ML18113A297

LER 1976-045-00 for St. Lucie Unit 1, During Plant Heatup, Low Pressure Safety Injection Pumps Were Stopped When System Pressure Had Been Raised Above 250 Psia

ML18113A297
Person / Time
Site:	Saint Lucie
Issue date:	12/28/1976
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
PRN-LI-76-313 LER 1976-045-00
Download: ML18113A297 (8)

Text

NRC FDRM 195 U.S. NUCLEAR REGULATOR MISSION DOCKET NUMBER I2-76 I 50-335 FILE NUMBER NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL INCIDENT REPORT TO:

Norman C. Moseley FROM: Florida Power 8a Light Co. DATE OF DOCUMENT Miam'1, Florida 33101 12-28-76 A.D. Schmidt DATE RECEIVED 1-14-77 LETTER ClNOTORIZED PROP INPUT FORM NUMSER OF COPIES RECEIVED

~ORIGINAL J5NCLASSIF I ED QCOPV 1 signed. org.

DESCRIPTION Ltr. Trans The Following: Licensee Event Report (RO-50-'335/t76

45) onll-28-76 concerning (LPSI) pumps vere stopped. when sys'em pressure raised. above 250 psia due to fifteen minute transitoion time limit was exceeded.. ~ .

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PLANT NAME. ST LUCIE UNIT l ~~P~7

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ACKNOWLEDGED DO NOT REMOVE NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION

'BRANCH CHIEF!

W 3 CYS. FOR ACTION LIC, ASST':

W ACRS

$ CYS CYS 5 i' INTERNAL DISTRI BUTION REG FILE

'NRC PDR I &E 2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY Jt EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBER LPDR TIC:

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P. 0) BOX 013100, MIAMI, FL 33101 I

FLORIDA POWER & LIGHT COMPANY Oj,418v~ December 28, 1976 sea@55 PRN-LI-76-313 n

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~D Mr. Norman C. Moseley, Director, Region Office of Inspection and Enforcement II go~ac u~

U. S. Nuclear Regulatory Commission 1 <np 230 Peachtree Street, N. W., Suite 818 gi Atlanta, Georgia

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30303

Dear Mr. Moseley:

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REPORTABLE OCCURRENCE 335-76-45 ST. LUCIE UNIT 1 DATE OF OCCURRENCE: NOVEMBER 28, 1976 ll SHUTDOWN COOLING 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. 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)

PEOPLE... SERVING PEOPLE

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LICENSEE EVENT REPORT 1

CONTROL 8LOCK: LEasE PRwT aU. REauIREn INFORMaTIom) 6 UCENSEE UCENSE EVENT UCENSE NUMBER TYPE TYPE 0 0 0 0 0 4 1 1 1 1 ~03

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,7 89 14 15 26 30 31 32 REPORT REPORT CATEGORY OOCKET NUMBER EVENT OATE REPORT OATE l l TYPE SOURCE

~01 CCN'I ~L L 0 5 0 0 3 3 5 2 8 2 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION

[oOz] Durin lant heatu , the Low Pressure Safet In'ection (LPSI um s were 89 80

[OD3] sto ed when s stem ressure had been raised above 250 sia. The LPSI 7 89 t004] um s which are also used for shutdown coolin SDC were sto ed 7 8 9 80 Qo 5 because the maximum ressure for shutdown coolin s stem o eration is 7 8 9 80 268 sia. Transition to the. Reactor Coolant Pumps RCP's was de av 7 8 9 PRME 80 SYSTEM CAUSE COMPO N&lT COOE COOE COMPONENT COOE SUP PLGI MANUFACTURER IQD>] ~CF A .P U M PX X B 5 8 0 N 7 8 9 10 11 12 17 44 47 48 CAUSE OESCRIPTION 7 8 9 The fi t m' ra

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i io time imi was exceed 80 tOOI on the 6.9 KV buses which revented o erations ersonnel from immediatel 7 8 9 7

Q~O 89 startin RCP '. 0 erations ersonnel have been instructed on the 80 METHOO OF OTHER STATUS OISCOVERY OISCOVERY DESCRIPTION 7

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lZaLJ 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE EH LiJ LiJ N A N A 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 PERS'ONNEL INJURIES NUMBER "'ESCRIPTION

~~4 ~00 0 N A 7 8 9 11 12 80 PROBABLE CONSEQUENCES N A 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCR:PTION z N A 7 89 10 80 PUSLICITY N/A 7 8 9 80 AOOITIONAL FACTORS 7 89 aio o D s ri 'on and ause Descri tion.

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'7 89 80 NAME. M. A. Scho man PHONE. 3 05 552-37 79 CPO ddt ddT

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Reportable Occurrence 335-76-45 Licensee Event Report Page Two Event Descri tion (Continued) because the 6.9 KV buses from which they .receive power were de-energized. The 6.9 KV buses were energized and the RCP's were started, but the transition from SDC to RCP operation exceeded the fifteen minute time limit of Technical Specification 3.4.l. Similar occurrences which involved ex-ceeding the time allowed for transition from SDC to RCP operation were described in Reportable Occurrences 335-76-6, 335-76-40, and 335-. 76-41, however, this was the first such occurrence caused by the 6.9 KV buses being de-energized.

(335-76-45).

Cause Descri tion (Continued) importance of ensuring proper initial conditions at the beginning of plant evolutions.

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