous Trip of Both Feedwater Pumps Transient 3 Simultaneous Closure of all MSIVs Transient 4 Simultaneous Trip of Both Recire Pumps Transient 5 Single Recire Pump Trip Transient 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp Transient 8 Reactor Coolant System Rupture with Loss of all AC Transient 9 Unisolable Main Steam Line Rupture Transient 10 Closure of all MSIVs with Single Stuck Open Relief Valve i
Steady State Test 25%,75%,100% Steady State Operations Real Time Computer Realtime Test Normal Operations Normal Operations Tests i
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Ceeper Nuclear Station Simsulator 1994 Certifleation Report Nevesiber 30,1994 1998 Performance Tests Attaclassent S Page 1 of 4 Test Title Malfunction AD06A Relief Valve 71 A Complete Failure Malfunction AD06B Relief Valve 71B Complete Failure Malfunction AD06C Relief Valve 71C Complete Failure Malfunction AD06D Relief Valve 71D Complete Failure Malfunction AD06E Relief Valve 71E Complete Failure Malfunction AD06F Relief Wlve 71F Complete Failure Malfunction AD06G Relief Valve 71G Complete Failure Malfunction AD06H Relief Valve 71H Complete Failure Malfunction CUO8 RWCU System Leak inside Containment Malfunction CUO9 Cold Water Cleanup Leak Malfunction ED07 Loss of Normal Transformer Malfunction EDI1 A Critical Dist Panel CDP-1 A Failure Malfunction EDIIB Critical Dist Panel CDP-1B Failure Malftmetion EDIIC Critical Power Panel CPP Failure Malfunction EDilD Critical Power Panel CPP-1 Failure Malfunction EDIIE Critical Power Panel CPP-2 Failure Malfunction EDilF Critical Power Panel CPP-3 Failure Malfunction EDIIG Critical Control Panel CCP 1 A Failure Malfunction ED1111 Critical Control Panel CCP 2 A Failure Malfunction EDI11 Critical Control Panel CCP 1B Failure Malfunction EDilJ Critical Control Panel CCP-2B Failure Malfunction EG09 Main Generator Trip Malfunction FW21 A Feedwater Control Signal Failure to RFP-1 A Malfunction FW21B Feedwater Control Signal Failure to RFP 1B Malfunction FW22 Feedwater Startup Master Controller Failure Malfunction FW23A RFP 1 A Lovejoy Controller Failure Malfunction FW23B RFP 1B Lovejoy Controller Failure Malfunction MS10 Steam Leakage in Turbine Building Malfunction NMl3A IRM Channel A Inop i
Malfunction NM13B IRM Channel B Inop
Cooper Nuclear Station Simulator 1994 Certification Report November 30,1994 1998 Performance Tests Page 2 of 4 Test Title Malfunction NM13C IRM Channel C Inop Malfunction NM13D IRM Channel D Inop Malfunction NM13E IRM Channel E Inop Malfunction NM13F IRM Channel F Inop Mdfunction NM13G IRM Channel G Inop Malfunction NM13H IRM Channel H Inop Malfunction NM14A APRM Channel A Inop Malfunction NM14B APRM Channel B Inop Malfunction NM14C APRM Channel C Inop
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Malfunction NM14D APRM Channel D Inop Malfunction NM14E APRM Channel E Inop Malfunction NM14F APRM Channel F Inop Malfunction NMI5A APRM Flow Converter A Inop Malfunction NMISB APRM Flow Converter B Inop Malfunction RD26 Backup Scram Valve Failure Malfunction RD27 Automatic ARI Failure Malfunction RH07 RHR Shutdown Cooling Valve Isolation Malfunction RR24 A RIrr Fails to Trip RR Pump 1 A Malfunction RR24D RPT Fails to Trip RR Pump 1B l
Malfunction RR25A LIS 57A (NR Yarway) Fails Downscale Malfunction RR25B LIS-57B (NR Yarway) Fails Downscale Malfunction RR25C LIS-58A (NR Yarway) Fails Downscale Malfunction RR25D LIS-58B (NR Yanvay) Fails Downscale Malfunction RR26A LIS-72A (NR Yarway) Fails Downscale l
Malfunction RR26B LIS-72B (NR Yanvay) Fails Downscale i
Malemetion RR26C LIS-72C (NR Yarway) Fails Downscale Malfunction RR26D LIS-72D (NR Yarway) Fails Downscale 1
Malfunction RR27A LT 52A (NR Gemac) Failure Malfunction RR27B LT-52B (NR Gemac) Failure Malfunction RR27C LT-52C (NR Gemac) Failure
Cooper Nuclear Station Simulator i
1994 Certification Report Nmmber 30,1994 1998 Performance Tests Attachaient 5 Page 3 of 4 Test Title J
Malfunction RR28A LIS-101 A (NR Barton) Failure Malfunction RR288 LIS-101B (NR Barton) Failure Malfunction RR28C LIS 101C (NR Barton) Failure l
Malfunction RR28D LIS 101D (NR Barton) Failure Malfunction RR29A LIS 83 A Switch Fails Upscale Malfunction RR29B LIS-83B Switch Fails Upscale l
Malfunction RR30A LITS-73 A (FZ Yanvay) Switch Fails Downscale Malfunction RR30B LITS-73B (FZ Yarway) Switch Fails Downscale Malfunction RR31 A Recire Suction Loop A Rupture Malfunction RR31B Recirc Suction Loop B Rupture Malfunction RR32A Recire Discharge Loop A Rupture Malfunction RR32B Recite Discharge Loop B Rupture l
Malfunction RR33 A Reference Leg 3 A Failure Malfunction RR33B Reference Leg 3B Failure Malfunction SWO3A Class i Isolation (SW-PS 364 A)
Malfunction SWO3B Class ! Isolation (SW-PS-346B)
Malfunction SW13A RECIIX 1 A Cooling Water Blockage Malfunction SW13B REC IIX IB Cooling Water Blockage Malfunction SWIS Loss of Drywell Cooling Malfunction SW16 PCIS Group 1 Isolation Malfunction TC05 DEH Computer Failure Malfunction TCl2 DEII System Load Reference Failure Transient !
Manual Scrarn f*om 100% Power Transient 2 Simultar.com Trip of Both Feedwater Pumps Transient 3 Simultaneous Closure of all MSIVs Transient 4 Simultaneous Trip of Both Recirc Pumps Transient 5 Single Recirc Pump Trip Transier.t 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp Transient 8 Reactor Coolant System Rupture with Loss of all AC Transient 9 Unisolable Main Steam Line Rupture
4.
Cooper Neelear Station Simulator ses4 Certencatlea Report novemser so, sss4 1998 Performance Tests Page 4 of 4 Test Title Transient 10 Closure of all MSIVs with Single Stuck Open Relief Valve Steady State Test 25%,75%,100% Steady State Operations Realtime Computer Real Time Test Normal Operations Normal Operations Tests
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NRC FORM 474 U.S, NUCLEAR REGULATORY COMMISSION APPROVED t.Y 0848: NO. 31944134 EXPtRES: 16/31/95 g
ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THl3 WFORMATION COLLECTION REQUEST:
120 HOURS.
FORWARD SIMULATION FACILITY CERTIFICATION
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RECORDS MANAGEMENT BRANCH NUCLEAR REOULATORY COMMISSION, WASHINGTON, DC 20655 0001,AND TO THE PAPERWORK REDUCTION PRO. LECT (3150 0138), OFFICE OF MANAGEMENT AND BUDGFT. WASHINGTON, DC 20503 iN TRUCTiON : in.s so,m i. io ne ni.d for in conmc. ion, r.c.nmc. ion v.. qui,.
.uch.,ian. P, ovide me sonowing in.o.mnen and e. m. a
,on,w. m to ina 4, and so, any.nange io a. mow.on,aca,,y peno,mance ie.iin, pian made ano,innw.ubm.u o, e,.ason so, sub,n F ACILITY '
DOCKET NUMBER Cooper Nuclear Station s0-298 UCENSEE DATE Nebraska Public Power District 11/30/94 This le to cerley that:
- 1. The above named facey licensee is uomg a simulat#on faclisty consistmg solely of a plant referenced simulator thal meets the requirements of 10 CFR SS.45.
- 2. Documentaltc,n is available for NRC teview in accordance with 10 CFR SS 4S(bb 3 Thee s6mulation facility mee's the guidance contamed in ANSI /ANS3.5. 1985, endorsed by NRC Regulatory Ou de 1.140.
W there are any EXCEPTIONS to the certmcation of tnis nem, CHECK HERE [ ] and describe fully on additonal pages as necessary.
NAME (or omer Afere8 cation) AND LOCAfloN OF SIMULATION F ACluTY.
Cooper Nuclear Station Nuclear Learning Center Brownville, NE 68321 SIMLAATION F ACluTY PERFORMANCE TEST ABSTRACTS ATT ACHED. (Forperbmance eeses conducted m es pened ending wfm me date of mis cer68caem)
DE8CRIYTION OF PEHFOHMANCE 1ESTINO COMPLETLD. (Atrech addmonalpages se necessary and kiertly be Mem desonpkon bemg conenved)
I i
SiWULATION FACluTY PERFORMANCE TESTNG SCHEDULE ATTACHEO. (For me conduct of approssmatory N o/pedormance tests per year Ibr me Abur-year penod commenemy wfm me date of evn eerencaeon)
DESGftPTION OF PEHF OHMANCE TESTING TO BE CONDUCTE D. (Arrech add /Donar pages as recessary old scientrfy me dem descitpoon bemg canonued) l I
I i
X PERFORMANCE TESTWO PMN CHANOE. (For any snodrAcean w e perkmance fosong pIrt suWnmed on a prewous cer6#caem)
DESCRIPTION OF PLHFORMANCE TESTNG PLAN CHANGE (Arrach addeponerpages as neceswy amf #derefy me nem desenpeon Deep conenued)
The content of the Performance Test Schedule for 1995 through 1998 is identical to the original ochedule in the initial certification report with the exception of tests which have been added to the scope of sinulation and meet the criteria of ANSI /ANS-3.5-1985, Section 3.1.2, Plant Halfunctions.
Refer to Nebraska Public Power District letter NLS940121 dated Decanber 12,1994, John H. Hueller to Director, Office of Nuclear Reactor Regulation, Cooper Nuclear Station Sinulator Certification Report, attachments 1 through 5.
RECERT1FlCATlON (Desenbe coeeckve acconn takers ettech resunts of comp #eted pedormance tes6ng m accordance
- to CFR SS.dS(b)(S)(v).
(Attach addrhonne pagee as necessa'y and iden69y me Mem descipnort be,ng conOnved)
Any fnies stasement or omemon m this document. Inclu*ng attachments, may te subsect to cui and enmmsu sanchens I corkfy under penany of pequy that the informaten m this tiocurnent and snachments le true and correct.
I EHOyTVHL. AUTHOHLILO HLPHEaENTAftVE IITLE DATE te Wer, bper Mear htion j) in ac4rdarme wem to CFH 55 5, Communications. this form shan be submmed to the NHC as follown-SY Mall ADOFIESSED TO-DIRECTOR, OFf1CE OF NUCLE AR RFACTOR REQULATION BY DELNERY IN PERSON ONE WHITE FL.tHT NORTH U.S. NUCLEAR,tFOULATORY COMMISSION TO THE NRC OFFICE AT:
11SSS ROCKVILLE PtKE WA&HINGTOsi, DC,0%S4001 ROCKVILLE. MD NHC FOHM 414 po 82)
PHINTED ON HECYCLED PAPER
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LIST OF NRC COMMITMENTS l ATTACHMENT 3 l Correspondence No: NLS940121 da.ted 12/12/94 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submitcal represent intended or planned actions by the District. They are described to the NRC for the NRC's information and are not regulatory commitments.
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE None.
PROCEDURE NUMBER 0.42 REVISION NUMBER 0 l
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