ML18110A880

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On Off-Site Power
ML18110A880
Person / Time
Site: Saint Lucie NextEra Energy icon.png
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 RM 195 (2-78 f U.S. NUCLEAR REGULATORY CO

.~ATION DOCKET NUMBER So-TO:

~ g. MOS ELEY FROM: FLORDIA POWER

& LIGHT CO MIAMI, FLRODIA A.D. SCHMIDT NPC DISTRIBUTION FDR PART 50 DOCKET MATERIAL 6/16/77 DATE RECEIVED 7/ll/77 FILE NUMBE R INCIDENT REPORT DATE OF DOCUMENT ETTE R RIG INAL QCOPV 0 NOTOR I2 E D

~C LASS IFIE 0 PROP INPUT FORM NUMBER OF COPIES RECEIVED l

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

ENCLOSURE ITION (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 BRANCH CHIEF:

W 3 CYS FOR ACTION LIC ASST0' CYS ACRS CYSUKLDXHG S NT FOR ACTION/INFORMATION NRC PDR I & E 2

MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES INTERNALD ISTRIBUTION BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BURGH KREGER/J ~ COLLINS LPDR:

TIC:

N EXTERNALDISTRIBUTION CONTROL NUMBER 77 1 93O4' 0

NRC FORM 19B {2.76)

. O. BOX 013100, MIAMI, FL 33101 Q~Ihi i CZ FLORIDAPOWER 5 LIGHTCOMPANY June 16, 1977 PRN-LI-77-188 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U.

S. Nuclear Regulatory Commission 230 Peachtree

Street, N. W., Suite 1217 Atlanta, Georgia 30303 igpgIItgpIII Dppkpt FIla

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

CONTROL 8LOCK:

lCENSEE EVENT REPORT (PL -

SE PRINT ALLREQUIRED INFORIItIATIDN)

IUCENSEE NAME 01 F

iL S

L S

1 0

7 89 14 15 LCENSE TYPE 1

1 1

25 26 UCENSE NUMBER 0

0 0

0 0

0 0

0 EVENT TYPE

~o 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE

~o 1 CON'T~

L L

7 8

57 58 59 60 EVENT OESCRIPTION

~

DOCKET NUMBER EVENT DATE REPORT DATE 0

5 0 0 3

3 5

0 5

1 6

7 7

0 6

1 6

7 7

61 68 69 74 75 80 in man a

ri due to i di rb es a

7 89

~0 3 s stem undervolta e condition occurred with the subse uent loss of all four reactor 7

89 80 Qp41 7

89

[oasj 7

8 9 tOOI 7

8 9 SYSTEM CAUSE CODE CODE COMPONENT CODE

[oczI ~zz

~c z

z z

z z

z 7

8 9 10 11 12 17 CAUSE OESCRIPTION Loss of normal RCS flow was caused 0

a d

FAME COMPONENT SUPPUER COMPONENT MANUFACTURER Z

9 9

9 er ff-N 48 b

a loss of off-site ower'oss of off-site ower 80 METHOD OF DISCOVERY A

44 45 46 44 45 NA NA 7

8 9 Qg was associated with a FP&L rid disturbance.

7 8 9

[iioj 7

89 FACIUTY STATUS 4C POWER OTHER STATUS Log Loco oo lI NA 7

8 9

10 12 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY G~H LzJ LzJ NA 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~>> ~oo z

7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION

~4 ~oo 7

89 11 12 DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80 80 PROBABLE CONSEQUENCES EZ I

NA 7

8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION

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

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

7 89 AOOITIONAL FACTORS Q~ I See a

e two for continuation of Event Descri tion.

7 89 80

~80 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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