ML19262C124
| ML19262C124 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/21/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Leonard J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 8002060128 | |
| Download: ML19262C124 (1) | |
Text
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,d UNITED STATES y
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g NUCLEAR REGULATORY COMMISSION E
REGION I a.,
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KING CP PRUSSIA, PENNSYLVANIA 19406
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Docket No. 50-333 JaN 2 : G3g Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr. J. D. Leonard
.'tesident Manager P. O. Box 41 Lycoming, New York 13093 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, r
1
/
,/ k f oyce H. Grier Director
Enclosures:
1.
List of Recently Issued IE Bulletins CONTACT:
S. D. Ebneter (215-337-5283) cc w/encis:
George T. Berry, Executive Director P. W. Lyon, Manager - Nuclear Operations A. Klausmann, Director, Quality Assurance M. C. Cosgrove, Quality Assurance Supervisor J. F. Davis, Chairman, Safety Review Committee C. M. Pratt, Assistant General Counsel G. M. Wilverding, Licensing Supervisor 1920 335 8 0 0 u 0 0 0 /98 g
ENCLOSURE 1 SSINS No.: 6820 Accession No.:
UNITED STATES 7912190653 NUCLEAR REGULATORY COMMISSION q g] q ; e7 0FFICE OF INSPECTION AND ENFORCEMENT Hg u! o :*%. a b-WASHINGTON, D.C.
20555 o dd J il IE Bulletin No. 80-02 Date:
January 21, 1980 Page 1 of 2 INADEQUATE QUALITY ASSURANCE FOR NUCLEAR SUPPLIED EQUIPMENT Descriotion 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 3ince 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 froa applicable codes, and contractual and regulatory requirements were documented in the areas of material identification and control, process control, weing and nondestructive examination.
Corrective Action The Marvin Engineering Company has bcca 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 faction during both normal and accident conditions.
I'920 336 IE Bulletin No. 80-02 Date:
January 21, 1980 Page 2 of 2 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.
i920 337
ENCLOSURE 2 IE Bulletin No. 80-02 Date: January 21, 1980 Page 1 of 1 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
79-17 Pipe Cracka 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 11/8/79 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 Temperatures79-01B 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 f920 338