ML18113A311

LER 1976-040-00 for St. Lucie Unit 1, During Reactor Shutdown and Cooldown, Pressurizer Level Would Drop Whenever Either Set of Shutdown Cooling System Suction Valves Was Opened

ML18113A311
Person / Time
Site:	Saint Lucie
Issue date:	08/18/1976
From:	Schmidt A Florida Power & Light Co
To:	Moseley N NRC/IE, NRC/RGN-II
References
PRN-LI-76-218 LER 1976-040-00
Download: ML18113A311 (6)

Text

NRC FOAM 196 ~SION DOCKL'T NUMDE A I2 70I 50-335 FILE NUMBER NRC DISTRIBUTION FoA PART 50 DOCKET MATERIAL INCIDI'5T REPORT TO: FROM: DATE OF DOCUMENT Florida Po~er 6 Light Company 8/18/76 Mr, Norman C. Moseley Miami, Florida DATE RECEIVED A. D..Schmidt 8/31/76 PfLETTEA DNOTOAI7ED PAOP INPUTFOAM NUMOER OF COPIES RECFIVED OOA IGINAI gUNC LASS IF I E D One signed copy PCCOP Y DESCRIPTION ENCLOSURE Ltr. trans the following: Licensee Event Report (RO 50-335/76-40) on 7/18/76 concerning pressurizer'.level dropping whenever either set of shutdown cooling system suction valves were opened, ACKNOWLEDGZD .during reactor shutdown and cooldown.

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PLANT NAME NOTE: IF PERSONNEL EXPOSURE IS INVOLVED

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FLORIDA POPOVER 5 LIGIIT COViPAi4Y August, 18, 1976 PRN-LI-76-218 Mr. Norman C. Moseley, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street, N. N., Suite 818 Atlanta, Georgia 30303

Dear Mr. Moseley:

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REPORTABLE OCCURRENCE 335-76-40 Io 6

ST. LUCIE UNIT 1 DATE OF OCCURRENCE: JULY 18, 1976 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 yoursf pQ COVETED N EQ Vice President II>Sz

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)I-REGUEATOEY,

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COMMISS 10M Power Resources MAS/cpc g 7 Pikgllggg g"(g [(<j >L ~gPy N) cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)

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

e CONTROL BLOCK: h LEASE PRINT ALL REQUIRED INFORMATIQa4)

~UCENSER UCENSE EVENT NAME LCENSE NUMBER FLSLS1 0 ol 00 polo 00 41 3.

TYPE i I 1 1 ~03 TYPE

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7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCK OOCKH'UMBER EVENT OATE REPORT OATE IOD~jOON'7 L L 0 5 0 0 3 315 0 7 1 8 7 6 0 8 1 8, 7 6 7 8 57 58 59 60 61 68 69 74 75 60 EVENT OESCRIPTION Qo2 7 8 9 Durin reactor shutdown and cooldown, it was found that pressurizer level Bo

[oaf would dro whenever either set of shutdown coolin svstem suction valves 7 8 9 80 QOg was o ened. Pressurizer level dro ed because there was flow throu h both 7 8 9 80 t005j the "A" and "B" suction relief valves. Xn order to maintain ressurizer 7

7 8 9 QoG 8 9 level it was necessar to start PAMK and then sto shutdown coolin flow on a 80 SYSTEM CAUSE COhiPONc~ COhiPONENT COOK COOE COMPONENT COOK SUPPUKR MAiIUFACTURER 7

~CUFF VALVE X 8 9 10 11 12 17 N

44 C 7 1 0 47 N

48 CAUSE OESCRIPTION 7

Qg8 9 The shutdown coolin' stem suction line relief valves were not seatin Go

~09 0 0 7 8 9 80 7

~1c 89.

valves were o ened. The relief valve roblem is bein evaluated and a FACAfTY METHCO OF STATUS '.4 POWER OTHER STATUS CISCOVERY OISCOVERY OESCRIPTICN 0 ~0( ol o N A a N A 7 8 9 10 12 13 44 45 46 60 FORM OF ACTIVITY CO@TENT RELEASEO OF RKLEASE AhICI,'NT OF ACTIVITY LOCATiON OF RELEASE

~z ~z N A N A 7 9 9 10 11 44 45 Go PERSONNEL EXPOSURES NUMBER TYPE O'ESCRIPTION

~ol 0 I o z N A 7 8 9 11 12 13 60 PERSONNEL INJURIES NUMBER CESCRIPTION

~010 0 7 8 9 11 12 zzRO3ABLE coNsFQUENc'Es Qsj N A 89 80 LOSS OR OAMAGE To FACILITY 7

Q~g 89

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TYPE 10 OKSCRIPTION 80 PUBLICITY N A 7 8 9 j AOOITIONAL FACTORS I

7 Q~gl 8 9 2 con ation f Eve Descrintion and ause Descrio ion.

7 89 80 M. A. Scho man PHONE. 305/552-3779 CFO ddI Col

REPORTABLE OCCURRENCE NO. 335-76-40 LICENSEE EVENT REPORT PAGE TWO Event, Description (Continued) t cycle of approximately 15 minutes which was contrary to Technical Specification 3.4.1. RCS pressure was maintained'below 210 psia and both relief valves were gagged shut to allow continuous operation of the shutdown cooling system. This was the second occurrence involving operation contrary to Technical Specification 3.4.1 (LER 335-76-6), however, the two occurrences were not related with respect to cause. (335-76-40)

Cause Description (Continued) supplementary report will be submitted upon completion of the evaluation.