ML19260C793
| ML19260C793 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 01/22/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8002060093 | |
| Download: ML19260C793 (1) | |
Text
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'o, UNITED STATES 8
7, NUCLEAR REGULATORY COMMISSION e
REGION lli
.:((
0, T99 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 UAfi 2 2 580 Docket No. 50-155 Consumers Power Company ATTN:
Mr. R. B. DeWitt Vice President Nuclear Operations 212 Jest Michigan Avenue Jackson, MI 49201 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, b
VJames G. Kepp er Director
Enclosure:
IE Bulletin No. 80-02 cc w/ encl:
Mr. D. P. Hoffman, Nuclear Licensing Administrator Mr. C. J. Hartman, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Myron M. Cherry, Chicago 1930 057 s ooem C)93
4 SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON. L.C.
20555 Janua y 21, 1980 IE Bulletin No. 80-02 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED EQUIPMENT Description of Circumstances:
Thr, 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 severt criticism by a former 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 f
examination.
Corrective Action The Marvin Engineering Company has been issued the NRC's detailed inspection report of the Company, and given 30 days to infom 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 information 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 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 prformance history associated with its usage. This should include the cause of any failures or at1 functions and the frequency of such events.
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IE Bulletin No. 80-02 January 21, 1980 Page 2 of 2 d
3.
Provide information 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 059
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IE Bulletin No. 80-02 Enclosure O
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 12n n9 All power reactor Namco Model EA 180 Limit facilities 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 11/20/79 All BWR power reactor Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2D9 All power reactor BFD Relays In Safety-Related facilities with an Systems OL or CP 79-17 Pipe Cracks In Stagnant 10/29R9 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 9/27n9 All power reactor facilities which have either OLs or cps and are in the late stage of construction 79-23 Potential Failure of 9/12R9 All Power Reactor Emergency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction permit 14 Seismic Analyses For 9nn9 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems
- -OL or a CP
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