ML16014A042

Acceptance Review - Peach Bottom 2 & 3 - TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities (CACs MF7209 & MF7209)

ML16014A042
Person / Time
Site:	Peach Bottom
Issue date:	01/14/2016
From:	Richard Ennis Plant Licensing Branch 1
To:	Hanson S Exelon Generation Co
Ennis R, NRR/DORL/LPLI-2
References
CAC MF7208, CAC MF7209
Download: ML16014A042 (2)

Text

From: Ennis, Rick Sent: Thursday, January 14, 2016 8:44 AM To: Stephanie.Hanson@exeloncorp.com Cc: David Helker

Subject:

Acceptance Review - Peach Bottom 2 & 3 - TSTF-484, "Use of TS 3.10.1 for Scram Time Testing Activities" (CACs MF7209 & MF7209)

Stephanie, By letter dated December 23, 2015 (ADAMS Accession No. ML15357A250), Exelon Generation Company, LLC submitted a license amendment request for Peach Bottom Atomic Power Station, Units 2 and 3. The proposed amendment would revise Technical Specification (TS)

Limiting Condition for Operation 3.10.1, to expand its scope to include provisions for temperature excursions greater than 212°F as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4. The proposed change is based on NRC-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities.

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