ML19260C783
| ML19260C783 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/21/1980 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Strand N WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| References | |
| NUDOCS 8002060062 | |
| Download: ML19260C783 (1) | |
Text
7/C ff.p av e,,,*h, UNITED STATES 3
NUCLEAR REGULATORY COMMISSION n
- E REGION V 0,
[
1930 N. CAllFORNI A BOULEVARD D
,o SulTE 202, WALNUT CRE E K PLAZA
- e,,e WALNUT CREE K, CALIFORNI A 94596 January 21, 1980 Docket No. 50-397 Washington Public Power Supply System P. O. Box 968 3000 George Washington Way Richland, Washington 99352 Attn:
Mr. N. O. Strand Managing Director 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, s
Y'
[E. H.
ngelken R
Director
Enclosures:
1.
Listing of IE Bulletins Recently Issued cc w/ enclosures:
M. E. Witherspoon, WPPSS W. C. Bibb, Manager, WPPSS G. C. Sorensen, WPPSS 1930 100 a
soom non
SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT l'
~l c'
I WASHINGTON, D.C.
20555 J
J January 21, 1980 IE Bulletin No. 80-02 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED E0VIPMENT 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 0A and QC programs which had come under severe criticism by a e gineering employee. The special inspection was judged fomer t'arvin n
necessary sine _ the Marvin Engineering Campany was a known subcontractor and supplier to General Electric of BWR reactor internal feedwater spargers and feedwater themal 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 infomation within 90 days for operating plants and 120 days for plants under construction.
1.a. Have reactor feedwater sparcers and 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 oriainated with the Marvin Company and was eventually supplied to your facility throuqh 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 perfomance history associated with its usage. This should include the cause of any failures or malfunctions and the frequency of such events.
1930 101
IE Bulletin No. 80-02 January 21, 1980 Pace 2 of 2 3.
Provide information on the suppliers and receiver's OA/0C program in effect at the time of purchase. This information should be discussed in terms o'f it providing sufficient bases for judgina that the integrity of the equipment is sufficient to permit plant operation during nomal 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.
1~930 102
IE Bulletin No. 80-02 Enclosure January 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 79-018 Environnental Oualification 1/14/80 All power reactor of Class IE Eauipment facilities with an OL 79-28 Possible Malfunction of 12/7/79 All power reactor Namco Podel 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 nearinq licensing 79-26 Boron Loss From BWR 11/20/79 All BWR por: 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 Staanant 10/29/79 All PWR's with an (Rev. 1)
Borated Hater Systen 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 103