ML18110A880

LER 1977-335-26 for St. Lucie, Unit 1 on Off-Site Power

ML18110A880
Person / Time
Site:	Saint Lucie
Issue date:	06/16/1977
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
LER 1977-335-26
Download: ML18110A880 (7)

Text

Nh5 (2-78 f RM 195 U.S. NUCLEAR REGULATORY CO .~ATION So-DOCKET NUMBER FILE NUM BE R NPC DISTRIBUTION FDR PART 50 DOCKET MATERIAL INCIDENT REPORT TO: ~ g. MOS ELEY FROM: FLORDIA POWER & LIGHT CO DATE OF DOCUMENT MIAMI, FLRODIA 6/16/77 A.D. SCHMIDT DATE RECEIVED 7/ll/77 ETTE R 0 NOTOR 2 E D I PROP INPUT FORM NUMBER OF COPIES RECEIVED RIG INAL QCOPV

~C LASS IFI E 0 l S I'Qm~M DESCRIPTION ENCLOSURE LICENSEE EVENT REPORT FOR R.0.8 77-26, ON 5/16/77 CONCERNING A SYSTEM UNDERVOLTAGE CO ITION OCCURRING WITH THE SUBSEQUENT LOSS OF ALL FOUR REACTOR COOLANT PUMPS (RCP'S)

(1P & 2P) ga NQT REMOVE PLANT NAME: ST. LUCIE i/ 1

.SAB ACKNOWLEDGED NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTION LIC ASST0' CYS ACRS CYSUKLDXHG S NT INTERNAL D IST RIBUTION NRC PDR I & E 2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BURGH KREGER/J ~ COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR:

TIC:

N 77 1 93O4' 0 NRC FORM 19B {2.76)

. O. BOX 013100, MIAMI, FL 33101 Q~Ihi i CZ FLORIDA POWER 5 LIGHT COMPANY June 16, 1977 PRN-LI-77-188 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission igpgIItgpIII Dppkpt FIla 230 Peachtree Street, N. W., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-77-26 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: MAY 16, 1977 OFF-SITE POWER 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, A. D. Schmidt 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) 771930410 PEOPLE... SERVING PEOPLE

~ i 1

lCENSEE EVENT REPORT CONTROL 8LOCK: (PL - SE PRINT ALL REQUIRED INFORIItIATIDN)

IUCENSEE LCENSE EVENT NAME UCENSE NUMBER TYPE TYPE 01 F iL S L S 1 0 0 0 0 0 0 0 0 0 1 1 1 ~o

7 89

~

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

DOCKET NUMBER EVENT DATE REPORT DATE

~o 1 CON'T L L 0 5 0 0 3 3 5 0 5 1 6 7 7 0 6 1 6 7 7 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION 7 89 in man a ri due to i di rb es a

~0 3 s stem undervolta e condition occurred with the subse uent loss of all four reactor 7 89 80 Qp41 0 a d 7 89 80

[oasj 7 8 9 tOOI 7 8 9 er ff-FAME SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTURER

[oczI 7 8 9 10

~zz ~c 11 12 z z z z z z 17 Z 9 9 9 N 48 CAUSE OESCRIPTION Loss of normal RCS flow was caused b a loss of off-site ower'oss of off-site ower 7 8 9 80 Qg8 was associated with a FP&L rid disturbance.

7 9 80

[iioj 7 89 80 FACIUTY METHOD OF STATUS 4C POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Log Loco oo lI NA A NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE G~H LzJ LzJ NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION 7

~>>

8 9

~oo 11 z

12 13 NA PERSONNEL INJURIES NUMBER DESCRIPTION 7

~4 89

~oo 12 NA 11 80 PROBABLE CONSEQUENCES EZ8 I NA 7 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION

~L Generation ca acit interru ted durin loss of off-site ower.

7 89 10 80 PUSLICITY Q1 7 Media covera e and FPL ress release on Ma 16 1977.

7 89 ~ 80 AOOITIONAL FACTORS Q~

7 I89 See a e two for continuation of Event Descri tion.

80 7 89 NAME. M. A. Scho man PRONE. 305 552-3802 CPO 44l 4 44Ti

c r'+vc-

RRPORTABL'E OCCURRENCE 335-77-26 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued) lost, and a natural circulation RCS cooldown re-commenced. Approximately 1 to 1-1/2 hours later, off-site power was restored, the RCP's were re-started, and a reactor heatup commenced. The plant was restored to a normal configuration within'he time limits specified by the PSL Technical Specifications.

This was the first occurrence of this type associated with a grid disturbance, and is being reported under PSL Technical Specifications 3.4.1 and 3.8.1.1.

(335-77-26)

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