ML19260C788
| ML19260C788 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Hartsville  |
| Issue date: | 01/21/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8002060072 | |
| Download: ML19260C788 (2) | |
Text
.
- pa atouq'o, UNITED STATES 8 ' )I
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NUCLEAR REGULATORY COMMISSION n
5
.E REGION 11 o
101 MARIETTA ST N.W., SulTE 3100
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ATLANTA, CEORGI A 30303 JAN 211980 In fec,To:
dD-259ff0-2603' c3Q-296,MO-518 50-519, Tennessee Valley Authority Attn:
H. G. Parris Manager of Power 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 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,
( --
James P. O' Reil Director
Enclosures:
1.
Listing of IE Bulletins Recently Issued 1930 085 S
8002060 O 9
Jr.?/ p 1 199,)
Tennessee Valley Authority cc w/ enc 1:
H. L. Abercrombie Plant Superintendent Post Office Box 2000 Decatur, Alabama 35602 J. F. Cox 400 Commerce Street W10C131 C-K Knoxville, Tennessee 37902 D. E. McCloud, Project Engineer 400 Chestnut Street Tower II Chattanooga, Tennessee 37401 E. G. Beasley Tennessee Valley Authority 309 Grant's Building Knoxville, Tennessee 37902 9 '
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1930 086
SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT ] r
~ ig r q, c a r, 2 WASHINGTON, D.C.
20555 gj 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 Marvia 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 Acti_on The Marvin Engineering Ccepany 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 087
IE Bulletin No. 80-02 January 21, 1980 Page 2 of 2 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 tat the integrity of the equipment is sufficient to permit plant operat 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 088
IE Bulletin No. 80-02 Enclosure Janua ry 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 Nuclear Supplied 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 3ystem 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 power reactors 79-24 Frozen Lines 9/27/79 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 9/7/79 All Power Reactor (Supplement 2) As-Built Safety-Related Facilities with an Piping Systems OL or a CP 1930 089