ML18110A477

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

ML18110A477
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: ML18110A477 (5)

Text

U.S. NUCLL'AB REGULATORY AMISSION DOCKET NUMIIEA I NRC FOBr~i.1JB I7 7GI I 50<<335 I-ILE NUMBER NRC DISTRIBUTION FDR PART 50 DOCI(fT MATfRIAL XNCXDENT REPORT TO: 'FROM: DATE OF DOCUMENT FLORIDA POWER & LIGHT CO 4/23/76 MR; NORMAN CD MOSELEY MIAMI~ FLORIDA DATE RECEIVED A D SCHMXDT 5/12/76 BETTE A ONOTOBIZED PROP INPUT FORM NUMOE B OF COP ILS,RE CE I VE0

'BORIGINAL QUNC LASSIF I ED ONE'IGNED QCOPY DESCRIPTION ENCLOSURE

- LTR, TRANS ~ THE FOLLOWING: 'ICENSEE 3/25/76 EVENT RPT, (RO 50-335/76-7) ON CONCERNING AN ERROR IN THE RCS LOOP TEMP ~ WIRING DIAGRAMS CAUSXNG ERRACTXC REACTOR'COOLANT'LOOP TEMPERATURES ~

ACKNOWLEDGED.

DO NOT REM0yE PLANT NAME: NOTE: XF PERSONNEL EXPOSURE XS XNVOLVED SEND DIRECTLY TO KREGER/J. COLLINS ST, LVCXE 81 SAFETY FOR ACTION/INFORMATION ENVXRO 5 13 76 - R JL 1IRANCH CHIEF: ZIEMANN W 3 CYS FOR ACTXON LXC ~ ASST: DIGGS W/ CYS ACRS CYS HOLDING/ ENT TO LA INTERNAL 0 ISTR I BUTION EG FIT I NRC PDR X & E 2 gZ=-

SCHROEDER/IPPOLXTO 0 8~0 NOVAK CHECK

('R ES NEN E

~Sj".

3RJMLEE 8AI'.R SIIAO VOLLMER~BUNC1 kREQ~E~OL/i NS EXTERNAL DISTRIBUTION CONTROL NUMBER 1.PDR: FT, PIERCE~ FL ~

TXC NSXC 4799 NAC f'OAM 196 I7.7GI

L I'

1 V a I 1 A%

~ IP h

l

~

(

t C C

C

tP.O, BOX 3100 MIAMI, FLORIDA 33101

'Its FLORIDA POWER 5 LIGHT COMPANY April 23, 1976 PRN-LI-76-97

.1 Mr."...Norman C. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303 tO

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-76-7 ST. LUCIE UNIT 1 DATE OF'CCURRENCE: MARCH 25, 1976 WIRING DIAGRAM ERROR

~q8 (Th INSTRUMENT) gNg0g 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,

+OJ A. D. Schmidt Vice President Power Resources

'K <<b.'g12$

Qi5o

~Pi, 510 ggI5SIOI MAS/cpc C~OI ~Io Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and Program Control (3)

~~CONTROL BLOCK: (PLEA RINT ALL REQUIRED INFORMATION'J UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE 89 F L S L S l14 15 0 0 0 0 0 0 0 0 0 25 26 4 1 1 1 1 30

~03 31 32 REPOAT. REPOAT REPORT DATE CATEGORY TYPE SOURCE ~

DOCKET NUMBER EVENT OATE

)1 CON'T~

L L 0 5 0 0 3 3 5 0 3 2 5 7 6 0 4 2 3 7 6 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 80 89 3 p rature indication was 8 9 80 4 observed. Subse uent review of Reactor Coolant S stem RCS loo 8 9 80 tern erature wirin dia rams revealed an error. The olarit of the 8 9 80 6

8 9 PAME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUEA MANUFACTURER 7 IIIAj B I N B R 0 17 N G 0 8 0 47 8 9 10 11 12 CAUSE OESCRIPTION r enc w s a s d b an r or in the RCS loo tern erature 8 9 80 9

8 9 80 I 0 89 60 FACILITY METHOO OF STATUS POWER OTHER STATUS DISCOVERY OISCOVERY OESCAIPTION B ~00 0 NA C Preo erational Test 8 9 10 12 13 44 45 46 60 FORM OF ACTIVITY COATENT RELEASEO OF AELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 2 Z NA NA 8 9 10 11 44 45 80 PERSONNEL EXPOSURES I3 89

~i~ NUMBER 11 TYPE 12 Z

13 DESCRIPTION 80 PERSONNEL INJURIES NUMBER DESCRIPTION I 4 ~00 0 NA 60 89 11 12 PROBABLE CONSEQUENCES I5 NA 80 8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION z NA 89 10 80 PUBLICITY NA 8 9 .80 AOOITIONAL FACTORS tion 80 8 9 89 80

REPORTABLE OCCURRENCE 3 3 5-7 6-7 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued) 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).