ML19260C780
| ML19260C780 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 01/21/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Weigand J GULF STATES UTILITIES CO. |
| References | |
| NUDOCS 8002060054 | |
| Download: ML19260C780 (1) | |
Text
7Z C-UNIT ED STATES
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o NUCLEAR REGULATORY COMMISSION REGloN IV f'*
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,,/ f January 21, 1980 In Reply Refer To:
RIV Docket Nos.
50-458/IE Bulletin No. 80-02 50-459/IE Bulletin No. 80-02 Gulf States Utilities Attn:
Dr. J. G. Weigand General Manager, Nuclear Projects Post Office Box 2951 Beaumont, Texas 77704 Gentlemen:
The enclosed IE Bulletin No. 80-02 is forwarded to you for action. A written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
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Karl V. Seyfri Director
Enclosures:
1.
Listing of IE Bulletins Recently Issued 1930 130 R 8002060o 5 9
SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
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em e-IE Bulletin No. 80-02 Date:
January 21, 1980 Page 1 of 2 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 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.
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 thermal 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 performance history associated with its usage.
This should include the cause of any failures or malfunctions and the frequency of such events.
i930 131
IE Bulletin No. 80-02 Date:
January 21, 1980 Page 2 of 2 3.
Provide information on the supplier's and receiver's QA/QC program in effect at the time of purchase.
This information should be discussed in terms of it providing sufficient basis 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 132
IE Bulletin No. 80-02 Janua ry 21, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
79-25 Failure of Westinghouse 11/2/79 All Power Reactor BFD Relays in Safety-Related Facilities with an Systems Operating License (OL) or a Construction Permit (CP) 79-26 Boron Loss from BWR 11/20/79 All BWR Power Reactor Control Blades Facilities with an Operating License (OL) for action.
All BWR's with a Construction Permit (CP) for information.
79-27 Loss of Non-Class-1-E 11/30/79 All power reactor Instrumentation and facilities holding Control Power System Bus Operating Licenses (OLs)
During Operation and to those nearing licensing 79-28 Possible Malfunction of 12/7/79 All power reactor Namco Model EA 180 Limit facilities with an Switches at Elevated Operating License (OL)
Temperatures or a Construction Permit (CP)79-01B Environmental Qualification 1/14/80 All power reactor of Class IE Equipment facilities with an Operating License (OL) 80-01 Operability of ADS Valve 1/11/80 All BWR power reactor Pneumatic Supply facilities with an Operating License (OL)
Enclosure 1930 133
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