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 P GATE OF DOC DATE R EC'D LTR TWX RPT OTHER Rochester, N.Y.

L.D. White Jr. 11-4-75 11-10-75 XXX ORIG CC OTHER SENT AEC PDR XXX TO'=1ame .~EiL1z 30 SENT LOCAL PDR CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:

XXX 30 50-244 DESCR IPTION: ENCLOSURES Letter trans the following...... Unusual Event Report ¹, 75-09; on 10-12-75, Concerning Reactor Coolant-131 Equivalent .

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(30 Copies Received)

PLANT NAME: RE Ginna ¹ 1 e

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November," 19 75 ego,,J oo

, C~X Mr. James P. O'Reilly, Director U. 'S. Nuclear 'Regulatory Commission Office of Inspection and Enforcement ',:=,~IT T6 Region I 631 Park Avenue King of Pru ssia, Pennsylvania 19406

Subject:

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)

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L(CENSEE EVENT REPORT CqNTROL BLOCI(: . LEASE PRINT ALL REQUIRED IMFDRIWATIDM) 6 LICENSEE LICENSE FVENT NAME LICENSE NUMSER TYPE TYPE

[oaj N Y R E G 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~03 7 89 14 15 85 36 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT OATE

'IoO~Icom ~PO L L 0 5 0 0 2 4 4 1 0 1 2 7 5 1 1 0 4 7 5 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT DESCRIPTION

[op~] During startup with reactor critical, reactor coolant temp. over 500 I-, I-131 equivalent 7 8 9 80 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) 7 89 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE COOE COMPONENT COOE 5UPPUER MANUFACTURER 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 47 48 CAUSE DESCRIPTION tOOI A partial cooldown and subsequent heatup and the accompan in de ressurizin and 7 8 9 80

[opg] pressurizing of the fuel resulted in. the increased reactor coolant I-131 equivalent 7 8 9 80 t11oj activity.

7 89 80 FACILITY METHOO OF STATUS  % POWER OTHER STATUS OISCOVERY OISCOVERY OESCRIPTION

[gg ~C ~00 0 NA sampling per startup procedure 7 8 9 10 18 13 44 45 46 30 FORM OF ACTIVITY COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g 8 8 . NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

[ig ~00 0 ~E NA 7 8 9 O'I 18 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION

[gQ4 ~00 0 NA 7 89 11 13 80 OFFSITE CONSEQUENCES Jig 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE OESCRIPTION NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS 7 89 80 89 7

NAME: Bruce A. Snow PHDNE.7 1 6/546 2700 'xt GPO 661 80 29 1-2 14 667

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