ML19260C790
| ML19260C790 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, LaSalle  |
| Issue date: | 01/22/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8002060084 | |
| Download: ML19260C790 (1) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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GLEN ELLYN, ILLINOIS 60137 d4N 2 2 1939 Docket Nos. 50-10, 50-237, 50-249, 50-254, 50-265, 50-373, 50-374, Commonwealth Edison Company ATTN:
Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 Gentlemen:
'15e 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, b)dnhw JamesG.Kepker Director
Enclosure:
IE Bulletin No. 80-02 cc w/ encl:
Mr. D. L. Peoples, Director Central Files of Nuclear Licensing Director NNR/DPM Mr. B. B. Stephenson,-
Director NNR/ DOR Station Superintendent PDR Mr. N. Kalivianakis, Local PDR Plant Superintendent NSIC Mr. L. J. Burke, Site TIC Project Superintendent Mr. Dean Hansell, Office of Mr. T. E. Quaka, Quality Assistant Attorney General Assurance Supervisor Mr. R. H. Holyoak, Station Superintendent 1930 069 8002060 OU h
SSINS No.: 6820 a
Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT m'-
r, WASHINGTON, D.C.
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.1 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 overall QA and QC programs which had come under severe criticism by a former Marvin Engineering employee. The special inspection was judged necessary since the Harvin 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 i.his inspection, twenty seven deviations from applicabic codes, and contrac-taal and regulatory requirements were documented b the areas of material icentification and control, process control, weldine and nondestructive s
exan;ination.
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.
Action To Be Taken All BWR licensees and construction permit holders shall supply the following infomation within 90 days for operating plants and 120 days for plants under construction.
1.a. Have reactor feedwater spargers and themal sleeves manufactured and/or fabricated by the Harvin 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 malfunctions and the frequency of such events.
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IE Dulletin No. 80-02 January 21, 1980 Page 2 of 2 e
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 normal 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 071
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IE Bulletin No. 80-02 Enclosure January 21, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-01 Operability of ADS Valve 1/11/80 All BWR power reactor Pneumatic Supply facilities with an OL 79-01B Environmental Qualification 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 facilities with an Switches at Elevated OL or a CP Temperatures 79-21 Loss Of Non-Class-1-E 11/30/79 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 11/20n9 All BWR power reactor Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2n9 All power reactor BFD Relays In Safety-Related facilities with an Systems OL or CP 79-17 Pipe Cracks In Stagnant 10/29D9 All PWR's with an (Rev. 1)
Borated Water System At OL and for information PWR Plants to other power reactors 79-24 Frozen Lines 9/27D9 All power reactor facilities which have either OLs or cps and are in the late stage of construction 79-23 Potential Failure of 9/12/79 All Power Reactor Emergency Diesel Facilit 4s with an Generator Field Operating License or Exciter Transformer a construction permit
-- 79-14 Seismic Analyses For 9hn9 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an
--OL or a CP Piping Systems 1930=072
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