ML121300491

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ME8534, E-mail to Licensee for Acceptance of Relief Request RR-PTRR-02
ML121300491
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/09/2012
From: Bhalchandra Vaidya
Plant Licensing Branch 1
To: Dosa J, Vandeputte D
Nine Mile Point
vaidya B, NRR/Dorl/lpl1-1, 415-3308
References
TAC ME8534
Download: ML121300491 (1)


Text

From: Vaidya, Bhalchandra Sent: Wednesday, May 09, 2012 3:31 PM To: 'Dosa, John J'; 'dennis.vandeputte@cengllc.com' Cc: Hoffman, Keith; Collins, Jay; Tsao, John; Alley, David; Wolfgang, Robert; Wilson, George; Lingam, Siva; Boyle, Patrick

Subject:

ME8534 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE: Relief Request RR-PTRR-02

SUBJECT:

Nine Mile Point Nuclear Station Unit No. 1; Docket No. 50-220 American Society of Mechanical Engineers (ASME) Code,Section XI, Inservice Inspection Program -

10 CFR 50.55a Request Number RR-PTRR-02 (TAC NO. ME8534)

By letter dated April 27, 2012, Pursuant to 10 CFR 50.55a(a)(3)(i), Nine Mile Point Nuclear Station, LLC (NMPNS) requested NRC approval for the application of a proposed alternative to use the provisions of IWA-4132 of the 2004 edition of the ASME Section XI code for the replacement of the reactor recirculation pump seal flange assemblies rotated from stock, for the remainder of the fourth ten-year Inservice Inspection (ISI) Interval for Nine Mile Point Unit 1 (NMP1). The proposed alternative in this request has been incorporated into IWA-4132 of the 2010 edition of the ASME Section XI code.

The purpose of this communication is to provide the results of the NRC staffs acceptance review of this relief request. The acceptance review was performed by the staff of NRC 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.

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 Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your application 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 relief request in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me.

Bhalchandra K. Vaidya Licensing Project Manager NRC/NRR/DORL/LPL1-1 (301)-415-3308 (O) bhalchandra.vaidya@nrc.gov