ML061600368

2006/06/09-June 1, 2006, Summary of Meeting with Amergen Energy Company, LLC, Representatives to Discuss the Staff'S Concerns on the Drywell Shell and the Oyster Creek Nuclear Generating Station LRA

ML061600368
Person / Time
Site:	Oyster Creek
Issue date:	06/09/2006
From:	Ashley D NRC/NRR/ADRO/DLR/RLRA
To:	AmerGen Energy Co
Ashley D
References
%dam200612
Download: ML061600368 (14)

Text

June 9, 2006 LICENSEE: AmerGen Energy Company, LLC FACILITY: Oyster Creek Nuclear Generating Station

SUMMARY

OF MEETING HELD ON JUNE 1, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND AMERGEN ENERGY COMPANY, LLC, REPRESENTATIVES TO DISCUSS THE STAFFS QUESTIONS REGARDING THE DRYWELL SHELL AND THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION On June 1, 2006, the U.S. Nuclear Regulatory Commission staff met with members of AmerGen Energy Company, LLC, (the applicant) in a public meeting to discuss the staffs questions regarding the applicants aging management program for the drywell shell at Oyster Creek Nuclear Generating Station (OCNGS). The staff provided AmerGen the opportunity to ask for clarification concerning the staffs questions. This meeting was conducted to support the staffs review of the license renewal application for the OCNGS. The application was submitted by letter dated July 22, 2005. A telephone conference line was provided, to allow members of the public who could not attend the meeting, an opportunity to participate in the meeting. At the conclusion of the meeting, the staff responded to questions from a State official and members of the public.

The list of attendees is provided in Enclosure 1. The summary of discussion topics are enclosed as Enclosure 2. The meeting was transcribed and a transcript of the meeting is available in the Agencywide Documents Access and Management System under Accession No.

ML061580242.

/RA/

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

Enclosures:

1. List of Attendees

2. Summary of Discussion Topics cc w/encls: See next page

June 9, 2006 LICENSEE: AmerGen Energy Company, LLC FACILITY: Oyster Creek Nuclear Generating Station

SUMMARY

OF MEETING HELD ON JUNE 1, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND AMERGEN ENERGY COMPANY, LLC, REPRESENTATIVES TO DISCUSS THE STAFFS QUESTIONS REGARDING THE DRYWELL SHELL AND THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION On June 1, 2006, the U.S. Nuclear Regulatory Commission staff met with members of AmerGen Energy Company, LLC, (the applicant) in a public meeting to discuss the staffs questions regarding the applicants aging management program for the drywell shell at Oyster Creek Nuclear Generating Station (OCNGS). The staff provided AmerGen the opportunity to ask for clarification concerning the staffs questions. This meeting was conducted to support the staffs review of the license renewal application for the OCNGS. The application was submitted by letter dated July 22, 2005. A telephone conference line was provided, to allow members of the public who could not attend the meeting, an opportunity to participate in the meeting. At the conclusion of the meeting, the staff responded to questions from a State official and members of the public.

The list of attendees is provided in Enclosure 1. The summary of discussion topics are enclosed as Enclosure 2. The meeting was transcribed and a transcript of the meeting is available in the Agencywide Documents Access and Management System under Accession No.

ML061580242.

/RA/

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

Enclosures:

1. List of Atendees

2. Summary of Discussion Topics cc w/encls: See next page DISTRIBUTION: See next page Adams Accession No.: ML061600368 DOCUMENT NAME:E:\Filenet\ML061600368.wpd

• See previous concurrence page OFFICE: LA:RLEP PM:RLEP SC:RLEP NAME: IKing DAshley LLund DATE: 06/ 07 /06 06/ 07 /06 06/ 09 /06 OFFICIAL RECORD COPY

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

Oyster Creek Public Meeting Summary dated: June 09, 2006

SUMMARY

OF MEETING HELD ON JUNE 1, 2006, BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND AMERGEN ENERGY COMPANY, LLC, REPRESENTATIVES TO DISCUSS THE STAFFS QUESTIONS REGARDING THE DRYWELL SHELL AND THE OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION HARD COPY DLR R/F DAshley E-MAIL:

JFair RWeisman AMurphy RPettis GGalletti CLi GBagchi SSmith (srs3)

SDuraiswamy YL (Renee) Li RidsNrrDlr RidsNrrDe RidsNrrDci RidsNrreEemb RidsNrrDeEeeb RidsNrrDeEqva RidsNrrDss RidsNrrDnrl RidsOgcMailCenter RidsNrrAdes DLR Staff

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HAshar MYoung DShum CColleli RKWild JStorch RLaufer GMiller VRodriguez RBellamy, RI RCureton, RI JLilliendahl, RI MModes, RI MSykes, RI RidsOpaMail RidsNrrDorl RidsOcaMail PMNS

Attendance List for Meeting Between the U.S. Nuclear Regulatory Commission Staff and AmerGen Energy Company, LLC, Representatives June 1, 2006 Name Organization Frank Gillespie NRC/NRR/DLR P.T. Kuo NRC/NRR/DLR Louise Lund NRC/NRR/DLR Donnie J. Ashley NRC/NRR/DLR Jim Davis NRC/NRR/DLR Kiyoto Tanabe NRC/NRR/DLR Tommy Le NRC/NRR/DLR Ken Chang NRC/NRR/DLR Daniel Merzke NRC/NRR/DLR Linh Tran NRC/NRR/DLR Michael J. Morgan NRC/NRR/DLR Raj Auluck NRC/NRR/DLR Maurice Heath NRC/NRR/DLR Jonathan Rowley NRC/NRR/DLR Kent Howard NRC/NRR/DLR Roy Mathew NRC/NRR/DLR Noel Dudley NRC/NRR/DLR Rebecca Karas NRC/NRR/DE Hans Ashar NRC/NRR/DE Tomeka Terry NRC/NRR/DE Cayetano Santos NRC/ACRS Mitzi Young NRC/OGC Steve Hamrick NRC/OGC Randy Blough NRC/RI John Segala NRC/RI Enclosure 1

Name Organization Michael Modes NRC/RI Bob Shewmaker NRC/NMSS/SFPO Herman Graves NRC/RES Michael P. Gallagher Exelon/AmerGen Fred Polaski Exelon/AmerGen Don Warfel Exelon/AmerGen Peter Tamberno Exelon/AmerGen Howie Ray Exelon/AmerGen John Hufnagel Exelon/AmerGen Don Silverman Morgan Lewis/AmerGen Steven Dolley Inside NRC/Platts Paul Gunter NIRS Dennis Zannoni NJDEP Ron Zak NJDEP **

Rich Pinney NJDEP **

Tom Quintenz Exelon/AmerGen **

Jim Laird Exelon/AmerGen **

Richard Webster Rutgers Environmental Law Clinic **

Nick Clunn Asbury Park Press **

Jeff Brown GRAMMES **

Paula Gotsch GRAMMES **

Edith Gbur Jersey Shore Nuclear Watch **

Don Warren JSNW **

Peter James Atherton JSNW **

• • Members of the public who participated in the meeting using the teleconference line.

Summary of Discussion Topics Between the U.S. Nuclear Regulatory Commission Staff and AmerGen Energy Company, LLC, Representatives June 1, 2006 On March 10, 2006, the U.S. Nuclear Regulatory Commission issued AmerGen requests for additional information concerning its review of the drywell corrosion time-limited aging analysis (TLAA), which is contained in the Oyster Creek license renewal application Section 4.7.2, Drywell Corrosion. AmerGen responded to the requests in a letter dated April 7, 2006. On the basis of the AmerGen responses, the NRC requested a meeting to clarify the following issues related to the TLAA.

Uncertainties in Ultrasonic Test (UT) Results: A of the GPU Nuclear Corporations letter dated November 26, 1990, contains a statistical evaluation of the UT measurement data taken up to 1990. On the cover page of the report, GPU Nuclear Corporation made a disclaimer that, The work is conducted by an individual(s) for use by GPU. Neither GPU nor the authors of the report warrant that the report is complete or accurate.

The NRC requested the applicant to clarify the disclaimer or explain how the UT measurement data were evaluated, and used in the drywell analysis.

Use of ASME Sec. III, Subsection NE-3213.10 for Localized Corroded Areas:

The applicant used the provisions in ASME Code Section III, Subsection NE-3213.10, for areas of localized thinning. This provision, though not directly applicable to the randomly thin areas caused by corrosion, can be used with care and adequate conservatism. The NRC requested the applicant to clarify how NE-3213.10 was applied to the areas of localized thinning.

UT Results Indicating Increased Drywell Shell Thickness:

Information provided by the applicant indicates that the UT measurements taken from inside the drywell after 1992 show a general increase in metal thickness. In at least one case, the increase is as much as 50 mils in a two-year period. The NRC requested the applicant to clarify what steps will be taken to verify the accuracy of UT measurements.

Use of ASME Code Case 284:

The applicant used the methods and assumptions contained in ASME Code Case-284-1 in the buckling analysis of the Drywell shell in the sand-pocket area. The staff has not yet endorsed ASME Code Case 284. The staff does not take exception to the use of average compressive stress across the metal thickness for buckling analysis of the as-built shell. However, if corrosion has reduced the strength of the remaining metal through the cross section, this assumption may not be valid. The NRC requested the applicant to clarify its use of ASME Code Case 284.

Enclosure 2

Junctions Between Plates of Different Thicknesses:

The UT measurements taken in the spherical portion of the drywell shell adequately represent the upper spherical area. However, there are no measurements taken in the lower portion of the spherical area above the sand-pocket area. To ensure that the spherical portion of the drywell shell is properly represented in the database, additional UT measurements taken approximately at or above the junction of the 0.722 inch and 1.154 inch thick plates would be desirable. Likewise, additional UT measurements taken on the cylindrical portion of the drywell shell at about 71 feet 6 inches (i.e. at the junction of the 0.640 inch plate and the thickened plate in the knuckle area) may be desirable. The NRC requested the applicant to clarify its UT sampling plan in context of the entire drywell shell assessment.

Inspection of Inaccessible Regions:

It is not clear to the NRC whether the junction between the 1.154 inch plate and the 0.676 inch plate at the elevation 6 foot 101/4 inches is represented in the UT sampling plan. This area is below the bottom of the sand-pocket area, and is in contact with the concrete alkaline environment. However in the past, before sealing of the junction between the steel and the concrete, this area would have been subjected to the same type of contaminated water as the drywell shell in the sand-pocket area. The NRC considers this junction to be an area for possible corrosion. The NRC requested the applicant to incorporate this area in the sampling plan or justify why it should not be part of the sampling plan.

Sand Bed Region Inspection Increments:

In a letter dated April 4, 2006, AmerGen committed to perform UT measurements of the sand bed region every 10 years. In view of the uncertainty regarding the long-term effectiveness of the coating and water leakage, the NRC requested the applicant to clarify the commitment for UT measurement frequency in the sand bed region.