ML15133A475

Acceptance Review for TAC MF6169 - Peach Bottom Unit 3 - Safety Limit Minimum Critical Power Ratio

ML15133A475
Person / Time
Site:	Peach Bottom
Issue date:	05/13/2015
From:	Richard Ennis Plant Licensing Branch 1
To:	Deborah Neff Exelon Generation Co
Ennis R, NRR/DORL/LPLI-2, 415-1420
References
TAC MF6169
Download: ML15133A475 (2)

Text

From: Ennis, Rick Sent: Wednesday, May 13, 2015 3:48 PM To: David Neff Cc: David Helker; Kevin Borton (kevin.borton@exeloncorp.com)

Subject:

Acceptance Review for TAC MF6169 - Peach Bottom Unit 3 - Safety Limit Minimum Critical Power Ratio

Dave, By letter dated April 30, 2015 (ADAMS Accession No. ML15120A290), Exelon Generation Company, LLC submitted a license amendment request for Peach Bottom Atomic Power Station (PBAPS), Unit 3. The proposed amendment would revise the Technical Specifications (TSs) related to the Safety Limit Minimum Critical Power Ratios (SLMCPRs). The proposed changes result from a cycle specific analysis performed to support the operation of PBAPS, Unit 3, in the upcoming Cycle 21. The re-analysis was performed to accommodate operation in the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain based on a separate license amendment request dated September 4, 2014 (ADAMS Accession No. ML14247A503).

The purpose of this e-mail is to provide the results of the NRC staffs 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 (10 CFR), an amendment to the license (including the TSs) 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 staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request 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 staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-1420.

Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation