ML062510224

Summary of Telephone Conference Calls Held on July 6,& July 7, 2006, Between the NRC & Amergen Energy Company, LLC, Concerning Clarification of Requests for Additional Information Pertaining to the Oyster Creek Nuclear Generating Station LR

ML062510224
Person / Time
Site:	Oyster Creek
Issue date:	09/08/2006
From:	Ashley D NRC/NRR/ADRO/DLR/RLRA
To:	AmerGen Energy Co
ASHLEY D NRR/DLR/RLRA 415-3191
References
%dam200612
Download: ML062510224 (8)

Text

September 8, 2006 LICENSEE: AmerGen Energy Company, LLC FACILITY: Oyster Creek Nuclear Generating Station

SUMMARY

OF TELEPHONE CONFERENCE CALLS HELD ON JULY 6, AND JULY 7, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING CLARIFICATION OF REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION The U.S. Nuclear Regulatory Commission staff (the staff), and representatives of AmerGen Energy Company, LLC, held two telephone conference calls on July 6, 2006, and July 7, 2006, to discuss and clarify the staffs requests for additional information concerning the Oyster Creek Generating Station license renewal application. The conference calls were useful in clarifying the intent of the staff. provides a listing of the conference call participants. Enclosure 2 contains a summary of the information discussed with the applicant, including a brief description on the status of the items discussed.

The applicant had an opportunity to comment on this summary.

/RA/

Donnie J. Ashley, Project Manager License Renewal Branch A Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosures:

As Stated cc w/encls: See next page

DOCUMENT NAME: E:\Filenet\ML062510224.wpd OFFICE PM:RLRA:DLR LA:DLR BC:RLRA:DLR NAME DAshley YEdmonds LLund DATE 09/ 06 /06 09/ 06 /06 09/ 08 /06 Oyster Creek Nuclear Generating Station cc:

Site Vice President - Oyster Creek Director - Licensing and Regulatory Affairs Nuclear Generating Station AmerGen Energy Company, LLC AmerGen Energy Company, LLC Correspondence Control P.O. Box 388 P.O. Box 160 Forked River, NJ 08731 Kennett Square, PA 19348 Senior Vice President of Manager Licensing - Oyster Creek Operations Exelon Generation Company, LLC AmerGen Energy Company, LLC Correspondence Control 200 Exelon Way, KSA 3-N P.O. Box 160 Kennett Square, PA 19348 Kennett Square, PA 19348 Kathryn M. Sutton, Esquire Regulatory Assurance Manager Morgan, Lewis, & Bockius LLP Oyster Creek 1111 Pennsylvania Avenue, NW AmerGen Energy Company, LLC Washington, DC 20004 P.O. Box 388 Forked River, NJ 08731 Kent Tosch, Chief New Jersey Department of Assistant General Counsel Environmental Protection AmerGen Energy Company, LLC Bureau of Nuclear Engineering 200 Exelon Way CN 415 Kennett Square, PA 19348 Trenton, NJ 08625 Ron Bellamy, Region I Vice President - Licensing and U.S. Nuclear Regulatory Commission Regulatory Affairs 475 Allendale Road AmerGen Energy Company, LLC King of Prussia, PA 19406-1415 4300 Winfield Road Warrenville, IL 60555 Correspondence Control Desk AmerGen Energy Company, LLC Regional Administrator, Region I 200 Exelon Way, KSA 1--1 U.S. Nuclear Regulatory Commission Kennett Square, PA 19348 475 Allendale Road King of Prussia, PA 19406-1415 Oyster Creek Nuclear Generating Station Plant Manager Mayor of Lacey Township AmerGen Energy Company, LLC 818 West Lacey Road P.O. Box 388 Forked River, NJ 08731 Forked River, NJ 08731 Senior Resident Inspector License Renewal Manager U.S. Nuclear Regulatory Commission Exelon Generation Company, LLC P.O. Box 445 200 Exelon Way, Suite 230 Forked River, NJ 08731 Kennett Square, PA 19348

Oyster Creek Nuclear Generating Station cc:

Mr. James Ross Nuclear Energy Institute 1776 I Street, NW, Suite 400 Washington, DC 20006-3708 Mr. Michael P. Gallagher Vice President License Renewal Exelon Generation Company, LLC 200 Exelon Way, Suite 230 Kennett Square, PA 19348 Mr. Christopher M. Crane President and Chief Nuclear Officer AmerGen Energy Company, LLC 4300 Winfield Road Warrenville, IL 60555

LIST OF PARTICIPANTS FOR TELEPHONE CONFERENCE CALLS TO DISCUSS THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION July 6, and July 7, 2006 Participants Affiliations Donnie Ashley U.S. Nuclear Regulatory Commission (NRC)

Veronica Rodriguez NRC Hansraj Ashar NRC Don Warfel AmerGen Energy Company, LLC (AmerGen)

John Hufnagel AmerGen Ahmed Ouaou AmerGen ENCLOSURE 1

DISCUSSION OF REQUESTS FOR ADDITIONAL INFORMATION OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION July 6, and July 7, 2006 The U.S. Nuclear Regulatory Commission staff (the staff) and representatives of AmerGen Energy Company, LLC (AmerGen), held telephone conference calls on July 6, 2006, and July 7, 2006, to discuss and clarify the staffs requests for additional information (RAIs) concerning the Oyster Creek Generating Station (Oyster Creek), license renewal application (LRA).

The following topics were discussed during the telephone conference calls:

In the original RAI 3.5-4, the staff needed information on the subject of Shielding Blocks and Plates, specifically a patented material described as Permali, for which no aging effects were indicated in Table 3.5.2.1.1. The staff requested the applicant to provide a brief description of the material, and the aging management review results that justified it does not need aging management during the period of extended operation.

The applicant responded with the following information:

Permali consists of vacuum impregnated material based on wood veneers (rosewood) and phenolic resin. The material was provided in Oyster Creek original design in combination with steel blocks to provide neutron shielding around recirculation piping nozzles at biological shield wall penetrations. The material is designed for its operating environment and aging management reviews did not identify aging effects requiring aging management during the period of extended operation.

The staff noted that the hydrogen content in wood veneers would make the material susceptible to neutron radiation, and high temperatures around the penetration could affect the stability of phenolic resin. AmerGen is requested to provide a detailed justification of its aging management review for this material that resulted in the conclusion that no aging management is required for this material. The staff requested AmerGen provide material test reports that show the material is capable of performing its intended function through the period of extended operation, or monitor aging effects of the material.

The applicant stated that they would research the information and provide an appropriate response.

In the original RAI 3.5-6, the staff requested additional information on Oyster Creeks evaluation and actions taken as a result of the through-wall cracking of Fitzpatrick torus that indicated a need for closer examination of the highly restrained and structurally discontinuous areas subjected to operational cyclic loads. The primary aging management program (AMP) used ENCLOSURE 2

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 requested the applicant to discuss how the program would detect initiation of such cracking in the Oyster Creek primary containment.

The applicant responded with the following information:

The Oyster Creek ASME Section XI, Subsection IWE aging management program (B.1.27) is not credited for managing crack initiation and growth. The program is based on visual examinations that may not detect cracking experienced at Fitzpatrick. However crack initiation and growth mechanism experienced at Fitzpatrick is not applicable to Oyster Creek.

Since the initial review, NRC issued Information Notice 2006-01, Torus Cracking in Boiling-Water Reactor (BWR) Mark I Containment, on January 12, 2006, to alert licensees of Fitzpatrick condition. Exelon is currently reviewing the impact of the Fitzpatrick experience on Oyster Creek. Corrective actions will be initiated if it is determined the condition described in the information notice is applicable to Oyster Creek.

The staff noted that loads similar to those generated by the Fitzpatrick event are also generated during safety/relief valve (SRV) discharges in Mark I containments. The staff requested AmerGen to provide the results of its current review of the event and a explanation of why loads from SRV discharges wont be a concern for Oyster Creek.

Note to: AmerGen Energy Company, LLC, from Donnie Ashley dated September 8, 2006.

SUMMARY

OF TELEPHONE CONFERENCE CALLS HELD ON JULY 6, AND JULY 7, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND AMERGEN ENERGY COMPANY, LLC, CONCERNING CLARIFICATION OF REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL APPLICATION HARD COPY DLR R/F E-MAIL:

JFair RWeisman AMurphy RPettis GGalletti DShum GBagchi SSmith (srs3)

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