ML12118A542

Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station License Renewal Application

ML12118A542
Person / Time
Site:	Davis Besse
Issue date:	05/15/2012
From:	Cuadradodejesus S License Renewal Projects Branch 1
To:	Allen B FirstEnergy Nuclear Operating Co
CuadradoDeJesus S, 415-2375
References
TAC ME4640
Download: ML12118A542 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 May 15, 2012 Mr. Barry S. Allen, Vice President Davis-Besse Nuclear Power Station FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor, OH 43449

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC NO. ME4640)

Dear Mr. Allen:

By letter dated August 27,2010, FirstEnergy Nuclear Operating Company submitted an application pursuant to Title 10 of the Code of Federal Regulations, Part 54 for renewal of Operating License NPF-3 for the Davis-Besse Nuclear Power Station. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future.

Items in the enclosure were discussed with Steven Dort, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel.CuadradoDeJesus@nrc.gov.

Sincerely,

~{p~//

S ~I Cuadrado-De Jesus, Project Manager

~~s Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosure:

As stated cc w/encl: Listserv

DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION REQUEST FOR ADDITIONAL INFORMATION RAI 4.2.24 - Upper Shelf Energy (USE) Evaluation

Background:

lRA Table 4.2-2 lists a generic initial USE of 70 ft-Ibs for all Linde SO reactor vessel (RV) beltline welds (Weld Nos. WF-232, WF-233, and WF-1S2-1). In its April 15, 2011, response to RAI 4.2.2-2, the applicant stated that 70 ft-Ibs is based on a statistical analysis of measured initial USE data from archived Linde SO weld specimens from plant-specific surveillance capsules. The applicant stated that the initial USE data and the statistical analysis is reported in B&W Owners Group (B&WOG) Topical Report BAW-1S03, "Correlations for Predicting the Effects of Neutron Radiation on Linde SO Submerged-Arc Welds," Revision 1, May 1991.

Issue:

The staff has concerns with the use of a generic initial USE of 70 ft-Ibs for Linde SO welds for implementation in direct projections of end-of-license (EOl) USE for the period of extended operation (52 EFPY), for the following reasons:

1.

The mean value from a database has generally not been acceptable to the staff for establishing a generic initial USE value for a specification, class, and/or type of RV material because generic mean values are not statistically defensible for embrittlement calculations. In the past, the staff has generally only accepted generic initial USE values if they are based on a statistically-conservative position, such as the mean value minus two standard deviations, or the lowest value in the database.

2.

The BAW-1S03 initial USE database has not been reviewed and approved by the staff as a statistical basis for the selection of any generic initial USE value for Linde SO welds.

Reguest:

To demonstrate acceptable USE for the RV beltline materials, WF-232 and WF-233, provide a response to either (a) or (b):

(a)

Provide a direct projection of USE through 52 EFPY based on either (i) measured heat specific initial USE values from certified material test reports (CMTRs), or (ii) a statistically-based conservative generic initial USE value, along with a technical justification for the value.

(b)

Provide EMAs for weld materials WF-232 and WF-233 in the shell region of the RV, which may use the existing methods developed in B&WOG Topical Reports BAW 2191 P-A and BAW-217SP-A, or the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Appendix K, accounting for neutron embrittlement through 52 EFPY. EMAs for non-shell welds must use applied J integral values based on the specific weld geometry.

Letter to Barry S. Allen from Samuel Cuadrado-De Jesus dated May 15, 2012

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DAVIS-BESSE NUCLEAR POWER STATION (TAC NO. ME4640)

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