ML16237A036

Acceptance Review: Limerick 1 & 2 - TS ISI and IST Program Requirements (CACs MF8193 and MF8194)

ML16237A036
Person / Time
Site:	Limerick
Issue date:	08/24/2016
From:	Richard Ennis Plant Licensing Branch 1
To:	Lynch L Exelon Generation Co
Ennis R
References
CAC MF8193, CAC MF8194
Download: ML16237A036 (2)

Text

From: Ennis, Rick Sent: Wednesday, August 24, 2016 8:17 AM To: Lynch, Laura:(GenCo-Nuc)

Cc: David Helker; Glenn Stewart (glenn.stewart@exeloncorp.com);

Stephanie.Hanson@exeloncorp.com

Subject:

Acceptance Review: Limerick 1 & 2 - TS ISI and IST Program Requirements (CACs MF8193 and MF8194)

Laura, By letter dated July 26, 2016 (ADAMS Accession No. ML16210A227), Exelon Generation Company, LLC submitted a license amendment request for Limerick Generating Station, Units 1 and 2. The proposed amendments would revise Technical Specification (TS) requirements relating to: (1) the inservice inspection (ISI) Program, required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Code (Code); and (2) the inservice testing (IST) Program, required by the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). The proposed changes are based, in part, on Technical Specifications Task Force (TSTF) Traveler TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR [Surveillance Requirement] Usage Rule Application to Section 5.5 Testing.

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

Docket Nos. 50-352 and 50-353