ML14100A325

Acceptance Letter Regarding Request for Relief SC-I4R-140 from American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI Requirements Regarding the Reactor Vessel Head Flange.

ML14100A325
Person / Time
Site:	Salem
Issue date:	04/29/2014
From:	John Lamb Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Lamb J, NRR/DORL/LPLI-2, 415-3100
References
TAC MF3898, TAC MF3899
Download: ML14100A325 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 29, 2014 Mr. Thomas Joyce President and Chief Nuclear Officer PSEG Nuclear LLC P.O. Box 236, N09 Hancocks Bridge, NJ 08038

SUBJECT:

SALEM NUCLEAR GENERATING STATION, UNITS 1 AND 2- ACCEPTANCE OF REQUESTED LICENSING ACTION REGARDING REQUEST FOR RELIEF SC-14R-140 FROM REQUIREMENTS REGARDING THE REACTOR VESSEL HEAD FLANGE SEAL LEAK DETECTION PIPING (TAC NOS. MF3898 AND MF3899)

Dear Mr. Joyce:

By letter dated April 8, 2014, 1 Public Service Enterprise Group Nuclear LLC (PSEG or 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 Salem Nuclear Generating Station, Units 1 and 2, for the duration of the fourth 10-year inservice inspection interval.

Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii),

the licensee requested to use an alternative on the basis that complying with the system leakage test that is required by the ASME Code,Section XI, Table IWB-25001-1, Examination Category B-P, and Table IWC-2500-1, Examination Category C-H, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

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.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of 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.

1 Agencywide Documents Access and Management System Accession No. ML14098A308.

T. Joyce 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.

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

. Lamb, Senior Project Manager Licensing Branch 1-2 Di sion of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311 cc: Distribution via Listserv

ML14100A325 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME JLamb A Baxter MKhanna JLamb DATE 4/29/2014 4/29/2014 4/29/2014 4/29/2014