ML18110A606

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

ML18110A606
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: ML18110A606 (5)

Text

U.S. NUCLEAR BEGULATOBV C 'IISSION DOCKET NUMBER NRC roBM 195 I2 7G) HO- .

.FILE NUMBER NRC DISTRIBUTION roB PART 50 DOCI(ET MATERIAL XNCIDENT REPORT DATE OF DOCUMENT Mr Moseley 'Florida Pwr & 7.ight 4.-26-76 Fla Co'iami, DATE RECEIVED 76 A D Schmidt 5 Q uLETTEB QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED 0 ORIGINAL SUNG LASS IF I E D,

.none signed RScopv DESCRIPTION ENCLOSURE Ltr,trans the following: /

License Event Rpt'RON76.-6) on 3-26-76 concern-ing technical specifications .time lait whr'eI.

.exceedea during Mansition from shutdown cool-ing pumps 'to reactor coolant -pumps............

(1 cy encl. rec'd)

PLANT NAME: St Lucie gl NOTE. IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGFR/J ~ COLLINS SAFETY FOR ACTION/INFORMATION ENVIRO >-L -/o enr BRANCH CHIEF:

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@we FLOEIIDA POVlER 2 LlGHT COVPAiIY April 26, 1976 PRN-LI-76-98 Mr. Norman C'. Moseley, Director, Region Office of Inspection and Enforcement II U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. W., Suite 818 S, NUCLEAR SEQlLAEOII$

EI COMAIISS IDN Atlanta, Georgia 30303 $1oII Sod Io~

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Dear Mr. Moseley:

REPORTABLE OCCURRENCE 335-76-6 ST. LUCIE UNIT 1 DATE OF OCCURRENCEs MARCH 26, 1976 TECHNICAL SPECIFICATION TIME LIMIT EXCEEDED DURING TRANSITION FROM SHUTDOWN COOLING PUMPS TO REACTOR COOLANT PUMPS The attached Licensee Event Report is being submitted in accordance with Technical Specification 6.9 to prov'de *30=day notification of the subject occurrence.

Very truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Jack R. Newman, Esauire Director, Office of Inspection and Enforcement {30)

Director, Office of Management Information and Program Control (3)

L1CENSEE B/ENT REPORT V ~ ~

CONTROL BLOCK: SE PRINT ALL REQUIRED INFORMATION)

UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE F L dS- L S 1 4 1 1 1 ~03

~

,7 89 14 15 25 26 30 31 32 REPORT. REPORT CATEGORY TYPE SOURCE ~ 'OCKET NUMBER ~ EVENT DATE REPORT DATE

[OD1J CON'T ~L 0 5 0 0 2 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION Jog 7 8 9 80

[OD3] ressurizer. When reactor coolant s stem ressure was about 268 sia the Low-Pressure 7 89 80

~04 Safet In ection LPSI um s were sto ed because the m ximum ressu e o utd T 7 8 9 80

[OD~] coolin (SDC) o eration is 268 sia. The transition from SDC o eration to reactor 7 8 9 eo Qp 6 coolant pump (RCP) operation took a roximatel 35 minutes. Technical S ecification 7 8 9 PRME (cont.d')

SYSTEM CAUSE COMPONENT COMPONENT COOE CODE COMPONENT COOE SUPPLER MANUFACTURER

[Cori ~CF P P U N P X A I 0 7 5 7 89 10 11 . 12 17 43 44 47 48 CAUSE OESCRIPTION Qg8 The cause of this occurrence was that more than 15 minutes was needed to verif that a 7 9 reeeurdzer bubble had been d aun and that RC teenerature and 7 8 9 80 Q4 0 a ro riate limits before ener izin RCP's. 15 minutes is considered insufficient time 7 89 FAC'AITY METHOO OF 80 STATUS POWER OTHER STATUS OSCOVERY OISCOVERY OESCRIPTION R ~OO O NA 7 8 9 10 12 13 44 45 46 80 FORM OF ACTMTY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Bl8 7

LJ 9

LJ 10 11 NA 44 45 NA 80

'a PERSONNEL EXPOSURES e'7 NUMBER TYPE OESCRIPTlON 7

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89

~IJJJ 11 z

12 13 eo PERS'ONNEL INJURIES NUMBER OESCRIPTION

~4 ~oo o NA 7 89 11 12 80 P+QBPJ3LE CONSEQUENCES

~15 NA 7 8 9 80 LOSS OR OAMAGE To FACILITY TYPE OESCRCPTION z NA 7 89 10 80 PU8LICITY NA 7 8 9 .eo AOOITIONAL FACTORS'~

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

7 89 80 7 89 eo NAME M. A. Schoppman 305/552-3779 Cl'0 dd'I ~ 44T

.'eportable Occurrence Licensee Event Report 76-6 O.

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 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.