ML20073S816
| ML20073S816 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/05/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8305100148 | |
| Download: ML20073S816 (2) | |
Text
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h DUKE POWER GOMPANY P.O.190K 33180 Cl!ARLOTTE, N.C. 28242 i
HAL H. TUCKER TELEPHONE vsom reemenant (70 4) 37M531 stueam recovernow May 5, 1983 i
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:
Ms. E. G. Adensam, Chief j
Licensing Branch No. 4 Re: McGuire Nuclear Station Docket Nos. 50-369, 50-370
Dear Mr. Denton:
Attached is revised information regarding the McGuire steam generator inspection prc, gram following installation of the preheater modification. The attached page replaces page 2 of the attachment to my April 28, 1983 letter on this same subject. Please advise if there are further questions regarding this matter.
Very truly yours,
.Hal B. Tucker l
GAC/php Attachment cc:
Mr. James P. O'Reilly, Regional Administrator U.-S. Nuclear Regulatory Commission Region II 101 Marietta-Street, NW, Suite 2900 Atlanta, Georgia 30303 4
Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station SON B305100148 830505 PDR ADOCK 05000369 G
to the NRC for information.
Long term potential of the manifold to reduce tube wear will be verified from ECT measurements taken at the first refueling outage and ECT measurements from subsequent outages. No acceptance criteria related to tube vibration have been established; however, as a general criterion, overall tube response should be within that of an unmodified steam generator at 50% power.
This program is applicable to Unit 1 only.
Eddy Current Testing The ECT program described in the February 3, 1983 submittal will be followed with a few additional clarifications. The table below summarizes the ECT program for the preheater region.
3 3
l Second Subsequent l
All S/Gs, Post-First Installation Examination Examination Examinations Row 49 X
X X
X Row 48 X
X X
Row 47 X
X Row 46 X
X Row 45 X
X Peripheral Tubes X
X Tubes w/ indications -
X X
from previous 2
testing 1 First S/G inservice examination following installation of modification to include all steam generators.
2 Applicable only if tubes are located in other than row 49 or row 48 (second examination) or row 49 (subsequent examinations).
3 To include at least two steam generators. Additional inspections will be performed as necessary so that degradation rate can be established.
The above program is supplemental to that required by Technical Specifications and will be applied to both Units 1 and 2 steam generators.
The minimum number of steam generators which are examined during each inspection period will be determined by Technical Specification require ents, f
Visual Inspection Duke Power Company will conduct the visual inspection of the modification using l
remote inspection techniques in accordance with ASME Boiler and Pressure Vessel l
Code,Section XI, IWA-2211, Visual Examination, VT-1.
This examination will I
be conducted on all steam generators following installation of the modification and again during the first examination performed inservice.
In subsequent outages during which the Technical Specification required ECT is performed, visual examination of one steam generator modification will be performed using the same criteria,Section XI, IWA-2211. This would mean that each steam generator modification would be visually examined at least every four years. Visual inspection at this frequency balances the positive l
Revised 5/5/83 l