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NUREG-1537, Part 2 - NRC

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CHAPTER 10<br />

dimensions, materials, angles of reflection, and material attenuation factors.<br />

Exposure to radioactivity produced by experimental operations should be<br />

consistent with the analysis in Chapter 11, *Radiation Protection Program<br />

and Waste Management," of the SAR. The potential exposure from<br />

malfunction or failures of an experimental facility must be within the values<br />

analyzed in Chapter 13. Special radiation detectors used for experiments<br />

should be discussed in Chapters 7, "Instrumentation and Control Systems,"<br />

or 11 of the SAR or in the experiment protocol.<br />

* For most non-power reactors, any required experiment or facility cooling<br />

might be accomplished through convection heat transfer to the surrounding<br />

reactor moderator or coolant water. The thermal-hydraulic analysis should<br />

demonstrate that experimental facility cooling is designed to prevent failure<br />

of the facility under all operating conditions of the reactor or the<br />

experiments. Any interdependence of the experiment cooling and reactor<br />

coolant systems should not compromise adequate fuel cooling or prevent<br />

safe reactor shutdown.<br />

For any experimental facilities that require a special cooling system<br />

independent from the reactor primary coolant system, the technical<br />

evaluation considerations should be basically the same as those for the<br />

reactor coolant system. The applicable guidance in Chapter 5 of this<br />

review plan should be followed. V<br />

L At many non-power reactors, beam ports penetrate the reactor vessel<br />

below the water level of the pool and in most of those cases below the top<br />

of the reactor core. Therefore, the LOCA analysis in Chapter 13 of the<br />

SAR is very important. The applicant should show that the design of<br />

experimental facilities does not introduce new mechanisms to initiate a<br />

LOCA, or that the potential consequences of a LOCA caused by the failure<br />

of experimental facilities are considered acceptable by the Chapter 13<br />

analysis. The applicant should show that fuel integrity would not be lost as<br />

a result of a LOCA initiated or affected by the design of an experimental<br />

facility or by the malfunction of an experiment or experimental facility.<br />

* With regard to the experimental facility safety systems and the functional<br />

interface between these systems and the reactor protection system, the<br />

applicant should demonstrate that in the event of any credible malfunction<br />

in the experimental facility, the design offers reasonable assurance that the<br />

safety system will be capable of protecting the reactor, the experiment, and<br />

the health and safety of the public.<br />

* For any large-volume irradiation facilities, such as an exposure room or dry<br />

chamber, an acceptable design should include provisions for (1) preventing<br />

<strong>NUREG</strong>-<strong>1537</strong>. PAar 2 10-6 REv 0,2196<br />

<strong>NUREG</strong> <strong>1537</strong>.PART2 10-6 REV 0. 2/96

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