ML20062G426

Forwards Clarification to Initial Simulator Certification Rept of 900813

ML20062G426
Person / Time
Site:	Comanche Peak
Issue date:	11/12/1990
From:	Jacqwan Walker TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	Hunemuller N Office of Nuclear Reactor Regulation
References
NUDOCS 9011290199
Download: ML20062G426 (8)

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NELECTRIC NPSES-9025436 Wovember 12, 1990 No Responso Required Mr. Neil K. Alunemuller Simulator Evaluations Office of Nuclear Reactor Regulation U.S. Nuclear Regulategy Commission Washington, D. C. 20555

SUBJECT:

CTSES UNIT 1 SIMULATOR CERTIFICATION

Dear Mr. Hunemeller:

In an effort to clarify information contained within'TU Electric's Comanche Peak Steam Electric Station Unit 1 initial simulator certification report of

August 13, 1990, the attached information is being forwarded for inclusion in l our report.

Should you have any questions, please contact me at (817) ~ 897-5367.

l Sincerely, a1 iQ_

J. R. Walker,.701 Operations / Engineering Training Manager JRW;pkm Attachment cc: G. L. Bell ST24 CCS E06 c-U u w . ., J 9011290199 901112 /-

PDR ADOCK 05000445 l8 pp.,

V PDC P.O. Box 2300 Glen Rose. Texas 760431147

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s CPSES-9025446 I

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1 The following pages for inclusion to TU. Electric's Comanche Peak Steam' ..

Electric Station. Unit 1 initial simulator certification'. report of August 13, .'  !

1990. Please take the following actions:1 i

Rephce the pages 6-3 through 6-5 with' attached pages 6-3,.

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through 6-7.

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2. Insert-the page titled "CPSES ANNUAL NORMALLOPERATiONS. TEST LIST" in Section 0 "FOUR-YEAR TEST' SCHEDULE."- 'I t

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. TU I!!cctric TURillNE STARTUP AND GENERATOR SYNCHRONIZATION 1his test was condo.teci in conjunction with the Nuclear Startup from Hot Starxiby to Rated Power.

This test was ocemed satisfactory.

REACFOR TRIP FOLLOWF D BY RECOVERY TO RATED POWER This test was conducted in compliance with ANSI /ANS-3.5-1985 section 3.1, It was a test to validate the simulator perfon tance from an initial condition of Mode I, Reactor Power 100%,

RCS Temperature 589 'F, RCS Pressure 2235 psig and Pressurizer hvel 60% - to a condition of -

Mode 1, Reactor Power 10095, RCS Temperature $89 'F, RCS Pressure 2235 psi; ai d ,

Pressurizer level 60 % - utiliziog carrent controlled plant Integrated Plant Operatin,I Prt cedures, System Operating Procedures aml Li ensed Operator Training Program selected 0; eratiens Testing Procedures (surveillance tests). ,

This test was deemed satisfactory.

OPERATIONS ATllOTSTANDBY This test was conducted in < iction with the Nuclear Startup From Hot Standby To Rated Power, Reactor Trip Follow Recovery To Rated Power and the Plant Shutdown From Rated Power To llot Standby An- .down To Cold Shutdown tests.

This test was deemed satis *actory.

LOAD CilANGES This test was conducted in conjunction with the Nuclear Staitup fium Hot Standby to Rated

Power.

'this test was deemed satisfactory.

PLANT SIIUTDOWN FROM RATED POWER TO HOT STANDBY AND COOLDOWN TO COLD SilUTDOWN This test was conducted i': compliance with ANSI /ANS-3.5-1985, section 3.1.1. It was a test to validate the simulator perfonnance from an initial condition of Mode 1 (RCS temperature 589 'P, RCS pressure 2235 psig and Pressurizer Level 60%) operation to Mode 5 (RCS temperature 5 200 'F, Keff < .99 and Power 0%) with RCS pressure < 400 psig and on Residual Heat Removal system cooling.

This test was deemed satisfactory.

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l STARTUP, SillJrDOWN AND POWER OPERATIONS WTTH LESS THAN FULL REACTOR COOLANT FIDW

'lhis test was not conducted due to Unit i Operating Licensc/rechnical Specifications not allowing this configuration. .

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. 'IU th-trie CORE PERFORMANCE TESTING:

Perfonnance of Plant lleat Balance and Shutdown Margin Calculations.

'these tests were conducted in conjunction with the Nuclear Stanup from Hot Standby to Rated Power.

• lhese tests were deemed satisfactory.

REAC11VITY COEFFICIENT AND CONTROL ROD WORTH MEASUREMENTS

'Ihese tests are conducted in the plant using temporarily installed instrumentation therefore, they have not been performed on the simulator for this certification. Ilowever, similar plant startup tests have teen performed on tim simulator by licensed operator training prior to actual plant perfoimance.

OPERATOR CONDUCTED SURVEILLANCE TESTING Licensed Operator Training selected tests were conducted in conjunction with the Nuclear Startup from llot Standby to Rated Power.

'these tests were deemed satisfactory.

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, 'IU I!!cetric TRANSIENT PERFORMANCE TESTS The ANSI /ANS-3.5 Appendix B2.2 transient tests have been corn,leted. Attached is a copy of the completed Manual Reactor Trip test procedure and copies of test a astracts from the following ,

perfonnance tests:  :

. Simultaneous Trip of All Feedwater Pumps Simultaneous Closure of All Main Steam Isolation Valves Simultaneous Trip of All Reactor Coolant Pumps Trip of Any Single Reactor Coolant Pump Main Turbine 'l rip (hiaximum Power Level which does not result in immediate Reactor Trip)

Maximum Rate Power Ramp (100% down to approximately 75% and back up to 100%)

Maximum Size Reactor Coolant System Ruptuir Combined with Loss of All Off Site Power Maximum Size Unisolable Main Steam Line Rupture Slow Primary System Depressurization to Saturated Condition using Pressurizer Relief or Safety Valve Stuck Open

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MALFUNCTION TESTS 1

1 The malfunctions listed in the attached " Malfunction Causes and Effect" document have been tested in compliance with ANSI /ANS 3.51985, section 3.1.2. The initial condition for introducing the l malfunction was as listed in the " Malfunctions Causes and Effect" document and maximum severities were used unless the minimum severity would produce the least desirable effect opon reference unit simulation. Malfunctions tested include:

(1) Loss of coolant:

(a) significant PWR steam generator leaks; (b) inskle and outside primary containment; (c) large arxl sinall reactor coolarit breaks including demonstration of saturation ,

condition; (d) failute of safety arxl relief valves; (2) Loss of instrument air to the extent that the whole system or individual headers lost pressure azul affected the phmt's static or dynamic perfonnance; (3) Loss or degnuled electrical power to the station, including loss of offsite power, loss of emergency power, loss of emergency generators, loss of power to the plant's electrical distribution buses ruxiloss of power to the irxlividual instmmentation buses (AC as well as IX') that provide power to control room indication or plant control functions affecting the plant's response; (4) Loss of forced core coolant flow due to single or multiple pump failure; (5) Loss of condenser vacuum including loss of condenser level control; (6) Loss of service water or cooling to individual components; (7) l_oss of shutdown cooling; (8) Loss of component cooling system or cooling to irxlividual components; (9) Loss of nomial feedwater or nonnal feedwater system failure; 3 (10) Loss of all feedwater (nonnal arul emergency);

(l1) Loss of protective system channel; (12) Control rod failure including stuck rods, uncoupled rods, drifting rods, rod drops, ruxl misaligned rods; (13) Inability to drive control rods; (14) Fuel cladding failure resulting in high activity in reactor coolant or off gas and the associated high radiation alnus; (15) Turbine trip; (16) Generator trip; Page 6-6

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I (17) Failure in automatic control system (s) that affect reactivity and core heat removal; ,

i (18) Failure of reactor coolant pressure and volume control systems; (19) Reactor trip; (20) Main steam line as well as main feed line break (both inside and outside containment);

(21) Nuclear instrumentation failure (s);

(22) Process instnimentation, alarms, and control system failures; (23) Passive malfunctions in systems, such as engineered safety features, emergency feedwater systems; ,

(24) Failure of the automaticicactor trip system. ,

i These tests were deemed satisfactory. Minor discrepancies identified during testing have been scheduled for completion as shown in Section 7. ,

A " Malfunction Cause anxi Effects" listing for all certified malfunctions is attached. 1 b

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CPSES ANNUAL NORMAL OPERATIONS TEST LIST

• Plant Startup - Cold Shutdown To Hot Standby ,

• Nuclear Startup From Hot Starxtby To Rated Power i

• Turbine Stanup Arxl Generator Synchronization  !

• Reactor Trip Followed By Recovery To Rated Power

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Operations At llot Standby

. Load Changes

• Plant Sliutdown Froin Rated Power To llot Standby And Cooldown To Cold I Shutdown

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Core Perfonnance  !

• Operator Conducted Surveillance Testing On Safety Related Equipment Or Systems F

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