ML12032A187

Request for Additional Information Related to the Response to License Renewal Commitment No. 10 Regarding Thermal Aging Irradiation Embrittlement of Cast Austenitic Stainless Steel

ML12032A187
Person / Time
Site:	Oyster Creek
Issue date:	02/21/2012
From:	Heather Jones NRC/NRR/DLR/RPOB
To:	Pacilio M Exelon Nuclear
Jones H
References
TAC ME7123
Download: ML12032A187 (4)

Text

DATE ADDED February 21, 2012 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION: REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE RESPONSE TO LICENSE RENEWAL COMMITMENT NO. 10 REGARDING THERMAL AGING IRRADIATION EMBRITTLEMENT OF CAST AUSTENITIC STAINLESS STEEL (TAC NO. ME7123)

Dear Mr. Pacilio:

By letter dated April 9, 2008, AmerGen Energy Company, the licensee, submitted for staff review and approval a response to Commitment No. 10 stated in NUREG-1875, Volume 2, Safety Evaluation Report Related to the License Renewal of Oyster Creek Generating Station

[(OCNGS)]. This commitment concerns thermal aging and neutron irradiation embrittlement of OCNGS reactor vessel internals components made of cast austenitic stainless steel materials.

The staff is reviewing the information contained in the license renewal commitment response and has identified, in the enclosure, an area where additional information is needed to complete the review.

The request for additional information (RAI) was discussed with David Helker of your staff, and a mutually agreeable date for the response is within 45 days from the date of this letter. If you have any questions, please contact me by telephone at (301) 415-4054 or by e-mail at Heather.Jones@nrc.gov.

Sincerely,

/RA/

Heather M. Jones, Project Manager Program Operations Branch Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-219

Enclosure:

As stated cc w/encl: Listserv

REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION COMMITMENT NO. 10 OF NUREG-1875, VOLUME 1, SAFETY EVALUATION REPORT RELATED TO THE LICENSE RENEWAL OF OYSTER CREEK NUCLEAR GENERATING STATION AMERGEN ENERGY COMPANY DOCKET NO. 50-219

RAI-1

Regarding the fuel support piece, it was stated that, [t]he loading on the fuel support piece is mostly in compression and as such any loss of fracture toughness is not expected to affect the structural integrity of the component. Please elaborate on the locations of the fuel support piece which are under tensile stresses, provide the maximum tensile stress value and confirm whether the highly stressed areas are accessible in the proposed supplemental inspections. If all accessible surfaces of the fuel support piece are under compressive stresses, what information do you expect to obtain from the proposed supplemental inspections? Further, discuss the inspection results documented to date.

Principle contributor: Simon Sheng, NRR ENCLOSURE

ML12032A187 OFFICE LA:RPB1/DLR PM:RPOB/DLR BC:RPOB/DLR PM:RPOB/DLR NAME IKing HJones YDiaz-Sanabria HJones DATE 02/8/2012 02/09/2012 02/21/2012 02/21/2012

Letter to M. Pacilio from H. Jones dated February 21, 2012

SUBJECT:

OYSTER CREEK NUCLEAR GENERATING STATION: REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE RESPONSE TO LICENSE RENEWAL COMMITMENT NO. 10 REGARDING THERMAL AGING IRRADIATION EMBRITTLEMENT OF CAST AUSTENITIC STAINLESS STEEL (TAC NO. ME7123)

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HJones YDiaz-Sanabria DTifft, RI NMcNamara, RI DScrenci, RI RConte, RI BHarris, OGC