ML060550317

2006/03/10-Request for Additional Information for the Review of the Oyster Creek Nuclear Generating Station, License Renewal Application (Tac No. MC7624)

ML060550317
Person / Time
Site:	Oyster Creek
Issue date:	03/10/2006
From:	Ashley D NRC/NRR/ADRO/DLR/RLRA
To:	Swenson C AmerGen Energy Co
Ashley D, NRR/DLR/RLRA, 415-3191
References
%dam200604, TAC MC7624
Download: ML060550317 (7)

Text

March 10, 2006 C. N. Swenson Site Vice President

AmerGen Energy Company, LLC

P.O. Box 388

Forked River, NJ 08731-0388

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL

APPLICATION (TAC NO. MC7624)

Dear Mr. Swenson:

By letter dated July 22, 2005, AmerGen Energy Com pany, LLC (AmerGen or the applicant) submitted to the U.S. Nuclear Regulatory Commission (NRC or the staff) an application

pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating license for Oyster Creek Nuclear Generating Station. The NRC staff is reviewing the

information contained in the license renewal application and has identified, in the enclosure, an

area where additional information is needed to complete the review.

These questions were discussed with a member of your staff, Mr. John Huffnagel, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you

have any questions, please contact me at 301-415-3191 or via e-mail at DJA1@nrc.gov

.Sincerely,/RA/Donnie J. Ashley, Project Manager License Renewal Branch A

Division of License Renewal

Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

As stated cc w/encl: See next page March 10, 2006 C. N. Swenson

Site Vice President

AmerGen Energy Company, LLC

P.O. Box 388

Forked River, NJ 08731-0388

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL

APPLICATION (TAC NO. MC7624)

Dear Mr. Swenson:

By letter dated July 22, 2005, AmerGen Energy Com pany, LLC (AmerGen or the applicant) submitted to the U.S. Nuclear Regulatory Commission (NRC or the staff) an application

pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54), to renew the operating license for Oyster Creek Nuclear Generating Station. The NRC staff is reviewing the

information contained in the license renewal application and has identified, in the enclosure, an

area where additional information is needed to complete the review.

These questions were discussed with a member of your staff, Mr. John Huffnagel, and a mutually agreeable date for this response is within 30 days from the date of this letter. If you

have any questions, please contact me at 301-415-3191 or via e-mail at DJA1@nrc.gov

.Sincerely,/RA/Donnie J. Ashley, Project Manager License Renewal Branch A

Division of License Renewal

Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

As stated cc w/encl: See next page

DISTRIBUTION

See next page Adams accession no.: ML060550317 Document Name: C:\MyFiles\Copies\Oyster Creek RAI - Hans_Ashar_drywell-.wpdOFFICEPM:RLRA:DLRLA:RLRA:DLRBC:RLRA:DLRNAMEDJAshleyYEdmondsLLund DATE 03/ 09 /0603/ 10 /06 03/ 10 /06 OFFICIAL RECORD COPY 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 08731 Senior Vice President of Operations

AmerGen Energy Company, LLC

200 Exelon Way, KSA 3-N

Kennett Square, PA 19348 Kathryn M. Sutton, Esquire Morgan, Lewis, & Bockius LLP

1111 Pennsylvania Avenue, NW

Washington, DC 20004 Kent Tosch, Chief New Jersey Department of

Environmental Protection

Bureau of Nuclear Engineering

CN 415 Trenton, NJ 08625 Vice President - Licensing and Regulatory Affairs

AmerGen Energy Company, LLC

4300 Winfield Road

Warrenville, IL 60555 Regional Administrator, Region I U.S. Nuclear Regulatory Commission

475 Allendale Road

King of Prussia, PA 19406-1415 Mayor of Lacey Township 818 West Lacey Road

Forked River, NJ 08731 Senior Resident Inspector U.S. Nuclear Regulatory Commission

P.O. Box 445

Forked River, NJ 08731 Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC Correspondence Control

P.O. Box 160

Kennett Square, PA 19348 Manager Licensing - Oyster Creek Exelon Generation Company, LLC

Correspondence Control

P.O. Box 160

Kennett Square, PA 19348 Regulatory Assurance Manager Oyster Creek

AmerGen Energy Company, LLC

P.O. Box 388

Forked River, NJ 08731 Assistant General Counsel AmerGen Energy Company, LLC

200 Exelon Way

Kennett Square, PA 19348 Ron Bellamy, Region I U.S. Nuclear Regulatory Commission

475 Allendale Road

King of Prussia, PA 19406-1415 Correspondence Control Desk AmerGen Energy Company, LLC

200 Exelon Way, KSA 1--1

Kennett Square, PA 19348 Oyster Creek Nuclear Generating Station Plant Manager

AmerGen Energy Company, LLC

P.O. Box 388

Forked River, NJ 08731 License Renewal Manager Exelon Generation Company, LLC

200 Exelon Way, Suite 230

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 Winifield Road

Warrenville, IL 60555 Ltr. to C.N. Swenson from Donnie Ashley dated: March 10, 2006

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE OYSTER CREEK NUCLEAR GENERATING STATION, LICENSE RENEWAL

APPLICATION (TAC NO. MC7624)

Adams accession no.:

ML060550317 DISTRIBUTION

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RidsNrrDorl Enclosure OYSTER CREEK NUCLEAR GENERATING STATION LICENSE RENEWAL APPLICATION (LRA)

REQUEST FOR ADDITIONAL INFORMATION (RAI)

RAI 4.7.2-1 Based on the monitoring of the drywell thickness to date, the staff requests the applicant to provide the following information:(a)For the drywell corrosion existing during the late 1980s, and the new corrosion found 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 has been adequate.(b)Provide a summary of the factors considered in establishing the minimum required drywell thickness at various elevations of the drywell.(c)LRA Reference 4.8-21 discusses pros and cons of various methods 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 on the assumed corrosion rate and the actual corrosion rate found after the mitigating

actions were implemented.

RAI 4.7.2-2 A number of Mark I containments have experienced corrosion inside their drywells at the junction of the bottom concrete floor and the steel shell. The staff requests the applicant to

provide information regarding corrosion of the drywell shell at this location or any other location

of the drywell inside surfaces.

RAI 4.7.2-3 Leakage from the refueling seal has been identified as one of the reasons for accumulation of water and contamination of the sand-pocket area. The refueling water passes through the gap

between the shield concrete and the drywell shell throughout the length of this inaccessible

area. As there is a potential for corrosion in this area, Subsection IWE of the ASME Code

would require augmented inspection of this area. The staff requests the applicant to provide a

summary of inspections performed (visual and NDE) and mitigating actions taken to prevent water leaks from the refueling seal components. RAI 4.7.2-4 Industry wide operating experience indicates a number of incidences of torus corrosion in Mark I containments. Neither LRA Table 3.5.2.1.1, nor AMP B.1.27 describes operating experience

related to corrosion of the torus. The staff request the applicant to provide a summary of the

results of IWE inspections performed on the torus, and a description of torus condition.

RAI 4.7.2-5 Drywell corrosion is a safety concern; therefore, the staff believes that 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 assertions to maintain it above certain

thickness to ensure that the containment could perform its intended function during the period of

extended operation. The time-limited aging analysis (TLAA) and Subsection IWE of the ASME

Code are the procedures by which it will maintain the containment functionality. The staff

requests the applicant to address this matter.