05000244/LER-2076-025, R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent

R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent

ML18142B247
Person / Time
Site:	Ginna
Issue date:	11/09/1976
From:	White L Rochester Gas & Electric Corp
To:	O'Reilly J NRC/IE, NRC Region 1
References
LER 1976-025-00
Download: ML18142B247 (6)

LER-2076-025, R. E. Ginna, Unit 1, Leak at Residual Heat Removal System Return Pipe Vent

Event date:
Report date:
2442076025R00 - NRC Website

text

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L.D. WHITE,JR.

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LTR. 'kRANS THE FOLLOWING...'...

ENCLOSUflE LICENSEE EVENT REPORT 8 76-25, ON 10-10-76

~ CONCERNING LEAK AT WELDOLET TO NIPPLE WELD ON 3/4>>

VENT! ON RHR RETURN LINE......

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( 30 CARBON SIGNED CYS.

RECEIVED)

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PIdQET NAME:

RE GINNA //

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89 EAST AYENUE, ROCHESTER, N.Y. I4649 LEON D. WHITE, JRi VICE PRESIOENT TELEPHONE ARCr COCE Tttt 5~6.?700 November 9, 1976 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 PocKETE0 g%,.$

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Subject:

Reportable Occurrence 76-25 (30-day report), Leak at Residual Heat Removal System return pipe vent 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 76-25, 30-day, is hereby submitted.

Two additional copies of this letter and the attachment are enclosed.

Very truly yours, t

rC r'C rv~rCdrr/y I L. D. Whi'te, Jr.

Attachment cc:

Dr. Ernst Volgenau (30)

Mr. William G. McDonald (3)

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CONTROL BLOCK:

(PLEASE PRINT ALLREQUIRED INFORMATION) 1 UCENSEE KE:EIYBIEYyt tE att:4~m';,

MBEMEE EVENT NAME EIBEMEE MBMBEB EYPE TYPE

~ot N Y R

5 G

1 0

0 I 0 0

0 0

0 0 0

4 1

1 1

1

~03 14 15 25 26 30 31 32 7

89 REPORT REPORT CATEGORY TYPE SOURCE [061IOON"t~

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57 58 59 60 61 7

8 DOCKET NUMBER EVENT DATE REPORT DATE 5

0 0 2

4 4

1 0

1 0

7 6

1 1

0 9

7 6

68 69 74 75 80

EVENT DESCRIPTION

Jog Durin o eration of RHR s stem an o erator noted small uddle on floor and discovered 7

8 9 80 I

leak at weldolet to nipple weld on 3/4" vent on RHR return line.

This is similar to 7

89 80 tppj4 Reportable Occurrence 74-5.

Replaced nipple and rewelded using approved procedures.

7 8 9I (Reportable Occurrence 76-25, 30-day).

7 8 9 Ett I COMPONENT MANUFACTURER 47 7

8 9 fpgg]

Nipple appeared bottomed in socket.

New nipple proper]y installed.

7 89 PRME SYSTEM

CAUSE

COMPONENT CODE CODE COMPONENT CODE SUPPUER VGLATGN [ogtj LLGGGGP~II0 P I P

5 X

X N

K 0

5 5

7 8 9 10 11 12 17 43 44 48 CAUSE DESCFIIPTION tppi Stresses were induced due to improper fitup of nipple to socket during construction.

80 80 OTHER STATUS AMOUNT OF ACTIVITY 7

8 9 Qo]

7 89 FACILITY STATUS POWER

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7 8

9 10 12 13 FORM OF 7

8 9

10 11 PERSONNEL EXPOSURES NUMBER TYPE

DESCRIPTION

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89 11 12 13 PERSONNEL INJURIES NUMBER

DESCRIPTION

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7 89 11 12 METHOD OF DISCOVERY, 44 45 46 44 45 DISCOVERY DESCRIPTION By operator LOCATION OF RELEASE NA 80 80 80 80 80 OFFSITE CONSEQUENCES Q~g 7

89 LOSS OR DAMAGE TO FACILITY TYPE

DESCRIPTION

t116L 7

89 10 PUBLICITY

,E 7

89 ADDITIONAL'ACTORS 7

89 NA NA 80 80 80 80 7

89 NAME'ack Noon 80 pqDNE. 7 1 6. 546-2700, ext.

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