ML17251A193
| ML17251A193 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/29/1988 |
| From: | Stahle C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8808040180 | |
| Download: ML17251A193 (12) | |
Text
Docket No. 50-244 July 29, 1988 APPLICANT:
Rochester Gas and Electric Corporation t
FACILITY:
6 INNA
SUBJECT:
Meeting Summary On July 19, 1988, the NRC staff met with representatives from Rochester Gas and Electric Corporation (RGE) and its consultants from Combustion Engineering to discuss steam generator sleeving utilizing a new technique for sleeve installation.
For the past several years RGE has,successfully sleeved the GINNA steam generators, whereby narrow tubes are inserted and welded in place over corroded portions of tubing which would leak if not sealed.
The alternative to sleeving is plugging at the tube ends which removes the tube from service.
Currently sleeving at GINNA is done with a 27 inch inconel sleeve welded at the top and bottom of the sleeve.
At present, only tubes in the central portion of the steam generator (about 60$ of the tubes) can be sleeved by conventional methods due to space limitations on 'the periphery of the hemispherical plenum at the face of the tube bundle.
Tubes requiring repair on the periphery are plugged.
The purpose of the meeting was for RGE to describe the development program which would result in a sleeve design and necessary tooling to service currently unreachable areas of the steam generators such that as much as 95$ of the steam generators could be sleeved for extended service life.
The development program consisted of three phases:
- 1) Bent sleeve testing to determine if bending results in residual stresses and testing the rotational accuracy of flexible weld/UT tools.
- 2) Prototype tooling and mock-up testing to build one complete set of flexible tools, to qualify the installation process for field use and to determine the optimum configuration of tooling.
- 3) Final tool fabrication and crew training to build field ready production tools, to certify equipment for field use, to finalize installation procedures, and to train crews.
The development program began in late 1987 and periphery sleeving is targeted for steam generator implementation during the March 1989 refueling outage.
RGE and Combustion 'Engineering stressed the fact that the program is built on the fully developed and -proven technology for sleeving steam generator.
To
- date, the new RGE program is proceeding on schedule and no difficulties are anticipated.
The NRC staff stated that it was interested in this program and it would like to see the results of the effort.
Some concern was noted on the capability of the eddy current testing system to insure detection of tube wall flaws through the sleeve.
The need for a formal approval of the new techniques was discussed;
- however, no conclusion was reached on the licensing actions that would be required on the GINNA docket.
8808040180 880729 PDR ADOCK 05000244 PDC fNl
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l The attendance list of the meeting is enclosed.
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Enclosure:
As stated Carl Stahle, Project Manager Project Directorate I-3 Division of Reactor Projects I/II DISTRIBUTION: SDocket Fil~e, NRC It Local
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Mr. Roger W. Kober Rochester Gas and Electric Corporation R.
E. Ginna Nuclear Power Plant CC:
Harry H. Voigt, Esquire
- LeBoeuf, Lamb, Leiby and MacRae 1333 New Hampshire
- Avenue, N.W.
Suite 1100 Washington, D.C.
20036 Ezra Bialik Assistant Attorney General Environmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector R.E.
Ginna Plant c/o U.S.
NRC 1503 Lake Road
- Ontario, New York 14519 Stanley B. Klimberg, Esquire General Counsel New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Supervisor of the Town of Ontario 1850 Ridge Road
- Ontario, New York 14519 Ms.
Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Mr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, N.Y. 14649-0001
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Enclosure Attendees Name 7/19/88 Or anization C. Stahle, PM George Wrobel, Sr. Engineer Paul Gorski, Station Engineer John F. Smith, Manager Mat. Engineer Clark M. Owens Alfred Depeau, Supervisor Tooling Develop.
Dick Wessman, Director, PDI-3 H. F. Conrad, Sr. Materials Engineering Keith Wichman, Section Chief Paul Wilkens, Manager NRC Engineer Emmett Murphy, Materials Engineer NRR Rochester Gas 5 Electric Rochester Gas I5 Electric Rochester Gas 5 Electric Combustion Engineering Combustion Engineering NRR NRR NRR/EMTB RGE NRR/EMTB
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Docket No. 50-244 July 29, 1988 APPLICANT:
Rochester Gas and Electric Corporation FACILITY:
GINNA
SUBJECT:
Meeting Summary On July 19, 1988, the NRC staff met with representatives from Rochester Gas and Electric Corporation (RGE) and its consultants from Combustion Engineering to discuss steam generator sleeving utilizing a new technique for sleeve installation.
For the past several years RGE has successfully sleeved the GINNA steam generators, whereby narrow tubes are inserted and welded in place over corroded portions of tubing which would leak if not sealed.
The alternative to sleeving is plugging at the tube ends which removes the tube from service.
Currently sleeving at GINNA is done with a 27 inch inconel sleeve welded at the top and bottom of the sleeve.
At present, only tubes in the central portion of the steam generator (about 605 of the tubes) can be sleeved by conventional methods due to space limitations on the periphery of the hemispherical plenum at the face of the tube bundle.
Tubes requiring repair on the periphery are plugged.
The purpose of the meeting was for RGE to describe the development program which would result in a sleeve design and necessary tooling to service currently unreachable areas of the steam generators such that as much as 95K of the steam generators could be sleeved for extended service life.
The development program consisted of three phases:
- 1) Bent sleeve testing to determine if bending results in residual stresses and testing the rotational accuracy of'flexible weld/UT tools.
- 2) Prototype tooling and mock-up testing to build one complete set of flexible tools, to qualify the installation process for field use and to determine the optimum configuration of tooling.
- 3) Final tool fabrication and crew training to build field ready production tools, to certify equipment for field use, to finalize installation procedures, and to train crews.
The development program began in late 1987 and periphery sleeving is targeted for steam generator implementation during the March 1989 refueling outage.
RGE and Combustion Engineering stressed the fact that the program is built on the fully developed and proven technology for sleeving steam generator.
To
- date, the new RGE program is proceeding on schedule and no difficulties are anticipated.
The NRC staff stated that it was interested in this program and it would like to see the results of the effort.
Some concern was noted on the capability of the eddy current testing system to insure detection of tube wall flaws through the sleeve.
The need for a formal approval of the new techniques was discussed;
- however, no conclusion was reached on the licensing actions that would be required on the GINNA docket.
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~
~ The attendance list of the meeting is enclosed.
rs/
cc:
See next page
Enclosure:
As stated Carl Stahle, Project Manager Project Directorate I-3 Division of Reactor Projects I/II DISTRIBUTION:
Docket File, NRC In Local
- PDRS, PDI-3 r/f, CStahle,
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88
- 07W/88 OFFICIAL RECORD COPY
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