ML19224D527

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Forwards IE Bulletin 79-13, Cracking in Feedwater Sys Piping. No Action Required
ML19224D527
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 06/25/1979
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Leonard J
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
References
NUDOCS 7907120516
Download: ML19224D527 (1)


Text

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UNITED STATES EY NUCLEAR REGULATORY COMMISSION

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,e KING OF PF USSI A, PENNSYLVANI A 19406 June 25, 1979 Docket No. 50-333 Power Authority of the State of New York James A. FitzPateick Nuclear Power Plant ATTN:

Mr. J. D. Leonard Resident Manager P. O. Box 41 Lycoming, New York 13093 Gentlemen:

The enclosed Bulletin 79-13 is forwarded to you for information. No written response is required.

lf you desire additional information regarding this matter, please contact this office.

Sincerely,

-> m. d#sm cyce H. Grier

[f-Director

Enclosures:

1.

IE Bulletin No. 79-13 w/ Attachments 2.

List of IE Bulletins Issued in Last 12 Months cc w/encls:

George T. Berry, Executive Director P. W. Lyon, Manager - Nuclear Operations A. Kiausmann, Director, Quality f.ssurance M. C. Cosgrove, Quality Assurance Supervisor J. F. Davis, Chairman, Safety Review Committee L. R. Bennett, Assistant General Manager - General Counsel G. M. Wilverding, Licensing Supervisor c F,

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ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY C0f 711SSION OFFICE OF INSPECTION AND ENFORCEf'ENT HASHIf!GTON, D.C.

20555 IE Bulletin No. 79-13 Date: June 25, 1979 Page 1 of 4 CRACKING IN FEEDUATER SYSTEfi PIPING Description of Circumstances:

On flay 20, 1979, Indiana ard fifchigan Power Company notified the NRC of cracking in two feedwater lines at their D. C. Cook Unit 2 facility.

The cracking was discovered following a shutdown on fiay 19 to investigate leakage inside containment.

Leaking circumferential cracks were identified in the 16-inch feedwater elbows adjacent to two stean ;anerator nozzle elbow welds.

Subsequent radiographic examination revealed crack indications in all eight steam generator feedwater lines at this location on both Units 1 and 2.

On fiay 25, 1979, a letter was sent to all PUR licensees by the Office of Nuclear Reactor Regulation which informed licensees of the D. C. Cook failures and requested soecific information on feedwater system design, fabrication, inspection and operating histories. To further explore the generic nature of the cracking problem, the Office of Inspection and Enforcement requested licensees of PNR plants in current outages to immediately conduct volumetric examination of certain feedwater piping welds.

As a result of these actions, several other licensees with Hestinghouse steam generators reported crack indications.

Southern California Edison reported on June 1979, that radiographic examination revealed indications of cracking in feedwater nozzle-to-piping welds on two of three steam cenerators of San Onofre Unit 1.

On June 15, 1979, Carolina Powe. and Light reported that radiography showed crack indications in similar locations at their H. B. Psobinson Unit 2.

Duquesne Power and Light confirmed on lune 18, 1979, that radiography has shown cracking in their Beaver Valley Unit 1 feedwater oiping to vessel nozzle weld.

Public Service Electric and Gas Company reported on June 20, 1979 that Salem Unit 1 also has crack indications.

Hisconsin Public Service company decided on June 20, 1979 to cut cut a feedwater nozzle-to-pipe weld which contained questionable indication, foi metallurgical examination.

As of June 22, 1979 and since fiay 15,197; seven other PUR facilities have inspected the feedwater nozzle-to-pipe welds without finding cracking indications.

The feedwater nozzle-to-pipe configurations for D.C. Cook and fCw A C

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shown on the attached figures 1 and 2.

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w weld joint detail chowing the principal i< DUPLICATE DOCUMENT d

are shown on the attached figure 3.

d Entire document Previously entered

!gg On fiarch 17, 1977, during heat-up for ho Unit 1, a leak was discovered in the ves: into system under:

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the 16-inch diameter feedwai.er pipina to' 339 7 % h b j

nondestructive examination of all nozzle i

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