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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
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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
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\Board of County Commissioners\Resolutions\1990-1999\1998
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28 <br />Nuclear Wasie Orsposal Cnsrs <br />Iv, the usability of the SSES containment .vstrms to limit the release of radiuachve <br />material following an accident invoh•ing fuel damage. These systems fail due to <br />design deficiendes associated with the coolinn of the spent fuel pools as <br />described in Chapter 9. <br />The NRC reyie«~ed the Susquehanna concerns and concluded that although <br />the SSES design did nut conform to numerous federal regulations in effect at the <br />time the plant vas designed and constructed, these safety regulations no longer <br />applied to this facility since both the o~~'ner of the plant and the NRC had failed <br />to detect the nun-conformance at that time. Apparently, in the \RC's eves, igno- <br />ranee of the la~.• is an excuse---e'en though the ~iRC cited noncompliance with <br />safety regulatiuru as a contributor to the wont accident in nuclear power histo- <br />rv: "The evidence from the accident suggests that Chernobyl [;nit 4 vas nut in <br />compliance with ... specific requirements in the 1982 regulations."' <br />The NRC further concluded that nonconfurmances at SSES represented re!- <br />atiyely minor safety significance. The NRC based its safety conclusion on a risk <br />assessment indicating a very low probability of SSES encountering a boiling <br />spent fuel pool. Hu~•~ever, this risk assessment ~.•as predominately biased <br />tu~vards the SSES configuration after numerous plant modifications, analyses, <br />procedure changes, and retraining had been implemented addressing the defi- <br />ciencies. The NRC's evaluation significantly underestimated the risk at the time <br />of discovery. The NRC's bias is important because it misrepresents the risk from <br />the design deficiencies-problems that may remain uncorrected at numerous <br />other operating nuclear power plants similar to SSES. <br />The NRC essentially determined that satisri~ing only the first two defense- <br />in-depth principles is adequate; apparently the public and the environment no <br />longer warrant protection from the release of radioactive material following an <br />accident with fuel damage. However, this determination conflicts v`~ith the stan- <br />dard American defense-in-depth risk management philusophv and more closely <br />resembles the Chernobyl design philosophy: <br />Suyiet safety analysis tends to place greater emphasis un prevention and <br />early mitigation of selected design-basis accidents than it dues on the con- <br />sequernes and mitigation of se~•ere accidents beyond the design basis of the <br />plant= <br />The Chernobyl design philusophv was roundly criticized in the west <br />lincluding critical ~vurds by the \P.C). vet it nu~~• seems that ~~•e are embracing it. <br />The Chernobyl design philosophy isn"t cup~'righted, so at least we won't pay <br />extra fur less protection. <br />(ndicidual Plant Examinations ([PEs) provide further evidence that the <br />~RL is neglecting the third defense-in-depth principle. [PEs are plant-=peck <br />probabilistic nsk assessments ~~t the cure damage frequencies from design bast <br />r~. ents. IPEs evaluate the plant's response to postulated initiatins; e~'ents, factor- <br />in~ in r~lwpment failure r;~tes and uperah~r rrn~n <br />' (i~7 <br />
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