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

U.S. NUCLEAR REGULATORV C IISSION DOCKET NUMBER NRC FoRM 195 I2 7GI rILE NUMBER NRC DISTRIBuTION roR PART 50 DOCKET MATERIAL XNCXDENT RrPORT DATE OF DOCUMENT Mr MoseWey Florida Pwr;6 Light Co 4-23-76 Miami, Fla DATE RECEIVED R E Uhrig EILETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED QORIGINAL CI VNC LASSIF I ED none signed Qcopv .

DESCRIPTION ENCLOSURE Ltr trans the following license event report: 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 FOR ACTION/INFORMATION ENVXRO 5-10" 76 ehf BRANCH CHIEF'I usa nn 3 CYS FOR ACTION LIC ~ ASST:

M/ CYS ACRS CYS QQKELW4/ ENT TO LA INTERNAL DISTRIBUTION EG PILE NRC PDR 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 EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR: I=i I c.v ~

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P.O. BOX 3100 MIAMI, FLORIDA 33101 I ~l'~ ~~+ I.U Sp~

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.~rigjij Li FLORIDA POWER & LIGHT COhIPAi'IY

.'B April 23, 1976 9

PRN-LI-76-97 joe CU Mr. Norman C. Moseley, Director, Region II c Office of Inspection and Enforcement I 00CNGIl3 U. S. Nucle'ar Regulatory Commission uSI4RC 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303 M~~5 )076' RE~

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Dear Mr..Moseley:

CgagkAB IAou >

'v OCCURRENCE 335-76 7 'EPORTABLE 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 1

Program Control (3)

HELPING BUILD FLOFIIOA

V f

LICENSEE EVENT REPORT ~

I'>> ~ ~

CONTROL BLOCK: SE PRINT ALL REOUIRED INFORMATION) 6 UCENSEE LICENSE EVENT NAME LICENSE NUMBER TYPE TYPE

~01 F L 4 L s 1 0 0 0 0 0 0 0 0 0 4 I. I. a I. ~OS

~

7 89 14 15 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE 'OCKET NUMBER ~ EVENT OATS REPORT DATE

[OD~ICoN'7 L ~L 0 5 0 0 3 3 5 0 3 2 5 7 6 0 4 2 3 7 6 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

@~2 While erformin reo erational testin of the Reactor Protection S stem 7 8 9 Bo 7

[oO~]

89 p i em rature indication was 80

+04 observed. Subseauent review of Reactor Coolant S stem RCS loo N'0 7 8 9 80 IOOI tern erature wirin dia rams revealed an error. The olarit of th'

'7 89 80 Jog "7 89 PRME SYSTEM CAUSE CCMPONENT COMPONENT CODE CODE COMPONENT CODE . SUPPUER MANUFACTURER 7

[oO~] [iiaJ 8 9 10

~o 11 12 z N S R U 17

. N 43 44 G 0 8 0 47 CAUSE OESCRIPTION

~os e c was ca s d an e or in the RCS loo tern erature 7 8 9 80 Iossj 7 8 9 Bo

~10 7 89 FACILITY METHOD OF 80 STATUS "  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION jg~ ~s LJoaoo J NA Preo erational Test 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT KQs 7 8 LJs'~l RELEASEO 9

OF RELEASE 10 11 AMOUNT OF ACTIVITY NA 4s LOCATION OF RELEASE NA 80 PERSONNEL, EXPOSURES 7

Q~g 89

[gJ i~

NUMBER 11 TYPE

'z 12 13 OESCRdoTION NA 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~i4 89

[0000 J NA 7 11 12 80 PROBABLE CON SEQUEN'CES Qs] NA 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION z NA 7 89 10 80 PUBLICITY 7

7 89 89 AOOITIONAL FACTORS'ti NA n

eo 7 89 eo M. A. Schoppman 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).