ML060580345
| ML060580345 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/24/2006 |
| From: | Ashley D NRC/NRR/ADRO/DLR/RLRA |
| To: | AmerGen Energy Co |
| Ashley D, NRR/DLR/RLRA, 415-3191 | |
| References | |
| %dam200604, TAC MC7624 | |
| Download: ML060580345 (8) | |
Text
February 24, 2006LICENSEE:AmerGen Energy Company, LLC FACILITY:Oyster Creek Nuclear Generating Station
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWALAPPLICATIONThe U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives ofAmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staff's draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application(LRA). The conference call was useful in clarifying the intent of the staff's D-RAI.Enclosure 1 provides a listing of the conference call participants. Enclosure 2 contains a listingof the D-RAI discussed with the applicant, including a brief description on the status of the items.The applicant had an opportunity to comment on this summary./RA LLund for/Donnie J. Ashley, Project ManagerLicense Renewal Branch A Division of License Renewal Office of Nuclear Reactor RegulationDocket No. 50-219
Enclosures:
As statedcc w/encls: See next page
DOCUMENT NAME: E:\Filenet\ML060580345.wpdOFFICEPM:RLRALA:RLRABC:RLRANAMEDAshleyYEdmonds LLund DATE2/10/062/10/062/24/06 Oyster Creek Nuclear Generating Station cc:Site Vice President - Oyster Creek Nuclear Generating Station AmerGen Energy Company, LLC
P.O. Box 388 Forked River, NJ 08731Senior Vice President of Operations AmerGen Energy Company, LLC 200 Exelon Way, KSA 3-N Kennett Square, PA 19348Kathryn M. Sutton, EsquireMorgan, Lewis, & Bockius LLP 1111 Pennsylvania Avenue, NW Washington, DC 20004Kent Tosch, ChiefNew Jersey Department of Environmental Protection Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625Vice President - Licensing and Regulatory Affairs AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415Mayor of Lacey Township818 West Lacey Road Forked River, NJ 08731Senior Resident InspectorU.S. Nuclear Regulatory Commission
P.O. Box 445 Forked River, NJ 08731Director - Licensing and Regulatory AffairsAmerGen Energy Company, LLC Correspondence Control
P.O. Box 160 Kennett Square, PA 19348Manager Licensing - Oyster CreekExelon Generation Company, LLC Correspondence Control
P.O. Box 160 Kennett Square, PA 19348Regulatory Assurance Manager Oyster Creek AmerGen Energy Company, LLC
P.O. Box 388 Forked River, NJ 08731Assistant General CounselAmerGen Energy Company, LLC 200 Exelon Way Kennett Square, PA 19348Ron Bellamy, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415Correspondence Control DeskAmerGen Energy Company, LLC 200 Exelon Way, KSA 1--1 Kennett Square, PA 19348Oyster Creek Nuclear Generating StationPlant Manager AmerGen Energy Company, LLC
P.O. Box 388 Forked River, NJ 08731License Renewal ManagerExelon Generation Company, LLC 200 Exelon Way, Suite 210 Kennett Square, PA 19348 Oyster Creek Nuclear Generating Station cc:
Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Letter to Licensee AmerGen Energy Company from Donnie Ashley dated February 24, 2006
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON JANUARY 26, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUEST FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWALAPPLICATIONAdams accession no.: ML060580345DISTRIBUTION
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RLauferGMiller RBellamy, RI RCureton, RI JLilliendahl, RIMModes, RI MSykes, RI AHodgdon OPA LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALLTO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONJanuary 26, 2006Participants AffiliationsDonnie AshleyU.S. Nuclear Regulatory Commission (NRC)Kenneth ChangNRC Roy MathewNRC James DavisNRC Dan HoangNRC Kiyoto TanabeNRC Rich MoranteNRC/Brookhaven National LaboratoriesMichael GallagherAmerGen Energy Company, LLC (AmerGen)
Fred PolaskiAmerGen Don WarfelAmerGen John HufnagelAmerGen Mike GuthrieAmerGen Peter TamburroAmerGen Tom QuintenzAmerGen Howie RayAmerGen Ron ZakNew Jersey Department of Environmental Protection DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAI)OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONJanuary 26, 2006The U.S. Nuclear Regulatory Commission staff (NRC or the staff) and representatives ofAmerGen Energy Company, LLC (AmerGen), held a telephone conference call on January 26, 2006, to discuss and clarify the staff's draft request for additional information (D-RAI) concerning the Oyster Creek Nuclear Generating Station license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.D-RAI 4.7.2-1Based on the monitoring of the drywell thickness to date, the applicant is requested to providethe following information:(a)For the drywell corrosion existing during the late 1980s, and the new corrosionfound during the subsequent inspections, provide the process used to establish confidence that the sampling done and the areas considered for identifying the areas of corrosion have been adequate.(b)Provide a summary of the factors considered in establishing the minimumrequired drywell thickness at various elevations of the drywell.(c)Reference 4.8-21 cited in the application discusses pros and cons of variousmethods of mitigating the drywell shell corrosion. Provide a summary of the actual mitigating actions taken and their effectiveness.(d)Provide a comparative graph (or chart) showing the drywell thickness based onthe assumed corrosion rate and the actual corrosion rate found after the mitigating actions were implemented.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-2A number of Mark I containments have experienced corrosion inside their drywells at thejunction of the bottom concrete floor and the steel shell. The applicant is requested to provide information regarding corrosion of the drywell shell at this location or any other location of the drywell inside surfaces.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-3Leakage from the refueling seal has been identified as one of the reasons for accumulation ofwater and contamination of the sand-pocket area. The refueling water passes through the gap between the shield concrete and the drywell shell in the long length of inaccessible areas. Asthere is a potential for corrosion in this area, Subsection IWE of the ASME code would require augmented inspection of this area. The applicant is requested to provide a summary of inspections performed (visual and NDE) and mitigating actions taken to prevent water leaks from the refueling seal components.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-4The industry-wide operating experience indicates a number of incidences of torus corrosion inMark I containments. Neither Table 3.5.2.1.1, nor AMP B.1.27, describes operating experiencerelated to corrosion of the Oyster Creek torus. The applicant is requested to provide a summary of the results of IWE inspections performed on the torus, and a description of the torus condition.Discussion: Licensee understands the question and will provide a response.D-RAI 4.7.2-5The staff believes that for this important issue, the updated final safety analysis report (UFSAR)Supplement, should, as a minimum, briefly describe the quantitative aspect of the drywell corrosion, and the applicant's plans to maintain it above a certain thickness to ensure that the containment could perform its intended function during the period of extended operation. Thetime-limited aging analysis (TLAA) and Subsection IWE of the ASME code are the procedures by which the licensee will maintain the containment functionality.Discussion: Licensee understands the question and will provide a response.