ML20198R764
| ML20198R764 | |
| Person / Time | |
|---|---|
| Issue date: | 12/31/1998 |
| From: | George Wunder NRC (Affiliation Not Assigned) |
| To: | Modeen D NUCLEAR ENERGY INSTITUTE (FORMERLY NUCLEAR MGMT & |
| References | |
| GL-97-06, GL-97-6, NUDOCS 9901110053 | |
| Download: ML20198R764 (4) | |
Text
Mr. D;vid Modeen, Director, Engineering December 31, 1998 Nucirr G:n: ration Group Nucirr Energy Institut3 1776 Eye St. NW -
Washington, D.C. 20006
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING COMBUSTION ENGINEERING OWNERS GROUP TOPICAL REPORTS SUBMITTED IN RESPONSE TO GENERIC LETTER 97-06, " DEGRADATION OF STEAM GENERATOR INTERNALS"
Dear Mr. Modeen:
On May 7,1998, the Nuclear Energy Institute submitted three Combustion Enginecting Owners Group topical reports that have been referenced by icensees in their responses to Generic Letter 97-06. In order to complete our review, we request that you provide the additionalinformation described in the enclosure. If you have any questions, please contact me at (301) 415-1494.
Sincerely, original signed by S.Bajwa for George F. Wunder, Project Manager Project Directorate 1-1 Division of Reactor Projects - I/il Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ encl: See next page DISTRIBUTION:
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December 31, 1998 Mr. David Modeen, Director, Engineering Nuclear Generation Group l
Nuclear Energy institute I
1776 Eye St. NW Washington, D.C. 20006 j
l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING COMBUSTION l
ENGINEERING OWNERS GROUP TOPICAL REPORTS SUBMITTED IN RESPONSE TO GENERIC LETTER 97-06, " DEGRADATION OF STEAM GENERATOR INTERNALS"
Dear Mr. Modeen:
l On May 7,1998, the Nuclear Energy Institute submitted three Combustion Engineering Owners Group topical reports that have been referenced by licensees in their responses to Generic Letter 97-06. In order to complete our review, we request that you provide the additionalinformation described in the enclosure. If you have any questions, please contact me at (301) 415-1494.
i Sincerely, George F. Wunder, Project Manager Project Directorate 1-1 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation
Enclosure:
Request for Additional Information cc w/ encl: See next page l
f A
Indian Point Nuclear Generating Unit No. 3 cc:
J Regional Administrator, Re0 ion i Resident inspector U.S. Nuclear Regulatory Commission Indian Point 3 Nuclear Power Plant 475 Allendale Road U.S. Nuclear Regulatory Commission King of Prussia, PA 19406 P.O. Box 337 4
Buchanan, NY 10511 1
Mr. Gerald C. Goldstein Assistant General Counsel Mr. Charles W. Jackson, Manager Power Authority of the State Nuclear Safety and Licensing i
of New York Consolidated Edison Company 3
1633 Broadway of New York, Inc.
4 New York, NY 10019 Broadway and Bleakley Avenues i
Buchanan, NY 10511 Mr. Eugene W. Zeltmann, President and Chief Operating Officer Mayor. Village of Buchanan Power Authority of the State 236 Tate Avenue of New York Buchanan, NY 10511
.99 Washington Ave., Suite # 2005 Albany, NY.12210-2820 Mr. Richard L. Patch, Director Quality Assurance Mr. Robert J. Barrett Power Authoritf of the State Site Executive Officer of NewYork Indian Point 3 Nuclear Power Plant 123 Main Street P.O. Box 215 White Plains, NY 10601 Buchanan, NY 10511 Mr. Paul Eddy Ms. Charlene D. Faison New York State Dept. of Director Nuclear Licensing.
Public Service Power Authority of the State.
3 Empire State Plaza,10th Floor
.of New York Albany, NY 12223 123 Main Street
- White Plains, NY 10601 Mr. Harry P. Salmon, Jr.
Vice President - Engineering Mr. F. William Valentino, President Power Authority of the State New York State Energy, Research, of NewYork and Development Authority 123 Main Street Corporate Plaza West White Plains, NY 10601 286 Washington Ave. Extension Albany, NY 12203-6399 Mr. James Knubel Chief Nuclear Officer Charles Donaldson, Esquire Power Authority of the State Assistant Attorney General of NewYork
- New York Department of Law 123 Main Street 120 Broadway White Plains, NY 10601 NewYork, NY 10271
Request for Additionalinformation Justify why the LOCA+SSE safety analysis performed for SONGS 3 and the Flow induced Vibration (FIV) safety analysis performed for Calvert Cliffs 2 are bounding for all CE steam generators. Address both design and operational considerations. Include pertinent assumptions in your answer (e.g., level of fouling, past inspection results, etc.).
1 Justify accepting stability ratios greater than 1.0 in the analysis of FIV for the CE steam generators. Provide either more realistic calculations that demonstrate the ratios remain j
below the acceptance criterion of 1.0 or provide convincing qualitative justifications that FIV will not be a problem. Discuss future activities necessary to ensure assumptions of this analysis are met.
The CEOG has concluded that flow-assisted corrosion (FAC) of steel eggerate supports is a potential degradation mechanism and has made the following recommendations (page 63 of CE-NPSD-1103): ' units with carbon steel eggcrates and severe tube bundle fouling should inspect peripheral eggerate locations during each refueling outage... Units without severe tube bundle fouling should perform a one-time inspection of the peripheral eggerate locations...lf no degradation is noted, a plan should be developed to perform additioral inspections at future refueling outages if tube bundle fouling becomes significant." Clarify the CEOG expectations regarding the criteria for performing secondary side inspections. For example, what parameter (s) is(are) monitored to determine if severe tube bundle fouling exists? How are they monitored? How often?
What criteria exist for a licensee to determine " severe tube bundle fouling?"
Enclosure
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