ML121070652

Acceptance Review Email, Relocate Technical Specification Limiting Condition for Operation 2.17, Miscellaneous Radioactive Material Sources, and Surveillance Requirement 3.13 to Updated Safety Analysis Report

ML121070652
Person / Time
Site:	Fort Calhoun
Issue date:	04/16/2012
From:	Lynnea Wilkins Plant Licensing Branch IV
To:	Hansher B Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
References
TAC ME8220
Download: ML121070652 (2)

Text

From: Wilkins, Lynnea Sent: Monday, April 16, 2012 3:38 PM To: HANSHER, BILL R Cc: Lent, Susan; Burkhardt, Janet

Subject:

Acceptance of Fort Calhoun LAR to Relocate Operating and SRs for TSs 2.17 and 3.13 Concerning Misc. Radioactive Materials (ME8220)

Bill, By letter dated March 9, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML120720151), Omaha Public Power District (OPPD, the licensee) submitted a license amendment request for Fort Calhoun Station, Unit 1 (FCS). The proposed amendment would relocate Technical Specifications (TS) Limiting Condition of Operation (LCO) 2.17, Miscellaneous Radioactive Material Sources, and the associated surveillance requirement (SR) 3.13, Radioactive Material Sources Surveillance, from the FCS TS. The operability and surveillance requirements for leak checking of miscellaneous radioactive material sources would be incorporated into the FCS Updated Safety Analysis Report (USAR) and associated plant procedures.

The purpose of this message is to provide the results of the NRC staff's acceptance review of this 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 NRC staff to complete 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. 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 staff's ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1377.

Lynnea Wilkins, Project Manager Fort Calhoun Station, Unit 1 Cooper Nuclear Station Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Phone: 301-415-1377