ML091180573
| ML091180573 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/08/2009 |
| From: | Feintuch K Plant Licensing Branch III |
| To: | Browning T - No Known Affiliation |
| Feintuch K, NRR/DORL/LPL2-1, 415-3079 | |
| References | |
| TAC ME0874 | |
| Download: ML091180573 (1) | |
Text
Karl Feintuch From:
Karl Feintuch Sent:
Wednesday, April 08, 2009 11 :39 AM To:
'Tony Browning' Cc:
'Catron, Steve'
Subject:
ME0874 - Application to amend TS 3.6.1.3 - Results of Acceptance Review - accepted By letter dated March 4,2009, FPL Energy Duane Arnold, LLC (the licensee) submitted a license amendment request for the Duane Arnold Energy Center (DAEC). The letter is available in the Agencywide Documents Access and Management System (ADAMS) with an ADAMS Accession Number of ML090680040.The proposed amendment would change Technical Specification (TS) Section 3.6.1.3 (Primary Containment Isolation Valves) to remove the repair criterion for Main Steam Isolation Valves (MSIVs) that fail their as-found leakage rate acceptance criterion found in current Surveillance Requirement (SR) 3.6.1.3.9.
The purpose of this email 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 (10 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 staff to proceed with 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. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
Karl Feintuch, Project Manager 301-415-3079 Plant Licensing Branch LPL3-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 1