ML18110A624

LER 1976-004-00 for Saint Lucie Unit 1, a Breach of Containment Integrity

ML18110A624
Person / Time
Site:	Saint Lucie
Issue date:	04/05/1976
From:	Schmidt A D Florida Power & Light Co
To:	Moseley N C NRC/IE, NRC/RGN-II
References
PRN-LI-76-70 LER 1976-004-00
Download: ML18110A624 (6)

Text

NRC FORM 195 I2 70)U,S.NUCLEAA REGULATORY COMMISSION DOCKET NUMBFR 50-335 NRC DISTRIBUTION FDR P T 50 DOCI(ET MATERIAL FILE NUMBEA INCIDENT REPORT TO: N.C.Moseley FRY>: Flordia Power 8 Light Co.Miami, Flordia A.D.Schmidt DATE OF DOCUMENT 4-5-76'ATE RECEIVED 4-15-76 QLETTER Q ORIGINAL.SCOPY QNOTOAIZED SUNCLASSIFIED PROP INPUT FORM NUMBER OF COPIES RECEIVED DESCRIPTION Ltr.trans the following.......

30 ENCLOSURE Reportable Occurrence 0 76 4iLicensee Event Report on 3-5-76;Concerning the Containment Vacuum Relief.'Mve Opening.......

(30 Cys.Received-No original)PLANT NAME: St.Lucie III 1 ACKNOWLEI)GEg P I DO NOT RZMOVH NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J.COLLINS SAFETY BRANCH CHIEF: W 3 CYS FOR ACTION LIC~ASST: W/CYS ACRS CYS NFORMATION 1ggS/ENT TO LA FOR ACTION/I Ziemann" ENVIRO INTERNAL 0 IST Rl BUTION NRC PDR I&E 2 SCHROEDER/IPPOLITO 0 NOVAK CHFCK S S HWEN ER TEDESCO NACCA BAER SHAO OLLMER BUNCH KRE E OL N LPDR4 TIC NSIC EXTE RNAL D I STR I BUTI ON CONTROL NUMBER, 3813 NRC FORM ISS I2-70I

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'4C 11 pit IiQCK0%/MQAC II (t.C.SAX S100 MIAALI, FLORIDA MIDI~zsVIJ@'~"i'~M FLORIDA POWER 8s LIGHT CO!eIPAiNY April 5, 1976 PRN-LI-76-70

%a,W<3~~arg i atDQ Mr.Norman C.Moseley, Director, Region II Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission 230 Peachtree Street, N.N., Suite 818 , Atlanta, Georgia 30303

Dear Mr.Moseley:

.gi6~10 lg REPORTABLE OCCURRENCE 335-76-4 ST.LUCIE UNIT 1 DATE OF OCCURRENCE:

MARCH 5, 1976 BREACH OF CONTAINMENT INTEGRITY 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,~chmi t 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)HELPING BUILD FLOFIIOA

'll'ji i/~'~0 Q'~~IfH'4 4 44\ediesi'4LJI I I V I I 0 I I II~M I~~CONTROL BLOCK: 1 6 LCENSEE NAME LCENSK NEIMBER[aa~]F l.s l.s 1 o o-o iI'0 o o.7 89 14 15 REPORT REPORT.CATEGORY TYPE SOURCE~OOCXKT NUMBER~0>CON<~L~L 0 5 0-0 3 7 8 57 58 59 60 61 EVENT OESCRIPTION Qo g Durin initial core loadin , a containment (P E PRINT ALL REQUIRED INFORMATION/

LE:ENSE EVENT TYPE TYPF.0 I 1 1 1 1~03 25 26 30 31 32~EVENT OATE REPORT OATE 3 5 0 3 0 5 7 6 0 4 0 5 7.6 68 69 74 75 60 ur e fan was started and containment pressure 7 8 9 a GQ QOg became subatmos heric causin a Containment Vacuum Relief Valve to o en.This was in 7 89~04 4 w re u r 60 at dur 7 8 9@~5 refuelin.ooerations, there be no direct access from containment to the outside 7 8 9~06 atmosohere which is inca able of automatic isolation.

In order to rotect the GO..60 7 8 9 SYSTEM CAUSE CQQE COO E COMPONENT CQOE ICOVI~so~F z z z z z 7 8 9 10'11 12 CAUSE OESCRIPTION gg Soecification 3.9.4 does not~E COMPONENT SUPERB z~z 17 43 VQEATON z9 9 9~N 47 48 consider the uni ue function of the Containment Vacuum 60 7 8 9 Re i f Valves.Even thou h containment inta rit is not exactl as described in the 7 8 9 Q~g s ecification when one of these valves o ens, it should be noted that the valves and 60 OTHER STATUS NA NA NA NA 7.89 LOSS OR OAMAGE TO FACIUTY TYPE QESCRPTZN~z'7 89 10 PU8UCITY 7 89 NA NA 7 89 FACUTY STATUS.%POWER EO~LsJ'oo o 7 8 9 10 12 13 FORM QF ACTIVfTY CQATENT RKLEASEO OF RELEASE AMOUNT OF ACTIVITY I I~Z~Z NA 7 9 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRtpnQN

~IS~00 0 Z 7 89 11 12 13 PERSONNEL INJURIES NUMBER OESCRlPTION 7 8 9 11 12 PROBABLE CONSEQUENCES

~15 METHOO OF OtSCOVERY LJ 45 46 44 45 OISCOVERY OESCRIPTQN NA LOCATION OF RELEASE NA 80 60 60 60 80 AOOITIQNAL FACTORS[11B]See Pa e Two for continuation of Event and Cause descriptions.

7 89 7 89 M.A.Scho man PHONE 305/552-3779 CFO eII-CCT REPORTABLE OCCURRENCE 335-76-4 LICENSEE EVENT REPORT PAGE TWO Event'escri tion continued) containment structure from excessive vacuum during all modes of'operation, the Containment Vacuum Relief Valves, by design, do not receive a Contain-ment Isolation Signal (CIS).They do close again when containment pressure approaches atmospheric, however, they are not capable of being closed auto-matically by CIS.The immediate corrective action was to suspend core loading until the valves were closed.Loss of containment integrity under the conditions of Technical Specification 3.9.4 occurred on one previous occasion and was described in Reportable Occurrence 335-76-1.(335-76-4).

'Cause 3escri tion (continued) their associated check valves do close automatically when containment pres-.sure approaches atmospheric..Thus, actuation of the relief valves for the purpose of.performing their design function (protection of the containment from excessive vacuum)does not violate the concept of containment integrity because there is no outflow of air from containment to the outside atmosphere through the relief valves.'Followup action will be to contact the appropriate office of the NRC for clarification of Technical Specification 3.'9.4.