View source for B10987, Forwards ASME Section Iii,Class 2 & 3 & ANSI B31.1.0 Piping Analysis, Ultrasonic Indications in Steam Generator Top Head Dome Weld. Evaluation Verified Structural Integrity of Plant Steam Generators,Per NRC

{{Adams
| number = ML20080K714
| issue date = 12/30/1983
| title = Forwards ASME Section Iii,Class 2 & 3 & ANSI B31.1.0 Piping Analysis, Ultrasonic Indications in Steam Generator Top Head Dome Weld. Evaluation Verified Structural Integrity of Plant Steam Generators,Per NRC
| author name = Counsil W, Sears C
| author affiliation = NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000336
| license number = 
| contact person = 
| document report number = B10987, B19987, TAC-51997, NUDOCS 8402160113
| title reference date = 10-21-1983
| package number = ML20080K715
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 1
| project = TAC:51997
| stage = Other
}}

=Text=
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                                      $ 7'~~                                                                                HARTFORD, CONNECTICUT 06141-0270 L   g                                                                                                                  (203) 666-6911 8e0Rf 44ST ssJCLE AR Ewmov cowape, December 30,1983 Docket No. 50-336 B10937 Dr. Thomas E. M urley                                                                                                                                       l Regional Administrator                                                                                                                                      l
[          Region I
!          U. S. Nuclear Regulatory Commission
[          631 Park Avenue
;          King of Prussia, PA 19406

==References:==
(1)                   R. W. Starostecki letter to W. G. Counsil, dated October 21,                                               )
1983.                                                                                                      I Gentlemen:
Millstone Nuclear Power Station, Unit No. 2                                                                I Steam Generator Upper Head Dome Welds                                                                     }
Inservice examinations of the Millstone Unit No. 2 steam generator shells indicated the presence of discontinuities at the mid-wall of weld THS-2 in both steam generators. Details of these indications were discussed in your inspection report of Reference (1). Northeast Nuclear Energy Company (NNECO) has
;          evaluated these indications in accordance with paragraphs IWB-3122.4 and IWB-
}          3600 of the ASME Code, Section XI,1980 Edition with Addenda through Winter, 1980.
The attached evaluation verifies the structural integrity of the Millstone Unit No. 2 steam generators and demonstrates the acceptability of the components for continued operation f or their 40 year design lif e.
In accordance with IWB-3122.4, the steam generator weld area containing the indications will be reexamined dtring the next three inspection periods. If the indications remain essentially tochanged, then the area will revert to its original inspection schedule.
We trust you find this inf ormation satistactory.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY W.h W . G. Ccunsil Senior Vice President 8402160113 831230 PDR ADOCK 05000336 O                                                                By: C. F. Sears PDR           Vice President, Nuclear and Environmental Engineering cc:     J. R. Miller
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