ML14086A552

Acceptance for Review Regarding License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor

ML14086A552
Person / Time
Site:	Salem
Issue date:	05/27/2014
From:	John Lamb Plant Licensing Branch 1
To:	Joyce T Public Service Enterprise Group
Lamb J
References
TAC MF3691, TAC MF3692
Download: ML14086A552 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 27, 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 RE: LICENSE AMENDMENT REQUEST TO REVISE POWER DISTRIBUTION LIMITS FOR AXIAL FLUX DIFFERENCE AND HEAT FLUX HOT CHANNEL FACTOR (TAC NOS. MF3691 AND MF3692)

Dear Mr. Joyce:

By letter dated March 24, 2014, (Agencywide Documents Access and Management System Accession No. ML14083A439), PSEG Nuclear LLC (PSEG) requested an amendment to the facility operating license for the Salem Generating Station (Salem) Units 1 and 2. The proposed change would revise Surveillance Requirements (SR) 4.2.1.3, 4.2.1.4, and 4.2.2.2.f associated with Power Distribution Limits Technical Specification (TS) 3/4.2.1, "Axial Flux Difference (AFD)," and TS 3/4.2.2, "Heat Flux Hot Channel Factor-Fq(Z)." The proposed SR changes eliminate or relocate information that is considered to be: (i) an inaccuracy; or (ii) an unnecessary level of detail.

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 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 Section 50.90 of Title 10 of the Code of Federal Regulations (1 0 CFR), 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.

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 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

T. Joyce 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) 415-3100 or via e-mail at John.Lamb@nrc.gov.

. Lamb, Senior Pr Ject Manager Pia t Licensing Branch 1-2 Divi on of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311 cc: Distribution via ListServ

..* ML14086A552 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME Jlamb ABaxter

• MKhanna Jlamb DATE 4/21/2014 04/17/2014 4/21/2014 5/27/2014