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 Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
PRN-LI-76-70 LER 1976-004-00
Download: ML18110A624 (6)

Text

NRC FORM 195 U,S. NUCLEAA REGULATORY COMMISSION DOCKET NUMBFR I2 70) 50-335 FILE NUMBEA NRC DISTRIBUTION FDR P T 50 DOCI(ET MATERIAL INCIDENT REPORT TO: FRY>: Flordia Power 8 Light Co. DATE OF DOCUMENT N.C. Moseley Miami, Flordia 4-5-76 A.D. Schmidt RECEIVED

'ATE 4-15-76 QLETTER QNOTOAIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED Q ORIGINAL . SUNCLASSIFIED SCOPY 30 DESCRIPTION ENCLOSURE Ltr. trans the following....... Reportable Occurrence 0 76 4iLicensee Event Report on 3-5-76;Concerning the Containment Vacuum Relief.'Mve Opening.......

(30 Cys. Received - No original)

ACKNOWLEI)GEg P I DO NOT RZMOVH PLANT NAME: St. Lucie III 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO BRANCH CHIEF: Ziemann" W 3 CYS FOR ACTION LIC ~ ASST: 1ggS W/ CYS ACRS CYS / ENT TO LA 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 EXTE RNAL D I STR I BUTION CONTROL NUMBER, LPDR4 TIC NSIC 3813 NRC FORM ISS I2-70I

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FLORIDA POWER 8s LIGHT CO!eIPAiNY II

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MQAC April 5, 1976 PRN-LI-76-70

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Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. N., Suite 818 . gi6~ 10

, Atlanta, Georgia 30303 lg

Dear Mr. Moseley:

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

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CONTROL BLOCK: (P E PRINT ALL REQUIRED INFORMATION/

1 6 LCENSEE LE:ENSE EVENT LCENSK NEIMBER TYPE TYPF.

[aa~] F l. s NAME

l. s 1 o o o iI'0 o o 0 I 1 1 1 1 ~03 32

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.7 89 14 15 25 26 30 31 REPORT REPORT CATEGORY TYPE SOURCE OOCXKT NUMBER ~ EVENT OATE REPORT OATE 7.6

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L 0 0 0 3 0 5 7 6 0 4 0 5

~0> CON< ~L 0 5 3 3 5 7 8 57 58 59 60 61 68 69 74 75 60 EVENT OESCRIPTION Qo g Durin initial core loadin , a containment ur e fan was started and containment pressure GQ 7 8 9 a QOg became subatmos heric causin a Containment Vacuum Relief Valve to o en. This was in 7 89 60

~04 4 w re u r at dur 7 8 9 GO

@~5 refuelin ooerations, there be no direct access from containment to the outside

.. 60 7 8 9

~06 atmosohere which is inca able of automatic isolation. In order to rotect the 7 8 9 SYSTEM CAUSE

~E COMPONENT 60 CQQE COO E COMPONENT CQOE SUPERB VQEATON ICOVI ~so ~F z z z z z z ~z z9 9 9 ~N 7 8 9 10 '11 12 17 43 47 48 CAUSE OESCRIPTION gg Soecification 3.9.4 does not consider the uni ue function of the Containment Vacuum 7 8 9 60 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 7 89

'oo FACUTY METHOO OF STATUS .  % POWER OTHER STATUS OtSCOVERY OISCOVERY OESCRIPTQN EO~

7 8 LsJ 9 10 o

12 13 NA LJ 45 46 NA 80 FORM QF ACTIVfTY CQATENT RKLEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE I I ~Z ~Z NA NA 7 9 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE OESCRtpnQN

~IS ~00 0 Z NA 60 7 89 11 12 13 PERSONNEL INJURIES NUMBER OESCRlPTION NA 7 8 9 11 12 60 PROBABLE CONSEQUENCES

~15 NA 7 .89 60 LOSS OR OAMAGE TO FACIUTY TYPE QESCRPTZN

~z NA

'7 89 10 80 PU8UCITY NA 7 89 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.

will be Followup action to contact the appropriate office of the NRC for clarification of Technical Specification 3.'9.4.