ML18113A309

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

ML18113A309
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: ML18113A309 (7)

Text

NRC FoRM 195 U.S. NUCLEAR REGULATORY CC 'SSION DOCKET NUMBER I2.76) 50-335

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FILE NUMBER OISTRIBUTION FoR PART 50 DOCKET MATERIAL

'RC INCIDENT REPORT TO: Mr, Norman CD Moseley FROM: FPL DATE OF DOCUMENT Miamia, Fla. 33101 8-18 76 A,D, Schmidt DATE RECEIVED 9-7-76 SLETTER ONOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED

@ORIGINAL SUNCLASSIFIED O COPY 1 signed DEscRII TloN Ltr trans the following: ENGLosURE Licensee Event Report 76-40 on 7<<18-76 re failure of the A Sc B suction relief

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(1 cy encl rec'd)

PLANT NAME: St. Lucie Unt 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGEH/J..COLLINS FOR ACTION/INFORMATION DHL urckHCIi CHIm:

MQ CYS FOH ACTION LIC..ASST.:

~V CYS ACRS CYS INTERNAL D IST RI BUTION FILE MIPC SCHROEDER IPPOLITO IIOUSTON NOVAK CIIECK GRIMES CASE i3UTLER HANAUEH TEDESCO MACCAHY EISENIIUT HAER SIIAO VOLLMEH HUNCII KHEGEH T COLLINS EXTEI3NAL DIS I'IEIBUTION CONTROL NUMBER LPDH; Ft. Pierce Fla

'1'LC'E3LQ: 9101 llc FOIlM IOII I2 7II)

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.O. BOX 013100, MIAMI, FLORIDA 33101 FLORIDA POWER 5 LIGHT COMPANY August 18, 1976 ll Regulatory Boche<. 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. W., Suite 818 pO<~

Atlanta, Georgia 30303

Dear Mr. Moseley:

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6 REPORTABLE OCCURRENCE 335-76-40 I 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.

truly yours, ,tAI Very )

Vice President

~', C~ 4'/PP@ ',8 Power Resources 41 Iy+ g~ g MAS/cpc Attachment cc: Jack R. Newman, Esquire Director, Office of Inspection and Enforcement (30)

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

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HELPING BUILD FLORIDA

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LICENSEE EVENT REPORT Euletorv Docket iie CONTROL BLOCK: EFPRI4TVITILREOUIREO IRPOOI!RRTIO47

' 1 8 I8$/IPL UCENSEE UCENSE EVENT 89 FLSLS10 NAME 0

LCENSE NUMBER 00000 0041111~03 TYPE TYPE

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.7 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE OOCKET NUMBER EVENT DATE REPORT OATE

[OD1]CONT ~L L 0 5 0 0 3 3 5 0 7 1 8 7 6 0 "8 1 8 7 6 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT OESCRIPTION Qo 2 89 Durin reactor shutdown and cooldown, it was found that pressurizer level 80 would dro whenever either set of shutdown coolin s stem suction valves 7 89 80 tOD4] was o ened. Pressurizer level dro ed because there was flow ~throu h both 7 8 9 80 the "A" and "B" suction relief valves. In order to maintain ressurizer 7

Qo 6 8

89 9

level it was necessar to start and then sto 'shutdown coolin flow on a PRME 80 80 SYSTEM CAUSE COMPONENT COMPONENT COOS COOS COMPONENT COOE SUPIRJEA MANUFACTURER

[OD7I ~CF ~F V A L V E X N C 7 1 0 N 7 8 9 10 11 12 17 44 47 48 CAUSE OESCRIPTION Qg8 9 The shutdown coolin 7

s stem suction line relief valves were not seatin 80 Jog 7 8 9 80

, Q~O 7 89 valves were o ened. The relief valve roblem is bein evaluated and a FACIUTY METHOO OF 80 STATUS POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION g7I ~0 ~oo o N A a h N A 7 8 9 FORM OF

.10 12 13 44 45 46 80 ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 7

Qg 9 N A N A 8 10 11 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION P~g ~oo 0 ~z N A 7 8 9 11 12 13 80 PERS'ONNEL INJURIES NUMBER,, OESCRIPTION

~4 ~oo o N' 7 89 11 12 80 PROBABLE CONSEQUENCES Qg8 N A 7 9 80 LOSS OR OAMAGE TO FACILITY TYPE OESCRIPTION

~16 7 89 10 80 PUBLICITY N A 7 89 ~ 80 AOOITIONAL FACTORS

~18 7 89 2 a ion f Des i 'on and aus Descri ion.

80 7 89 80 NAME M. A. Scho man PHONE. 305/552-3779 GPO ddl 667

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REPORTABLE OCCURRENCE NO. 335-76-40 LICENSEE EVENT REPORT PAGE TWO Event Descri tion (Continued) 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 Descri tion (Continued) supplementary report will be submitted upon completion of the evaluation.