ML18139A246
| ML18139A246 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 04/21/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8005210670 | |
| Download: ML18139A246 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 APR 2 l 7980 Virginia Electric and Power Company Attn:
J. H. Ferguson Executive Vice President-Power P. O. Box 26666.
Richmond, VA 23261 Gentlemen:
This Information Notice is provided as an early notification of a possible significant matter. It is expected that recipients will review the information for possible applicability to their facilities~
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to
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recommend or request specific licensee actions. If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Enclosures:
- List of Recently Issued IE Information Notice~
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Sincerely, James P. O'Reilly Director
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W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry
- Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W. L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883
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APR 2 1 1980
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UNITED STATES.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 April 21, 1980 SSINS No. :
6870 Accession No.
8002280660 IE Information Notice No. 8015 AXIAL (LONGITUDINAL) ORIENTED CRACKING IN PIPING 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 during a reactor coolant system leakage test at their Quad-Cities Unit 2 Nuclear Power Station. The source of leakage was subsequently identified to be located adjacent to a shop weld joining a 90° elbow and a wedge section of elbow material
- used to extend the elbow to 105°.
Subsequent ultrasonic inspections revealed additional cracking in several other elbows in "A" and "B" 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 root area revealed axial oriented cracks on both sides of the weld in the counter bores adjacent to the weld roots.
From the limited metallography 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 ultrasonically 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 NDE 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 per£ ormed 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 is requested at this time. If you
- *" have.any questions regarding this matter, please contact the Director of the
- appropriate NRC Regional Office.
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IE Information Notice No. 80-15 April 21, 1980 Information Notice No. 80-15 80-14 80-13 80-12 80-11 80-10 80-09 80-08 80-07 80-06 80-05 RECENTLY ISSUED IE INFORMATION NOTICES Subject Axial (Longitudinal)
Oriented Cracking in Piping Safety Suggestions From Employees General Electric Type SBM Control Swiches - Defective Cam Followers Instrument Failure Causes Opening of PORV and Block Valve General Problems with ASCO Valves,in Nuclear Application Including Fire Protection Systems Partial Loss of Non-Nuclear Instrument System Power Supply During Operation Possible Occupational Health Hazard Associated with Closed Cooling Systems The States Company Sliding Link Electrical Terminal Block Pump Shaft Fatigue Cracking Notification of Significant Events Chloride Contamination of Safety Related Piping Date Issued 4/21/80 4/2/80 4/2/80 3/31/80 3/14/80 3/7 /80 3/7/80 3/7/80 2/29/80 2/27/80 2/8/80.
Enclosure Issued To All power reactor facilities with an OL or CP All power reactor facilities with an OL or CP All light water reactor facilities holding power reactor OLs or CPs All holders of power reactor OLs and CPs All holders of Reactor OL, CP, fuel fabrica-tion and processing facilities All power reactor facilities holding OLs and CPs All holders of power reactor OLs and near term CPs All power reactor facilities with an OL or a CP All Light Water Reactor Facilities holder power reactor OLs and CPs All holders of Reactor OLs and to near term OL applicants All licensees of nuclear power reactor facilities and applicants and holders of nuclear power reactor CPs
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