ML18110A609

LER 1976-006-00 for St. Lucie Unit 1, Technical Specification Time Limit Exceeded During Transition from Shutdown Cooling Pumps to Reactor Coolant Pumps

ML18110A609
Person / Time
Site:	Saint Lucie
Issue date:	04/26/1976
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
PRN-LI-76-98 LER 1976-006-00
Download: ML18110A609 (6)

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I C'r onM I7.7!II 194 NRC DISTRIBUTION ron PABT 50 DQCICET MATERIAL F IIOM:

I~UCLL'An ncGULATonv FLORIDA POWER & LIGHT co COMPANY ssioN OOCKGT NUM(IL'n 50-335 IiILF. NUM!I!In XNCXDEIIT REPORT OATC OF OOCUIAFNT 4/26/76

'MR, NORMAN C ~ MOSELEY OATF. RECDIVL'O MIAMI~ FLORIDA AD H GHHIDIIIO~~~'".7 5/4/76 NLL=TTEB 0 NOTofli7 C 0 pnop INPUT FORM NUMOFB or. cor IES ReccivFO I QfonIGINAL QkUNC LASSII'IEO ~ ONE 'SIGNED Qcopv I OSSCBIPTION LNCI.OSU BC I',

LTD TRANS THE FOLLOWING:, LICENSEE EIJENTJgT. (RO 50'-335/1976-6') ON .

3/26/76 'CONCERl43,"NG 3 ~ 4 ' ' PERMITS OPERATION IN MODES', 4 & 5 FOR A MAXIMUM OF 15 MINUTES WITH NO SHUTDOWN.QOOLXNG (LPSI) PUMP OR. RCP,

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9 FLORIDA POWER 5 LIGHT COMPANY April 26, 1976 d e~la~eJRRe ~ ~

PRN-LI-76-98 8

~l:y,ETE0 6 Mr. Norman C. Moseley, Director, Region II 1I)11IIQ Office of Inspection and Enforcement 8 IIIg P IS7S 9 U. S. Nuclear Regulatory Commission .

QQVLA1 230 Peachtree Street, N. W., Suite 818 Atlanta, Georgia 30303

Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-76-6

'ST. LUCIE UNIT 1 DATE OF OCCURRENCE: MARCH 26, 1976 TECHNICAL SPECIFICATION TIME LIMIT EXCEEDED DURING TRANSITION FROM SHUTDONN COOLING PUMPS TO REACTOR COOLANT PUMPS 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, gg1 A. D. Schmidt q8~

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 FLORIDA

LICENSEE EVENT REPORT CONTROL BLOCK:

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(PLEASE PRINT AI.L REQUIRED INFORMATION) 1 UCFNSEE LICENSE EVENT NAME UCENSE NUMBER TYPE TYPE F L S L S 1 4 1 1 LoOJ

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.7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE ~

OOCKET NUMBER EVENT OATE REPORT DATE I001] CON'7 ~L ~L 0 5 0 0 2 7 8 57 58 59

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60 61 68 69 74 75 80 EVENT DESCRIPTION

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7 8 9 80

~0 3 ressurizer. When reactor coolant s stem ressure was about 268 sia the Low-Pressure 89 80 f74 Safet In ection LPSI um s were sto ed because the maximum re u o utd 7 8 9 80

~0 5 coolin (SDC) o eration is 268 sia. The transition from SDC o eration to reactor 7 8 9 80 Qp g coolant pump (RCP) operation took a roximatel 35 minutes. Technical S ecification 7 8 9 SYSTEM CAUSE PRME COMPONENT COMPONENT (cont.d')

COOE COOE COMPONENT COOS SUPPUER MANUFACTURER

~07 ~CF ~F P' M P 7t A I 0 7 5 N 7 8 9 10 11 12 17 44 47 CAUSE DESCRIPTION

[ODg The cause of this occurrence was that more than 15 minutes was needed to verif that a 7 8 9 80 tOOI ressurizer bubble had been drawn and that RC Le erature and 7 8 9 80 a ro riate limits before ener izin RCP's. 15 minutes is considered insufficient time 7 89 FACIUTY 80 METHOO OF STATUS 96 POWER OTHER STATUS OSCOVERY OISCOVERY OESCRIPTION 7

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12 13 NA 44 a NA 45 46 80 FORM OF p ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Qg Lzl ~z NA NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7

C<03 89

~IJII 11 lZJ 12 13 80 PERSONNEL INJURIES NUMBER 89'1 OESCRPTION Qg~0. o o NA 7 12 80 PROBABLE CONSEQUENCES Qg 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION

~16 Z NA 7 89 10 80 PUBLICITY NA 7 89 .80 ADDITIONAL I

FACTORS'~

See Pa e Two for continuation of Event and Cause descri tion.

7 8 9 80 7 89 80 NAME. M. A. Schoppman 305/552-3779 GPO Gent GGT

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Reportable Occurrence 3 76-6 Licensee Event Report Page Two Event Descri tion (continued) 3.4.1 permits operation in Modes 3, 4, and 5 for a maximum of 15 minutes with no shutdown cooling (LPSI) pump or RCP in operation. This was the first occurrence of this type. (335-76-6).

Cause Descri tion continued) to perform the transition from SDC 3 operation to RCP operation. Followup action will be to submit a request to amend the Technical Specifications to extend the time limit for transition from SDC operation to RCP operation in Modes 3, 4, and 5.