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Staff Responses to Frequently Asked Questions Concerning Decommissioning of Nuclear
Power Reactors
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3.
Decommissioned Sites
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 :
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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)
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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
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environmental-protection techniques, such as automated asbestos removal and
in situ chemical conversion of asbestos to non-hazardous material
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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
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" ?
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
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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.
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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.
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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.
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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.
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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.
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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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