ML20040B688
| ML20040B688 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 01/13/1982 |
| From: | Cagnetta J, Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, AEC-MP3-260, B10378, NUDOCS 8201260318 | |
| Download: ML20040B688 (3) | |
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. January 13, 1982 Docket No. 50-423 AEC-MP3-260 f
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Mr. Ronald C. Ilaynes j
Region I
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Office of luspection and Enforcement U. S. Nuclear Regulatory Commission
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631 Park Avenue
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King of Prussi.a, PA 19406
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Centlemen:
Millstone Nuclear Power Station, Unit No. 3 Reportiny of Potential Significant Deficiences in Design and Construction Reliorts outstanding On November 24, 1981 our Mr. B.
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Carlson, Assistant Project Engineer, and Mr.
.l. M. Powers, l.icensing Engineer, met with your on-site inspector Mr. J. C. Mattia. One of the topics discussed was open 10 CFR 50.55e Significant Deficiency Reports which have interim reports, but lack final docketed reports. During the meeting, Mr. J.
C. Mattia verbally relayed those items he considered open.
After reviewing our records we have determined t hat some of these have been closed out by docketed final reports that have not been questioned by the NRC.
Some of the discrepancies extst because field corrective actions have not been completed, however, documentation and correspondence requirements with the NRC have been completed. We are hereby documenting the results of our review in order to confirm the status of these items.
Our dis-cussions with Mr. Mattia have been very beneficial towards achieving resolution of their status.
Group 1, shown below, contains six (6) iterm which we consider open and we owe you further correspondence on.
Group 2 contains four (4) items we have closed out but have been indicated as open items by your site inspector.
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. CROUP 1 - OUTSTANDING:
o SD-2 Colt Emergency Diesel Generator Last Report January 25, 1981 AEC-MP3-217 The'following are open:
- a. Omission of plugs in oil supply system
- b. Inadequate thrust bearing cicarance
- c. Flared fuel lines - Ik" Final Report Will be sent by January 25, 1982 o
SD-6 Westinghouse Guidetube Support Pins Last Report April 15, 1980 AEC-MP3-207 Status Westinghouse is currently developing inspection tooling and procedures. A site and date has not yet been set for the U. S. Operating Plant Inspections referred to in our previous report.
Next Interim Report ny July 1,1982 o
SD-9 Main Feedline Rupture With Failure of Blowdown System Last Report October 9, 1980 AEC-MP3-222 i
Status The feedwater simulation study is being completed.
Final review will rest on it's results.
Final Report Will be sent March 1, 1982 o
SD-8 Maintenance of Minimum Charging Pump Flow After Secondary Side liigh Energy Line Rupture Last Report June 14, 1980 AEC-MP3-210 Status S&W and NUSCO have been involved in lengthy discussions as to the need, if any, for a fix.
Final Report Will be sent February 1, 1982 o
SD-11 Potential for Loss of All Auxiliary Feedwater Following a Small Steam Line Rupture Last Report November 20, 1980 AEC-MP3-225 Status Currently under final review at NUSCO.
Final Report Will be sent by February 1, 1982 o
SD-17 Containment Liner Fire Damage Last Report October 13, 1981 AEC-MP3-240 Status Currently undergoing further inspection prior to detailed engineering of a repair design.
Next Interim Report By January 15, 1982, containing schedule and i
fire prevention information.
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GROUP 2 - COMPLETED:
o SD-5*
Missing Orefices Between Class 1 and Class 2 Piping Systems Final Report Sent February 25, 1980 AEC-MP3-205 o
SD-7*
Component Cooling / Heating Exchanger Supports Final Report Sent May 8, 1980 AEC-MP3-207 o
SD-14 Graver Weld Procedures Final Report Sent December 17, 1981 AEC-MP3-257 o
SD-16 Volume Control Tank Level Control System Closed as not significant by Telecon on 6/22/81 from Mr.
Carlson to Mr. Callo of NRC.
- In both these cases Mr. Matti, is holding his file open until completion of physical repair at the site.
We trust you are in agreement with us concerning the six (6) 10 CFR 50.55e reports which are currently open.
For four (4) of them a final report is forthcoming.
In the case of the other two (2), interim status reports will be forwarded before the final reports.
Very truly yours, l
NOhTilEAST NUCLEAR ENERGY COMPANY lb. 6 Gm s'/
W. G. Counsil Senior Vice Prei.ident LM /lb By:
. Cagne a Vice esident Niclear and Environmental Engineering cc:
Mr. James 11. Sniezek, Director Division of Resident and Regional Reactor Inspection Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.
20555
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