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Minutes - 19990209
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BOCC
Date
2/9/1999
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Work Session
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Minutes
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Agenda - 02-09-1999
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. . �, .../\ T��� . <br /> t.l,\ � <br /> 2 <br /> 1 cooling and electrical supply for pools C & D will have to be met from unit one. He explained the <br /> 2 design of the facility and how the plant operates. He mentioned that the water in the pools provides <br /> 3 both shielding and cooling for the high levels of radioactivity and that fuel is brought to the site from <br /> 4 other reactors operated by CP&L. All nuclear plants in the country have a problem with accumulating � <br /> 5 stocks of spent fuel because the Federal government has not yet developed a repository for spent <br /> 6 fuel. CP&L intends, by putting into use pools C & D, to provide a capacity at the Shearon Harris Plant <br /> 7 to accommodate all of the spent fuel that CP&L produces in all four of its reactors. He explained that <br /> 8 there are racks at the base of the pools where the spent fuel is stored. The Harris Plant is a <br /> 9 Pressurized Water Reactor(PWR). This is a very long, thin structure made up of many small tubes. I <br /> 10 These tubes are made of a zirconium alloy and fuel pellets are placed inside them. He described the <br /> 11 design of the Boiling Water Reactor (BWR) and the Pressurized Water Reactor(PWR). He <br /> 12 mentioned that as the quantities of spent fuel have accumulated at nuclear piants, the lice,nsees have <br /> 13 switched to more compact storage design. They have moved from an open frame design to a closed <br /> 14 box design which allows for the storage of more spent fuel. He stated that the closed box design has <br /> 15 an important safety implication which he would discuss later in his presentation. He explained the <br /> 16 cooling systern design used in nuclear plants. <br /> 17 Safetv Issues: Dr. Thompson stated that there were technical issues identified in the License <br /> 18 Amendment Application. The design intent of the Shearon Harris Plant was that Unit Two, which was <br /> 19 not constructed, would perform the support functions for pools C & D. That is no longer possible. The <br /> 20 licensee has calculated that the maximum heat load that will be present in these pools is 15.6 million <br /> 21 BTU's per hour. The licensee also has determined that the component cooling water system for unit <br /> 22 one cannot accommodate a heat-load of that magnitude. The company's plan for the next several <br /> 23 years is to adrninistratively limit the heat-load in pools C & D to one million BTU per hour and to <br /> 24 exploit the margin in the existing component cooling water(CCW) systems so as to meet that heat <br /> 25 load. This raises what is known as an "Unreviewed Safety Question" because this same system <br /> 26 serves safety functions at the reactor. Therefore, the licensee has to demonstrate, and the NRC has <br /> 27 to agree that the system has enough capability to meet the additional load of the spent fuel pools and j <br /> 28 serve the safety functions of the reactor. The critical point is the ability of the CCW system to serve �� ' <br /> 29 the reactor in the event of an accident because of loss of coolant. The company's longer-term plan is <br /> 30 to upgr�de the CCW system. That upgrade would presumably accommodate the heat load of 15.6 <br /> 31 million BTU's per hour. This situation alone is sufficient to challenge the NRC staffs determination of <br /> 32 "No Significant Hazard". First, because an "Unreviewed Safety Question" exists and secondly that the <br /> 33 license application is for the ability to fill pools C & D with fuel even though there is no design on the <br /> 34 table for a cooling system that could accommodate a full load in the pools. Another point is that in <br /> 35 pools C & D the racks will not be safe against criticality for fuel that has a low burn-up. Low burn-up <br /> 36 fuel has been used for a relatively short time or is relatively high in enrichment. <br /> 37 <br /> 38 Dr. Gordon Thompson stated that there are a variety of ways in which these pools could run dry. It is <br /> 39 relatively low probability event but it is an extremely high consequence event. He mentioned that the <br /> 40 NRC only focuses on the possibility of pools running dry. They have not considered the risk <br /> 41 significance of a partial drainage. This is another matter that challenges the finding of the"No <br /> 42 Significant Hazard" determination. He explained how cooling would have to occur if all of the water <br /> 43 were lost. For relatively recently discharged fuel the fuel temperature can rise in this event to the <br /> 44 point where a fire occurs. If that occurs a substantial fraction of the radioactivity in the pool can be <br /> 45 released into the atmosphere. This could become significant in the case of pools C & D at Shearon <br /> 46 Harris because the intent is to use them to store relatively older fuel. The question as to whether or <br /> 47 not this older fuel can ignite in the event of a loss of cooling is an important one that should be settled <br /> 48 through the hearing process. This cannot be dismissed with a "No Significant Hazard" determination. <br /> 49 He mentioned that in the case of a pool fire there is volatile material that enters the atmosphere and <br /> 50 travels downwind as fine particles, settles on structures and the ground, and irradiates people or <br /> 51 enters the food chain or water supply. � <br /> 52 � <br /> 53 Dr. Thompson further stated that an alternative is to return to the low-density type of rack. When the <br /> 54 water is lost with this configuration the water does not heat up to the point where fire is possible. This <br />
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