ML080670089
| ML080670089 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/18/2008 |
| From: | Boska J NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Entergy Nuclear Operations |
| Boska J, NRR, 301-415-2901 | |
| References | |
| TAC MD6216 | |
| Download: ML080670089 (6) | |
Text
March 18, 2008 Vice President, Operations Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249
SUBJECT:
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - REVIEW OF THE STEAM GENERATOR TUBE INSERVICE INSPECTION REPORT FOR THE REFUELING OUTAGE IN 2007 (TAC NO. MD6216)
Dear Sir or Madam:
By letter dated July 19, 2007, Agencywide Documents Access and Management System (ADAMS) accession number ML072120612, Entergy Nuclear Operations, Inc. (Entergy) submitted the steam generator (SG) inspection report for Refueling Outage 14 (RFO 14) in accordance with Technical Specification (TS) Section 5.6.8. Additional information regarding the 2007 SG tube inspections for RFO 14 was provided by Entergy in a letter dated February 5, 2008 (ML080440264).
The Nuclear Regulatory Commission (NRC) staff has completed its review of these reports and concludes that Entergy provided the information required by Indian Point Unit 3 TSs and that no additional follow-up is required at this time. The NRC 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. 50-286
Enclosure:
As stated cc w/encl: See next page
- See memo dated 2/28/08 OFFICE LPL1-1/PM LPL1-1/LA CSGB/BC LPL1-1/BC NAME JBoska SLittle AHiser*
MKowal DATE 3/14/08 3/18/08 2/28/08 3/18/08
Indian Point Nuclear Generating Unit No. 3 cc:
Senior Vice President Entergy Nuclear Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Vice President Oversight Entergy Nuclear Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Senior Manager, Nuclear Safety & Licensing Entergy Nuclear Operations, Inc.
P.O. Box 31995 Jackson, MS 39286-1995 Senior Vice President and COO Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Assistant General Counsel Entergy Nuclear Operations, Inc.
440 Hamilton Avenue White Plains, NY 10601 Manager, Licensing Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Mr. Paul Tonko President and CEO New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Mr. John P. Spath New York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector=s Office Indian Point 3 U. S. Nuclear Regulatory Commission P.O. Box 59 Buchanan, NY 10511 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza Albany, NY 12223-1350 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Raymond L. Albanese Four County Coordinator 200 Bradhurst Avenue Unit 4 Westchester County Hawthorne, NY 10532 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 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 Mr. Sherwood Martinelli FUSE USA via email
Enclosure REVIEW OF THE 2007 STEAM GENERATOR TUBE INSERVICE INSPECTION REPORTS INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 By letter dated July 19, 2007 (ML072120612), Entergy Nuclear Operations, Inc. (the licensee),
submitted information pertaining to their 2007 steam generator (SG) tube inspections at Indian Point Nuclear Generating Unit No. 3 (IP3). These inspections were performed during the fourteenth refueling outage (RFO) of IP3. The licensee provided additional information regarding the SG inspections in a letter dated February 5, 2008 (ML080440264).
At the time of the inspection, the SGs had approximately 137 effective full-power months (EFPM) of operation since the first inservice inspection performed in 1990 (the 2007 inspection outage was the last planned inspection in the 144 EFPM sequential period).
After review of the information provided by the licensee, the Nuclear Regulatory Commission (NRC) staff has the following comments/observations:
The steam drum areas of the 31 and 32 SGs were visually inspected, focusing on general condition, primary separators, secondary separators, J-nozzles and the feed ring.
No anomalies or evidence of erosion corrosion was seen in either SG. The internals in SG 34 are currently scheduled for inspection in 2013 (RFO 17).
The tube with the trackable anomaly that was identified in 2003 (row 5, column 37 in SG 32) and the tube with the small ding identified in 1997 (row 8, column 21 in SG 34) were not expected by the licensee to have undergone any degradation, and thus were not inspected during the 2007 outage.
Sixteen potential loose parts that were identified during the SG eddy current inspections were identified by the +PointTM probe and not by the bobbin probe. Only two of these indications were attributed to a significant foreign object. The majority of the potential loose part indications were in areas where small piles of sludge mixed with very small pieces of wire. These small pieces of wire were impractical to retrieve and were evaluated to have no impact on tube integrity. Their small size could explain why the bobbin probe did not detect them.
Based on a review of the information provided by the licensee, the NRC staff concludes that the licensee provided the information required by their technical specifications. In addition, the SG tube inspections at IP3 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.