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NUREG-1537, Part 2 - NRC

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. AuxiLARY SYSTEMS<br />

* Methods for inspection and verification of new fuel to ensure that<br />

procurement specifications have been met.<br />

* Systems and methods for movement, physical control, and storage of new<br />

fuel within the facility.<br />

* Methods, analyses, and systems for secure storage of new and irradiated<br />

fuel that will prevent criticality (kff not to exceed 0.90) under all conditions<br />

of moderation during storage and movement. (The use of criticality<br />

monitors, if applicable, should be reviewed, in accordance with 10 CFR<br />

70.24.)<br />

* Tools,'systems, and methods for inserting fuel into the reactor core and for<br />

removing fuel from the core. (This discussion should include physical and<br />

administrative methods to ensure that fuel is handled only by authorized<br />

persons.)<br />

* Systems, components, and methods for radiation shielding and for<br />

protecting irradiated fuel from damage during removal from the core,<br />

movement within the reactor facility, and storage. (Thermal and -<br />

-mechanical damage should be discussed. The cooling of stored irradiated<br />

fuel should be discussed in detail in Chapter 5, 'Reactor Coolant Systems,"<br />

of the SAR, if the system is integral to that function. Otherwise, it should<br />

be described in this section.)<br />

* Systems, components, and methods-used to prepare and ship fuel off site in<br />

accordance with applicable regulations (This function should also be<br />

discussed for facilities that expect to retain the fuel until reactor<br />

decommissioning. The reviewer should note that the applicant may be<br />

discussing events many years in the future and that some degree of<br />

uncertainty may exist.)<br />

* Technical specifications that define controls on fuel during handling and<br />

storage, including testing and surveillance.<br />

Acceptance Criteria<br />

The acceptance criteria forbthe information on the handling and storage of reactor<br />

fuel include the following: 7<br />

- -*<br />

* The design of all systems, components, and methods for handling, moving,<br />

or storing fuel outside the reactor core should ensure with a high<br />

confidence level that the neutron multiplication, kdf, will not exceed 0.90<br />

under any possible conditions. (Existing usage with kf greater than 0.90<br />

REV 0,2/96 9-s Smuu, REVIEW Px,N<br />

REV 0, 2196 9 I5 STAmADMDREviEwPLAN

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