ML062230440
| ML062230440 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/11/2006 |
| From: | Ashley D J NRC/NRR/ADRO/DLR/RLRA |
| To: | Office of Nuclear Reactor Regulation |
| Ashley D J | |
| References | |
| %dam200612 | |
| Download: ML062230440 (11) | |
Text
August 11, 2006LICENSEE:AmerGen Energy Company, LLC FACILITY:Oyster Creek Nuclear Generating Station
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 8, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUESTS 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 February 8, 2006, to discuss and clarify the staff's draft requests for additional information (D-RAIs) 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-RAIs.Enclosure 1 provides a listing of the conference call participants. Enclosure 2 contains a listingof the D-RAIs 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/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
ML062230440DOCUMENT NAME: E:\Filenet\ML062230440.wpdOFFICEPM:RLRALA:DLRBC:RLRANAMEDAshleyYEdmonds LLundDATE08/ 9 /0608/ 11 /0608/ 11 /06 ENCLOSURE 1LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALLTO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONFebruary 8, 2006Participants AffiliationsDonnie J. AshleyU.S. Nuclear Regulatory Commission (NRC)John MaNRC Hans AsharNRC Don WarfelAmerGen Energy Company, LLC (AmerGen)
George BeckAmerGen Ahmed OuaouAmerGen ENCLOSURE 2DRAFT REQUESTS FOR ADDITIONAL INFORMATION (D-RAIs)OYSTER CREEK NUCLEAR GENERATING STATIONLICENSE RENEWAL APPLICATIONFebruary 8, 2006The U.S. Nuclear Regulatory Commission staff (NRC or the staff), and representatives ofAmerGen Energy Company, LLC (AmerGen), held a telephone conference call on February 8, 2006, to discuss and clarify the staff's draft requests for additional information (D-RAIs) concerning the Oyster Creek Nuclear Generating Station, license renewal application (LRA). The following D-RAIs were discussed during the telephone conference call.D-RAI 2.4.1-1A review of Table 2.4.1 indicates that drywell seismic support and anchorages are not within thescope of license renewal, though they are relied upon for drywell stability. A component type"Biological Shield Wall - Lateral Support" is in the Table. The staff requests the applicant to provide justification for not including the drywell seismic lateral supports within the scope of license renewal.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4.1-2Neither Table 2.4.1 nor Table 2.4.2 incorporates refueling cavity seal components within thescope of license renewal, though the plant has experienced significant corrosion (as described in Item 4 of LRA Section 3.5.2.2) of the drywell as a result of leakage from the seal. The staff requests the applicant to include the seal in the scope of license renewal, or provide justification for not including it in the scope of license renewal.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4.2-1LRA Section 2.4.8 states that structural seals are within the boundary of evaluation, but withoutexplaining what they are. The staff requests the applicant to identify all the structural seals inthe reactor building.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 2.4.8-1LRA Section 2.4.8, Fire Pond dam, states that the dam is classified as Safety Class III. Providethe location in the LRA or updated final safety analysis report (UFSAR) where the definition of Safety Class III was provided. If the definition was not provided in the LRA or UFSAR, the staffrequests the applicant to provide a definition for Safety Class III. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
D-RAI 2.4.9-1LRA Section 2.4.9, Fire Pumphouses, states that the pumphouse and the tank foundations areclassified non-safety related, Seismic Class II. Provide the location in the LRA or UFSAR where the definition of Safety Class II was provided. If the definition was not provided in the LRA or UFSAR, the staff requests the applicant to provide a definition for Safety Class II. Discussion: The question will be revised to read as follows. This D-RAI will be sent as aformal RAI. "LRA Section 2.4.9, Fire Pumphouses, states that the pumphouse and the tank foundations areclassified non-safety related, Seismic Class II. Provide the location in the LRA or UFSAR where the definition of Seismic Class II was provided. If the definition was not provided in the LRA or UFSAR, the staff requests the applicant to provide a definition for Seismic Class II." D-RAI 3.5-1Table 3.5.2.1.1 indicates that fretting and lockup of suppression pool downcomers will bemanaged by ASME Section XI, Subsection IWE, (AMP B.1.27). Directly, the downcomers are not part of the pressure boundary. Subsection IWE does not provide examination requirements and acceptance criteria for downcomers. However, as a convenience, the examinations of downcomers can be included in Subsection IWE requirements, with special provisions for examining the downcomers for fretting or lockups in the plant-specific procedures. The staff requests the applicant to provide (1) a discussion of operating experience related to downcomers fretting or lockups, and (2) the ISI provisions incorporated in the plant-specific IWE program. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-2Table 3.5.2.1.1 credits 10 CFR 50, Appendix J (AMP B.1.29) for management of downcomers "Loss of Material." It is not apparent, how the leak testing requirement of Appendix J will detectloss of material of downcomers. The staff requests the applicant to discuss the use of Appendix J in managing loss of material in downcomers.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-3Under component types "Reactor Pedestal" and "R.C. Floor Slab," a reference is made to Table1 Item 3.5.1-29. The discussion in Item 3.5.1-29 indicates that the concrete temperatures in theupper part of the drywell could be as high as 259F. As a result, the reactor building drywellshield concrete had significant cracking. However, the cause of the high temperature is not indicated. In light of the above discussion, the staff requests the applicant to provide thefollowing information:a.Type and adequacy of the cooling system used to control the temperatures in drywell.b.Operating experience related to the reliability of the cooling system.
c.Actions taken to reduce the high temperatures in the upper part of the drywell.
d.A summary of the results of the last inspection of reactor pedestal, R.C. floor slabs,drywell lateral supports, and sacrificial shield wall, including the date of the inspection, and frequencies of inspection during the period of extended operation. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-4Component type "Shielding Blocks and Plates," uses patented material "Permall," for which noaging effects are indicated in Table 3.5.2.1.1. The staff requests the applicant to provide a briefdescription of the material, and the AMR results that justified that it does not need agingmanagement during the period of extended operation.Discussion: "Permall" should be changed to "Permali". This D-RAI will be sent as a formalRAI following this change. D-RAI 3.5-5For all component types described in Table 3.5.2.1.1 (Primary Containment), "water chemistryprogram" is vital for the components fully or partially submerged in water, in addition to the programs noted in the individual component types. The staff requests the applicant to provide reasons for not including water chemistry program to manage the aging degradation of these components.Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-6The through-wall cracking of Fitzpatrick torus indicates a need for closer examination of thehighly restrained and structurally discontinuous areas subjected to operational cyclic loads. Theprime aging management program used for managing degradation of the primary containment structure is Subsection IWE (AMP B.1.27). The program is focused towards detecting loss of material. The staff requests the applicant to discuss how the program would detect initiation of such cracking in the Oyster Creek primary containment. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.D-RAI 3.5-7Table 3.5.3.1.18 indicates that the aging of Class MC component supports is managed byASME Section XI, Subsection IWF during the CLB. However, a review of the "Enhancement" in AMP B.1.28 (ASME Section XI, Subsection IWF) indicates that the program will be enhancedduring the period of extended operation to include additional MC supports and underwater structures in the torus. The staff requests the applicant to provide clarifications regarding the inspection of Class MC supports during the CLB and during the PEO. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-8Tables 3.5.2.1.6, 3.5.
2.1.15, 3.5.2.1.16, and 3.5.2.1.17 identify loss of preload as the agingeffect requiring management for structural bolts, and the structural monitoring program (B.1.31) as its aging management program. The structural monitoring program (B.1.31) states that exposed surfaces of bolting are monitored for indications of loss of preload, and that the program relies on procurement controls and installation practices, defined in plant procedures, to ensure that only approved lubricants and proper torque are applied consistent with the NUREG-1801 bolting integrity program. LRA B.1.12 bolting integrity program states that thebolting integrity program takes exception to NUREG-1801 and that the aging management ofstructural bolting is addressed by structural monitoring program (B.1.31). The staff's questions are as follows: a.The applicant needs to resolve the apparent inconsistence that the structural monitoringprogram states that the proper torque for bolts is applied consistent with the NUREG-1801 bolting integrity program while the bolting integrity program takesexception to NUREG-1801 and refer the aging management of structural bolting back tothe structural monitoring program.b.Does the identification of the loss of preload of structural bolts by visual inspection or byapplying a torque wrench? If it is by visual inspection, explain how the loss of preload can be estimated by visual inspection.c.B.1.31 states that the structural monitoring program relies on procurement controls andinstallation practices, defined in plant procedures, to ensure that only approved lubricants and proper torque are applied. The staff believes that bolt procurement controls and installation practices were supposedly used before, during, or immediately after the bolts were installed. Since the structural monitoring program is being used to inspect structural bolts after the bolts were installed for sometime, the staff requests the applicant to explain how could the structural monitoring program rely on bolt procurement controls and installation practices.d.Are there any structural bolts or fasteners, which have a yield strength equal to orgreater than 150 ksi, managed by the structural monitoring program? If yes, provide justification for not using the bolting integrity program as the aging management program for structural bolts. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-9Table 3.5.2.1.7 lists structural monitoring program as the aging management program forpenetration seals of elastomer and grout in the soil environment. The aging management program in LRA, Appendix B states that the program will require inspection of penetration seals,but does not state how the inspection should be conducted for penetration seals of elastomerand grout in the soil environment and the frequency of the inspection. The staff requests the applicant to describe the inspection method and frequency for penetration seals of elastomer and grout in the soil environment. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI. D-RAI 3.5-10Table 3.5.2.1.7 lists aluminum material embedded in concrete, and states no aging effect andrequiring no aging management program. The ACI Building Code prohibits the use of aluminum in structural concrete unless it is coated or covered to prevent aluminum-concrete reaction or electrolytic action between aluminum and steel. The staff requests the applicant to provide reasons for the use of aluminum material in concrete and for stating no aging effect and requiring no aging management program. Discussion: The applicant indicated that the question is clear. This D-RAI will be sent as aformal RAI.
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 230 Kennett Square, PA 19348 Oyster Creek Nuclear Generating Station cc:
Mr. James RossNuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708Mr. Michael P. GallagherVice President License Renewal Exelon Generation Company, LLC 200 Exelon Way, Suite 230 Kennett Square, PA 19348Mr. Christopher M. CranePresident and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555 Note to AmerGen Energy Company, LLC, from Donnie Ashley dated August 11, 2006
SUBJECT:
SUMMARY
OF A TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 8, 2006, BETWEEN THE U.S. NUCLEAR REGULATORYCOMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING DRAFT REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWALAPPLICATIONHARD COPYDLR R/FE-MAIL:JFairRWeisman AMurphy RPettis GGalletti CLi GBagchi SSmith (srs3)
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