ML19262C129
| ML19262C129 | |
| Person / Time | |
|---|---|
| Issue date: | 01/23/1980 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8002060140 | |
| Download: ML19262C129 (2) | |
Text
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8 NUCLEAR REGULATORY COMMISSION y
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GLEN ELLYN. ILLINOIS 60137 JAN 2 31980 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. 80-02 titled " Inadequate Quality Assurance For Nuclear Supplied Equipment" was sent to the following licensees on January 21, 1980, for action.
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company 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)
Consumers Power Compsny Big Rock Point (50-155)
Dairyland Power Cooperative IFBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462) l'920 308
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Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
The Ohio Edison Company Erie 1, 2 (50-580, 50-581)
Sincerely, 54
. WY orothy Carroll, Acting Chief Administrative Br-ci
Enclosure:
IE Bulletin No. 80-02 cc w/ enc 1:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC TIC 1920 309
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SSINS No.: 6820
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Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT q
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January 21, 1980 IE Bulletin No. 80-02 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED EQUIPMENT Description of Circumstances:
The Harvin 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 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 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 pemit holders shall supply the following information within 90 days for operating plants and 120 days for plants under constructic:..
1.a. Have reactor feedwater spargers and thermal 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. Provida 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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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.
1920 311 u-_;
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IE Bulletin No. 8t0-02 Enclosure January 21, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Icsued 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/79 All power reactor Namco Model EA 180 Limit facilities with an Sititches at Elevated OL or a CP Temperatures 79-27 Loss Of Non-Class-1-E 11/30D9 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 11/20D9 All BWR power reactor Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2M9 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 9/27n9 All power reactor facilities which have either OLs or cps and are in the late stage of construction 79-23 Potential Failure of 9/12/79 All Power Reactor Emergency Diesel Facilities with an Generator Field Operating License or Exciter Transformer a construction permit 79-14 Seismic Analyses For 9Bn9 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems
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