ML20214L106

Package Consisting of Undated LER Sequence & Coding & Search Sys Data Run,Data from NRC ES7 Actuation Data Base & Handwritten Staff Notes Re LER 87-071

ML20214L106
Person / Time
Site:	Palo Verde
Issue date:	05/22/1987
From:	NRC
To:
Shared Package
ML20214K718	List: ML20214K716 ML20214L106
References
FOIA-87-261 NUDOCS 8705290192
Download: ML20214L106 (4)

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oite 3: COMP e t-NR +ur i t isi i insN5FOnNthf ta 'r- 1 A t is t!vtNt ) rii silA t t ri Witsi UFF51TE POWER 50ui st t0. wAi t ri __z 1. C e C u-4_. t uuwn t x _. I tR lish E Ar Lt l'EO.

WATC H-LIST CODrii FOR Yts]5 LER HRE:

942 UNU5UAL EvkNT 232 UNE APECTED COr!FONC Ni HC TION OR RL _f utist REPORTAbiLITY CODE 5 FOn Tril ;. LER ARE:

11 10 CFR Sv.73(a)(2 tii): Une n a i rz e ci conoirions.

13 10 CFR 50.~/3taitz)'iv;; E5F actuations.

REFERENCE LER5:

1 528/85--063 ABSTRACT POWER lev'EL - OOu?.. AT 1 25 ON 1-9-Oc., s TdiiB1NL TRIP ANO :_-UbbtOulN i REACTOR TRIP WA5 Tu BE IN iii A iEU A5 A SCntiuOttu Use,i vi; Thd POWER A5CENSION TES TING PROGRAM. T Hti TURB1NE TR1P WAi 1NITIA EU by MAmVAL ACTUAriON OF THE UNIT 01FrEntNiist OtNEnsTun FRuftCliuN REtnv. iHE 525 f:N OENERATOR OUTPUT bRE4h ERS OFENED AS EXPLCTED, t50T THE NON-ESSENTIAL STATION LOAD 5 DiD NOf AviOMAYiCAtti i- AST- f hsN5f-ER FO Trid OFF5ITE POWER SOURCE. THIS RESULTED IN A LOSS uF POWER TO THE REACTOR COOLANT PUMP 5 ANO A REACTOR TRIP WA5 OENERATED fFv THE CORE PROTECTION CALCULATOR 5 FROM A FLOW PROJECTi.ib LOW DEPAniuhE FROM NUCLEATE BOilINO RsfiO. bur 1Nu ind t.vkN i , UNc hAIN 31tsh 5HFEiy vatvt

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s.~ePENED AND AN EXCE5siVE LOOLDOWN OCCURRED TriAT Ri 5ULTED IN A NAIN a iEfC1 ISOLATION SiONAL ACTUATION. Dut < 1 NO fhE EVENT, fht RCP COASIED DOWN SLIGHTLY FA5TER THAN THE RATE A5.iUNED I N i r1E 1.AFLi i ANetY515. UN 1 - 1 3 - 8 c., ti Was DEitn.hiHED insi and hte COso DuwN nAfd WA.5 A r CONDITION OUisiDE THE DE510N EA5I5 A550MEb IN itiE 5AFEii ANAL f 512. sd A RE5 ULT OF THIS EVENT: lHE APPtiC A riUN ut Int 5t htlisuNil A fiON CliECb.

i RELAY 15 TO DE EVALUATED; LICEN5ED OPERATORS HAvE BEEN INSTRUCTED Oh HOW TO RESPOND TO A LO55 Oi; PuwtiR 10 int :iEAh syPA'au CONTROL si5TtM INSTRUMENT PANEL 5; AND A PENALTY Fst.iuR HA5 bEEN ADDED TO THE CURE OPERATING LIMii 5UPERVISORy system.

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J.YhbOL : HP5 REruMi HBILITY CODE 5 FOR THIS LER AriL:

13 10 Cr~h iO.73(as(2itiv>: ESF actuations.

ABSTRACT POWER LEVEL ~ 00u%. ON Nr;RIL 4, 1906, Hi 1344, WlTii UNII J lN NUUt_ o (HOT STANDB'yi, AN AufOnsTiC stfusi10N Of- ALL 4 tr1sNNEta Ur-' iHt REsttOM PROTECTION 5y'51EM (RP5) OCCURRED DUE iO LOW iiEAtiOR CuOLANT 5 5iEH FLOW THROUOn iTEAM OEhERATOR NO. z. HL i tiOUOr stt CONfRvL ELLhthi ASSEMBLIES WERE IN lHE iOLLY INdthitD F051TivN, ALL fiEACl OR i r<iP BREAKERS OPENED AS EXrECit'O, saifaFyiNO THE hihihUM HCfvAT10N lou 1C FOR RP5 ACTU4710N. ALL Sy'5 TEM 5 AND COMPONENTS RESPONDED SATISFACTORILV. ittu Res AC r'UA fiON OtCvhiiEO WrtEN iiEACTOii Lv0LAN T t'Uht' (RCP) 2B WAS SECUiiED. IN ACCORDANCE WITH AN At'PROVEL PriOCEDURE, DUE TO A LO55 OF SEAL 1NJECTIvh FLOW WhiLH HESULfED iH A HtOil GEAL INJECTION TEMFERATURE. THE CAUSE OF THE Loss OF THE SEAL INJECTiuN FLOW wAs A RESTRICTION IN A SYSTEM 5 TRAINER. A _, COHriEt i~ivE At.T10N, it st Git <AINEN WA5 FLUSHED, AND SEAL INJECTION WA5 RESTORED TO RCP 28 AT 1635.

ADEifTIONALLY, AN ENGINEERING EVALUATION HAS DEEN INITIATED TO DETERMINE IF ADDITIONAL ACTIONS ARE NECESSARY TO ENHANCE Trit PERFORMANCE OF THE siRAINER. THERE hAVE DEEN NO PREVIOUS SihILAK EVENT 5.

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