ML19347F724
| ML19347F724 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/30/1981 |
| From: | Snaider R Office of Nuclear Reactor Regulation |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8105260135 | |
| Download: ML19347F724 (5) | |
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APR 3 01981 Memorandum for: Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing From:
Richard P. Snalder, Project Manager Operating Reactors Branch f5 Division of Licensing
Subject:
SlM%RY OF APRIL 28,1981 MEETING WITH ROCHESTER GAS AND ELECTRIC CORPORATION (
TO DISCUSS STEAh GENERATOR SLEEYiNG On Tuesday, April 28,1981, members of the NRC staff met with representatives of Rochester Gas and Electric (RG&E) Corporation and the Babcock and Wilcox Company (B&W). The meeting was convened to discuss the forthcoming reactor coolant punp bowl inspection and steam generator repairs at the R. E. Ginna Nuclear Power Plant, for which RG&E is the licensee. The attendance list is enclosed.
The bowl inspection for reactor coolant pump A is to be performd during the current refueling outage (Pump B will be inspected during the next inservice inspection 10 year interval. The three welds o# the pump bowl are being inspected by radiography utilizing a portable linear accelerator (MINAC). The MINAC unit will be physically located inside the pump bowl and the film cassette (shielded against background radiation) will be positioned on the exterior of the bowl. The major difficulty appears to be the radiography of the A weld because the location of the pump diffuser adds additional metal thickness. This weld may require four hours of exposure.
Radiation se.fety has played a major role in the design of equipment and the development of procedures. The controls and power supply will be located outside containment, and a full scale pump mockup, including internals, has been constructed of fiberglass in order to facilitate equipment design and testing and also to provide training for personnel who will be performing i
the radisgraphy. The radiographs will be available for review shortly after the inspections are completed.
With regard to the steam generator inspection and repair, RGd personnel noted that this is a continuation of the program presented to, and accepted l
by, the NRC staff during the fall of 1980. Approval was granted at that time for de installation of ten sleeves in the B steam generato". These sleeves restore steam generator integrity otherwise degraded by corrosion l
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in tubes subjected to intergranular attack in the generator tubesheet, and are an alternative to plugging of the tubes and, ultimately, replace-j ment of the steam generators if plugging limits are reached. Ginna's l
design basis includes a 10% plugging limit per generator, and with 112 tubes plugged, the 8 generator is at 3.4%.
Unlike other facilities encountering the intergranular attack in the tubesheet, Ginna has relatively little problem with sluge buildup. This is attributed partly to a 1978 shift to all-volatile chemical treatment of the generators and use of full-flow deep-bed feedwater domineralizati2n.
Substantial information was presented regarding development efforts for
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improved sleeves, tools and procedures. The majority of this information is proprietary to Babcock and Wilcox and has been sut,mitted to the NRC In report form. The main point is that, although the sleeving efforts last year resulted in an average of 13.5 rem / sleeve installed, the advances made to date have lowered that to less than 1 rem / sleeve during the present outage and show promise of future reduction to approximhtely 400 mr/ sleeve. RGAE and B&W are also confident that their i
eddy-current testing technique is sufficiently advanced for use in inspect-ing the sleeves and the sleeve-to-tube interfaces.
As a final point, RG&E discussed a proposed modification to the Ginna Inservice Inspectio^. Program. This mdification, submitted by letter dated April 23, 1981, would allow plugging or sleeving of degraded generator tubes and would allow the sleeving of 25 tubes in each generator during each outage without prior NRC approval. The NRC staff noted its approval of the plans for the present refueling outage but stated that approval of the overall plan would be delayed until detailed review could be completed.
Richard P. Snaider, Project Manager Operating Reactors Branch #5 Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page
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i Mr. John E. Maier CC Harry H. Voigt Esquire Director, Criteria and Standards LeBoeuf. Lamb, Le!by and MacRae Division 1333 New Hampshire Avenue, N. W.
Office of Radiation Programs Suite 1100 (ANR-460)
Washington, D. C.
20036 U. S. Environmental Protection Agency Mr. Michael Slade
' Washington, D. C.
20460 12 Trailwood Circle Rochester, New York 14618 U. 5. Environmental Protection Agency Ezra Bialik Region II Office Assistant Attorney General ATTN: EIS COORDINATOR Environmental Protection Bureau 26 Federal Pla:a New Ycrk State Department pf Law New York, New York 10007 2 World Trade Center New York, New York 10047 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Jeffrey Cohen U. S. Nuclear Regulatory Commission New York State Energy Office Washington, D. C.
20555 Swan Street Building Core 1 Second Floor Dr. Richard F. Cole Empire State Plaza Atomic Safety and Licensing Board Albany, New York 12223 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Director, Technical Development Programs Dr. Emmeth A. Luebke State of New York Energy Office Atomic Safety and Licensing Board Agency Building 2 U. S. Nuclear Regulatory Commission Empire State Plaza Washington, D. C.
20555 Albany, New York 12223 Mr. Thomas B. Cochran Rochester Public Library Natural Resources Defense Council, Ir.c.
115 South Avenue 1725 I Street, N. W.
Rochester, New York 14604 Suite 600 Washington, D. C.
20006 Supervisor of the Town of Ontario 107 Ridge Road West Ontario, New York 14519
' Resident Inspecter R. E. Ginna Plant c/o U. S. NRC 1503 Lake Road Ontario, New York 14519
ENCLOSURE ATTENDANCE LIST i
Name Organization Tom Baldwin B&W Licensing Al Paglia B&W Special Products J.R. Gleim NRC, MTEB Everett Beatty RG&E Special Projects William J. Collins NRC, IE Reactor Ops.
R. E. Johnson NRC/ DST /GIB caniel T. Huang NRC/00E/MTEB Dick Snaider
.NRC/DL/0RBf5 Michael W. Henig B&W Engr. Services Denny Crutchfield NRR/DL/0RBf5 Charles Marotta NPR/AEB Joel Feldstein B&W Research & Develop.
Bob Smith RG&E Engiaearing Jack Noon RG&E Ginna Statien John E. Maier RG&E Officer James C. Hutton RG&E Mechanical Engr.
Bob Mecredy RG&E Al Curtis RG&E Tir. Colburn NRC/0RBf3 Emett Murphy NRC/MTEB George Johison NRC/DE/MTEB r
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