ML18082A433

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Forwards IE Info Notice 80-15, Axial (Longitudinal) Oriented Cracking in Piping. No Written Response Required
ML18082A433
Person / Time
Site: Salem PSEG icon.png
Issue date: 04/21/1980
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Schneider F
Public Service Enterprise Group
References
NUDOCS 8005220017
Download: ML18082A433 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket No.. 50-272 Public Service Electric-and Gas Company ATIN:

Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen.:

April 21, 1980 The enclosed IE Information Notice No._,80-15, 11Axial (Longitudinal) Oriented Cracking* in Piping, 11 is forwarded to you for information.

No written-response is required.

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

Sincerely,.

Enclosures.:

1.

IE Information Notice No. 80-15 2~

List of Recently Issued IE Information Notices CONTACT:

L. E. Tripp (215-337-5282) cc w/encls:

F.

P~ Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L.. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station soo52~oot/

LI

... - ~......... ~

ENCLOSURE 1 UNITED STATES SSINS No.:

6870 Accession No.

8002280660 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECIION AND ENFORCEMENT WASHINGTON. O.C.

20555 AXIAL (LONGITUDINAL) ORIENTED CRACKING IN PIPING IE Info.rmatton Notice No. 80-15 Date:

April 21, 1980 Page l of 1 On March 8, 1980, the Commonwealth Edison Company reported to the NRC that slight leakage was observed from the "A" loop core spray injection piping duri.ng a reactor coolant system leakage test at their Quad-Cities Unit 2 Nuclear Power Station.

The source of leakage was subsequent.ly identified to be 1ocated adjacent to a shop weld joining a 90° elbow an.d a wedge section of elbow material used to extend the elbow to 105°.

Subsequent ultrasonic inspec-tions revealed additional cracking in several other elbows in 11A11 and 118 11 core spray loops.

The cracks are located adjacent to welds and oriented transverse to: the weld in the axial (longitudinal) piping direction.

The.affected elbows have been removed and currently failure analyses are in progress.

Preliminary results from liquid penetrant examinations of the elbow interior surface in the counter bore/weld rocit area revealed axial oriented crac;ks on both sides of the weld in the counter bores adjacent to the weld roots.

From the limited metal1ography performed to date, the cracking mode appears to be intergranular stress corrosion cracking.

The cracking,. however, only appears to be slightly branched.

A determination as to whether or not the cracking extends into and across the welds cannot be made at this time.

It* is significant to point out. that these service sensitive lines, as defined by NUREG 313, had been examined on an augmented basis per NUREG 313 requirements.

Two of the affected welds were inspected ult.rasonically at the current outage prior to the leakage being observed at the pressure test with no indication of cracking reported.

Further ultrasonic examinations, using standard ASME Section XI methods, performed after discovery of the leak clearly revealed the cracking (approximately 100% over the reference level).

Licensees are requested to inform NOE inspection personnel of the above stated information and to emphasize the need for care when performing circumferential UT scans of the weld and adjacent areas in piping components.

Particular importance should be stressed when the examinations are performed on BWR service sensitive 304 stainless steel piping and on PWR 304 stainless steel piping in stagnant *systems.

This Information Notice is provided as an early notification of a possibly significant matter that is still under review by the NRC staff. It is expected that recipients will review the information for possible applicability to their facility.

No specific action or response isrequested at this time.

If you have any questions regarding this matter, please contact the DiT"ector of the appropriate NRC Regional Office.

Information Notice No. 80-05 80-06 80-07 80-08 80*09 80-10 80-11 80-12 80-13 80-14 ENCLOSURE 2 IE Information Notice No. 80-15 Date:

April 21, 1980 Page l of i RECENTLY ISSUED IE INFORMATION NOTICES Subject Chloride Contamination of

  • Safety Related Piping and Comp.onents Notffication of Signif-icant Events Pump Fatigue Cracking The States Company Sliding Link Electrical Terminal Block Date
  • Issued to Issued 2/8/80 All Power Reactor-Facil-i*ties with an Operating*

License (OL) or Construction Permit (CP) and applicants for a CP 2/27/80 All Power Reactor Facil-ities with an OL and applicant for OL 2/29/80 All Power Reactor Facil-ities* ~ith an OL or CP 3/7/80 All Power Reactor Facil-ities with an OL or CP Possible Occupational Health 3/7/80 Hazard Associated with* Closed Cooling Systems for Operating Ail Power Reactor Facil-ities with an OL or CP Power Plants Partial Loss of Non-Nuclear 3/7/80 Instrument System Power Sup-ply During Operation Generic Problems With ASCO 3/14/80 Valves in Nuclear Applica-tions including Fire Pro-tection Systems All Power Reactor Facil-ities with an Ol or CP All Power Reactor Facil-ities with an OL or CP, Fuel Fabrication and Processing Facilities Instrument Failure Causes Opening of PORV and Block Valve 3/31/80. A 11 Power Reactor Faci 1-iti es with an OL or CP General Electric Type SBM 4/2/80 Control Switches - Defective CAM Followers Safety Suggestions from 4/2/80 Employees All Power Reactor Facil-ities with an O.L o.r CP All Power Reactor Facil-ities with an Ol or CP, Fuel Fabrication and Processing Facilities and Materi:als Priority 1 Licensees