ML20199D225

Forwards 1998 CNS Simulator Certification Rept,As Required by 10CFR55.45.Rept Describes Performance Tests Conducted from 1995-98,discusses Performance Test Discrepancies from 1995-98 & Provides Revised Test Plan for 1999-2002

ML20199D225
Person / Time
Site:	Cooper
Issue date:	12/30/1998
From:	Swailes J NEBRASKA PUBLIC POWER DISTRICT
To:	NRC (Affiliation Not Assigned)
References
NLS980205, NUDOCS 9901200034
Download: ML20199D225 (18)

Text

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Nebraska Public Power District Nebraska's Energy Leader NLS980205 December 30,1998 l

Director, Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission l Washington, D. C. 20555-0001 l

Subject:

Cooper Nuclear Station Simulator Certification Report l

NRC Docket No. 50-298, DPR-46  !

Reference:

(1) NLS9000537 dated November 30,1990, G. R. Horn to the Oflice of Nuclear Reactor Regulation, Cooper Nuclear Station Simulator Initial Certification Report (2) NLS950189 dated November 16,1995, John H. Mueller to the Director, ,

Office of Nuclear Reactor Regulation, Cooper Nuclear Station Simulator Performance Test Plan Change  ;

Dear Sir:

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The Nebraska Public Power District (District) is submitting the 1998 Cooper Nuclear Station Simulator Certification Report. This report is submitted as required by 10CFR55.45 every four years on the anniversary of the initial certification of the Cooper Nuclear Station Simulator ,

(reference 1). g3 Per Reference 2 the District informed the Director, Office of Nuclear Reactor Regulation of changes to the Cooper Nuclear Station Simulator Performance Test Plan. The enclosed report describes performance tests conducted from 1995 to 1998, discusses performance test discrepancies from 1995 to 1998, and provides a revised Performance Test Plan for 1999 through 2002. This report also discusses exceptions to the ANSI /ANS-3.5-1985 Standard.

NRC Form 474, Simulation Facility Certification, is enclosed due to a change in the Performance l Test Plan. i l

9901200034 DR 981230 ADOCK 05000298 PDR _

Cooper Nuclear Station PO. Box 98/ Brownville. NE 683210098 Telephone: (402) 825-38H / Fax: (402) 825-52n l http //www nppd com i

NLS980205 December 30,1998 Page 2 If you have any questions regarding this submittal, please contact my office.

Sincerely,

\ Vi e- re e o Nuck [

nr Enclosure cc: Regional Administrator w/ enclosure USNRC - Region IV NRC Resident Inspector w/ enclosure Cooper Nuclear Station NPG Distribution w/o enclosure

Ccoper Nuclear Station Simulator 1998 Cenification Report December 23,1998 Page 1 of 3 Cooper Nuclear Station Simulator 1998 Certification Renort Introduction The Cooper Nuclear Station 1998 Simulator Certification Report is required to be submitted to the Nuclear Regulatory Commission in accordance with 10CFR55.45 every four years on the anniversary of the initial certification of the Cooper Nuclear Station Simulator (November 30, 1990).

This report describes performance tests conducted from 1995 to 1998, discusses performance test discrepancies from 1995 to 1998, and provides a revised Performance Test Plan for 1999 through 2002. This report also reiterates exceptions to the ANSI /ANS-3.5-1985 Standard (reference 2).

The owner / operator of the Simulator is the Nebraska Public Power District Cooper Nuclear Station (CNS) located near Brownville, Nebraska. The Simulator vendor was S3 Technologies of Columbia, Maryland. CNS is a General Electric Boiling Water Reactor (BWR/4) rated at 2381 MWTh.

The Simulator was available for training on June 4,1990.

Additional information regarding the 1998 CNS Simulator Certification Report is available upon request.

Performance Tests Conducted 1995-1998 All annual and quadrennial performance tests for the years 1995 through 1998 were completed on the CNS Simulator as scheduled in reference 2.

Performance Test Discrepancies 1995-1998 All discrepancies documented during conduct of performance tests from 1995 through 1997 have been corrected to date.

Nine performance test discrepancies were documented during the conduct of the 1998 performance tests on Training Work Requests as priority work items for resolution in 1999.

Eight of the nine discrepancies are attributed to various electrical distribution power supply deficiencies. One discrepancy was a dynamic condition where steam flow and core flow oscillations were observed in shutdown conditions; this discrepancy was immediately resolved.

Cooper Nuclear Station Simulator 1998 Cenification Reprt December 23,1998 Page 2 of 3 Performance Test Plan 1999-2002 A revised Performance Test Plan for 1999 through 2002 is enclosed with this report.

Maior Changes Since Last Report All applicable outage modifications to reference plant systems have been evaluated and implemented to the simulator to date.

An intensive physical fidelit. <udit 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 CNS Simulator and Main Control Room are maintained in a configuration database.

The CNS Simulation and Instructor Stations were upgraded with PC technology,

, including an upgrade to the Plant Process Computer.

Sound and vibration systems were implemented to the simulator to simulate main turbine vibration malfunctions and seismic events.

Exceptions to the ANSI /ANS-3.5-1985 Standard

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Section 3.1.1(4), Normal Plant Evolutions, states that "the simulator shall be capable of performing, using only operator action normal to the reference plant; Reactor trip followed by recovery to ratedpower. "

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 time interval following a reactor trip.

Appendix B, section Bl.1 specifies various data to be recorded during Steady State Performance Testing.

a. ControlRodDrive Hydraulic System Flow

b. ControlRodDrive Hydraulic System Temperature

c. Reactor Water Cleanup System inlet and Return Flows

d. Reactor Water Cleanup Return Temperature l

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ccoper Nuclear Station Simulator 1998 Certification Report -

December 23,1998 Page 3 of 3 Control Rod Drive Hydraulic System temperature is not monitored at CNS by local / remote temperature gauge or the plant process computer. Since actual plant data does not exist, Control Rod Drive Hydraulic System temperature is not recorded or verified during CNS Simulator Steady State Performance testing.

The CNS Simulator takes no further exceptions to the standard other than those reported in the initial certification.

End ofRenort

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! Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 1 of11 I999 Performance Tests l~

IRit .Ill!C Transient 1 Manual Scram from 100% Power Tunsient 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 Stabihty/ Accuracy 25% 75% 100% and Steady State Operations Realtime Overtime Verification Normal Operations Normal Operations Tests Malfunction CR01 Fuel Clad Failure Malfunction CS01 A Core Spray Pump 1 A Trip Malfunction 1)G01 A Diesel Generator i Fails to Start Malfunction DG02A Diesel Generator 1 Trip l Malfunction ED08A 4160V Bus I A Power Failure .

1 Malfunction ED08B 4160V Bus IB Power Failure Malfunction ED08C 4160V Bus 1C Power Failure

! Malfunction ED08D 4160V Bus ID Power Failure  ;

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Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 i

December 23,1998 Page 2 of 11 l

1999 Performance Tests Test Title i Malfunction ED08E 4160V Bus IE Power Failure Malfunction ED08F 4160V Bus IF Power Failure Malfunction ED08G 4160V Bus 1G Power Failure Malfunction ED12A Loss of 125VDC IIPCI Starter Rack Malfunction ED12B Loss of 125VDC RCIC Starter Rack Malfunction ED12C Loss of 125VDC Reactor Building Starter Rack Malfunction ED12D Loss of 125VDC Distribution Panel A Malfunction ED12E Loss of 125VDC Distribution Panel B Malfunction ED12F Loss of 125VDC Starter Rack B Malfunction EDl5 Loss of 12.5KV Power Malfunction FWOIA Reactor Feedwater Pump 1 A Trip Malfunction FWO5A RFP 1 A Individual M/A Station Controller Failure Malfunction FW17 Condensate Pump Suction Boot Rupture l i

Malfunction HP01 IIPCI System Failure to Auto Start l

l Malfunction HP05 IIPCI Inadvertant Initiation Malfunction IA01 Instrument Air System Depressurizes I Malfunction MC01 Main Condenser Air in Leakage Malfunction NM02A SRf f Channel A Failure Malfunction RD02 ATWS

, Malfunction RD04A CRD Flow Control Valve 19A Failure Malfunction RII01 A RiiR Pump 1 A Trip 1

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Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 3 of 11  !

l999 Performance Tests ,

I Tfit Title Malfunction RP01 A Group 1 Scram Pilot Solenoids Fail to De-energize Malfunction RR06A RR Pump 1 A Control Signal Failure Malfunction SWOI A Service Water Pump 1 A Trip l

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i Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 4 of 11 l

l 2000 Performance Tests i 1

Inst Title )

i l Transient 1 Manual Scram from 100% Power l Transient 2 Simultaneous Trip of Both Feedwater Pumps I s

Transient 3 Simultaneous Closure of all MSIVs Transient 4 Simultaneous Trip of Both Recire Pumps

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Transient 5 Single Recire Pump Trip 1 i

Transient 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp i ,

Transient 8 Reactor Coolant System Rupture with Loss of all AC I

Transient 9 Unisolable Main Steam Line Rupture i

I Transient 10 Closure of all MSIVs with Single Stuck Open Relief Valve Stability / Accuracy 25% 75% 100% and Steady State Operations Realtime Overtime Verification  ;

I Normal Operations Normal Operations Tests ,

i Malfunction AD08A Reactor Safety Valve 70A Spurious Opening Malfunction CS02A Core Spray injection Valve 12A Fails to Auto Open Malfunction DG03A Diesel Generator Breaker EGl Fails to Auto Close Malfunction ED04 Loss of All AC Power

- Malfunction ED09A 480V Bus I A Power Failure Malfunction ED09B 480V Bus IB Power Failure

( Malfunction ED09C 480V Bus 1E Power Failure o ,

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s Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 5 of 1I i

2000 Performance Tests Icit Title Malfunction ED09D 480V Bus IF Power Failure Malfunction ED09E 480V Bus 1G Power Failure l Malfunction EDl3A Loss of 250VDC IIPCI Starter Rack Malfunction EDl3B Loss of 250VDC RCIC Starter Rack Malfunction ED13C Loss of 250VDC DIV-1 Starter Rack Malfunction EDl3D Loss of 250VDC DIV-2 Starter Rack i

Malfunction ED13E Loss of 250VDC Turbine Building Starter Rack .

Malfunction ED13F Loss of 250VDC Starter Rack B Malfunction ED14A Loss of 24VDC Power Panel DC-A 1 Malfunction ED14B Loss of 24VDC Power Panel DC-B Malfunction FWO9 RFP Master Controller Failure ,

Malfunction FW11 A Feedwater Flow Signal Failure to RVLC System - 50A l Malfunction FW13A Steam Flow Signal Failure to RVLC System - 51 A Malfunction HP04 HPCI Flow Controller Failure Malfunction HP09 Failure of HPCI Auto Isolation j Malfunction MS03A MSL-A Line Rupture Outside Primary Containment Maifunction NM05A IRM Channel A Failure Malfunction NM08 LPRM Failure

Malfunction RD09 Control Rod Drift in

't Malfunction RD10 Control Rod Drift Out i

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! 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 I Page 6 of 11 l

! 2000 Performance Tests 1

i Test Title Malfunction RD12 Control Rod Stuck Malfunction RD13 Control Rod Uncoupled Malfunction R1104A LPCI INBD Injection Valve 25A Failed Closed Malfunction RPO4 Group 1 Isolation Failure Malfunction RP05 Group 2 Isolation Failure i

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Cooper Nuclear Station Simulator 1998 Certification Report Enclosure l Performance Test Plan 1999-2002 December 23,1998 Page 7 of 11 2001 Performance Tests

_Tsit Title ,

Transient 1 Manual Scram from 100% Power Transient 2 Simultaneous Trip of Both Feedwater Pumps l Transient 3 Simultaneous Closure of all MSIVs

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l Transient 4 Simultaneous Trip of Both Recire Pumps Transient 5 Single Recire Pump Trip l I

Transient 6 Main Turbine Trip Transient 7 Maximum Rate Power Ramp i

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' Stability / Accuracy 25% 75% 100% and Steady State Operations l Realtime Os enime Verification Normal Operations Normal Operations Tests Malfunction ED05 Loss of Startup Transformer Malfunction ED06 Loss of Emergency Transfonner l l

l l l Malfunction ED10A MCC-A Failure '

Malfunction ED10B MCC-F Failure Malfunction ED10C MCC-LX Failure Malfunction EDIOD MCC-TX Failure l Malfunction ED10E MCC-K Failure Malfunction ED10F MCC-L Failure t

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Cooper Nuclear Station Simulator ,

1998 Certification Report Enclosure  !

Performance Test Plan 1999-2002 December 23,1998 Page 8 of11 F

2001 Performance Tests 1

.Ig31 Title  !

f Malfunction ED10G MCC-S Failure i

Malfunction ED10ll MCC-T Failure Malfunction ED17 Loss of NBPP #1 Malfunction FW16A Ilotwell Level Controller Auto Failure (LIC-2A)

Malfunction FW18A Feedwater A Line Break Inside Containment Malfunction FW19A Feedwater A Line Break Outside Containment >

Malfunction FW20A .Feedwater lieater 1-A-5 Level Control Failure Malfunction MS08A Deli Pressure Transmitter 81 A Failure i Malfunction NM09A APRM Channel A Signal Failure Malfunction RD20 RPIS Failure - Total Malfunction RM01 A Service Water Rad Monitor Failure Malfunction RM02A Gaseous Radiation Monitor Failure Malfunction RP07 Group 6 liigh Rad Isolation Failure j j Malfunction RP12 Group 3 Isolation Failure i

Malfunction RR14A RR Loop Flow Transmitter 110A Failure Malfunction RR17A Recire Pump 1 A M/A Flow Controller Failure Malfunction RR20A RR Loop A Coolant Leak Inside Primary Containment i Malfunction SWO9A REC Line Break 1 A Malfunction SW10 TEC Line Break Malfunction TC07A Bypass Valve #1 Failure

- Malfunction TC09A Control Valve #1 Failure 4

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- Cooper Nuclear Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 9 of11 2002 Performance Tests

.Tssi Title

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Transient 1 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

Stability / Accuracy 25% 75% 100% and Steady State Operations Realtime Overtime Verification

- Normal Operations Normal Operations Tests Malfunction AD06A Relief Valve 71 A Complete Failure

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, Malfunction CUO8 RWCU System Leak Inside Containment

Malfunction CUO9 Cold Water Cleanup Leak i l

Malfunction ED07 Loss of Normal Transformer l

Malfunction EDI1 A Critical Dist Panel CDP-1 A Failure Malftmetion EDIIB Critical Dist Panel CDP-1B Failure l Malfunction EDIIC Critical Power Panel CPP Failure  ;

, Malfunction EDIID Critical Power Panel CPP-1 Failure f

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Cooper Nuclear Station Simulator 1998 Certification Report Enclosure >

- Performance Test Plan 1999-2002 December 23,1998 Page 10 of11 I 2002 Performance Tests Test Title Malfunction EDI1E Critical Power Panel CPP-2 Failure Malfunction EDIIF Critical Power Panel CPP-3 Failure l

Malfunction EDI1G Critical Control Panel CCP-1 A Failure Malfunction EDIIH Critical Control Panel CCP-2A Failure Malfunction ED111 Critical Control Panel CCP-1B Failure Malfunction EDI1J Critical Control Panel CCP-2B Failure Malfunction EG09 Main Generator Trip

. Malfunction FW21 A Feedwater Control Signal Failure to RFP-1 A l Malfunction FW22 Feedwater Startup Master Controller Failure Malfunction MS10 Steam Leakage in Turbine Building j Malfunction RD26 Backup Scram Valve Failure Malfunction RD27 Automatic ARI Failure l- Malfunction Rif07 RilR Shutdown Cooling Valve Isolation l

Malfunction RR24A RPT Fails to Trip RR Pump 1 A  ;

Malfunction RR25A LIS-57A (NR Yarway) Fails Downscale l Malfunction RR25C LIS-58A (NR Yarway) Fails Downscale I Malfunction RR26A LIS-72A (NR Yarway) Fails Downscale Malfunction RR26C LIS-72C (NR Yarway) Fails Downscale Malfunction RR27A LT-52A (NR Gemac) Failure Malfunction RR28A LIS-101 A (NR Barton) Failure Malfunction RR28C LIS-101C (NR Barton) Failure J

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Cooper Nucicar Station Simulator 1998 Certification Report Enclosure Performance Test Plan 1999-2002 December 23,1998 Page 11 of 11 2002 Performance Tests Test Title Malfunction RR30A LITS-73A (FZ Yarway) Switch Fails Downscale Malfunction TCl2 Deli System Load Reference Failure Malfunction TC05 Deli Computer Failure

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l NRC FORM 474 U.S. NUCLEAR REGULATORY COMMISSION APPROYFO SY OMA NO. SN138 EXPlRES: 08/31/2001 (B 1898) Estimated burden per response e comply vnth the manda 6nformetrn cohochon request 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> The mformanon a used to cerbfy a simu teon facdev Forward I comments regarden0 burden eshmate to the Records M Branch (T4 F33). U S SIMULATION FACILITY CERTIFICATION  %"f%"T'bM"87."J""o*e o C"f- a=* Bk'g"t *eh n' "ion""e '*

20503 Nan bon collechan does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to sospond to, the mtormaten rollecton INSTRUCTIONS: The form as b be Aled for mibal certecahon, racertshcabon (if requued), and for any chan0e to a samutaban facehty performance tesbng plan made sher ewhal submrttal of such a etaa Pemte the fo'imwmc wdrwmahon end check the opprrstmate bor to mdcate fesson for submmal FACILITY DOCKET NUMBER Cooper Nuclear Station so- 298 LICENSEE DATE i Nebraska Public Power District 12/23/98 The is to cerbty that i

1. The above named facehty hcenhoe a usmg a smulabon facshty consasang solely of a plant referenced simulator that meets the requuements of to CFR 55 45.

2. Documentaban a evadable for NRC review m accordance we 10 CFR 55 45(b) l 3. This ownulabon facehty meets the guidance conteened in ANSUANS 3 51985 or ANSUANS 3 51993, as endorsed by NRC Regulatory Guide 1149 N there are any EXCEPTIONS to the certscaban of the item, CHECK HERE g ] and desenbe fully on addmonal pages as necessary NAME (cr other adentricehon) AND LOCATION OF SIMULATION F ACILffY.

Cooper Nuclear Station I

Nuclear learning Center Brownville, NE 68321 SIMULATION F ACILITY PERFORMANCE TEST ABSTRACTS ATTACHED (Forper*rmance seats condccfed a me penod end#ng we he debe of rus certencehon)

DESCRIPTION OF PERFORMANCE TESTING COMPLETED (Afrech addeonet pages as necessay and adentry the dem desenp6an 6emp contmoed)

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SIMULATION FACILfTY PERFORMANCE TESTING SCHEDULE ATTACHED fFor me conduct of apprtmasseiy 25 percent of parkrmance aests pr year Ar the Axr-yearpasod commencmg we he done of nos corkfrebon )

DESCRIPTlON OF PERFORMANCE TESTING TO BE CONDUCTED (Attach e6erbonet peges as necessay and odenhty be nem desenptnan boeng conhnued)

I PERFORMANCE TESTING PLAN CHANGE. (For any inodifcaban b o pw*rmenw ses6ng pJen subnwfsed on a provsous overfeeban.)

DESCRIPTION OF PERFORMANCE TESTING PLAN CHANGE (Ansch addsisonetpages sa necer.awy and asenet me nem desanp6 m borne con 6nued)

'1he content of the Perfonaance Test Plan for 1999 through 2002 is identical to the test plan sutxaitted to the NRC in Novanber,1995, with the exception of the addition of one malfunction, Service Water Pump Trip.

Refer to Nebraska Public Power District letter NLS950189 dated Noveaber 16, 1995, John H. Mueller to Director, Office of Nuclear Reactor Regulation, Coope- Nuclear Station Simulator Perfonnance Test Plan Qungt .

1 RECERTlFICAT)ON (Descrnbe correchve achans teken, onech results of compJetedpekamence toetrno an accordence wm 10 CFR SS 45(b)(5)(v).

l (Anoch eddskonet pages as necessay and ndentrfy be nem descnytoon bomp conknuoi)

Any false statement or ommason in the cument, metudmg ettachments, may be subsect to ceni and enmmal sanchons I certify under penalty of perjury that the informabon m this document and

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SIGNA E- AUTHORIZED RE SENTATIVE TTTLE DATE l

a W ice President of Nuclear Energy /2 2hf

! In acmedence with 10 dR SS 6, C .

i 6s form shall be submmed to the NRC es follows

• BY MAIL ADORESSED TO \plRECTOR, OFFICE OF NUCLEAR REACTOR REGULATION BY DELfVERY IN PERSold ONE WHITE FLINT NORTH U.$. NUCLEAR REOULATORY COMMISSION TO THE NRC OFFICE AT 11555 ROCKVILLE PlKE WA&HINOTON, DC 205554001 ROCKVILLE, MD NRC FORM 474 (8-1998) PRINTED ON RLCYCLED PAPLR l

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l ATTACHMENT 3 LIST OF NRC COMMITMENTS l

Correspondence No: NLS980205 l

l The following table identifies those actions committed to by the District in this l document. Any other actions discussed in the submittal represent intended or i planned actions by the District. They are described to the NRC for the NRC's l information and are not regulatory commitments. Please notify the NL&S Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.

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COMMITTED DATE COMMITMENT l

OR OUTAGE None l

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l PROCEDURE NUMBER 0.42 l REVISION NUMBER 6 \ PAGE 9 OF 13 l t