ML19260C784
| ML19260C784 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/21/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | John Miller GEORGIA POWER CO. |
| References | |
| NUDOCS 8002060065 | |
| Download: ML19260C784 (2) | |
Text
'/
'o UNITED STATEb
~,,
NUCLEAR REGULATORY COMMISSION
-A <.nE REGION 11 3-o 101 MARIETT A ST., N.W., SUITE 3100
%,.....,/
ATLANTA, G EoRGI A 30303 JAN 211990 In Reply Refer To:
Rll:JP0 (50-321,50-366)
Georgia Power Company Attn:
J. H. Miller, Jr.
Executive Vice President 270 Peachtree Street, N.W.
Atlanta, Georgia 30303 Gentlemen:
The enclosed 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,
.-yQ
(
3g e4 James P. O'Reilly Director
Enclosures:
1.
Listing of IE Bulletins Recently Issued 1930 095 8002060O( S
JAN 211980 Georgia Power Company.
cc w/ encl:
M. Manry, Plant Manager Post Office Box 442 Baxley, Georgia 31513 C. E. Belflower Site QA Supervisor Post Office Box 442 Baxley, Georgia 31513 W. A. Widner, General Manager Nuclear Generation Georgia Power Company s
Post Office Box 4545 Atlanta, Georgia 30303 e
8 a
4 S
1930 096
SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT mp g
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,E WASHINGTON, D.C.
20555 J
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- m GJ11 [ b 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 war, Lc vbiect 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 le 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 desiga function dur.ng 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.
1930 097
4 IE Bulletin No. 80-02 January 21, 1980 Page 2 of 2 3.
Provide information on the suppliers and receivmr'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 098
IE Bulletin No. 80-02 Enclosure January 21, 1980 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
80-02 Inadequate Quality Assurance 1/21/80 All BWR power reactor for Nuclea; Jupplied Equipment licensees with OL or CP 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 12/7/79 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 11/30/79 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 11/20/79 All BWR power reactor Control Blades facilities with an OL 79-25 Failures of Westinghouse 11/2/79 All power reactor BFD Relays In Safety-Related facilities with an Systems OL or CP 79-17 Pipe Cracks In Stagnant 10/29/79 All PWR's with an (Rev. 1)
Borated Water System At OL and for information PWR Plants to other pcwer reactors 79-24 Frozen Lines 9/27/79 All power reactor facilities which have either OLs or cps and a re 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 9/7/79 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems OL or a CP i930 099