ML19276F533
| ML19276F533 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/13/1979 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 7903300585 | |
| Download: ML19276F533 (2) | |
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UNITED STATES l'
NUCLEAR REGULATORY COMMISSION f
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G LE N E LLYN, ILLINols 60137 M 131979 State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Bulletin No. 79-03 titled " Longitudinal Weld Defects in ASME SA-312 Type 304 Stainless Steel Pipe Spools Manufactured by Youngstown Welding and Engineering Company" was sent to the following licensees on March 12, 1979, for action:
American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (59-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456, 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-254, 50-265)
Zion 1, 2 (50-295, 50-304)
Consumers Power Company Big Rock Point (50-155)
Midland 1, I (50-329, 50-330)
Palisades (50-255)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462) 790330 o 5Ts 5
State of Illinois Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Prairie Island 1, 2 (50-282, 50-306)
Tyrone Energy Park 1 (50-484)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Toledo Edison Company Davis-Besse 1 (50-346)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (' J-305) s Sincerely, Helen Pappas, Chief Administrative Branch
Enclosures:
1.
List of IE Bulletins Issued in Last Twelve Months cc w/encls:
Mr. D. W. Kane, Sargent & Lundy Central Files p
Reproduction Unit NRC 20b Local PDR NSIC TIC P
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTOPCEMENT REGION III March 12, 1979 IE Bulletin No. 79-03 LOHGITUDINAL WELD DEFECTS IN ASME SA-312 TfPE 304 STAINLESS STEEL FIPE SPOOLS MANUFACTURED BT YOUNGSTOWN WELDING AND ENGINEERING COMPANY Deacription 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
("nS). On November 17, 1978, the Southern California Edison Company t
..ted similar defects in pipe supplied for the San Onofre Nuclear Ge erating Station, Units 2 and 3.
Pullman Power Products of Los Angeles, California supplies safety-related fabricated piping spools of various diameters for the PVNGS.
The defects were discovered by Pullman in ASME SA-312 type 304 stainless steel pipe supplied to Pullman by Youngstown Welding and Engineering Cca:pany of Youngstown, Ohie. The pipe is manufactured by rolling plate into cylinders and then fusich welding the longitudinal seam without filler metal.
Pullman discovered defects in the longitudinci velds while radiographing their circumferential shop welds. Further radiographic examtaa:icn of the longitudinal welds revealed rejectable porosity ani la:k af f a 1 n.
Pullman then performed ultrasonic examinscion of the full lengta ei :ne 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 wil 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 s
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e 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 the rejectable indications were not identified.
A special inspection was performed at Teungstown 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 parraeters although no specific ASHI Code violations could be identified. Youngstarn 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 mater 17' 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 ptried during which the welding and ultrasonic testing proble=s 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 Ludlun 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.
w
. March.12, 1979 IE Bulletin No. 79-03 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) shen they will be completed shall be submitted within 30 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 sub=itted within 60 days of receipt of this Bulletin.
Reports should be submitted to the Directar of the nap i.oria.: TW.
Regional Office and a copy should be f orwarded to the !;KC )f;2ce cf Inspection and Enforcement, Division cf Reactor Constructian 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.
IE Bulletin No. 79-03 March 12, 1979 LISTING OF IE BULLETINS ISSUED IN 1AST TWELVE MONTHS Bulletin Subject Date Issued Issued To No.
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 A31 Power Reactor Ha=mer, Type N Relays Facilities with an With DC Coils 01 or CP 78-07 Protection afforded 6/1278 AJ. Fcret M m;or by Air-Line 1tespirators F4 c211 tie r wi.13 a, 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 Dryvell Leakage 6/14/79 All BWR Power Paths Associated with Reactor Facilities Inadequate Dryvell 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 I
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IE Bulletin No. 79-03 March 12, 1979 LISTING OF IE BULLETINS ISSUED IN LAST IVELVE HONTHS Bulletin Subj ect Date Issued Issued To MO.
78-11 Examination of Mark I 7/21/78 BWR Power Reactor Containment Torus Facilities for Welds action: Peach Bottom 2 and 3, Quad 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 Yeswel 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 Models 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 CE BWR facilities Coc:ponents In ASCO with an OL or CP Solenoids 7 9-01 Environmental Qualifica-2/8/79 All Power Reactor tion of Class IE Equipment Facilities with an OL or CP 79-02 Pipe Support Base Plate 3/ 8/7!
h1 l'over R unctor Designs Using Concrete
?.<ct31tiec ettt an Expansion Anchor Bolts OL or CP Page 2 of 2 4
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