NRC Generic Letter 1980-08
| ML031350284 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/1980 |
| From: | Grier B NRC Region 1 |
| To: | |
| References | |
| BL-80-002 GL-80-008, NUDOCS 8002060136 | |
| Download: ML031350284 (4) | |
vqjplc-%-' UNITED STATES NUCLEAR REGULATORY
COMMISSION
REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA
19406 C7L-'?0-S'Docket No. 50-271 JAN 2 1 1980 Vermont Yankee Nuclear Power Corporation ATTN: Mr. Robert L. Smith Licensing Engineer 25 Research Drive Westborough, Massachusetts
01581 Gentlemen:
The enclosed IE 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,: Boyce H. Grier Director Enclosures:
L IE Bulletin No. 80-02 2. List of Recently Issued IE Bulletins
CONTACT
- S. 0. Ebneter (215-337-5283)
cc w/encls: W. F. Conway, Plant Superintendent Ms. J. Abbey, Technical Secretary Mr. J. E. Griffin, President 6 9, 0002 060 1-36 (q.
ENCLOSURE
1 SSINS No.: 6820 Accession No.: UNITED STATES 7912190653 NUCLEAR REGULATORY
COMMISSION
OFFICE OF INSPECTION
AND ENFORCEMENT
WASHINGTON, D.C. 20555 IE Bulletin No. 80-02 Date: January 21, 1980 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 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 contractual 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 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/sup- plier.1.b. Provide a description of this equipment to include its purchase date and its design function during both normal and accident conditions.
Enclosure
1 IE Bulletin No. 80-02 Date: January 21, 1980 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.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 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.
\.-.. I ENCLOSURE
2 IE Bulletin No. 80-02 Date: January 21, 1980 RECENTLY ISSUED IE BULLETINS Bulletin No.79-17 (Rev. 1)Subject Date Issued Pipe Cracks in Stagnant Borated Water Systems at PWR Plant 10/29/79 79-25 Failures of Westinghouse
11/2/79 BFD Relays in Safety-Related Systems Pipe Base Plate Designs 11V/8/79 Using Concrete Expansion Bolts 79-02 (Rev. 2)Issued To All PWRs with an Operating License (OL)(for Action). All other Power Reactor Facilities with an OL or Construction CP Permit (CP) (for In-formation)
All Power Reactor Facilities with an OL or CP (for Action)All Power Reactor Facilities with an OL or CP All BWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL and those nearing Licensing (for Action)All Power Reactor Facilities with a CP (for Information).
All Power Reactor Facilities with an OL or CP 79-26 79-27 Boron Loss From BWR Control Blades Loss of Non-Class-1-E
Instrumentation and Con-trol Power System Bus During Operation Possible Malfunction of NAMCO Model EA180 Limit Switches at Elevated Temperatures Environmental Quali-fication of Class IE Equipment 11/20/79 11/30/79 12/7/79 79-28 79-O1B 80-01 1/14/80 All Power Reactors with an OL except SEP Plants All BWRs with an OL Operability of ADS Valve 1/14/80 Pneumatic Supply