ML18052A258: Difference between revisions
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| issue date = 01/27/1986 | | issue date = 01/27/1986 | ||
| title = Forwards 1985 Steam Generator Inservice Insp Rept of Eddy Current Testing,Data Evaluation & Tube Repair. Insp Conducted on 851201-30.No Further Degradation of Steam Generator a or B Tubing Occurred | | title = Forwards 1985 Steam Generator Inservice Insp Rept of Eddy Current Testing,Data Evaluation & Tube Repair. Insp Conducted on 851201-30.No Further Degradation of Steam Generator a or B Tubing Occurred | ||
| author name = | | author name = Kuemin J | ||
| author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | ||
| addressee name = | | addressee name = | ||
Revision as of 20:48, 17 June 2019
| ML18052A258 | |
| Person / Time | |
|---|---|
| Site: | Palisades |
| Issue date: | 01/27/1986 |
| From: | Kuemin J CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18052A259 | List: |
| References | |
| NUDOCS 8602030153 | |
| Download: ML18052A258 (1) | |
Text
- consumers Power company General Offices: 1945 West Parnell Ro11d, Jackson, Ml 49201 * (517) 788-0550 January 27, 1986 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 -LICENSE
-PALISADES PLANT -
STEAM GENERATOR INSERVICE INSPECTION REPORT ; \ \ * / In accordance with Technical Specificatiq'.n 4.14.6, the enclosed Steam Generator Inseivice Inspection Report is The inspection occurred from December 1 to December.'
30, 1985 when the final tube plugging occurred.
A total of eight (8) tubes,;.were plugged following the inspection; all were located in "B" Steam Generator:"* (see Attachment 5 for details).
The number of tubes plugged does not the assumptions or change the safety analysis. ,I " It is Consumers Power Company's belief that the str1'cf *adherence to secondary water .purity limits and maintaining the secondary s'a:de of the steam generators in wet lay-up, as much as possible, during conditions has limited tube corrosion.
The results of 1985 show, essentially, no further degradation of the "A" or "B" steam tul;>ing occurred during the last operating cycle.
L Kuemin -Staff Licensing Engineer CC Administrator, Region III, USNRC NRC Resident Inspector
-Palisades
- ea02030153 860127 w* . '1* PDR ADOCK 05000255
- G PDR ! . I . -( ". OC0186-0012-NL02