ML18110A608

LER 1976-007-00 for St. Lucie Unit 1, an Error in the RCS Loop Temperature Wiring Diagrams

ML18110A608
Person / Time
Site:	Saint Lucie
Issue date:	04/23/1976
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
PRN-LI-76-97 LER 1976-007-00
Download: ML18110A608 (6)

Text

NRC FoRM 195 I2 7GI U.S.NUCLEAR REGULATORV C IISSION DOCKET NUMBER Mr MoseWey Florida Pwr;6 Light Co Miami, Fla R E Uhrig NRC DISTRIBuTION roR PART 50 DOCKET MATERIAL rILE NUMBER XNCXDENT RrPORT DATE OF DOCUMENT 4-23-76 DATE RECEIVED EILETTER QORIGINAL Qcopv.ONOTORIZED CI VNC LASSIF I ED PROP INPUT FORM NUMBER OF COPIES RECEIVED none signed DESCRIPTION Ltr trans the following license event report: ENCLOSURE RO/P 76-7 on 3-25-76 concerning erratic reactor coolant loop Th rIBmperature indication........

PLANT NAME: St Lucie 81 NOTE: IF PERSONNEL EXPOSURE IS XNVOLVED SEND DIRECTLY TO KREGER/J.COLLINS SAFETY BRANCH CHIEF'I 3 CYS FOR ACTION LIC~ASST: M/CYS FOR ACTION/INFORMATION usa nn ENVXRO 5-10" 76 ehf ACRS CYS QQKELW4/ENT TO LA EG PILE NRC PDR INTERNAL DISTRIBUTION SCHROEDER/XPPOLITO 0 NOVAK CHECK R IES S.NE TEDE g CO~CC~A i'AI'R SIIAO VOI~LYHR BUBCtl KRI:~E~~O~..

NS LPDR: I=i I c.v~TIC NSXC EXTERNAL DISTRIBUTION CONTROL NUMBER qg 4R

~~~~~~~

CO.'B 9 joe P.O.BOX 3100 MIAMI, FLORIDA 33101 I.U I~l'~~~+Sp~;.;~~~:.~rigjij Li FLORIDA POWER&LIGHT COhIPAi'IY April 23, 1976 PRN-LI-76-97 Mr.Norman C.Moseley, Director, Region Office of Inspection and Enforcement U.S.Nucle'ar Regulatory Commission 230 Peachtree Street, N.W., Suite 818 Atlanta, Georgia 30303

Dear Mr..Moseley:

CU c II I 00CNGIl3 uSI4RC M~~5)076Ž~IDR<CL~R RE~CgagkAB IAou>'EPORTABLE OCCURRENCE 335-76 7'v ST.LUCIE UNIT 1 DATE OF OCCURRENCE:

MARCH 25, 1976 WIRING DIAGRAM ERROR (Th INSTRUMENT)

The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to provide 30-day notification of the subject occurrence.

Very truly yours, RE8ULAT",.Y

'."""'T I-II E CO Vice President Power Resources MAS/cpc Attachment cc: Jack R.Newman, Esquire Director, Office of Inspection and Enforcement (30)Director, Office of Management Information and Program Control (3)1 HELPING BUILD FLOFIIOA V f I'>>~CONTROL BLOCK: LICENSEE EVENT REPORT~~SE PRINT ALL REOUIRED INFORMATION) 6 UCENSEE NAME~01 F L 4 L s 1 0 0 7 89 14 15 LICENSE NUMBER 0 0 0 0 0 0 0 LICENSE EVENT TYPE TYPE 4 I.I.a I.~OS 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE[OD~ICoN'7

~L~L 0 7 8 57 58 59 60 61'OCKET NUMBER~EVENT OATS 5 0-0 3 3 5 0 3 2 5 7 6 68 69 74 REPORT DATE 0 4 2 3 7 6 75 80 EVENT OESCRIPTION

@~2 While erformin reo erational testin of the Reactor Protection S stem 7 8 9 Bo[oO~]p i em rature indication was 7 89+04 observed.Subseauent review of Reactor Coolant S stem RCS loo 7 8 9 IOOI tern erature wirin dia rams revealed an error.The olarit of th7 89 Jog 80 80 80"7 89 SYSTEM CAUSE CODE CODE[oO~][iiaJ~o z 7 8 9 10 11.12 CAUSE OESCRIPTION PRME CCMPONENT COMPONENT COMPONENT CODE.SUPPUER MANUFACTURER N S R U.N G 0 8 0 17 43 44 47 N'0~os 7 8 9 Iossj 7 8 9~10 7 89 FACILITY STATUS"%POWER jg~~s LJoaoo J 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY KQs LJs'~l NA 7 8 9" 10 11 PERSONNEL, EXPOSURES NUMBER TYPE OESCRdoTION Q~g[gJ i~'z 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION

~i4[0000 J 7 89 11 12 PROBABLE CON SEQUEN'CES Qs]7 8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION z 7 89 10 PUBLICITY 7 89 METHOD OF DISCOVERY OTHER STATUS NA DISCOVERY DESCRIPTION Preo erational Test 44 45 46 LOCATION OF RELEASE NA 4s NA NA NA NA NA AOOITIONAL FACTORS'ti n 7 89 e c was ca s d an e or in the RCS loo tern erature 80 Bo 80 80 80 80 80 80 80 eo 7 89 M.A.Schoppman eo Cl'0 44t~447 REPORTABLE OCCURRENCE 335-76-7 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued)

I the Thermal Margin/Low Pressure reactor trip was found reversed on the diagrams.Component modifications were completed prior to continuing heatup to within the Th instrument range.The modifica-tions were made to comply with the original design intent, and no functions or equipment were added or deleted.Further preoperational testing and reviews of RPS wiring have indicated that this is not a repetitive problem.This was the first occurrence of this type.(335-76-7).