ML18110A881

LER 1977-335-23 for St. Lucie, Unit 1 on RCS Flow

ML18110A881
Person / Time
Site:	Saint Lucie
Issue date:	05/13/1977
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
LER 1977-335-23
Download: ML18110A881 (8)

Text

NRC FO'iM 195 U.S. NUCLEAR REGULATORY COMMiSSION DOCKET NUMBER (2.78) s., ~

FILE NUMBER

, NRC DISTRIBUTION FQR PART 50 DO CKET MATERIAL INCIDENT REPORT DATE OF DOCUMENT TO'.C MOSELEY FRONI: FLORDIA POWER & LIGHT CO.

MIAMI," FLORDIA A.D. SCHMIDT. .DATE RECEIVED GI.ETTE R ONOTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED

&ORIGINAL CfUNCLASSIFIED 0 COPY DES C RIP T I 0 N ENCLOSURE LTR TRANS THE FOLLOWING.. '....... LICENSEE EVENT REPORT FOR R.O./f 77-g3, ON 4/15/

77 CONCERNING THE CONTAINMENT -INSTRUMENT A'IR )

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'1P) SYSTEM (2P)

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<ACKWOWr,ZDGF.O NOTE. IF PERSONNEL EXPOSURE IS INVOLVED

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SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTION LIC ASSTo:

W / CYS ACRS CYS INTERNAL D IST Rl BUTION NRC PDR I&E(2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:

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NRC FORM )98 I2.78)

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FLORIDA POWER & LIGHT COMPANY SZ) - isa May 13, 1977 PRBI-LI-77-147 gggg~mg 90Gt(G FIK@5 8

Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement, Afcfivfl3 U. S. Nuclear Regulatory Commission JUX ZS tg77 230 Peachtree Street, N. W., Suite 1217 N>h HUQEAR RE~zyg, Atlanta, Georgia 30303 l5fl

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-77-23 ST. LUCIE UNIT 1 DATE OF OCCURRENCE APRIL 15i 1977 RCS FLOW 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, D. chmidt Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (30)

Director, Office of Management Information and Program Control (3) 7i6SOg22 PEOPLE... SERVING PEOPLE

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CENSEE EVENT REPORT CONTROL BLOCK: (PL SE PRINT ALL REQUIRED INFORMATION)

J 1 ucENsEE INCENSE EVENT NAME LICENSE NUMBER TYPE TYPE F L S L S 1 0 0 0 0 0 0 0 4 1 1 1 1 ~0 89

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7 14 15 25, 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE ~

OOCKET NUMBER EVENT OATE REPORT OATE

~01 CON'T ~L ~L 0 5 0 0 5 5 5 0 4 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

~0 2 Durin normal lant o erations the Containment Instrument Air S stem failed causin los 89 80 gg of control of all air-o crated valves in the containment. This result d in the loss of 7 8 9 80

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7 8 9 seal coolin water to the Reactor Coolant Pum s. The Reactor was tri ed and Reactor 80 Qg8 o an P m s were secured'. Air ressure was restored to he containmen 7 9 80 Jog 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT COOE COOS COMPONENT COOE SUPPUER MANUFACTURER

~PA ~E B I 0 W E R ~A N 0 1 0 N 7 8 9 10 11 12 17 43 44 47 48 CAUSE OESCRIPTION

~08 o n inm i trument air c ressor faile d 0 f e 7

7 8 9 8 9 ir o sta ed b due o h er i air so'. ha e 80 80 Q~ g check valve stickin o en air from the backu corn ressor blew back throu h the failed 7 89 80

~0 METHOO OF FACILITY STATUS '%OWER OTHER STATUS OISCOVERY OSCOVERY OESCRIPTION .

LEJ NA NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AVIOUNT OF ACTIVITY LOCATION OF RELEASE EH L~J L~J NA NA 7 8 9 10 11 60 PERSONNEL EXPOSURES 7 8 9

~oo NUMBER 11 TYPE

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13 OESCRIPTION NA 80 PERSONNEL INJURIES NUMBER OESCRIPTION 7

~14 89 L00 ~0 11 12 NA 60 PROBABLE CONSEQUENCES

'~g NA 7 8 9 60 LOSS OR OAMAGE TO FACILITY TYPE OESCRIPTION L Loss of use of facilit durin re lacement of RCP seals.

7 89 10 80 PUBLICITY

~17 NA 7 8 9 60 ADDITIONAL FACTORS Qg See a e 2 for continuation of Event Descri tion and Cause Descri tion.

7 89 A 80 Qg 7 89 80 NAME M. A. Scho man PHONE 305 552-3802 GPO IIdI ~ III'

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REPORTABLE OCCURRENCE REPORT 335-77-23 LICENSEE EVENT REPORT PAGE TWO EVENT DESCRIPTION (Continued) plant management decided not to restar't the RCP's. The unit was borated to cold shutdown conditions and plant cooldown was made using natural circulation.

The plant was placed on Shutdown Cooling in ten hours. This is being reported under Technical Specification 3.4.3.. This was the first occurrence of loss of RCS flow under hot conditions. (335-77-23).

CAUSE DESCRIPTION (Continued) compressor. Subsequent corrective actions were: (1) to perform complete checkouts on the two compressors, (2) add new discharge check valves, and (3) add a modification to allow turbine building instrument air to auto-matically backup containment instrument air.

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