ML20069M750

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Forwards TMI plant-referenced Simulator Exceptions to Ansi/ ANS 3.5-1985,description of Simulator Testing Completed Since June 1990,simulator Certification Test Schedule & Description of Simulator Testing to Be Conducted
ML20069M750
Person / Time
Site: Crane 
Issue date: 06/10/1994
From: Mascari C
GENERAL PUBLIC UTILITIES CORP.
To: Russell W
Office of Nuclear Reactor Regulation
References
6000-94-036, 6000-94-36, C311-94-2073, NUDOCS 9406220131
Download: ML20069M750 (13)
v • d • e


Text

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GPU Nuclear Corporation Middletown, Pennsylvania 17057-0480 (717)944-7621 Writer's Direct Dial Nurnber:

(201) 316-7603 June 10, 1994 C311-94-2073 6000-94-036 William T. Russell Director, NRR US Nuclear Regulatory Commission Washington, DC 20555

Subject:

Three Mile Island Nuclear Station, Unit 1 (TMI-1)

Operating License No. DPR-50 Docket No. 50-289 Simulation Facility Report

Dear Mr. Russell:

This letter and its attachments documents that the Three Mile Island Unit 1 Simulation Facility continues to meet the Commission's regulations as contained in 10 CFR 55.4.

GPU Nuclear initially certified in letter C311-90-2092 dated June 28, 1990, that the Three Mile Island Unit 1 Simulation Facility met the Commission's regulations.

10 CFR 55.45.b.5 (ii) and (vi) require a report to the Commission every four years which identifies any uncorrected performance test failures, a schedule to correct these test failures, description of performance testing completed, and test schedule for the next four year period.

There are no uncorrected test failures for the Three Mile Island Simulation Facility.

GPU Nuclear has enclosed a copy of the following test information for the Three Mile Island Simulation Facility.

J Attachment A - Exceptions to ANSI /ANS 3.5-1985 Attachment B - Description of Simulator Testing Completed Since June 1990 Attachment C - Simulator Certification Test Schedule Attachment D - Description of Simulator Testing To Be Completed Sincerely,

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AA 4 d C. A. Mascari Wed r, Nuclear Assurance 9406220131 940610 DVH/ emf PDR ADoCK 0500o289 P

PDR cc:

M. G. Evans - TMI Senior Resident Inspector (w/o attachment)

R. W. Hernan - Senior Project Manager (w/o attachment) o.,

T. T. Martin - NRC Regional Administrator, Region I (w/o attachment)

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00f GPU Nudear Corporation is a subsidiary of General Public Utikties Cerporation

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ATTACHMENT A TIIREE MILE ISLAND PLANT-REFERENCED SIMULATOR EXCEPTIONS TO ANSI /ANS 3,5-1985 Item Number 1

ANS 3.5 Reference Appendix B B2.1(1)

B2.2.3 i

B2.2.4 Requirement Record pressurizer pressure during selected performance tests.

Justification In accordance with the reference plant design, the simulator for Exception pressurizer pressure instrument is ranged from 0 - 500 PSIG for accurate indications at low reactor coolant system pressure. Where pressurizer pressure response was required to be recorded, a reactor coolant pressure instrument which was on-scale was used so that meaningful data was collected to document simulator performance.

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There should be no impact on the conduct of operator licensing examinations due to this exception.

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Item Number 2

l ANS 3.5 Reference Appendix B B2.2.1 l

Requirement Record total steam flow (if available) during selected performance tests.

Justification There is no total steam flow instrumentation installed in the for Exception reference plant, therefore there is no steam flow instrumentation on the simulator panels.

There should be no impact on the conduct of operator licensing examinations due to this exception.

1 June 9,1994 l

ATTACIIMENT A THREE MILE ISLAND PLANT-REFERENCED SIMULATOR EXCEPTIONS TO ANSI /ANS 3.5-1985 Item Number 3

ANS 3.5 Reference Appendix B B2.2.4 Requirement Record relief valve flow (if available) during selected performance tests.

Justification There are no relief valve flow indicators installed in the reference for Exception plant, therefore there is no relief valve flow instrumentation on the simulator panels.

There should be no impact on the conduct of operator licensing examinations due to this exception.

Item Number 4

ANS 3.5 Reference Appendix B B2.2.4 Requirement Record reactor vessel level (if available) during a selected performance test.

Justification This indication is available on the plant process computer if for Exception the operator stops all four Reactor Coolant Pumps. Since the Reactor Coolant Pumps were not stopped during this test (in accordance with Appendix B requirements) the indication was not available, and therefore was not recorded. In actual plant operation the operators would secure the Reactor Coolant Pumps, and the indication would be activated.

Current ATOG procedures do not require the operator to use this indication, therefore there should be no impact on the conduct of operator licensing examinations due to this exception.

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June 9,1994

ATTACHMENT A THREE MILE ISLAND PLANT-REFERENCED SIMULATOR EXCEPTIONS TO ANSI /ANS 3.5-1985 l

Item Number 5

ANS 3.5 Reference 3.4.2 3.1.2 Requirement It shall be possible to conveniently insert and terminate the plant malfunctions specified in Section 3.1.2 (Plant Malfunctions).

l Justification The Fuel Failure malfunction (TH01) can not be terminated for Exception following activation on the TMI Plant-Referenced Simulator. This exception is justified since fuel failure is not recoverable during a normal training or testing scenario. All malfunctions (including TH01) are automatically cleared during simulator Reset operations, l

where the instructor ends the scenario and changes to a new Initial Condition.

There should be no impact on the conduct of operator licensing l

examinations due to this exception.

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June 9,1994 i

9 ATTACllMENT B TIIREE MILE ISLAND PLANT REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING COMPLETED SINCE JUNE 1990 The following list describes the simulator certification tests conducted since the initial submittal dated June 28,1990. In accordance with the 4-year schedule included in the l

initial simulator certification submittal, tests marked with an asterisk (*) were conducted annually, and the remaining tests were conducted once over the 4-year certification.

A.

REAL TIME TEST TEST DESCRIPTION

  • RTT01 Real Time Test l

B.

STEADY STATE PERFORMANCE TESTS l

i TEST DESCRIPTION l

SSP 01 Simulator Stability l

l SSP 02 Simulator Accuracy l

C.

NORMAL OPERATIONS TESTS TEST DESCRIPTION NOT01 Plant IIeatup l

NOT02 Plant Start-up l

NOT03 Reactor Trip and Recovery NOT04 3 RC Pump Operations NOT05 Zero Power Physics Testing NOT06 Core Flood System Valve Operability Test NOT07 Emergency Power System NOT08 RB 30 PSIG Analog Channels NOT09 Main Steam Isolation Valves Surveillance NOT10 Main Steam Isolation Valves Monthly Surveillance NOT11 Shift and Daily Checks Surveillance NOT12 Weekly Surveillance Checks NOT13 RCS Leakrate 1

June 9,1994 l

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l ATTACHMENT B THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING COMPLETED SINCE JUNE 1990 C.

NORMAL OPERATIONS TESTS (Continued)

TEST DESCRIIrrION NOT14 Control Rod Movement NOT15 RB Cooling and Isolation System Logic Channel and Component Test NOT16 Loading Sequence and Component Test and HPI 1.ogic Channel Test NOT17 High Pressure Injection NOT18 RB Emergency Cooling System NOT19 ES System Emergency Sequence and Power Transfer Test NOT20 Turbine Overspeed Testing NOT21 Low Pressure Injection NOT22 Plant Shutdown NOT23 Plant Cooldown NOT24 Shutdown Margin and Reactivity Balance NOT25 Heat Balance Calculations D.

TRANSIENT TEST SERIES TEST DESCRIPTION TFS01 OTSG Tube Leak TFS02 OTSG Tube Rupture TTS03 RCS I.eak Inside Containment TFS04 RCS Leak Outside Containment TFS05 I2rge Break LOCA TTS06 Small Break LOCA

  • TFS07 RCS Safety Valve Failure TFS08 RCS PORV Failure TTS09 Loss ofInstrument Air TFS10 Station Blackout TTS11 DC Distribution Failure 2

June 9,1994

ATTACIIMENT B THREE MILE ISIAND PIANT-REFERENCED SIMUIATOR DESCRIPTION OF SIMULATOR TESTING COMPLETED SINCE JUNE 1990 D.

TRANSIENT TEST SERIES (Continued)

TEST DESCRIPTION TFS12 Emergency Diesel Generator TTS13 6.9 KV Bus Fault TFS14 4.16 KV Bus Fault TFS15 480 V Bus Fault TFS16 480 V MCC Fault TIS 17 ICS Auto Power Failure TFS18 Inverter Failure

  • TFS19 Imss of Forced Flow TFS20 Loss of Condenser Vacuum TFS21 Condenser Level Control Failure TFS22 Imss of Service Water TTS23 Loss of Shutdown Cooling TFS24 Imss of Component Cooling TTS25 Loss of Normal Feedwater TTS26 Normal Feedwater System Failure TTS27 less of all Feedwater TFS28 Loss of Protective System Channel TFS29 Stuck Control Rod TFS30 Continuous Rod Insertion TFS31 Dropped Rod TTS32 Uncoupled Rod TTS33 Inability to Drive Rods TFS34 Failed Fuel TTS35 Turbine Trip TFS36 Generator Trip TFS37 Inadvertent OTSG Isolation TTS38 Inadvertent OTSG Overfeed TFS39 Pressurizer 12 vel Control Failure TFS40 Pressurizer Heater Failure 3

June 9,1994

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A'ITACHMENT B THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMUL.ATOR TESTING COMPLETED SINCE JUNE 1990 D.

TRANSIENT TEST SERIES (Continued)

TEST DESCRIPTION TFS41 Reactor Trip

'ITS43 Main Steam Leak Outside RB 1

TFS44 Main Feedwater Line Break Inside RB TTS45 Main Feedwater Line Break Outside RB TFS46 NI 5 Failure l

TFS47 NI 6 Failure TFS48 Pressurizer 12 vel Control l

TFS49 Feedwater Flow Transmitter Failure TFS50 RC Cold Leg Temperature Transmitter Failure TFS51 OTSG Pressure Transmitter Failure TTS52 Emergency Diesel Generator Failure TFS53 Emergency Feedwater Failure TFS54 ESAS Actuation Failure TFS55 ATWS

  • TTS57 Simultaneous Closure of all MSIVs
  • TFS58 Loss of One RC Pump
  • TTS59 Maximum Rate Power Ramp

4 June 9,1994

ATTACHMENT C THREE MILE ISLAND PLANT-REFERENCED SIMULATOR simul.ATOR CERTIFICATION TEST SCHEDULE Annual Simulator Test Reauireminis 100% of ANSI /ANS 3.5-1985 Benchmark Tests (10) 25% of Transient Test Series (TTS) 25% of Normal Operations Tests (NOT) 100% Steady State Performance Tests (SSP) i 100% Meter Accuracy Tests Real Time Test Annual Quadrennial Tests Benchmark Additional Iests

  • Year #1 Tests
  • Year #2 Tess
  • Year #3 Tests
  • Year #4 Tests TFS07 TTS01 TFS15 TTS30 TTS44 TTS19 TFS02 TFS16 TTS31 TFS45 TTS27 TTS03 TFS17 TFS32 TTS46 TTS35 TFSO4 TFS18

'ITS33 TFS47 TFS42 TFS05 TFS20 TTS34 TFS48 TFS56 TTS06 TFS21 TTS36 TFS49 TTS57 TTS08 TFS22 TTS37 TFS50 TFS58 TTS09 TFS23 TTS38 TTS51 TFS59 TTS10 TFS24 TFS39 TTS52 TTS60 TFS11 TFS25 TFS40 TTS53 TFS12 TFS26 TFS41 TFS54 Steady TTS13 TFS28 TFS43 TTS55 Slate TFS14 TFS29 Iests SSP 01 NOT01 NOT08 NOT14 NOT20 SSP 02 NOT02 NOT09 NOT15 NOT21 NOT03 NOT10 NOT16 NOT22 i

Real NOT04 NOT11 NOT17 NOT23 Iimf.

NOT05 NOT12 NOT18 NOi24 Iqst NOT06 NOT13 NOT19 NOT25 4

RTF01 NOT07

  • Year #1 = July 1994 through June 1995
  • Year #2 = July 1995 through June 1996
  • Year #3 = July 1996 through June 1997
  • Year #4 = July 1997 through June 1998 1

June 9,1994 r

ATTACHMENT D THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING TO BE CONDUCTED The following list describes the simulator certification tests to be conducted in support of the Three Mile Island Plant-Referenced Simulator certification program during the next four (4) years. The scheduled tests will be conducted in accordance with the four year test plan. When simulator modifications produce significant deviations in simulator response, selected certification tests will be conducted as part of the acceptance for the modification.

A.

REAL TIME TEST TEST DESCRIPTION RTf01 Real Time Test B.

STEADY STATE PERFORMANCE TESTS TEST DESCRIPTION SSP 01 Simulator Stability SSP 02 Simulator Accuracy C

NORMAL OPERATIONS TESTS TEST DESCRIPTION NOT01 Plant Heatup NOT02 Plant Start-up NOT03 Reactor Trip and Recovery NOT04 3 RC Pump Operations NOT05 Zero Power Physics Testing NOT06 Core Flood System Valve Operability Test NOT07 Emergency Power System NOT08 RB 30 PSIG Analog Channels NOT00 Main Steam Isolation Valves Surveillance NOT10 Main Steam Isolation Valves Monthly Surveillance NOT11 Shift and Daily Checks Surveillance 1

June 9,1994

ATTACHMENT D THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING TO BE CONDUCTED C.

NORMAL OPERATIONS TESTS (Continued)

TEST DESCRIPTION NOT12 Weekly Surveillance Checks NOT13 RCS I2akrate NOT14 Control Rod Movement NOT15 RB Cooling and Isolation System Imgic Channel and Component Test NOT16 Loading Sequence and Component Test and HPI logic Channel Test NOT17 High Pressure Injection NOT18 RB Emergency Cooling System NOT19 ES System Emergency Sequence and Power Transfer Test NOT20 Turbine Overspeed Testing NOT21 Low Pressure Injection NOT22 Plant Shutdown NOT23 Plant Cooldown NOT24 Shutdown Margin and Reactivity Balance NOT25 Heat Balance Calculations D.

TRANSIENT TEST SERIES TEST DESCRIPTION TFS01 OTSG Tube Leak TFS02 OTSG Tube Rupture TFS03 RCS Leak Inside Containment TFSO4 RCS Leak Outside Containment TTS05 12rge Break LOCA TTS06 Small Break LOCA TTS07 RCS Safety Valve Failure TFS08 RCS PORV Failure TFSO9 Imss of Instrument Air TFS10 Station Blackout 2

June 9,1994

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ATTACHMENT D THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING TO BE CONDUCTED l

D.

TRANSIENT TEST SERIES (Continued) l TEST DESCRIPTION TFS11 DC Distribution Failure TTS12 Emergency Diesel Generator TFS13 6.9 KV Bus Fault TFS14 4.16 KV Bus Fault TTS15 480 V Bus Fault TTS16 480 V MCC Fault TFS17 ICS Auto Power Failure l

TFS18 Inverter Failure TTS19 IAss of Forced Flow TTS20 Loss of Condenser Vacuum TFS21 Condenser 12 vel Control Failure TTS22 Loss of Service Water TFS23 Loss of Shutdown Cooling TFS24 Imss of Component Cooling TFS25 Loss of Normal Feedwater TFS26 Normal Feedwater System Failure TTS27 Loss of all Feedwater TFS28 Loss of Protective 7ystem Channel TTS29 Stuck Control Rod TFS30 Continuous Rod Insertion TFS31 Dropped Rod TFS32 Uncoupled Rod TFS33 Inability to Drive Rods TTS34 Failed Fuel TFS35 Turbine Trip TFS36 Generator Trip TFS37 Inadvertent OTSG Isolation TTS38 Inadvertent OTSG Overfeed TfS39 Pressurizer 12 vel Control Failure TFS40 Pressurizer Heater Failure TTS41 Reactor Trip TFS42 Main Steam Leak Inside RB 3

June 9,1994

ATTACHMENT D THREE MILE ISLAND PLANT-REFERENCED SIMULATOR DESCRIPTION OF SIMULATOR TESTING TO BE CONDUCTED D.

TRANSIENT TEST SERIES (Continued)

TEST DESCRIPTION TTS43 Main Steam Leak Outside RB TrS44 Main Feedwater Line Break Inside RB TTS45 Main Feedwater Line Break Outside RB TTS46 NI 5 Failure TFS47 NI 6 Failure TTS48 Pressurizer Level Control TFS49 Feedwater Flow Transmitter Failure TFS50 RC Cold Leg Temperature Transmitter Failure TTS51 OTSG Pressure Transmitter Failure TFS52 Emergency Diesel Generator Failure TTS53 Emergency Feedwater Failure TFS54 ESAS Actuation Failure TFS55 ATWS TFS56 Manual Reactor Trip TTS57 Simultaneous Closure of all MSIVs TTS58 Imss of One RC Pump j

TTS59 Maximum Rate Power Ramp TFS60 loss of Offsite Power with Design Basis LOCA 1

4 June 9,1994

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