ML19257D754
| ML19257D754 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 01/22/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 8002060105 | |
| Download: ML19257D754 (1) | |
Text
/
'o,%
UNITED STATES NUCLEAR REr.0LATORY COMMISSION rg~Ngi
(
.E nEGION 111 o,
'[
799 ROOSEVELT ROAD
% *****/
GLEN ELLYN. ILLINOIS 60137 JM 2 21980 Docket No. 50-367 Northern Indiana Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vica President 5265 Hohman Avenue Hammond, IN 46325 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, mb No ^ A ames G. Kep"pTer%
Director
Enclosure:
IE Bulletin No. 80-02 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dern Hansell, Office of Assistant Attorney General 195D 0\\1 0 0 0:10 6 0 l gg-CD
.-7.,,;n.n,c n n. m n : n ~,~. v.~.w v.~
w~
~, ~ ~
8I SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY C0tEISSION OFFICE OF INSPECTION AND ENFORCEMENT h pn, j
g,.
WASHINGTON, D.C.
20555 January 21, 1980 IE Bulletin No. 80-02 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED EQUIPMENT Description cf Circumstances:
The Marvin Engineering Company (MEC) of Inglewood, Cali#ornia was the subject of a special NRC inspection conducted on September 18 '.1, 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 ' actor internal feedwater spargers and feedwater thermal sleeves. The ress of the NRC's inspection established that serious deficiencies exist in uie 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, prccess control, welding and nondestructive examination.
Corrective Action The Harvin 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.
Acticn 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 6nd 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 perfor: ance history associated with its usage. This should include the cause of any failures or salfunctions and the frequency of such events.
1930 018 e-e+
-d e-.e
--.,.---.-e**=...--e e
e
I IE Bulletin No. 80-02 January 21, 1980 Page 2 of 2 3.
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.
f930 019
=__=====...
4 i'
IE Bulletin No. 80-02 Enclosure Janusry 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 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 79-2S Failures of Westinghouse 11/2/79 All power reactor BFD Relays In Safety-Related facilities with an Systams 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
.iy, 3
e
+ -,
,