ML16090A106

E-mail Acceptance Review - Peach Bottom 2 & 3 - Recirculation Pump Discharge Valves Surveillance Frequency (CACs MF7528 & MF7529)

ML16090A106
Person / Time
Site:	Peach Bottom
Issue date:	03/30/2016
From:	Richard Ennis Plant Licensing Branch 1
To:	Hanson S Exelon Generation Co
Ennis R
References
CAC MF7528, CAC MF7529
Download: ML16090A106 (2)

Text

From: Ennis, Rick Sent: Wednesday, March 30, 2016 11:07 AM To: Stephanie.Hanson@exeloncorp.com Cc: David Helker

Subject:

Acceptance Review - Peach Bottom 2 & 3 - Recirculation Pump Discharge Valves Surveillance Frequency (CACs MF7528 & MF7529)

Stephanie, By letter dated March 24, 2016 (ADAMS Accession No. ML16084A567), Exelon Generation Company, LLC submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would revise the frequency for cycling of the recirculation pump discharge valves as specified in Technical Specification (TS) Surveillance Requirement (SR) 3.5.1.5. Specifically, SR 3.5.1.5 requires verification that each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position. Currently, this SR needs to be performed once each plant startup prior to exceeding 23 percent rated thermal power (RTP), if the SR had not been performed within the previous 31 days. The amendment would change the frequency for the SR such it is performed in accordance with the Surveillance Frequenc y Control Program (SFCP). The requirements associated with the SFCP are specified in TS 5.5.14.

The purpose of this e-mail is to provide the results of the 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 (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 in stances in which issues that impact the NRC staff's 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 staff's 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