ML101870720

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Acceptance Review Regarding a Relief Request for Approval of an Alternative Inservice Inspection Method for Six Pressure Retaining Dissimilar Metal Welds in the Reactor Pressure Vessel Nozzles
ML101870720
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 07/09/2010
From: Vaaler M
Plant Licensing Branch II
To: Burton C
Carolina Power & Light Co
Vaaler, Marlayna, NRR/DORL 415-3178
References
TAC ME3894
Download: ML101870720 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 9, 2010 Christopher Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - ACCEPTANCE REVIEW REGARDING A RELIEF REQUEST FOR APPROVAL OF AN ALTERNATIVE INSERVICE INSPECTION METHOD FOR SIX PRESSURE RETAINING DISSIMILAR METAL WELDS IN THE REACTOR PRESSURE VESSEL NOZZLES (TAC NO. ME3894)

Dear Mr. Burton:

By letter dated May 27,2010, Carolina Power & Light Company (the licensee), now doing business as Progress Energy Carolinas, Inc., submitted a relief request for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). The proposed relief request seeks approval to allow an alternative to the inservice inspection requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," for six pressure retaining dissimilar metal welds in the reactor pressure vessel nozzles. The proposed alternative pertains to the third 10-year inspection interval at HNP.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of 10 CFR 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The purpose of this letter is to provide the final 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 and make an independent assessment regarding the acceptability of the proposed change. 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.

The NRC staff has reviewed the licensee's relief request 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 request in terms of regulatory requirements and the protection of public health and safety and the environment.

C. Burton -2 If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.

Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ

C Burton - 2 If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact me at (301) 415-3178.

Sincerely, IRA!

Marlayna Vaaler, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400 cc: Distribution via ListServ DISTRIBUTION:

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