25.06.2013 Views

NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

NUREG-1537, Part 2 - NRC

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

11 RADIATION PROTECTION-PROGRAM AND<br />

WASTE MANAGE-MENT--<br />

This chapter provides guidance for the review and evaluation of Chapter 11 of the<br />

applicant's SAR, which should contain information about radiation protection and<br />

radioactive waste management provisions at the facility. Information should<br />

include radiological design bases of the reactor structures, systems, components,<br />

experimental facilities, and laboratories under the reactor license; procedures,<br />

policies, and practices employed to ensure compliance with applicable standards<br />

and regulations on radiation doses and protection; procedures, policies, and<br />

practices to ensure that radioactive wastes are managed in compliance with<br />

appli6able regulations and standards; and the program to keep radiation exposure<br />

at the facility as low as is reasonably achievable (ALARA). The responsibilities of<br />

the health physics organization at the reactor facility and of any other onsite<br />

radiation protection and radioactive waste management organizations should also<br />

be described. Throughout this chapter, the applicant should show that licensed<br />

activities will be conducted in compliance with applicable regulations, with<br />

emphasis on 10 CFR <strong>Part</strong> 20.<br />

This chapter should address all radioactive materials and radiation sources that are<br />

produced in the reactor or used within the reactor facility and that are possessed<br />

under the authority of the reactor operating license. Radioactive standards, check<br />

sources, and other byproduct material used in the reactor program, reactor startup<br />

sources, fuel and other special nuclear material, and source material that may be<br />

under the authority of the reactor license should be included.<br />

The complexity'of reactor facilities Will vazy widely from one non-power reactor to<br />

another, as will the risks due to radiation. Furthermore, a non-power reactor..<br />

facility may be only a small component of a large organization, such as a university<br />

or corporation, and could obtain its radiation protection and radioactive waste<br />

management services from other parts of the organization. Therefore, the scope<br />

and magnitude of the radiation protection and radioactive waste management<br />

programs should be expected to vary, and may be found acceptable as long as the<br />

program is consistent with a uniform requirement to adequately protect the health<br />

and safety of the public.<br />

In some places in this chapter, reference is made to conservative best estimates or<br />

conservative but realistic' calculations.: This means that estimates or calculations<br />

performed by the applicant should always give results that are conservative<br />

However, the applicant should try to avoid such large'levels of conservatism that<br />

results are orders of magnitude from the expected true'answer. In -some cases,<br />

non-power reactor applicants have used assumptions or calculation methods that<br />

have produced very conservative, but acceptable results. Subsequently, regulatory<br />

REv 0,2/96 11-I STANDARD REVIEW PLAN<br />

REV 0, 2M 11-1 STANDARD REvmwPLAN

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!