ML20205C737

Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl

ML20205C737
Person / Time
Site:	Davis Besse
Issue date:	03/25/1999
From:	Campbell G CENTERIOR ENERGY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2590, NUDOCS 9904010349
Download: ML20205C737 (12)

Text

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Y- - -Q ER j Davis-Besse Nudear Power Station 5501 North State Route 2 m Oak Harbor, Chio 43449 9760 Guy G. Campbell 419 321-8 % 8 woe President- Nuclear Fax:41 % 21-8337 Docket Number 50-346 License Number NPF-3 Serial Number 2590 March 25, 1999 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555-0001

Subject:

Davis-Besse Nuclear Power Station Simulator Certification Report Ladies and Gentlemen:

The purpose of this letter is to certify that the Davis-Besse Nuclear Power Station (DBNPS) Unit No. I plant-referenced simulator continues to meet the requirements of 10 CFR 55.45(b) for a simulation facility consisting solely of a plant-referenced simulator. This letter is submitted in accordance with the simulator certification reprt requirements of 10 CFR 55.45(b)(5)(ii) and 10 CFR 55.45(b)(5)(vi).

Performance testing of the simulator, completed during the past four-year period, is listed in l

Attachment 1. This testing was completed in accordance with the schedule that was provided in the previous certification report (Toledo Edison letter Serial Number 2281) dated March 17,1995.

The two performance test failures identified in that report were corrected. There are no uncorrected performance test failures for the current testing period. As shown in Attachment 1, y this test schedule will be repeated for the next four-year cycle beginning March 25,1999. k(g During the present test period, several noteworthy projects were completed on the simulator that )

required additional performance testing. This additional testing was performed to validate

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simulator enhancements and was in addition to ie requirements of 10 CFR 55.45(b). It is included in this letter as additional information. In 1998, the simulator completed re-hosting the existing real-time models to personal computer-based simulation using OpenSim NT as the operating system. Following completion of the re-host, the reactor core model was replaced with a higher resolution model that is capable of being upgraded each fuel cycle. The initial upgrade was performed in conjunction with the plant's conversion to a 24-month operating cycle. The upgrade allows training on the new higher enrichment and longer burnup fuel installed for the 24-month operating cycle. Attachment 2 shows the acceptance test program utilized to validate acceptable performance of this updated system.

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9904010349 990325 I!!. _ . j PDR ADOCK 05000346 1 9 1

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Docket Number 50-346 License Number NPF-3 Serial Number 2590 Page 2 The simulation computer was also upgraded to a higher speed computer. The additional testing performed to validate the higher speed computer and to test changes associated with the new reactor core model is shown in Attachment 3.

Although there were no performance test failures, there were test discrepancies that require resolution. The outstanding test discrepancies assoc ated with these two projects, as well as the plan to resolve those deficiencies, are discussed in Attachment 4.

Should you have any questions or require any additional information, please contact Mr. James L. Freels, Manager- Regulatory Affairs, at (419) 321- 8466.

I Very truly yours, t TM E.Ddn b c.c. canrau.a.

SFIJsfl attachments cc: S. J. Campbell, NRC Region III, DB-1 Senior Resident Inspector (Acting)

J. E. Dyer, Regional Administrator, NRC Region III  ;

A. G. Hansen, NRC/NRR Project Manager  ;

Utility Radiological Safety Board l

Docket Number 50-346 License Number NPF-3 l Serial Number 2590 l

Atta'chment'l i

! Page 1 of 3 Four Year Certification Test Schedule TESTNO. TITLE YEAR 1 (NEXTTESTPERIOD: MARCH 25,1999-MARCH 24,2000]

NO1A PLANT STARTUP COLD SHUTDOWN TO HOT SHUTDOWN N01B PLANT STARTUP HOT SHUTDOWN TO HOT STANDBY N010 STARTUP - HOT STANDBY TO 500 DEGREES 1

N01D STARTUP 500 DEGREES TO SAFETY RODS OUT S11 MAKE-UP PUMP (s) QUARTERLY SURVEILLANCE TEST I S12 HIGH PRESSURE INJECTION PUMP (s) OUARTERLY SURVEILLANCE TEST T01C OTSG TUBE LEAK T01F SG TUBE RUPTURE T03A LOSS OF ALL OFFSITE POWER T03D LOSS OF 120 VAC BUS PANEL Y1 TO5A LOSS OF CIRCULATING WATER PUMPS T08 LOSS OF COMPONENT COOLING WATER T12A STUCK ROD T14 FUEL FAILURE T17B3 FAILURE OF THE AUTO RUNBACK SIGNAL 86/UL-FWL T18C LOSS OF RCS MAKEUP PUMP 37-1 T21 FAILURE OF THE POWER RANGE UNCOMPENSATED ION CHAMBER YEAR 2 [NEXTTESTPERIOD: MARCH 25,2000-MARCH 24,2001]

NO2A SHUTDOWN FULL POWER STEADY STATE TO 500 DEG. F NO2B SHUTDOWN - 500 DEG. F TO COLD SHUTDOWN S13 LOW PRESSURE INJECTION PUMP (s) OUARTERLY SURVEILLANCE TEST S14 CONTAINMENT SPRAY (CS) PUMP QUARTERLY SURVEILLANCE YEST T01B LOCA OUTSIDE CONTAINMENT T01D HPl LINE BREAK T03F LOSS OF D1P BUS TOSB LOSS OF CONDENSER LEVEL CONTROL T09A MAIN FEEDWATER PUMP TRIP / RUNBACK l T10 TOTAL LOSS OF FEEDWATER i' T12B UPCOUPLED ROD T16 GENERATOR / TURBINE TRIP

E Docket Number 50-346 License Number NPF-3 Serial Number 2590 Atta'chment'l Page 2 oi3 Four Year Certification Test Schedule -

TESTNO. TITLE T171 FAILURE OF THE Tus CONTROLLER CALIBRATING INTEGRAL T200 STEAM LINE BREAK OUTSIDE CONTAINMENT T22A RCS HOTLEG RTO FAILURE T23A PASSIVE MALFUNCTIONS - SFRCS MANUAL ACTUATION FAILURES & AUXILIARY FEEDWATER (AFW)

PUMP TURBINE FAILS AT HIGH SPEED STOP YEAR 3 [NEXT TEST PERIOD: MARCH 25, 2001 - MARCH 24, 2002]

NO3 CORE PHYSICS TESTING N05 3RCP STARTUP/ SHUTDOWN SO4 INTEGRATED SFAS SURVEILANCE TEST SOS INDEPENDENT OFF-SITE AC SOURCES BUS TRANSFER S15 COMPONENT COOLING WATER PUMP (s) OUARTERLY SURVEILLANCE TEST T01A LARGE LOCA T01E RCP DISCHARGE LINE BREAK T03B LOSS OF ALL AC POWER AND LOSS OF BOTH DIESELS T03H AUTOMATIC CONTROL SYSTEM FAILURE INTEGRATED CONTROL SYSTEM (ICS) MALFUNCTION -

LOSS OF ICS AC POWER T06B COMPLETE LOSS OF SERVICE WATER COOLING T098 FORTY PERCENT POWER FEEDWATER PUMP TRIP T12C DRIFTING RODS

.T12D DROPPED ROD T17K FAILURE OF THE RAPID FEEDWATER REDUCTION SIGNAL T20C FEEDWATER LINE BREAK INSIDE CONTAINMENT T22D RCS PRESSURE TRANSMITTER FAILURE T238 PASSIVE MALFUNCTIONS - APN, LPI AND CS PUMPS FA!L TO START YEAR 4 [NEXT TEST PERIOD: MARCH 25, 2002 - MARCH 24, 2003]

N01E STARTUP SAFETY RODS OUT TO CRITICAL l N01F STARTUP 1.0 E-8 AMPS TO TURBINE ROLL I

N04A TRIP RECOVERY - FPSS TO POST TRIP PEAK XENON N04B PEAK XENON STARTUP TO 100% POWER S07 SFAS MONTHLY TEST S16 SERVICE WATER PUMP (s) QUARTERLY SURVEILLANCE TEST S17 AUXILIARY FEEDWATER PUMP (s) OUARTERLY SURVEILLANCE TEST t

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Docket Number 50-346 License Number NPF-3  ;

Serial Number 2590

~ Atta'chment'l Page 3 of 3 Four Year Certification Test Schedule TESTNO. TITLE T01G INADVERTANT OPENING OF A PRESSURIZER SAFETY VALVE ,

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T02 LOSS OF INSTRUMENT AIR T03L LOSS OF NON-NUCLEAR INSTRUMENTATION POWER (Y-AC)

T07B LOSS OF SHUTDOWN COOLING WITH RCS DRAINED T11 LOSS OF PROTECTIVE SYSTEM CHANNELS j T12E MISALIGNED RODS T13 INABILITY TO DRIVE CONTROL RODS T18A PRESSURIZER SPRAY VALVE FAILS FULLY OPEN T20D FEEDWATER LINE BREAK OUTSIDE CONTAINMENT l T22F PRESSURIZER LEVEL TRANSMITTER FAILURE T24 ATWS ANNUAL N01G TURBINE ROLL- FPSS N06 SIXTY MINUTES DRIFT TEST RTT REAL TIME TEST SOL SIMULATOR OPERATING LIMITS TEST I TAB 01 MANUAL REACTOR TRIP l

TAB 02 SIMULTANEOUS TRIP OF ALL MAIN FEEDWATER Pl!MPS TAB 03 SIMULTANEOUS CLOSURE OF ALL MSIVs TAB 04 SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS l TAB 05 TRIP OF ONE REACTOR COOLANT PUMP TAB 06 MAIN TURBINE TRIP FROM 40% POWER NO REACTOR l TRIP TAB 07 MAXIMUM RATE POWER RAMP 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 BUILD!NG -

DOUBLE ENDED SHEAR TAB 10 THE PORV FAILS OPEN AND HPl DOES NOT ACTUATE

Docket Number 50-346 License Number NPF-3 Serial Number 2590 Atta'chment 2 Page 1 of 3 New Reactor Core Test Status Report Test Number Test Name Open Simulator Trouble Reports Beginning OfLife(BOL) .

l N01e Startup Safety Rods Out to Cdtical none I

N01f Startup 1.0 E 8 Amps to Turbine Roll none N01g Turbine Roll to FPSS none NO3 Low Power Physics Test none N06 Sixty Minute Drift Test none T12a Stuck Rod none l

T12b Uncoupled Rod s1709 T12c Drifting Rods none T12e Misaligned Rods none TAB 01 Manual Reactor Trip s1653,s1671 TAB 02 Simultaneous Trip of All Main Feedwater Pumps s1653,s1671 TAB 03 Simultaneous Closure of All MSIVs s1653,s1671 TAB 04 SimuPaneous Trip of All Reactor Coolant Pumps s1653,s1671 TAB 05 Trip of One Reactor Coolent Pump s1653,s1671 TAB 06 Main Turbine Trip from 40% Power No Reactor Trip none TAB 07 Maximum Rate Power Ramp - 100% to 75% to 100% none TAB 08 Double Ended Hot Leg Shear w/ Loss of Offsite AC s1673 TAB 09 Main Steam Line Rupture inside Containment s1653,s1673,s1653 TAB 10 The PORV Falls Open and HPl Does Not Actuate s1653,s1671,s1673, Simulator Work Order (swo 95-0063)

End ofLife (EOL)

N06 Sixty Minute Drift Test none T12a Stuck Rod none T12b Uncoupled Rod s1709 T12c Drifting Rods none

Docket Number 50-346 License Number NPF-3 Serial Number 2590 Atta'chment 2 i Page 2 of 3 New Reactor Core Test Status Report l

l Test Number Test Name Open Simulator Trouble Reports l l T12d Dropped Rod none T12e Misaligned Rods none l

T14 Fuel Failure s1697 TAB 01 Manual Reactor Trip s1653,s1671 TAB 02 Simultaneous Trip of All Main Feedwater Pumps s1653,s1671 TAB 03 Simultaneous Closure of All MSIVs s1653,s1671 TAB 04 Simultaneous Trip of All Reactor Coolant Pumps s1653,s1671 TAB 05 Tnp of One Reactor Coolant Pump s1653,41671 TAB 06 Main Turbine Trip from 40% Power No Reactor Trip none TAB 07 Maximum Rate Power Ramp 100% to 75% to 100% none TAB 08 Double Ended Hot Leg Shear w/ Loss of Offsite AC s1653, s1671, swo 95-0063 TAB 09 Main Steam Line Rupture inside Containment s1673,s1653 TAB 10 The PORV Fails Open and HPl Does Not Actuate s1653,s1671,s1673, swo DS-0063 EOL (Coastdown)

NO2a Plant Shutdown from 100% to 500 Deg. F none MOL N01e Startup-Safety Rods Out to Critical s1672 N01f Startup 1.0 E-8 Amps toTurbine Roll none N01g Turbine Rollto FPSS s1696 N04a Trip Recovery FPSS to Post Trip Peak Xenon s1693 N06 Sixty Minute Drift Test none T01a Large LOCA s1673. swo 95-0063 T01c OTSG Tube Leak s1692 T01d HPl Line Break s1673, swo 95-0063 l T08 Loss of Component Cooling Water none

f Docket Number 50-346 License Number NPF-3 Serial Number 2590 Attachment 2 Page 3 of 3 New Reactor Core Test Status Report Test Number Test Name Open Simulator Trouble Reports T11 Loss of Protective System Channels none T12a Stuck Rod none T12b Uncoupled Rod s1709 I

T12c Drifting Rods none T12d Dropped Rod T12e Misaligned Rods none T13 Inability to Drive Control Rods s1698 T14 Fuel Failure s1697 l

T16 Generator / Turbine Trip none T20b Steam Line Break Outside Containment none T20c Feedwater Line Break inside Containment none T24 ATWS swo 95-0063 TAB 01 Manual Reactor Trip s1653,s1671 TAB 02 Simultaneous Trip of All Main Feedwate! Pumps s1653,s1671 TAB 03 Simultaneous Closure of All MSIVs s1653,s1671 TAB 04 Simultaneous Trip of All Reactor Coolant Pumps s1653,s1671 TAB 05 Trip of One Reactor Coolant Pump s1653,s1671 TAB 06 Main Turbine Trip from 40% Power - No Reactor Trip none TAB 07 Maximum Rate Power Ramp 100% to 75% to 100% none ,

TAB 08 Double Ended Hot Leg Shear w/ Loss of Offsite AC s1653,s1671,s1673, swo 95-0063 TAB 09 Main Steam Line Rupture inside Containment s1653,s1671 TAB 10 The PORV Fails Open and HPl Does Not Actuate s1653,s1671,s1673, swo 95-0063

. . l Docket Number 50-346 i License Number NPF-3 f

Serial Number 2590 Attachment 3 Page 1 of 3 I

Simulator Computer Upgrade Test Program Status Report  ;

l l Test 1 No. TITLE Open Simulator Trouble Reports l

N01A Plant Startup - Cold Shutdown to Hot Shutdown none N01B PLANT STARTUP - HOT SHUTDOWN TO HOT STANDBY none N010 STARTUP - HOT STANDBY TO 500 DEGREES none N01D STARTUP 500 DEGREES TO SRO none NO2A PLANT SHUTDOWN FROM 100% RTP TO 500 DEG. F none NO2B SHUTDOWN 500 DEGREES TO CSD none NO2C RCS Draindown to 80" Hot Leg Level s1518 S07 SFAS MONTHLY TEST s1528,s1529,s1530, s1531 S11 MAKE-UP PUMP (s) QUARTERLY none ,

S12 HIGH PRESSURE INJECTION PUMP (s) OUARTERLY none S13 LOW PRESSURE INJECTION PUMP (s) QUARTERLY none ,

S14 CS PUMP OUARTERLY none S15 COMPONENT COOLING WATER PUMP (s) QUARTERLY none S16 SERVICE WATER PUMP (s) QUARTERLY none S17 AUXILIARY FEEDWATER PUMP (s) QUARTERLY none T01A LARGE LOCA none T01B LOCA OUTSIDE CONTAINMENT none T01C OTSG TUBE LEAK none T01D HPI LINE BREAK none T01E RCP DISCHARGE LINE BREAK none T01F SG TUBE RUPTURE none T01G INADVERTANT OPENING OF A PRESSURIZER SAFETY VALVE none T02 LOSS OF INSTRUMENT AIR s1456 T03A LOSS OF ALL OFFSITE POWER none T03aa Load Table Verification none T03B LOSS OF ALL AC POWER AND LOSS OF BOTH DIESELS none T03c Loss of All Offsite Power trorn 35% Power none T03d LOSS OF 120 VAC BUS PANEL Y1 s1347 T03e Loss of 120 VAC Bus Panef Y2 none i

l Docket Number 50-346 License Number NPF-3  !

Serial Number 2590 Atta'chment'3 Page 2 of 3 Simulator Computer Upgrade Test Program Status Report  ;

I Test No. TITIE Open Simulator Trouble Reports T03f Loss of D1P and DAP s1320 T03g Loss of D2P and DBP none )

TO'.ih AUTO. CTRL SYS. FAIL - ICS MALF. - LOSS OF ICS AC none POWER T03i Loss of ICS DC Power s1705 T03J Loss of NNI X-AC Power s1706,s1707 T03k Loss of NNI X-DC Power u1458 T03L LOSS OF NNI POWER (Y-AC) s1373,u1496 T03rn toss of NNI Y-DC Power s1708 T06a Loss of Service Water none T06B COMPLETE LOSS OF SERVICE WATER COOLING none j T07a Loss of Decay Heat Removal (With RCS Filled and Vented) none T08 LOSS OF COMPONENT COOLING WATER none T09A MAIN FEEDWATER PUMP TRIP / RUNBACK none T09B FORTY PERCENT POWER FEEDWATER PUMP TRIP none T10 TOTAL LOSS OF FEEDWATER none T11 LOSS OF PROTECTIVE SYSTEM CHANNELS none T12a STUCK ROD none T12c DRIFTING RODS none T16 GENERATOR / TURBINE TRIP none T171 FAILURE OF THE TAVE CONTROLLER CAllBRATING INTEGRAL none T17q Failure of FW to Control Tavg none T18a PRESSURIZER SPRAY VALVE FAILS FULLY OPEN s0694 T18c LOSS OF RCS MAKEUP PUMP 37-1 none T20c FEEDWATER LINE BREAK INSIDE CONTAINMENT none T20d FEEDWATER LINE BREAK OUTSIDE CONTAINMENT none T21 FAILURE OF THE POWER RANGE UNCOMPENSATED ION none CHAMBER T22a RCS HOTLEG RTD FAILURE s1532 T22d RCS PRESSURE TRANSMITTER FAILURE none

p Docket Number 50-346 License Number NPF-3 Serial Number 2590 Atta'chment'3 Page 3 of 3 Simulator Computer Upgrade Test Program Status Report Test No. TITLE Open Simulator Trouble Reports T22] Turbine Header Pressure Transtnitter Fails to Mid-Scale (900 none psig)

T23a PASS. MALF. - SFRCS MAN. ACT. FAIL. & AFPT FAILS AT HI none SPEED STOP T23b PASSIVE MALFUNCTIONS - AFW, LPI AND CS PUMPS FAllTO none START T24 ATWS none TAB 01 MANUAL REACTCR TRIP none TAB 02 SIMULTANEOUS TRIP OF ALL MAIN FEEDWATER PUMPS none TAB 03 SIMULTANEOUS CLOSURE OF ALL MSIVs none TAB 04 SIMULTANEOUS TRIP OF ALL REACTOR COOLANT PUMPS none TAB 05 TRIP OF ONE REACTOR COOLANT PUMP none TAB 06 MAIN TURBINE TRIP FROM 40% POWER NO REACTOR TRIP none TAB 07 MAXIMUM RATE POWER RAMP 100% 75% 100% none TAB 08 DBL END. HOT LEG SHEAR WITH A COINCIDENT LOSS OF ALL swo 95-0063 OFFSITE PWR TAB 09 MAIN STEAM LINE FAILURE IN THE REACTOR BLDG. DOUBLE swo 95-0063 ENDED SHEAR TAB 10 THE PORV FAILS OPEN AND HPl DOES NOT ACTUATE swo 95-0063

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l Dock:t Number 50-346 l License Number NPF-3

! Serial Number 2590 l 'Attachinent 4 I Page1of1 Simulator Computer and New Reactor Core Model Upgrade Discrepancy Correction Plan Approximately six Priority B discrepancies and 23 Priority C discrepancies remain from the computer upgrade and the new reactor ccre tesdng programs. Internal meetings were held in early March,1999, following the declaration of " Ready for Training" for the new Reactor Core Model to prioritize the outstanding discrepancies, as well as those remaining from before the computer upgrade, and to establish a plan for resolution of those discrepancies. The focus has been and will be during the second quarter of 1999 to reduce this backlog on a prioritized basis, with the discrepancies most significant to upcoming training addressed first.

Discrepancies will be prioritized, corrected, and tested in accordance with existing Nuclear Training procedures.

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