ML18142B893

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LER 1976-003-00 for R. E. Ginna, Residual Heat Removal System Low Pressure Piping Excessive Leakage
ML18142B893
Person / Time
Site: Ginna Constellation icon.png
Issue date: 02/06/1976
From: White L
Rochester Gas & Electric Corp
To: O'Reilly J
NRC/IE, NRC Region 1
References
LER 1976-003-00
Download: ML18142B893 (6)


Text

N RC EDAM 195 U.S. NUCLEnA REGULATORY COMMISSION DOCKET NUMBER I2.75 I 50-244 FILE NUMBER NRC DISTRIBUl ION FDB PAR Ii60 DOCl<ET MATERIAL XNCIDENT REPORT

'FROM: DnTE OF DOCUMENT J P O'ei ly1 'ochester Gas 8 Elec. Corp. 2-6-76 Rechester, N.Y. DnTE RECCIVCD L.D. White, Jr. 2-11-76 I9I ETTER ONOTOAIZED PROP INPUT FOAM NUMBER OF COPIES RECEIVED Q OR IG IN nL C3UNCLaSSIFIED

+COPY 30 DESCRIPTION ENCLOSUBF Letter trans the following...... Reportable Occurrence 8 76-. 3, on 1-15-76, Concer/ning Excessive leakage of the Removal System low preesure piping...

+

(30 Cys. Recieved).

CKNOVrI EDGE~

DO NOT REMOVE PLANT NAME: RE Ginna III 1 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGHR/J, COLLXNS SAFETY FOR ACTION/INFORMATION ENVXRO BRANCH CHIEF:

q/3 CYS FnR ACTXnN LIC ASST:

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' / ENT TO LA INTERNAL DISTRI8UTION NRC PDR XEcE XLC~~ 2 SCHROEDER/IPPOLXTO 0

NO~AK CHHC Rl,'EK~SSCEKFN H Ch, DMhHF TEDE, CO MACCA SEIAO VOLLMB~H BUNCH KRH ER OL NS EXTERNAL DISTRIBUTION CONTROL NUM8F R LpDR: yons oc es er TIC NSXC 363 NBC FOAM 195 I2-7GI

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coen ROCHESTER GAS AMO ELECTRlC CORPORAllOH 89 EAST AYEHUE, ROCHESTER, H.Y. 14649 l.EON D, WHITE. Jll. TCLKPHOBC vlcc pnaslDRNT nncn conc 7co 546.2 100 February 6, 1976 00' I l / /Q

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Mr. j'ames P. O'Reilly, Director U. S. Nuclear Regulatory Commission U.S. NUCMPR R~<

Office of Inspection and Enforcement COMMlSSiO~TOR Mal i Socll~

Region I

)g jp 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Reportable Occurrence 76-03 (30-day report) Residual Heat Removal System low, pressure piping excessive leakage.

R. E. Ginna Nuclear Power Plant, Unit No. 1 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications, Article 6.9.2b, the attached report of Reportable Occurrence 76-03, 30-day, is hereby submitted. Two additional copies of this letter and the attachment are enclosed.

Uery truly yours, L. D. Whi e, jr.

Attachment DOCKGSD cc: Mr. john G. Davis (30) (i USMC Mr. William G. McDonald (3) li')Bi.B k Mail Soccion Doc4l Cloct

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L~I~ENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQUIREO Il'4FORMATIObl)

I LICENSEE LCENSE EVENT NAME LICENSE NUMBER TYPE TYPE

[oa~j N Y R 9 G 1 0 0 0 0 0'0 0 0 0 4 1 1 1 1 . ~0033

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7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT OATS REPORT DATE IOD1) CON'T 0 5 0 0 2 4 4 0 1 1 5 7 6 0 2 0 6 7~6 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT DESCRIPTION Qgg During routine 105 psig hydro test'of residual heat removal (RHR) suction piping from CU 7 8 9 80 sump B to reactor coolant drain tank pumps, 2 . 85 gal ./hr. was measured at "A",pump 7 89 80

~04 suction flan e. Flan e bolts were ti htened and leakage was reduced to zero.

7 8 9 80 Qpg (Reportable Occurrence 76-03, 30-day) 7 8 9 80 Jog 7 8 9 PNME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE  %

COMPONENT CODE SUPPUER MANUFACTURER VIOIATION IoO7I 8'

~wG A P 1 P 9 x x ~N ~89~99 44 Y

7 10 11 12 17 43 47 48 CAUSE DESCRIPTION

[QD8] Maintenance personnel had tightened flange bolts after maintenance for proper perform-7 8 S 80 Q~g ance at normal o eratin ressure, but had failed to do so sufficientl to withstand test 7 8 9 80

~10 pressure. The PORC recommended that maintenance (cont'd. under Additional Factors)

7. 89 METHOD OF 60 FACR.ITY STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

~9 ~OS O NA 7

7 Q1g 8

8 9

FORM OF

'S ACTIVITY RELEASEO 9

8 10 COATENT OF RELEASE PERSONNEL EXPOSURES 10 12 13

'A AMOUNT OF ACTIVITY 44 44 45 45 46 NA LOCATION OF RELEASE 80 80 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

+so ~00 0 NA 7 89 11 12 80 OFFSITE CONSEQUENCES 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE 'ESCRIPTION

~16 H NA 7 89 10 80 PUBLICITY NA 7 89 80 ADDITIONAL FACTORS

~18 (cont'd. from Cause Description) procedure used for inspection of pump would include 7 89 80 Q~g verification that flanges were properly tightened.

7 89 80 Charles U. Hartlieb PHDNE. 716 546-2700 ext. 291-216 GPO 881 ~ 88Y

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