NRC Generic Letter 1980-08

NRC Generic Letter 1980-008: Transmittal of IE Bulletin 1980-002: Inadequate Quality Assurance for Nuclear Supplied Equipment

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)

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%-' 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 a their overall QA and QC programs which had come under severe criticism by former Marvin Engineering employee. The special inspection was judged necessary to since the Marvin Engineering Company was a known subcontractor and supplier 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.

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ENCLOSURE 2 IE Bulletin No. 80-02 Date: January 21, 1980 RECENTLY ISSUED IE BULLETINS

Bulletin Subject Date Issued Issued To No.

79-17 Pipe Cracks in Stagnant 10/29/79 All PWRs with an (Rev. 1) Borated Water Systems Operating License (OL)

at PWR Plant (for Action). All other Power Reactor Facilities with an OL or Construction CP

Permit (CP) (for In- formation)

79-25 Failures of Westinghouse 11/2/79 All Power Reactor BFD Relays in Safety- Facilities with an Related Systems OL or CP (for Action)

79-02 Pipe Base Plate Designs 11V/8/79 All Power Reactor (Rev. 2) Using Concrete Expansion Facilities with an Bolts OL or CP

79-26 Boron Loss From BWR 11/20/79 All BWR Power Reactor Control Blades Facilities with an OL

79-27 Loss of Non-Class-1-E 11/30/79 All Power Reactor Instrumentation and Con- Facilities with an OL

trol Power System Bus and those nearing During Operation Licensing (for Action)

All Power Reactor Facilities with a CP

(for Information).

79-28 Possible Malfunction 12/7/79 All Power Reactor of NAMCO Model EA180 Facilities with an Limit Switches at OL or CP

Elevated Temperatures

79-O1B Environmental Quali- 1/14/80 All Power Reactors fication of Class IE with an OL except Equipment SEP Plants

80-01 Operability of ADS Valve 1/14/80 All BWRs with an Pneumatic Supply OL