ML20081J581

Certifies That Facility Plant Simulator Continues to Meet Requirements of 10CFR55.45(b)

ML20081J581
Person / Time
Site:	Davis Besse
Issue date:	03/17/1995
From:	Stetz J CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2281, NUDOCS 9503280045
Download: ML20081J581 (6)

Text

GNFEgR 300 Masson Amue John P. Stetr Toledo, OH 43652 0001 Vice President Nucioar 419-249-2300 Davis-Besse Docket Number 50-346 License Number NPF-3 Serial Number 2281 March 17, 1995 United States Nuclear Regulatory Commission Document Control Desk Vashington, D. C.

20555 Subj ect :

Simulator Certification Report Pursuant to 10 CFR 55.45(b)(5)(ii)

Ladies and Gentlemen:

The purpose of this letter is to certify that the Davis-Besse Nuclear Power Station (DBNPS) Unit No. 1 plant-referenced simulator continues to meet the requirements of 10CFR Section 55.45(b) for a simulation facility consisting solely of a plant-referenced simulator. This letter complies with the requirements for the simulator certification report required by 10 CFR Sections 55.45(b)(5)(ii) and 10 CFR 55.45(b)(5)(vi).

Periodic performance testing of the simulator has been completed in accordance with the schedule provided in the original DBNPS simulator certification submittal (Toledo Edison letter Serial Number 1913) dated March 25, 1991. Two performance test failures remain uncorrected from this testing period and are identified on Attachment 1.

The corrections for these two failures are addressed in Attachment 1.

All discrepancies identified by examiners during NRC license examinations have been corrected.

The performance testing completed during the past four years is shown on and this test schedule vill be repeated for the next four-year cycle. The next testing cycle vill begin on March 25, 1995.

260033 coS Operating Componies:

Cteveland Electre mummotmo l

l Toledo Edson 9503280045 950317

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PDR ADOCK 05000346 P

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.Dockat'Nu2ber 502346 1*

Li'censa Nunber NPF-3 m '

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' Serial Number 2281

,Page 2

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.Should you have.any questions or' require additional information,-please.

' contact Mr. William T. O'Connor, Manager - Regulatory Affairs, at j

D(419) 249-2366.

Very.truly yours,-

i 400 ll 1

FVK/laj.

attachments

.cc:

L. L. Gundrum, DB-1 NRC/NRR Project Manager-J. B. Martin, Regional Administrator, NRC Region III S. Stasek, DB-1 NRC. Senior Resident Inspector Utility Radiological Safety Board I

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Dockst Nuzber 50-346

' -Lic nsa Nurbar NPF-3 Se' rial Nuzber 2281 Page 1 Uncorrected Performance Test Failures T03B Loss of all AC Power and Loss of Both Diesels During the performance of this test, two lights remained illuminated on the control room fire alarm panel, and the fire alarm printer continued to print alarms.

In addition to a loss of all AC power and a loss of Emergency Diesel Generators, this test also opens the station battery disconnects which removes all simulated electrical power from the control room.

Since this scenario removes virtually all indication from the control room, it is not used in training.

Correction of these deficiencies has been deferred due to the scheduled replacement of the fire detection system on the simulator.

Vork is in progress for installing this modification on the simulator within the time limits of ANSI 3.5, 1985. This modification is being performed in stages and is not yet complete in the plant.

NO3 Core Physics Testing The simulator did not meet test acceptance criteria for control rod worths.

This test is written to perform core physics testing with the actual plant procedure. The performance test acceptance criteria states that the test shall meet the acceptance criteria of the plant test.

All objectives for training and examinations are being met satisfactorily with the present core model. This discrepancy is not observable during routine training situations. The overall simulator core performance is sufficiently accurate to accomplish training objectives and not detract from training.

Core performance has not surfaced as a fidelity issue in routine training or examinations.

A simulator core upgrade has been deferred due to the high cost and relatively low value added to training. Toledo Edison intends to reevaluate a simulator core upgrade in the future as technology improves and in conjunction with the planned conversion to a 24-month fuel cycle.

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~Dockst Nuxber 50-346-Lictnsa Nu ber NPF-3 Sirial Nu:bar 2281 i.

Page 1

' Test Description and_ Schedule I

i This test' schedule was used'for the initial four year period and vill be

, repeated as. indicated for the next four year period. Approximately 25% of

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'the scheduled testing vill be performed each year.

i Year 1 March 25,1995 - March 25,'1996 N0la Startup - Cold Shutdown to Hot Shutdown N0lb Plant Startup - Hot Shutdcvn.to Hot Standby N01c Startup - Hot Standby to 500 degrees N01D Startup - 500 degrees to Safety Rods Out S11-Make-up Pump (s) Quarterly Surveillance Test 512 High Pressure. Injection Pump (s)'Ouarterly Surveillance Test T01c Once Through' Steam Generator Tube Leak T0lf Steam Generator Tube Rupture T03a Loss of all Offsite Power T03d Loss of 120 VAC Bus Panel Y1 T05a Loss of Circulating Vater Pumps T08 Loss of Component Cooling Water T12a Stuck Rod l

T14 Fuel Failure T17b3 Failure of the Auto Runback Signal 86/UL-FVL j

T18c Loss of RCS Makeup Pump 37-1 T21 Failure of the' Power Range Uncompensated Ion Chamber 3

Year 2 March 25,1996 - March 25,~1997 N02a Shutdown - Full Power Steady State (FPSS) to.500 degrees NO2b Shutdown - 500 degrees to Cold Shutdown S13 Lov Pressure Injection Pump (s) Quarterly Surveillance Test S14 Containment Spray Pump Quarterly Surveillance Test T0lb Loss Of Coolant Accident (LOCA) Outside Containment T0ld High Pressure Injection Line Break i

T03f Loss of D1P Bus

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T05b Loss of Condenser Level Control T09a Main Feedvater Pump, Trip / Runback T10 Total Loss of Feedvater l

T12b Uncoupled Rod T16 Generator / Turbine Trip T171 Failure of the Tave controller Calibrating Integral T20b Steam'Line Break Outside Containment T22a RCS Hotleg RTD Failure T23a Passive malfunctions - Steam and Feedvater Rupture Control System Manual Actuation Failure & Auxiliary Feedvater Pump Turbine Fails at High Speed Stop J

Dockst Nuzb:r 50-346 Licens2 Nn2btr NPF-3

'Sirial Numb 2r 2281 C Attachegnt 2-

-Page 2 Test. Schedule (continued)

Year 3 March 25,1997 - March 25, 1998 NO3 Core Physics Testing N05 3RCP Startup/ Shutdown SO4 Integrated Safety Features Actuation System (SFAS).

Surveillance Test S05 Independent Off-Site AC Sources Bus Transfer Surveillance Test S15 Component Cooling Vater Pump (s) Quarterly Surveillance Test T01a Large LOCA T0le RCP Discharge Line Break T03b Loss of All AC Power and Loss of Both Diesels T03h Automatic Control System Failure - Integrated Control System (ICS) Halfunction - Loss of ICS AC Power T06b complete Loss of Service Vater Cooling T09b Forty Percent Power Feedvater Pump Trip T12c Drifting Rods T12d Dropped Rod T17k Failure of the Rapid Feedvater Reduction Signal T20e Feedvater Line Break Inside Containment T22d RCS Pressure Transmitter Failure T23b Passive Malfunctions - Auxiliary Feedvater, Low Pressure Injection, and Containment Spray _ Pumps Fail to Start Year 4 March 25,1998 March 25, 1999-N0le Startup - Safety Rods Out to Critical

'N01f Startup - 1.0 E-8 Amps to Turbine Roll N04a Trip Recovery - FPSS to Post Trip Peak Xenon N04b Peak Xenon Startup to 100% Power 507 SFAS Monthly Surveillance Test S16 Service Water Pump (s) Quarterly Surveillance Test S17 Auxiliary Feedvater Pump (s) Quarterly Surveillance Test T01g Inadvertent Opening of a Pressurizer Safety Valve T02 Loss of-Instrument Air T031 Loss of Non-Nuclear Instrumentation Power (Y-AC)

T07b Loss of Shutdown Cooling with the RCS Drained Til Loss of Protective System Channels T12e Misaligned Rods T13 Inability to Drive Control Rods T18a Pressurizer Spray Valve Fails Fully Open T20d Feedvater Line Break Outside Containment T22f Pressurizer Level Transmitter Failure T24 Anticipated Transient Vithout Scram (ATVS)

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. Serial Nuxbar 2281 Attachapnt.2.

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P Test Schedule (continued)

The following are annual tests and vill be performed each year of the next four year test period..

l N01g Turbine Roll - FPSS N06 Sixty Minutes Drift Test RTT Real Time Test SOL Simulator Operating Limits Test TAB 01 Hanual Reactor Trip i

TAB 02 Simultaneous Trip of all Main Feedvater' Pumps TAB 03 Simultaneous Closure of All Main Steam Isolation Valves TAB 04 Simultaneous Trip of All Reactor Coolant Pumps

-TAB 05 Trip of One Reactor Coolant Pump TAB 06 Main Turbine Trip from 40% power - No Reactor Trip TAB 07 Maximum Rate Power Ramps 100%, 75%, 100%

TAB 08 Double Ended Hot Leg Shear with a Coincident Loss of All Offsite Power TAB 09 Main Steam Line Failure in the Reactor Building - Double Ended Shear TAB 10 The PORV Fails Open and High Pressure Injection Does.Not Actuate t

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