ML070710007
| ML070710007 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/19/2007 |
| From: | Boska J NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Kansler M Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD2783 | |
| Download: ML070710007 (6) | |
Text
March 19, 2007 Mr. Michael R. Kansler President Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 -
SUMMARY
OF THE STAFFS REVIEW OF THE 2006 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORTS FOR REFUELING OUTAGE 17 (TAC NO. MD2783)
Dear Mr. Kansler:
By letter dated June 14, 2006, Agencywide Documents Access and Management System (ADAMS) accession number ML061780303, Entergy Nuclear Operations, Inc. (Entergy) submitted the steam generator (SG) inspection report for Refueling Outage 17 (RFO 17) in accordance with Technical Specification (TS) Section 5.5.7.f.2. Additional information regarding the 2006 SG tube inspections for RFO 17 was provided by Entergy in letters dated February 13, 2006 (ML060530378), March 29, 2006 (ML061000616), and November 15, 2006 (ML063240144).
The Nuclear Regulatory Commission staff has completed its review of these reports and concludes that Entergy provided the information required by Indian Point Unit 2 TSs and that no additional follow-up is required at this time. The staffs review of the reports is enclosed.
Please contact me at (301) 415-2901 if you have any questions on this issue.
Sincerely,
/RA/
John P. Boska, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-247
Enclosure:
As stated cc w/encl: See next page
- See memo dated 1/19/07 OFFICE LPL1-1/PM LPL1-1/LA CSGB/BC LPL1-1/BC NAME JBoska SLittle AHiser*
DPickett DATE 3/12/07 3/14/07 1/19/07 3/19/07
Indian Point Nuclear Generating Unit No. 2 cc:
Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. John T. Herron Senior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Fred R. Dacimo Site Vice President Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Paul Rubin General Manager, Plant Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway P.O. Box 249 Buchanan, NY 10511-0249 Mr. Oscar Limpias Vice President Engineering Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Christopher Schwarz Vice President, Operations Support Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. John F. McCann Director, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Ms. Charlene D. Faison Manager, Licensing Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Michael J. Columb Director of Oversight Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. James Comiotes Director, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Patric Conroy Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P. O. Box 249 Buchanan, NY 10511-0249 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Mr. Peter R. Smith, President New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223 Indian Point Nuclear Generating Unit No. 2
cc:
Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspectors Office Indian Point 2 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mr. William DiProfio PWR SRC Consultant 139 Depot Road East Kingston, NH 03827 Mr. Garry Randolph PWR SRC Consultant 1750 Ben Franklin Drive, 7E Sarasota, FL 34236 Mr. William T. Russell PWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232 Mr. Jim Riccio Greenpeace 702 H Street, NW Suite 300 Washington, DC 20001 Mr. Phillip Musegaas Riverkeeper, Inc.
828 South Broadway Tarrytown, NY 10591 Mr. Mark Jacobs IPSEC 46 Highland Drive Garrison, NY 10524
INDIAN POINT UNIT 2
SUMMARY
OF THE STAFFS REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORTS FOR REFUELING OUTAGE 17 DOCKET NO. 50-247 By letter dated June 14, 2006, Agencywide Documents Access and Management System (ADAMS) accession number ML061780303, Entergy Nuclear Operations, Inc. (Entergy or the licensee) submitted the steam generator (SG) inspection report for Refueling Outage 17 (RFO
- 17) in accordance with Technical Specification (TS) Section 5.5.7.f.2. Additional information regarding the 2006 SG tube inspections for RFO 17 was provided by Entergy in letters dated February 13, 2006 (ML060530378), March 29, 2006 (ML061000616), and November 15, 2006 (ML063240144).
Indian Point Unit 2 SGs are replacement SGs which were installed during RFO 14 in 2000.
The replacement SGs are Westinghouse model 44F SGs and are designated SG21 through SG24. All four SGs were inspected during RFO 17. The 44F SG contains approximately 3,214 thermally treated Alloy 600 tubes which have an outside diameter of 0.875-inch and a 0.050-inch nominal wall thickness. The tubes are supported by stainless steel plates with quatrefoil-shaped holes and V-shaped anti-vibration bars.
The licensee provided the scope, extent, methods, and results of the Indian Point Unit 2 SG tube inspections in the documents referenced above. In addition, the licensee described corrective actions (i.e., tube plugging) taken in response to the inspection findings.
The Nuclear Regulatory Commission (NRC) staff has the following notes/observations as a result of reviewing the aforementioned submittals:
Several tubes were identified with permeability variations. The size of the permeability variations could limit the ability to reliably detect degradation; however, given the limited service time on the replacement SGs and the results of the inspections of other tubes without permeability variations, it is reasonable not to suspect degradation is occurring at locations with permeability variations. The licensee's long-term strategy for the tubes with permeability variations is to keep them in service until degradation is anticipated at the locations with the permeability variation, at which time the tubes will be preventatively plugged unless new inspection techniques are developed that can reliably inspect these locations.
Although the licensee planned to perform a visual inspection of the top of the flow distribution baffle in all four SGs (refer to the February 13, 2006 letter), the licensee subsequently determined this inspection to be unnecessary and it was not performed.
Enclosure A visual inspection of the top tube support plate was performed in two SGs. No degradation was found during the inspections; however, a very thin layer of deposits on the upper surface of the support plate and in the area between the tube hole land and the tubes was found.
Based on a review of the information provided, the NRC staff concludes that the licensee provided the information required by their TSs. In addition, the NRC staff concludes that there are no technical issues that warrant follow-up action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.