ML080290311
| ML080290311 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/31/2008 |
| From: | Tanya Smith NRC/FSME/DWMEP |
| To: | Joseph E Pollock Entergy Nuclear Operations |
| Smith T (301) 415-6721 | |
| References | |
| Download: ML080290311 (6) | |
Text
January 31, 2008 Mr. Joseph Pollock Site Vice President - Administration Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING ENTERGY NUCLEAR OPERATIONS INC. REQUEST FOR AMENDMENT TO INDIAN POINT UNIT 1 LICENSE FOR USE OF FUEL HANDLING BUILDING CRANE
Dear Mr. Pollock,
By letters dated February 22, 2007, (ML070740552), and October 3, 2007 (ML073050247)
Entergy Nuclear Operations Inc. requested an amendment to the Indian Point Unit 1 License for use of the Fuel Handling Building crane for dry spent fuel cask handling operations.
After reviewing your request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required for completing the review. Please provide the additional information requested in the enclosure within 30 days of receipt of this letter.
If you have any questions, please call me at (301) 415-6721.
Sincerely,
/RA/
Theodore Smith, Project Manager Decommissioning Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No: 50-003
Enclosure:
Request for Additional Information cc: Indian Point Service List
Indian Point Nuclear Generating Station, Unit 1 cc: Service List Mr. Gary J. Taylor Chief Executive Officer Entergy Operations, Inc.
1340 Echelon Parkway Jackson, MS 39213 Mr. Joseph Pollock 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
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 Senior Resident Inspectors Office Indian Point 3 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
Mr. Joseph Pollock Site Vice President - Administration Entergy Nuclear Operations, Inc.
Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION REGARDING ENTERGY NUCLEAR OPERATIONS INC. REQUEST FOR AMENDMENT TO INDIAN POINT UNIT 1 LICENSE FOR USE OF FUEL HANDLING BUILDING CRANE
Dear Mr. Pollock,
By letters dated February 22, 2007, (ML070740552), and October 3, 2007 (ML073050247)
Entergy Nuclear Operations Inc. requested an amendment to the Indian Point Unit 1 License for use of the Fuel Handling Building crane for dry spent fuel cask handling operations.
After reviewing your request, the U.S. Nuclear Regulatory Commission staff has determined that additional information is required for completing the review. Please provide the additional information requested in the enclosure within 30 days of receipt of this letter.
If you have any questions, please call me at (301) 415-6721.
Sincerely,
/RA/
Theodore Smith, Project Manager Decommissioning Directorate Division of Waste Management and Environmental Protection Office of Federal and State Materials and Environmental Management Programs Docket No: 50-003
Enclosure:
Request for Additional Information cc: Indian Point Service List DISTRIBUTION:
RidsRgn1MailCenter ML080290311 OFC DURLD DURLD NAME TSmith APersinko DATE 1/27/08 1/31/08 OFFICIAL USE ONLY
Enclosure REQUEST FOR ADDITIONAL INFORMATION ENTERGY OPERATION, INC. INDIAN POINT, UNIT 1 USE OF THE FUEL HANDLING BUILDING CRANE FOR DRY SPENT FUEL CASK HANDLING OPERATIONS DOCKET NO: 50-003
References:
(1) Letter dated February 22, 2007 from Fred R. Dacimo of Indian Point Entergy Center to U.S. Nuclear Regulatory Commission (ML070740552) with regard to License Amendment Request (LAR) - Indian Point Unit 1 Fuel Handling Building.
(2) Letter dated October 3, 2007 from Fred R. Dacimo of Indian Point Entergy Center to U.S. Nuclear Regulatory Commission (ML073050247) with regard to Reply to Request for Additional Information (RAI) for Indian Point Unit 1 LAR for Fuel Handling Building Crane.
- 1.
Provide the basis for the 1% failure strain limit for stainless steel cladding subjected to the burnup and temperatures of the Indian Point Unit 1 (IP-1) spent fuel.
In response to NRC staff RAIs related to License Amendment Request (LAR) Sections 4.7.1 and 4.7.2, The cask vendor, Holtec International (Holtec) developed a comparative evaluation approach to demonstrate that stainless steel fuel rod integrity is maintained for the 39-2 drop of the transfer cask onto the impact limiter located on the pool slab. Using the impact results from NUREG-1864, (A Pilot Probabilistic Risk Assessment of a Dry Cask Storage System At a Nuclear Power Plant, March 2007) for Zircalloy clad fuel rods; Holtec compared the properties of the Zircalloy rods to those of the stainless steel rods to assert that the NUREG-1864 results bound the IP-1 analysis for the stainless steel rods.
To make the point Holtec constructed a table comparing various metrics of the Zircalloy rods with the stainless steel rods, and asserted by this comparison that the strain in the stainless steel clad fuel rod would be less than the maximum strain experienced by the Zircalloy rod for the same drop height onto a concrete floor. Specifically, it was stated that The metrics in the above table indicate that results for the NUREG-1864 Reference fuel will bound results for the IP-1 Analysis Basis fuel (i.e., the PI-1 fuel has lower burnup, has fuel rods of lower total weight, has a larger critical buckling load, and requires a smaller lateral movement before contact with the fixed wall of the storage cell. The merits of these four metrics, in-so-far-as they are bounding, are discussed below.
2 The first metric is that IP-1 fuel has lower burnup. While it is true that low burnup Zircalloy fuel rods are more ductile than high burnup Zircalloy rods, the problem at hand is not a comparison of two Zircalloy fuel rods with different burnups, but rather a comparison of a high burnup Zircalloy rod with a low burnup stainless steel rod. The ductility of stainless steel rods responds differently to burnup than Zircalloy rods, and some studies have shown that the ductility of stainless steel rods may be quite sensitive to burnup. For this metric to be bounding, therefore, it must be shown that for the burnup and temperature of the IP-1 stainless steel rods the failure strain is above the 1% strain limit used for the Zircalloy rods in NUREG-1864.
With respect to the second, third and fourth metrics, the staff agrees that they are bounding.
- 2.
Provide an analysis and evaluation of consequences for the MPC lid drop onto the Transfer Cask flange that conforms to the guidance of NUREG-0612, Appendix A.
Because the IP-1 Fuel Handling Building Crane is not single failure proof, the applicant evaluated the consequences of several hypothetical drops of heavy loads associated with cask loading consistent with the guidance of NUREG-0612 (Control of Heavy Loads at Nuclear Power Plants, July 1980). One such event, summarized in Section 4.7.2 (e), is the drop of the MPC lid onto the Transfer Cask flange and subsequent impact of the lid on the fuel basket. The MPC lid, which weighs approximately 10,000 lbs, falls 7.5 feet in air and 14.8 feet in water before impact. The lid is assumed to fall through water in a perfectly horizontal orientation before impacting the cask flange, then rotate and impact the fuel basket. The lid impacts the cask flange at a velocity of 220 in/sec, which is less than the velocity at which the lid enters the water (264 in/sec).
For load drops over spent fuel, NUREG-0612 stipulates that Analysis should conform to the guidelines of Appendix A. Section A.1 of Appendix A stipulates that The following should be considered for any load drop analysis (1) That the load is dropped in an orientation that causes the most severe consequences; and (7) The analysis should postulate the maximum damage that could result The analysis in Section 4.7.2(e) assumes the lid falls in a perfectly horizontal orientation through the water. This orientation maximizes the drag forces on the lid, which in turn minimizes the impact velocity on the cask flange, and therefore minimizes the consequences of lid impact on the fuel basket. On-the-other-hand, if the lid falls in a side first orientation, the drag forces are considerably less, the impact velocity significantly higher and the consequences more severe.