ML13241A317

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Acceptance Review for License Amendment Request to Implement 10CFR50.61 A. Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
ML13241A317
Person / Time
Site: Beaver Valley
Issue date: 09/10/2013
From: John Lamb
Plant Licensing Branch 1
To: Emily Larson
FirstEnergy Nuclear Operating Co
Lamb J
References
TAC MF2505
Download: ML13241A317 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2013 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNIT 1 -ACCEPTANCE REVIEW FOR LICENSE AMENDMENT REQUEST TO IMPLEMENT 10 CFR 50.61a, "ALTERNATE FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOCK EVENTS" (TAC NO. MF2505)

Dear Mr. Larson:

By letter dated July 30, 2013 (Agencywide Documents Access and Management System Accession No. ML13212A027), FirstEnergy Nuclear Operating Company submitted a license amendment request to implement Title 10 of the Code of Federal Regulations (10 CFR), Section 50.61a, "Alternate Fracture Toughness Requirements for Protection Against Pressure Thermal Shock [PTS]," also referred to as the Alternate PTS Rule, for Beaver Valley Power Station, Unit 1.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the submittal has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

The NRC staff has reviewed your submittal, and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed changes in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence.

E. Larson - 2 If you have questions, I may be reached at 301-415-3100 or via e-mail at John.Lamb@nrc.gov.

G. Lamb, Senior Project Manager nsing Branch 1-2 ision of Operating Reactor Licensing ffice of Nuclear Reactor Regulation Docket No. 50-334 cc: Distribution via Listserv

ML13241A317 OFFICE NRRlDORULPLI*2IPM NRRlDORULPLI*2/LPLI*21LA NRRlDORULPL 1*2/BC(A ) NRRlOORULPLI*2IPM NAME JLamb ABaxter VRodriguez JLamb DATE 09/10/13 09/06113 09/10/13 09/10113