ML18142B902

LER 1975-009-00 for R. E. Ginna, Reactor Coolant Iodine-131 Equivalent Activity

ML18142B902
Person / Time
Site:	Ginna
Issue date:	11/04/1975
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1975-009-00
Download: ML18142B902 (6)

Text

v as vs'ess'wUvswsAxslrsw x'slJ/Vs(J Xx(eALllil fQRC 1 RIBUTION FOR PART 50 DOCK VIATERIAL (TEMPORARY FORM}CONTROL NO:&289D FILE lNCXDENZ PEPOI',T I:ILP FROM: Rochester Gas&Elec.Co Rochester, N.Y.L.D.White Jr.P GATE OF DOC 11-4-75 DATE R EC'D 11-10-75 LTR TWX XXX RPT OTHER TO'=1ame CLASS UNCLASS XXX.~EiL1z PROP INFO ORIG INPUT CC OTHER 30 NO CYS REC'D 30 SENT AEC PDR XXX SENT LOCAL PDR DOCKET NO: 50-244 DESCR IPTION: Letter trans the following......

ENCLOSURES Unusual Event Report¹, 75-09;on 10-12-75, Concerning Reactor Coolant-131 Equivalent

.GCtiVity e~~~~~~(30 Copies Received)PLANT NAME: RE Ginna¹1 e FOR ACTION/INFO RMAT!ON SAB 11-11-75 BUTLER (L)W/Copies CLARK (L}W/Cooies PARR (L)W/Copies KiNI EL{L)W/Copies SCHWENCER{L)W/Copies S1OI.Z (I)W/Copies VASSALLO (I)W/'opies EMPURPLE (L)"5@Copies ZIEMANN (L)W/Copies DICKFR{F)W/Copies KNIGHTON (F)W/Copies YOU,NGBLOOD (E)W/Copies REGAN (E)W/Copies LEAR (L)W/Copies SPELS W/Copies REI:0 W/Copies 0T REM@NOWLEDCTED F~}IF TECH REVIEW NIRC PD R~SCHROEDE R OGC, ROOM'P.506A

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IAS.I9 93 rorr II@I C/November," 19 75 ego,,J oo , C~X',:=,~IT T6 Mr.James P.O'Reilly, Director U.'S.Nuclear'Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Pru

Subject:

ssia, Pennsylvania 19406 Unusual Event 75-09, Reactor Coolant Iodine-131 Equivalent Activity R.E.Qinna Nuclear Power Plant, Unit No.1 Docket No.50-244

Dear Mr.O'Reilly:

In accordance'with Technical Specifications, Article 6.6.2b, the attached report of Unusual Event 75-09 is hereby submitted.

Two additional copies of this letter and the attachment are enclosed.Very t'ruly yours,'C~l~~P L.D.White, Jr.Attachment cc: Mr.Donald F.Knuth (30)Mr.William G.McDonald (3)

" J I>~*I.j(a Ih CqNTROL BLOCI(: LICENSEE NAME LICENSE NUMSER 1 0 0-0 0 0 0 0-0 0[oaj N Y R E G 7 89 14 15 L(CENSEE EVENT REPORT.LEASE PRINT ALL REQUIRED IMFDRIWATIDM) 6 LICENSE FVENT TYPE TYPE 4 1 1 1 1~03 85 36 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER'IoO~Icom~PO L L 0 5 0-0 2 4 4 7 8 57 58 59 60 61 68 EVENT DATE REPORT OATE 1 0 1 2 7 5 1 1 0 4 7 5 69 74 75 80 EVENT DESCRIPTION

[op~]During startup with reactor critical, reactor coolant temp.over 500 I-, I-131 equivalent 7 8 9 80 I activity was reported to be at 5.43 micro Ci/gm, a degraded condition permitted by 7 89 80 Qp~]limiting conditions for operation.

Increased primary coolant sampling was begun with 7 8 9 80 Qpg increasing purification flow to max.The I activity was returned to less than 3 micro Q 7 8 9 80 Qpg Ci/gm in about 9 hrs.(Unusual Event 50-244/75-09)

COMPONENT MANUFACTURER 47 7 8 9[opg]pressurizing of the fuel resulted in.the increased reactor coolant I-131 equivalent 7 8 9 t11oj activity.7 89 FACILITY STATUS%POWER[gg~C~00 0 7 8 9 10 18 13 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Q~g 8 8.NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

[ig~00 0~E NA 7 8 9 O'I 18 13 PERSONNEL INJURIES NUMBER OESCRIPTION

[gQ4~00 0 NA 7 89 11 13 METHOO OF OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION NA sampling per startup procedure 44 45 46 LOCATION OF RELEASE 44 45 OFFSITE CONSEQUENCES Jig 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION NA 7 89 PRME SYSTEM CAUSE COMPONENT CODE COOE COMPONENT COOE 5UPPUER VGLATION~or~RC~E E U E L X X N W 1 2 0 N 7 8 S 10 11 13 17 43 44 48 CAUSE DESCRIPTION tOOI A partial cooldown and subsequent heatup and the accompan in de ressurizin and 80 80 80 80 30 80 80 80 7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS NA 80 80 7 89 80 7 89 NAME: Bruce A.Snow 80 PHDNE.7 1 6/546 2700'xt 29 1-2 14 GPO 661 667

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