ML113550203

Acceptance Review: MPS3 Proposed Amendment Request and Exemption Request for Use of Optimized Zirlo

ML113550203
Person / Time
Site:	Millstone
Issue date:	12/21/2011
From:	Sanders C J Plant Licensing Branch 1
To:	Bartron W D Dominion Nuclear Connecticut
Sanders, C J, NRR/DORL/LPL1-2, 415-1603
References
Download: ML113550203 (2)

Text

From: Sanders, Carleen Sent: Wednesday, December 21, 2011 11:01 AM To: William D Bartron Cc: 'Wanda D Craft'

Subject:

Acceptance Review: MPS3 Proposed Amendment Request and Exemption Request For Use of optimized ZIRLO

Dear Mr. Bartron:

By letter dated November 17, 2011 (Agencywide Documents Access and Management System Accession No. ML11329A003), Dominion Nuclear Connecticut, Inc. (DNC) submitted a license amendment and exemption request for Millstone Power Station, Unit No. 3 (MPS3). The proposed amendment would add Optimized ZIRLO TM as an allowable fuel rod cladding material at MPS3 and add the Westinghouse topical report on Optimized ZIRLO to the MPS3 Technical Specifications (TSs). In addition a typographical error would be corrected. The proposed exemption would support the use of Optimized ZIRLO TM. Title 10 of the Code of Federal Regulations (10 CFR), Section 50.46 and Appendix K of 10 CFR Part 50 presume the use of either Zircaloy or ZIRLO fuel rod cladding. Optimized ZIRLO TM has a slightly different composition than Zircaloy or ZIRLO and therefore an exemption request is needed. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment and exemption 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 application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with 10 CFR 50.90 an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

Pursuant to 10 CFR 50.12, "Specific exemptions," the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements or 10 CFR Part 50 when the exemptions are authorized by law, will not present an undue risk to the public health and safety, are consistent with the common defense and security, and special circumstances are present as described in 10 CFR 50.12(a)(2).

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment and exemption in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1603.

Sincerely, Carleen J. Sanders, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-423