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Agenda - 11-17-1998 - 5a
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Agenda - 11-17-1998 - 5a
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6/25/2010 12:11:33 PM
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BOCC
Date
11/17/1998
Meeting Type
Regular Meeting
Document Type
Agenda
Agenda Item
5a
Document Relationships
Minutes - 19981117
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\Board of County Commissioners\Minutes - Approved\1990's\1998
RES-1998-039 A Resolution Regarding Proposed Expansion of High Level Radioactive Waste Storage Facilies at CP &L Shearon Harris Nuclear Power Plant 11-17-1998-5a
(Linked From)
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\Board of County Commissioners\Resolutions\1990-1999\1998
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1.1 <br />Nuclear Wasre Disposal Cns~s <br />accident e+•erv 60,UO1) years given the lUy plants Lvrrently operating. Due to the <br />accident's perceived low probability, the I~RC concluded that it represented an <br />acceptable nsk to public health and safety despite the severe consequences. <br />The 1leart of probabilistic risk assessment IPRA) is statistical analysis. Such <br />ciphering has valuable applications, but PRA proponents quantifying nuclear <br />safety risks should consider the fief that a SRC statistician published this c~n- <br />clusion un Vlarch 9, 1979: <br />The probability is less than 0.~ that the next (i.e.. the first) major accident <br />occurs within the next-100 reactor vein. The probability is less than .0. that <br />the next major accident occurs in the next 21 reactor years. The probability <br />is larger than 0.~ that the next major accident will occur after the next SOU <br />reactor years." <br />The major accidcr~t•at Three IV[ile Island Unit 2 occurred on March 3b, 1979- <br />fe++•er than 500 hours later. <br />The primary faults of PRAs include nut addressing all credible initiating <br />e+•ents and using invalid assumptions. (t is exceedingly difficl-lt to co+•er every <br />conceivable failure mule and effect in a PRA for something as complex as a <br />nuclear power plant. According to a consultant to the ~iRC who reviewed <br />Individual Plant Examinations featuring PRA, "attention to detail makes sate <br />plants-lack of attention to details kills people."~ <br />The nuclear power industn• has nut evaluated the integrated risk from <br />nuclear pu~ver plant operation with the on-site storage of significantly more <br />spent fuel assemblies than had been considered +vhen the plants +~•ere designed. <br />Spent fuel risk assessments assume that only one-third of a reactor core's inven- <br />turv ++•ill be damaged, vet spent fuel pools now contain up++ards of seven reactor <br />cures of irradiated fuel assemblies as shown in Table i-l. These details demand <br />proper attention. <br />The spent fuel rises sessments dismiss the se+•ere consequences from a <br />spent fuel accident primarily due to the perceived lung time that the operating <br />staff his to perform mitigating actions. However, these risk assessments fail to <br />account fur the single must important element in any mitigation effort-name!v, <br />the problem's detection. The instrumentation used to monitor spent fuel pool <br />temperature and level is almost al+vavs nonemergencv equipment. This means <br />that it is nut designed, procured, installed. maintained. or tested with the same <br />high standards applied to emergency system components to guarantee their per- <br />furmance. As repeatedly illustrated by the fulluwin~; incidents, the initiating <br />e+~ent frequently Sues undetected fur hours ur even days due to inoperable spent <br />fuel pout instrumentation. It seems prudent, if nut mandaturc, to pnn•ide reason- <br />,ible a~sur,~nce that spent fuel pu~~l hr~~blrm~ ~~ III be readily detected before their <br />~r.~~•e cun.e~luence~ are disrmr. ed h,i~+•~1 .,n remedi<il actuuu. <br />r;p <br />
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