Licensing Process for Nuclear Installations
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Added on 2021-04-22
Licensing Process for Nuclear Installations
Added on 2021-04-22
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Question 1 A combined license is able to authorize both the construction and conditional operation of nuclear plant. For the application of the combined license, the application for the operational license is done according to 10 CFR Part 50. The details which are required in the application forthe operating license are also considered important in the application of the combined license. Financial and antitrust information as well as assessment needs for the power are required in the application. In addition, inspections, tests, analyses, and acceptance criteria (ITAAC) are considered in this process unlike in the two-step licensing (U.S. Nuclear Regulatory Commission, 2004). Operation standards and safety are the key elements which are focused in the combined license.On the other hand, the key requirements which are needed for the obtaining of the operational license in two-step licensing in contained in NRC’s regulations. The two processes in this process include the issuance of a construction permit and an operating license. The Two-Step licensing process is able to cover wider events of activities unlike the combined licenses which concentrate on nuclear plants (U.S. Nuclear Regulatory Commission, 2004). In addition, the two-step licensing procedure is able to consider different aspects such as the preliminary safety analyses, the environmental review and the financial and antitrust statements. The needs of the power plant are the other important aspects which are considered in this process. The NRC must be able to perform the acceptance review for the licensing to takes effect. Question 2The early site permit is an approval which can be issued in order to address emergency and review of some key elements of nuclear plants. The early site permits are issued to address some
key issues such as safety issues, environmental protection issues and plans for coping with emergencies as well as review of specific nuclear plan designs. Question 3The opportunities which are involved in public involvement include optional pre-application meeting, tech meeting on site safety review (U.S. Nuclear Regulatory Commission. (n.d.), 2012),public meeting on environmental review; ACRS review meeting and mandatory hearing on BSP.The level of public participation is dictated by notices which are issued for different events. Question 4Regulatory Guide 10.3 applies to preparation of applications for special nuclear material licenseswhich are for less than critical mass quantities. The key requirement used for the guide is the code of federal regulations found on 10 CFR Part 70. The guide is able to provide the information to applicants needed to complete NRC form 313. The guide supports the volume 17 of NUREG- 1556. Question 5 The analogous standard adopted by the IAEA for the protection against radiations in 10 CFR 20 include the control of issuance of licenses, controlling of receipts and their possession, control ofuse, transfer, and disposal of the licensed radiations. The evaluation of the probability of the accidents and consequences are also incklud3d in the safety consideration for the nuclear plants. Reduction of the margin of safety is an analogue consideration which is made in this regulation. PSAR and FSAR are able to provide the safety requirements to consider at different instances. The control of dose exposure is usually defined under this section for different parties. All these
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