ML17251A191
| ML17251A191 | |
| 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 8808040104 | |
| Download: ML17251A191 (10) | |
Text
Docket No.:
APPLICANT:
FACILITY:
SUBJECT July 29, 1988 50-244 Rochester Gas 8 Electric Corporation GINNA Meeting Summary On July 20, 1988, the NRC staff met with representatives from Rochester Gas 8
Electric Corporation (RGE) and its Westinghouse consultants to discuss the status of NRC review on the RGE application for amending the license to replace the steam generator snubbers.
A representative from Brookhaven National Laboratory was also in attendance to support the NRC staff.
The intent is to replace six of the eight hydraulic snubbers per steam generator with rigid structural members or bumpers.
A pair of existing snubbers will remain in the upper support configuration for each steam generator.
The replacement is expected to take place during the March 1989 refueling outage.
RGE and l<estinghouse representatives provided the staff further explanation and insight on various aspects of the report that was submitted in the amendment package of May 13, 1988.
The report summarizes the analysis performed to demonstrate that the proposed replacement will have no adverse effect on the reactor coolant system and any other safety-related system or component.
- Also, the discussion included comments on a series of questions from the NRC that was submitted on April 13, 1988.
The staff was satisfied that the existing documentation was sufficient for reviewing the proposed amendment with the exception of two areas in the Steam Generator Hydraulic Snubber Replacement
- Program, May 8, 1988, Revision 2.
In section 3.1.4, page 3-9, further clarification of the analysis is needed and a
basis for performing two analyses.
.In section 5.2. 1, page 5-1, further descriptive material is needed on the selected analyses that were performed for the cold shutdown condition.
The NRC staff review of this application is on schedule.
lilith the timely submittal of the aforementioned information, the Safety Evaluation Report should be completed by the end of August 1988.
Enclosed is the list of attendance for this meeting.
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Carl Stahle, Project Manager Project Directorate I-3 Division of Reactor Projects I/II C
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MET.SUMARRY GINNA 7/20/88 DISTRIBUTION:
Docket File NRC 5 Local PDRs PDI-3 r/f RWessman CStahle OGC-Rockville EJordan BGrimes ACRS (10)
HBClayton NRC Partici ants L. B. Mars P. Bezler P. T.
Kuo Mark Hartzman Lee Bettenhausen, Region I
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Docket No.:
50-244 0
July 29, 1988 APPLICANT:
FACILITY:
SUBJECT:
Rochester Gas
& Electric Corporation GINNA Meeting Summary.
On July 20, 1988, the NRC staff met with representatives from Rochester Gas Electric Corporation (RGE) and its Westinghouse consultants to discuss the status of NRC review on the RGE application for amending the license to replace the steam generator snubbers.
A representative from Brookhaven National Laboratory was also in attendance to support the NRC staff.
The intent is to replace six of the eight hydraulic snubbers per steam generator with rigid structural members or bumpers.
A pair of existing snubbers will remain in the upper support configuration for each steam generator.
The replacement is expected to take place during the March 1989 refueling outage.
RGE and Westinghouse representatives provided the staff further explanation and insight on various aspects of the report that was submitted in the amendment package of May 13, 1988.
The report summarizes the analysis performed to demonstrate that the proposed replacement will have no adverse effect on the reactor coolant system and any other safety-related system or component.
- Also, the discussion included comments on a series of questions from the NRC that was submitted on April.13, 1988.
The staff was satisfied that the existing documentation was sufficient for reviewing the proposed amendment with the exception of two areas in the Steam Generator Hydraulic Snubber Replacement
- Program, May 8, 1988, Revision 2.
In section
- 3. 1.4, page 3-9, further clarification of the analysis is needed and a
basis for performing two analyses.
In section 5.2. 1, page 5-1, further descriptive material is needed on the selected analyses that were performed for the cold shutdown condition.
The NRC staff review of this application is on schedule.
With the timely submittal of the aforementioned information, the Safety Evaluation Report should be completed by the end of August 1988.
Enclosed is the list of attendance for this meeting.
Original signed by';
Carl Stahle, Project Manager Project Directorate I-3 Division of Reactor Projects I/II cc:
See next page
Enclosure:
As stated
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lAMEQ lATE:07 hie:mw
- RW ssman
/88
- 07
/88 OFFICIAL RECORD COPY
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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 Mr. Bruce A. Snow, Superientendent Nuclear Production Rochester Gas 5 Electric Corporation 89 East Avenue Rochester, N.Y. 14649-0001 Ms.
Donna Ross Division of Policy Analysis 5 Planning New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223
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MET.SUMARRY GINNA 7/20/88 DISTRIBUTION:
<Docket-Fi.l eg
~NRC-5-Local PDRs PDI-3 r/f RWessman CStahle OGC-Rockville EJordan BGrimes ACRS (10)
HBClayton NRC Partici ants L. B. Mars P. Bezler P. T.
Kuo Mark Hartzman Lee Bettenhausen, Region I
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