<section xmlns="http://xml.house.gov/schemas/uslm/1.0" xmlns:xsi="http://www.w3.org/2001/XMLSchema-instance" xmlns:dc="http://purl.org/dc/elements/1.1/" xmlns:dcterms="http://purl.org/dc/terms/" style="-uslm-lc:I80" id="id47cbabc1-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703"><num value="9703">§ 9703.</num><heading> Research, development, and demonstration program; establishment; purposes; implementation</heading><subsection style="-uslm-lc:I11" class="indent0" id="id47cbabc2-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a"><num value="a">(a)</num><chapeau> The Secretary shall establish a research, development, and demonstration program to carry out the purpose of this chapter. As part of such program, the Secretary shall at a minimum—</chapeau><paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabc3-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/1"><num value="1">(1)</num><content> refine further the assessment of risk factors associated with the generic design and operation of nuclear powerplants to determine the degree and consequences of propagation of failures of systems, subsystems, and components, including consideration of the interaction between the primary and secondary systems;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabc4-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/2"><num value="2">(2)</num><content> develop potentially cost-beneficial changes in the generic design and operation of nuclear powerplants that can (A) significantly reduce the risks from unintentional release of radioactive material from the various engineered barriers of nuclear powerplants and (B) reduce the radiation exposure to workers during plant operation and maintenance;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabc5-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/3"><num value="3">(3)</num><content> develop potentially cost-beneficial generic methods and designs that will significantly improve the performance of operators of nuclear powerplants under routine, abnormal, and accident conditions;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabc6-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/4"><num value="4">(4)</num><content> identify the effect of total or partial automation of generic plant systems on reactor safety, operation, reliability, economics, and operator performance;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabc7-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5"><num value="5">(5)</num><chapeau> conduct further experimental investigations under abnormal operational and postulated accident conditions primarily for light water reactors to determine the consequences of such conditions. These investigations shall include, but not be limited to, the following:</chapeau><subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabc8-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/A"><num value="A">(A)</num><content> fuel failure at higher than standard burn-up levels;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabc9-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/B"><num value="B">(B)</num><content> fuel-cladding interactions;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabca-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/C"><num value="C">(C)</num><content> fuel and cladding interactions with coolant under various temperatures and pressures;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabcb-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/D"><num value="D">(D)</num><content> thermohydraulic behavior in the reactor core;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabcc-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/E"><num value="E">(E)</num><content> mechanisms to suppress and control the generation of hydrogen gas;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabcd-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/F"><num value="F">(F)</num><content> improved instrumentation for monitoring reactor cores;</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabce-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/G"><num value="G">(G)</num><content> engineered-barrier failure modes; and</content>
</subparagraph>
<subparagraph style="-uslm-lc:I13" class="indent2" id="id47cbabcf-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/5/H"><num value="H">(H)</num><content> fission product release and transport from failed fuel;</content>
</subparagraph>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd0-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/6"><num value="6">(6)</num><content> provide for the examination and analysis of any nuclear powerplant fuel, component, or system which the Secretary deems to offer significant benefit in safety analysis and which is made available to the Secretary for a nominal cost, such as $1: <i>Provided, however</i>, That the Secretary shall accept only the number of samples of such fuel, component, or system necessary to carry out such examination and analysis; and</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd1-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/a/7"><num value="7">(7)</num><content> identify the aptitudes, training, and manning levels which are necessary to assure reliable operator performance under normal, abnormal, and emergency conditions.</content>
</paragraph>
</subsection>
<subsection style="-uslm-lc:I11" class="indent0" id="id47cbabd2-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/b"><num value="b">(b)</num><chapeau> In carrying out the generic safety research, development, and demonstration program established under this chapter, the Secretary—</chapeau><paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd3-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/b/1"><num value="1">(1)</num><content> shall coordinate with the Commission and, to the extent necessary, enter into a new memorandum of understanding or revise existing memoranda for the purpose of eliminating unnecessary duplication and avoiding programmatic conflict with any reactor safety research program of the Commission, including the Improved Safety Systems Research program;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd4-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/b/2"><num value="2">(2)</num><content> shall, to the extent practical, coordinate his activities with such other Government agencies, foreign governments, and industry as he deems appropriate to utilize their expertise, to minimize duplication of effort, and to ensure that information useful for improved concepts applicable to nuclear powerplant safety can be applied in a timely manner. The Secretary may enter into agreements and memoranda of understanding to accomplish these ends, but no such agreement shall have the effect of delaying the development and implementation of programs authorized under this chapter;</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd5-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/b/3"><num value="3">(3)</num><content> shall utilize, to the extent feasible, underutilized federally owned research reactors and facilities, along with the associated personnel, to maintain existing capabilities and to ensure that the research is generic in nature; and</content>
</paragraph>
<paragraph style="-uslm-lc:I12" class="indent1" id="id47cbabd6-3271-11e3-ab2f-8f7fedb88afd" identifier="/us/usc/t42/s9703/b/4"><num value="4">(4)</num><content> shall make such recommendations as are practical to minimize the complexity of nuclear powerplant systems, including secondary systems, and operations.</content>
</paragraph>
</subsection>
<sourceCredit id="id47cbabd7-3271-11e3-ab2f-8f7fedb88afd">(<ref href="/us/pl/96/567/s4">Pub. L. 96–567, § 4</ref>, <date date="1980-12-22">Dec. 22, 1980</date>, <ref href="/us/stat/94/3330">94 Stat. 3330</ref>.)</sourceCredit>
<notes type="uscNote" id="id47cbabd8-3271-11e3-ab2f-8f7fedb88afd">
<note style="-uslm-lc:I85" topic="transferOfFunctions" id="id47cbabd9-3271-11e3-ab2f-8f7fedb88afd">
<heading class="centered smallCaps">Transfer of Functions</heading>
<p style="-uslm-lc:I21" class="indent0">For transfer of certain functions from Nuclear Regulatory Commission to Chairman thereof, see Reorg. Plan No. 1 of 1980, 45 F.R. 40561, <ref href="/us/stat/94/3585">94 Stat. 3585</ref>, set out as a note under <ref href="/us/usc/t42/s5841">section 5841 of this title</ref>.</p>
</note>
</notes>
</section>