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Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear Power Reactors

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1. General 8. License Termination And the Ultimate Disposition of the Facility
2. Decommissioning Process 9. Hazards Associated with Decommissioning
3. Decommissioned Sites 10. Finances
4. NRC Activities 11. Socio-economic Issues
5. Spent Fuel 12. Public Involvement
6. Radioactive Low-Level Waste 13. Getting Additional Information
7. Transportation 14. Bibliography


3.    Decommissioned Sites


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3.3. What improvements have been made as a result of previous decommissioning experience ?
3.4. What research is being performed to find improved methods to be used during decommissioning ?
3.5. What differences are there in decommissioning between different types of reactor designs ?


3.3.  What improvements have been made as a result of previous decommissioning experience ?
Some improvements in the process, such as the removal of large components, including the reactor vessel, and the use of a primary system chemical flush to reduce worker exposure, have resulted from the experience gained from previous plant decommissionings.
These include strippable coatings of latex or plastic that are used for decontaminating surfaces and the increased use of robotics.
In addition, most licensees have gained experience with decommissioning techniques during routine preventive maintenance programs or as part of repairs required during operations.

3.4.  What research is being performed to find improved methods to be used during decommissioning ?
The following types of improvements are being investigated :
  •   surface-removal techniques to remove the outer surface of a contaminated structure, such as lasers or microwaves combined with vacuums, electrohydraulic scabbling (water-pressure shock waves that are electrically controlled), and electrokinetic decontamination of concrete (gel electrolytes are used with electrodes to leach ionic contaminants from deep inside porous concrete)
  •   cutting techniques, such as laser cutting or oxy-gasoline torches (which work twice as fast as an acetylene torch on 1-inch steel) to remove structures
  •   improved methods for worker protection, such as protective suits with liquid air-cooling apparatus and lightweight breathable suits with chemical absorption protective layers
  •   environmental-protection techniques, such as automated asbestos removal and in situ chemical conversion of asbestos to non-hazardous material
  •   survey/monitoring techniques, such as pipe-explorer internal survey/characterization systems and a remote 3-D characterization and archiving system (robotic sensor and mapping platforms analyze for hazardous organic and radioactive contaminants).
Commercial firms are also developing promising avenues of research into usable technologies.

3.5.  What differences are there in decommissioning between different types of reactor designs ?
An analysis (of decommissioning at nuclear facilities, including nuclear power plants) looked at total estimated costs, occupational and public dose, and low-level waste volumes.
The GEIS estimates for cost for the reference facility were generally higher by about 20 % for the boiling water reactors (BWRs) than for pressurized water reactors (PWRs), depending on the decommissioning option selected.
Occupational dose estimates in the GEIS were slightly higher for the reference BWR, by 10 to 50 %, depending on the decommissioning option.
Estimates of public dose were lower for the reference BWR by up to a factor of 2, depending upon the scenario.
Burial-volume estimates for low-level waste for reference BWRs and PWRs for SAFSTOR and DECON options were very close to the same. The staff expects to issue a draft supplement in the year 2001.
One other major difference between decommissioning BWRs versus PWRs is that BWRs are designed so that the spent fuel pool is located in the reactor building, rather than in a separate building that can be isolated from the rest of the facility.
This eliminates the possibility of decontaminating and decommissioning the remainder of the facility while leaving the spent fuel pool building as a "nuclear island".


4.    NRC Activities


See original FAQs from the NRC.


5.    Spent Fuel


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Here also only some "general questions / answers" will be broached; indeed, in the European Community, rules differ from one land to another.
It will be, when possible, paid attention to this topic and answers will be adapted.

5.1. What are "high-level wastes" ?
5.2. What is meant by the term "spent fuel" ?
5.8. Spent Fuel Pools
5.8.1. Why is spent fuel stored in a pool of water ?
5.8.2. Has the spent fuel pool been analyzed to determine the limits for heat removal due to spent fuel storage ?
5.8.3. Do spent fuel pools leak, and if they do, how much radioactive material could be leaked, and where would it go ?
5.8.4. What would happen if there were a loss of heat-removal capability of water in a spent fuel pool when it was fully loaded ?
5.8.5. What would happen to the fuel in the spent fuel pool if an earthquake ruptured the pool, or if an airplane crashed into the pool ?
5.8.6. What can be done to prevent the spent fuel pool from boiling dry ?


5.1.  What are "high-level wastes" ?
High-level radioactive waste (HLW), as it pertains to commercial nuclear power reactors, is mainly irradiated (spent) reactor fuel.

5.2.  What is meant by the term "spent fuel" ?
Spent nuclear fuel is uranium-bearing fuel elements that have been used at commercial nuclear power reactors.
Although spent (used) fuel can no longer produce enough heat to produce electricity, it contains highly radioactive material resulting from the fission process that takes place within the reactor.
As a result, it still continues to generate radiation and heat. This heat and radiation are caused by "radioactive decay" of the products of the fission process.
The heat and radioactivity in spent fuel necessitate that any shipment be made in containers or casks that provide the necessary degree of protection.
In practice, this means that a cask must shield and contain the radioactivity and dissipate the generated heat.

5.8.  Spent Fuel Pools
  5.8.1.  Why is spent fuel stored in a pool of water ?
Even after the nuclear reactor is shut down, the fuel continues to generate decay heat.
Decay heat results from the radioactive decay of fission products. The rate at which the decay heat is generated decreases the longer the reactor has been shut down.
So the longer the spent fuel has been out of the reactor, the less heat that it gives off.
Storing the spent fuel in a pool of water is a way to provide an adequate heat sink for the removal of heat from the irradiated fuel. In addition, the fuel is located far enough under water that the radiation emanating from the fuel is shielded by the water to adequately protect the workers from the radiation.

  5.8.2.  Has the spent fuel pool been analyzed to determine the limits for heat removal due to spent fuel storage ?
Yes. The regulations give criteria that must be met for fuel storage and handling. This includes designing fuel-storage systems to ensure adequate safety under normal and postulated accident conditions. The system is to be designed with suitable shielding for radiation protection, with appropriate containment, confinement, and filtering systems, and with a heat-removal capability that is reliable and that can be tested to ensure that it meets the requirements for removing the heat produced by the spent fuel.

  5.8.3.  Do spent fuel pools leak, and if they do, how much radioactive material could be leaked, and where would it go ?
All nuclear power plants have a reinforced-concrete spent fuel pool (SFP) structure designed to retain its function, even following the design-basis seismic event (that is, seismic Category 1 or Class 1 [earthquake]) that is anticipated for the area. The SFP also has a welded, corrosion-resistant liner.
All plants except for one have leak-detection channels positioned behind liner plate welds to collect any leakage and to direct the leakage to a point at which it can easily be monitored.
Nearly all nuclear power reactors have passive features preventing draining or siphoning of the SFP to a coolant level below the top of stored, irradiated fuel. Excluding paths used for irradiated fuel transfer, passive features at nearly all nuclear reactors prevent draining or siphoning the coolant to a level that provides inadequate shielding for fuel seated in the storage racks.

In the event that SFP coolant inventory decreases significantly, several indicators are available to alert operators to that condition. The primary indication is a low-level alarm.
A secondary indication of a loss of coolant is provided by area radiation alarms.
These primary and secondary alarms indicate a loss of shielding that occurs when SFP coolant inventory is lost. Except for the SFP located inside the containment building, the area radiation alarms are set to alarm at a level low enough to detect a loss of coolant inventory early enough to allow for recovery before radiation levels could make such a recovery difficult.

The level of radioactivity in the water of the spent fuel pool is low. In addition, nuclear plants have cleaning systems to maintain the purity of the water in the spent fuel pools. All nuclear plants have a groundwater monitoring system around the facility so that if a system leaks, there is a method for alerting the licensee to the problem as well as for providing information regarding the location of the contamination.

  5.8.4.  What would happen if there were a loss of heat-removal capability of water in a spent fuel pool when it was fully loaded ?
The consequences of losing the heat-removal capability or water (coolant) in a spent fuel pool depends on the amount of time since the fuel was last used for power operation inside the reactor.
If fuel was recently used for power operation, there may be enough decay heat to cause the spent fuel pool coolant to heat up to the boiling point if forced cooling were lost to the spent fuel pool.
If plant operators took no action, boiling would cause the level in the spent fuel pool to decrease over time. However, operators have redundant sources of water to add to the pool to maintain coolant level should a loss of forced cooling occur.
Operators are alerted to a loss of level condition by a series of alarms at the cooling system control station and in the main control room. Given the unlikely event that no operator action is taken, the pool level would decrease at a very slow rate (about one foot every several hours to weeks, depending on the age of the stored fuel).
The longer the time interval since the last batch of fuel was used to generate power in the reactor, the longer it would take for the spent fuel to boil off the spent fuel pool coolant.
Boiling the spent fuel pool coolant is, however, an acceptable method for cooling spent fuel and has a minimal effect on public health and safety. In the unlikely event that a large loss of coolant uncovers the spent fuel, if sufficient time has not elapsed since the fuel was used to generate power in the reactor, the spent fuel may have enough decay heat to overheat the cladding in air and cause it to ignite.
The resulting fire could carry radioactive particles offsite and the consequences could be significant.
However, the NRC staff considers this a very low probability accident because of design features required at all spent fuel storage pools that minimize the possibility of losing all of the spent fuel pool coolant.

  5.8.5.  What would happen to the fuel in the spent fuel pool if an earthquake ruptured the pool, or if an airplane crashed into the pool ?
Spent fuel pools are designed to withstand earthquakes greater than any earthquake that actually occurred or is expected to occur in the area of the plant. Therefore, the probability of the spent fuel pool rupturing due to an earthquake is very low. However, in the unlikely event that a very large earthquake does occur, one that is larger than the pool was designed to withstand, the pool structure could fail and allow the coolant to drain out. The consequences of an accident like this are discussed in the response to Question 5.8.4, above. In the unlikely event that an aircraft crashed into the spent fuel pool, the pool structure could be severely damaged and not capable of maintaining coolant level. In this event, consequences such as those discussed in Question 5.8.4 could result. However, the staff has evaluated the possibility of an aircraft impacting the spent fuel pool and consider it a very low probability event.

  5.8.6.  What can be done to prevent the spent fuel pool from boiling dry ?
A cooling system removes decay heat from the spent fuel pool. The coolant in the spent fuel pool is maintained below a specific temperature and the level of the water is maintained at a specific height over the spent fuel. Temperature indicators are installed and are either equipped with an alarm or require visual surveillance on a daily basis. High/low-water-level monitors are installed in spent fuel pools. The monitor alarms at the spent fuel pool and in the control room when the spent fuel pool's water level is not within the specified limit.

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