ML14085A362

Acceptance Letter Regarding Request for Relief 3IR-6 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI Requirements Regarding the Reactor Vessel Head Flange Seal Leak Detection Piping

ML14085A362
Person / Time
Site:	Seabrook
Issue date:	04/01/2014
From:	John Lamb Plant Licensing Branch 1
To:	Walsh K NextEra Energy Seabrook
Lamb J, NRR/DORL/LPLI-2, 415-3100
References
TAC MF3674
Download: ML14085A362 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 1, 2014 Mr. Kevin Walsh, Site Vice President c/o Michael Ossing Seabrook Station NextEra Energy Seabrook, LLC P.O. Box 300 Seabrook, NH 03874

SUBJECT:

SEABROOK STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING REQUEST FOR RELIEF 31R-6 (TAC NO. MF3674)

Dear Mr. Walsh:

By letter dated March 24, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML14086A017), NextEra Energy Seabrook, LLC (NextEra or the licensee) requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, for pressure testing the reactor vessel head flange seal leak detection piping at Seabrook Station, Unit 1 (Seabrook), for the duration of the third 10-year inservice inspection interval.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (1 0 CFR), the licensee shall demonstrate that the proposed alternative 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. Accordingly, pursuant to 10 CFR 50.55a(a)(3)(ii), the licensee requested to use an alternative to the system leakage test than what is required in ASME Code,Section XI, Table IWC-2500-1, Examination Category C-H.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this relief 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.

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 NRC staff to complete its technical review, you will be advised by separate correspondence.

K. Walsh If you have any questions, please contact me at (301) 415-3100 or via e-mail at John.Lamb@nrc.gov.

>>~

amb, Senior Project Manager icensing Branch 1-2 Divi

• n of Operating Reactor Licensing Offi e of Nuclear Reactor Regulation Docket No. 50-443 cc: Distribution via Listserv

ML14085A362 *via e-mail OFFICE LPL 1-2/PM LPL 1-2/LA* LPL 1-2/BC LPL 1-2/PM NAME Jlamb ABaxter MKhanna Jlamb DATE 03/31/14 03/31/14 03/31/14 04/01/14