ML19282B909
| ML19282B909 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/12/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| References | |
| NUDOCS 7903190016 | |
| Download: ML19282B909 (1) | |
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WALNUT CREEK, C AllFORNI A 94596 March 12,1979 Docket No. 50-312 Sacramento Municipal Utility District P. O. Box 15830 Sacramento, California 95813 Attention: Mr. John J. Mattimoe Assistant General Manager Gentlemen:
Enclosed is IE Bulletin No. 79-03, which requires action by you with regard to your power reactor facility (ies) with an operating license or a construction permit.
Should you have any questions regarding this Bulletin or the actions required by you, please contact this office.
Sincerely, w[b R. H. Engelken Director
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months cc w/ enclosures:
R. J. Rodriguez, SMUD L. G. Schwieger, SMUD 7 9 0 319 0 0 f ro
UNITED STATES NUCLEAR REGULATORY COMMISS10tl 0FFICE OF IIISPECTION Ai!D ENFORCEMENT WASHIfiGTON, D.C.
20555 March 12, 1979 IE Bulletin No. 79-03 LONGITUDINAL WELD DEFECTS IN ASME SA-312 TYPE 304 STAINLESS STEEL PIPE SP0OLS MANUFACTURED BY YOUNGSTOWN WELDING AND ENGIt!EERIf;G COMPANY Description of Circumstances:
On September 27, 1978, the Arizona Public Service Company reported that defects had been discovered in longitudinal welds in ASME Section III class 2 pipe supplied for the Palo Verde Nuclear Generating Station (PVNGS). On f;ovember 17, 1978, the Southern California Edison Company reported similar defects in pipe supplied for the San Onofre Nuclear Generating Station, Units 2 and 3.
Pullman Power Products of Los Angeles, California supplies safety-related fabricated piping spools of various diameters for the PVf;GS.
The defects were discovered by Pullman in ASME SA-312 type 304 stainless steel pipe supplied to Pullman by Youngstown Welding and Engineering Company of Youngstown, Ohio. The pipe is manufactured by rolling plate into cylinders and then fusion welding the longitudinal seam without filler metal.
Pullman discovered defects in the longitudinal welds while radiographing their circumferential shop welds. Further radiographic examination of the longitudinal welds revealed rejectable porosity and lack of fusion.
Pullman then performed ultrasonic examination of the full length of the longitudinal welds and discovered indications exceeding the acceptance criteria of ASME Section III. Further ultrasonic examination revealed indications in other piping subassemblies where pipe was supplied by Youngstown. Two indications verified by radiography were identified as porosity and measured 0.350 inch by 0.125 inch in one case and 0.300 inch by 0.125 inch in another case in pipe with a nominal wall thickness of 0.375 inch.
The additional examinations revealed that of 103 spools and four pipe supports shipped to PVNGS, 44 spools and one pipe support were found to contain ultrasonic indications exceeding those permitted by the ASME Code. Of 65 partially fabricated piping spools, 30 were found to be similarly defective. The acceptance criteria for the pipe supplied by Youngstown includes 100 percent ultrasonic examination of the longitudinal 1 of 3 16013g
IE Bulletin No. 79-03 March 12, 1979 welds in accordance with ASME Section III. The documentation provided with the pipe indicated that the required ultrasonic examination had been performed by Youngstown but tha rejectable indications were not identified.
A special inspection was performed at Youngstown by NRC inspectors during the week of January 22, 1979.
It was determined that the apparent cause of the identified defects was inadequate control of welding parameters although no specific ASME Code violations could be identified. Youngstown has recently hired a consultant to reevaluate the fusion welding parameters and revised their welding procedures to provide better control of welding current, voltage and travel speed for all material thickness ranges.
Ultrasonic examinations of the pipe welds were performed by a subcontractor to Youngstown. The reason why this subcontractor's ultrasonic testing did not detect indications exceeding ASME Code acceptance criteria was not determined. The piping was known to have been tested in the heat treated condition, prior to the removal of surface oxides. However, a comparison of attenuation of the pipe in as heat treated vs. heat treated and pickled condition did not reveal a discernible difference.
The NRC inspectors could not determine a definite time period during which the welding and ultrasonic testing problems are thought to have existed. All type 304 or 316 SA 312 pipe manufactured before mid-November, 1978 may have been shipped in similar condition. As a large supplier, Youngstown is known to have supplied piping for nuclear applications to the Dravo Corporation, Chicago Bridge and Iron, Flowline Corporation and ITT Grinnell Industrial Piping Inc.
In addition, piping was also supplied to material warehousing operations including Albert Pipe Supply, Guyon Alloys Inc., and Allegheny Ludlum Steel Corporation which may have eventually been used in safety-related nuclear applications.
Action to be Taken by the Licensees and Permit Holders:
For all power reactor facilities with an operating license or a construction permit:
1.
Determine whether ASME SA-312, type 304 or other welded (without filler metal) pipe manufactured by Youngstown Welding and Engi-neering Company is in use or planned for use in safety-related systems at your facility.
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IE Bulletin fio. 79-03 flarch 12, 1979 2.
For those safety-related systems where the subject piping is in use or planned for use, identify the application of the piping including system, pipe location, pipe size and design pressure / temperature requirements.
3.
Develop a program for volumetric examination of the longitudinal welds including acceptance criteria for the piping identified in Item 2 above.
Describe planned corrective actions if acceptance criteria are not met.
If a sampling program is utilized explain the basis for the sample size.
4.
For facilities with an operating license, a report of the above actions, including the date(s) when they will be completed shall be submitted within 60 days of receipt of this Bulletin.
5.
For facilities with a construction permit, a report of the above actions, including the date(s) when they will be completed shall be submitted within 60 days of receipt of this Bulletin.
Reports should be submitted to the Director of the appropriate fiRC Regional Office and a copy should be forwarded to the flRC Office of Inspection and Enforcement, Division of Reactor Construction Inspection, Washington, D.C., 20555.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
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IE Bulletin No. 79-03 March 12, 1979 LISTIrlG 0F IE BULLETIflS ISSUED Ill LAST TWELVE M0flTHS Bulletin Subject Date Issued Issued To llo.
78-05 Malfunctioning of 4/14/78 All Power Reactor Circuit Breaker Facilities with an Auxiliary Contact OL or CP Mechanism-General Model CR105X 78-06 Defective Cutler-5/31/78 All Power Reactor Hammer, Type M Relays Facilities with an With DC Coils OL or CP 78-07 Protection afforded 6/12/78 All Power Reactor by Air-Line Respirators Facilities with an and Supplied-Air Hoods OL, all class E and F Research Reactors with an OL, all Fuel Cycle Facilities with an OL, and all Priority 1 Material Licensees 78-08 Radiation Levels from 6/12/78 All Power and Fuel Element Transfer Research Reactor Tubes Facilities with a Fuel Element transfer tube and an OL.
78-09 BWR Drywell Leakage 6/14/79 All BWR Power Paths Associated with Reactor Facilities Inadequate Drywell with an OL or CP Closures 78-10 Bergen-Paterson 6/27/78 All BWR Power Hydraulic Shock Reactor Facilities Suppressor Accumulator with an OL or CP Spring Coils Page 1 of 2
IE Bulletin No. 79-03 March 12, 1979 LISTING 0F IE BULLETINS ISSUED IN LAST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action:
Peach Bottom 2 and 3, Guad Cities 1 and 2, Hatch 1, Monti-cello and Vermont Yankee 78-12 Atypical Weld Material 9/29/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-12A Atypical Weld Material 11/24/78 All Power Reactor in Reactor Pressure Facilities with an Vessel Welds OL or CP 78-13 Failures In Source Heads 10/27/78 All general and of Kay-Ray, Inc., Gauges specific licensees Model s 7050, 7050B, 7051, with the subject 7051B, 7060, 7060B, 7061 Kay-Ray, Inc.
and 7061B gauges 78-14 Deterioration of Buna-N 12/19/78 All GE BWR facilities Components In ASCO with an OL or CP Solenoids 79-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Clcss IE Equipment Facilities with an OL or CP 79-02 Pipe Support Base Plate 3/8/79 All Power Reactor Designs Using Concrete Facilities with an Expansion Anchor Bolts OL or CP Page 2 of 2