ML19260C794
| ML19260C794 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 01/22/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 8002060096 | |
| Download: ML19260C794 (1) | |
Text
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'o UNITED STATES
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NL' CLEAR REGULATORY COMMISSION o
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0, 799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 00N 2 2 BY)
Docket No. 50-409 Dairyland Power Cooperative ATTN:
Mr. F. W. Linder General Manager 2615 East Avenue - South La Crosse, WI 54601 Gentlemen:
The enclosed Bulletin No. 80-02 is forwarded to you for action. A written response is required.
If you desire additional information re-garding this matter, please contact this office.
Sincerely, S
VJames G. Kepp er Director
Enclosure:
IE Bulletin No. 80-02 cc w/ enc 1:
Mr. R. E. Shimshak, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. John Duffy, Chief Boiler Inspector, Department of Industry, Labor and lluman Relations 1930 053 3002000 0 9 6 9
I SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 HUCLE*.D *EGULATORY COMMISSION OFFICE uF INSPtul0N AND ENFORCEMENT T
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January 21, 1980 IE Bulletin No. 80-02 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED EQUIPMENT Description of Circumstances:
The Marvin Engineering Company (MEC) of Inglewood, California was the subject of a special NRC inspection conducted on September 18-21, 1979 to evaluate their overal'. QA and QC programs which had come under severe criticism by a fomer Marvin Engineering employee. The special inspection was judged necessary since the Marvin Engineering Company was a known subcontractor and supplier to General Electric of BWR reactor internal feedwater spargers and feedwater thermal sleeves. The results of the NRC's inspection established that serious deficiencies exist in the implementation of the MEC quality assurance program relative to the manufacture of these components.
During this inspection, twenty seven deviations from applicable codes, and contrac-tual and regulatory requirements were documented in the areas of material identification and control, process control, welding and nondestructive examination.
Corrective Action The Marvin Engineering Company has been issued the NRC's detailed inspection report of the Company, and given 30 days to inform the NRC how the deviations discussed in the report will be corrected and preventive action taken.
Act:on To Be Taken All BWR licensees and construction permit holders shall supply the following information within 90 days for operating plants and 120 days for plants under construction.
' a. Have reactor feedwater spargers and thermal sleeves manufactured and/or fabri;;ated by the Marvin Engineering Company been purchased and/or installed in your facility? Since Marvin Engineering is principally a subcontracting Company, determine if your equipment originated with the Marvin Company and was eventually supplied to your facility through another contractor / supplier.
1.b. Provide a description of this equipment to include its purchase date and its design function during both normal and accident conditions.
2.
For each piece of identified equipment, provide the performance history associated with its usage. This should include the cause of any failures or salfunctions and the frequency of such events.
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IE Bulletin No. 80-02 January 21, 1980 Page 2 of 2
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3.
Provide infomation on the suppliers and receiver's QA/QC program in effect at the time of purchase. This information should be discussed in terms of it providing sufficient bases for judging that the integrity of the equipment is sufficient to permit plant operation during nomal and accident conditions.
Approved by GAO, B180225 (R0072); clearance expires 7-31-80.
Approval was given under a blanket clearance specifically for identified generic problems.
1930 055
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IE Bulletin No. 80-02 Enclosure January 21, 1980 RECENTLY ISSUED IE BULLETIM Bulletin Subject Date !ssued Issued To No.
80-01 Operability of ADS Va~lve 1/11/80 All BWR power reactor Pneumatic Supply facilities with an OL 79-01B Environmental Qualificatien 1/14/80 All power reactor of Class IE Equipment facilities with an OL 79-28 Possible Malfunction of 12nn9 All power reactor Namco Model EA 180 Limit faciltties with an Switches at Elevated OL or a CP Temperatures 79-27 Loss Of Non-Class-1-E 11/30n9 All power reactor Instrumentation and facilities holding Control Power System Bus OLs and to those During Operation nearing licensing 79-26 Boron loss From BWR 11/2009 All BWR power reacter Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2n9 All power reacter BFD Relays In Safety-Related facilities with an Systems OL or CP 79-17 Pipe Cracks In Stagnant 10/29n9 All PWR's with an (Rev. 3)
Borated Water System At OL and for information PWR Plants to other power reactors 79-24 frozen Lines 9/27n9 All power reactor facilities which have either OLs or cps and are in the late stage of construction 79-23 Potential Failure of 9/12n9 All Power React.r Emergency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction perinit 14 Seismic Analyses For 9hn9 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems
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