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-The Project Gutenberg EBook of The Nuclear Ship Savannah, First Atomic
-Merchant Ship, by Anonymous
-
-This eBook is for the use of anyone anywhere in the United States and most
-other parts of the world at no cost and with almost no restrictions
-whatsoever.  You may copy it, give it away or re-use it under the terms of
-the Project Gutenberg License included with this eBook or online at
-www.gutenberg.org.  If you are not located in the United States, you'll have
-to check the laws of the country where you are located before using this ebook.
-
-Title: The Nuclear Ship Savannah, First Atomic Merchant Ship
-
-Author: Anonymous
-
-Release Date: October 30, 2020 [EBook #63584]
-
-Language: English
-
-Character set encoding: UTF-8
-
-*** START OF THIS PROJECT GUTENBERG EBOOK THE NUCLEAR SHIP SAVANNAH ***
-
-
-
-
-Produced by Stephen Hutcheson and the Online Distributed
-Proofreading Team at https://www.pgdp.net
-
-
-
-
-
-
-
-
-
-                                  the
-                              nuclear ship
-                                SAVANNAH
-
-
-                      _first atomic merchant ship_
-
-
-                           one of the world’s
-                                 SAFEST
-                                 ships
-
-
-                      U.S. DEPARTMENT OF COMMERCE
-                   Frederick H. Mueller, _Secretary_
-
-                        MARITIME ADMINISTRATION
-          Ralph E. Wilson, _Chairman_, Federal Maritime Board
-                      and _Maritime Administrator_
-
-                        ATOMIC ENERGY COMMISSION
-                       John A. McCone, _Chairman_
-
-    [Illustration: Multiple advanced electronic and mechanical safety
-    devices guard this “atomic heart.”]
-
-  CONTROL ROD DRIVE MOTORS
-  HYDRAULIC SCRAM CYLINDERS
-  DRIVE LINE LEAD SCREW SECTION
-  BUFFER SEAL ENCLOSURE
-  BORON STEEL CONTROL RODS
-  PRESSURE VESSEL
-  OUTLET NOZZLE
-  REACTOR CORE
-  THERMAL SHIELD
-  FUEL ELEMENTS
-  FLOW BAFFLE
-  SUPPORT RING
-  INLET NOZZLE
-  PRESSURIZED WATER REACTOR
-
-
-The N.S. SAVANNAH, the first nuclear-powered cargo-passenger ship, is
-one of the safest seagoing craft in the world.
-
-This is the result of careful and deliberate planning.
-
-Every appropriate safety device, factor, and technique were sought in
-the design and planning stage, and the ship’s construction has probably
-been more closely and intensively inspected, tested, and scrutinized
-than that of any other merchant ship ever built.
-
-
-SAFETY POLICY BASIC
-
-The Declaration of Policy of the Merchant Marine Act of 1936 calls upon
-the Maritime Administration for the promotion and maintenance of an
-American Merchant Marine for trade and defense “composed of the best
-equipped, safest, and most suitable types of vessels.”
-
-The Atomic Energy Commission is engaged in the N.S. SAVANNAH project as
-a part of its responsibility under the Atomic Energy Act of 1954 “to
-encourage widespread participation in the development and utilization of
-atomic energy for peaceful purposes to the maximum extent consistent
-with the common defense and security and with the health and safety of
-the public.” The Commission has the responsibility of providing a safely
-operable nuclear power plant for the vessel; instructions and
-regulations for the disposition of wastes; the use, handling, and
-disposal of source, special nuclear, and by-product material; and the
-health and safety aspects associated with these responsibilities.
-
-Ship safety ashore, abroad, on the high seas, and in port is of major
-interest to the Maritime Administration, the Atomic Energy Commission,
-the U.S. Coast Guard, the Public Health Service, and such private
-agencies as the American Bureau of Shipping.
-
-The N.S. SAVANNAH is constructed to meet or surpass every standard set
-by all of these responsible agencies and will have a substantial
-built-in safety margin in excess of the most stringent requirements of
-applicable standards, which are among the highest in the world. Where
-there were no existing standards every precaution in keeping with sound
-judgment and engineering experience has been applied in the construction
-and safety considerations of the ship.
-
-                   _The N.S. Savannah Is a Safe Ship_
-
-The reputation of American industry and the integrity of the Government
-of the United States stand behind this statement.
-
-Following is a detailed listing of the factors that make the N.S.
-SAVANNAH so safe:
-
-
-SAFETY FACTORS
-
-As the world’s first commercial, nonstationary type of nuclear power
-plant, the SAVANNAH’s design and construction have resulted in a vessel
-with an unprecedented degree of safety. Basically, the safety
-considerations concern two separate but closely inter-related factors:
-
-(1) The hull and interior structure surpass the highest standards of
-safety, both in the conventional marine sense and in the light of the
-additional factors created by the installation of a nuclear propulsion
-plant; and
-
-(2) The nuclear propulsion system creates no more hazard to the crew and
-passengers, and other ships in a busy port, than any modern conventional
-steam propulsion system—actually, in the light of safety factors,
-included because of its prototype nature, the N.S. SAVANNAH is as safe
-as, and in some respects safer than, a steam-powered vessel that burns
-coal or oil.
-
-The basic difference in safety between a nuclear-powered ship and a
-conventionally powered ship involves radioactivity which results from
-the fission process. Provision has been made to control this
-radioactivity on the SAVANNAH under all foreseeable conditions. This
-control is accomplished through the following design and operational
-features:
-
-
-HULL AND INTERIOR STRUCTURE
-
-In general, the following safety requirements were used by the
-SAVANNAH’s architects, George G. Sharp, Inc., in the design of the ship:
-
-(1) The ship is as safe as, or safer than, any other vessel of its class
-with regard to the usual “hazards of the sea”; and
-
-(2) In no credible accident can there be any hazardous release of
-radioactivity to the surroundings.
-
-The SAVANNAH is designed to a two-compartment standard of subdivision
-(i.e., the ship will remain afloat with two main compartments totally
-flooded) at a draft of 29 feet, 6 inches. The ship complies with all the
-applicable laws of the United States and requirements of the regulatory
-bodies and rules in force as to standards of safety.
-
-Structurally, the SAVANNAH differs from conventional passenger-cargo
-ships only in that the reactor and containment foundations are
-comparatively much heavier than the foundations for normal ship’s
-machinery. The heavy longitudinal members are carried well beyond the
-reactor space bulkheads to tie with a smooth transition into the
-double-bottom structure.
-
-Stability equivalent to that of a conventional passenger-cargo ship with
-fuel oil tanks full has been obtained in the SAVANNAH. In addition,
-because there is no fuel oil to be consumed in passage, there is less
-variation in the stability of the ship during the course of a long
-voyage.
-
-
-VITAL COMPONENTS DUPLICATED
-
-From the standpoint of ship safety, assurance of sufficient power to
-maintain steerage and maneuverability is the principal requirement of
-the propulsion plant. To this end, duplication of machinery and power
-sources on the SAVANNAH has been carried to the fullest practicable
-degree. An electric “take-home” motor is installed for emergency
-operation. Developing 750 hp (nominal), it is coupled to one of the
-high-speed pinions in the reduction gear. A quick-connect coupling
-permits engagement in less than 2 minutes. In addition, a temporary
-supplementary startup steam plant is installed in No. 7 hold. This plant
-is capable of developing 2,000 shp ahead and about 1,750 shp astern,
-using the main propulsion unit; in emergencies this steam plant may be
-used in lieu of the take-home motor. Using forced circulation boilers,
-it can, like the take-home motor, be brought on the line in about 2
-minutes. In case of a reactor plant failure, the stored heat in the
-reactor system will be available during the interim period, so that at
-no time will the SAVANNAH be without power to the shaft.
-
-From the standpoint of conventional ship operation, the SAVANNAH is
-designed and constructed to the highest degree of operational safety.
-
-Reactor safety is ensured by the heavy steel containment shell
-surrounding the reactor system. This shell is designed to withstand the
-pressure surge from the hypothetical example, “maximum credible
-accident,” used in nuclear reactor analysis. Thus, any internal accident
-will be contained within the reactor containment shell and no hazardous
-amount of radioactivity can escape to the environment.
-
-Protection of the containment complex from ship accidents was studied in
-detail in establishing the SAVANNAH’s design criteria. In particular,
-ship collisions were carefully reviewed and methods developed to predict
-structural damage to vessels struck in collision as a function of speed
-and displacement of the vessels involved. On the basis of the data
-obtained from these studies, the SAVANNAH is designed and constructed to
-withstand, without damage to the nuclear reactor compartment, any
-collision with any of the ships making up 99 percent of the world’s
-merchant fleet.
-
-
-COLLISION POSSIBILITY LOW
-
-The probability of collision with a ship of this remaining 1 percent
-group is extremely low. Considering that the SAVANNAH, as the first
-nuclear-powered merchant ship, will be handled with extreme care, the
-probability of a dangerous release of radioactivity through collision is
-negligible. Because large ships proceed at relatively low speeds in
-harbors, and because of the built-in invulnerability of the SAVANNAH,
-the probability of a collision of sufficient severity to damage the
-reactor compartment is extremely low.
-
-Surrounding the reactor compartment are heavier-than-normal structural
-members. The inner-bottom, below the reactor space, is “egg crated” with
-transverse floors at every frame; and a deep vertical keel with more
-than the usual number of keelsons in the fore and aft direction add to
-this strengthening. Outboard of the reactor compartment are two heavy
-longitudinal collision bulkheads; outboard of these bulkheads there is
-heavier-than-normal plating continuously welded to the beams. Inboard of
-the collision bulkheads are collision mats made up of alternate layers
-of 1-inch steel and 3-inch redwood planks for a total thickness of 24
-inches.
-
-In the event of a collision broadside to the reactor compartment, the
-ramming ship would have to penetrate 17 feet of stiffened ship
-structure, the collision mat, and the reactor containment vessel, before
-reaching the reactor plant.
-
-
-SINKING, GROUNDING WEIGHED
-
-Other accidents, such as grounding, fire and explosion, and sinking also
-were considered in the design and construction of the N.S. SAVANNAH.
-Grounding is very similar to collision in its effects, except that the
-damage is ordinarily more localized. The heavy reactor and containment
-foundations in the inner-bottom provide adequate protection to the
-reactor system.
-
-The SAVANNAH, as a passenger ship, is prohibited by Coast Guard
-regulation from carrying dangerous and explosive cargo in quantity.
-
-The ship’s fire-protection and fire-fighting systems are fully adequate.
-
-In case of sinking, provision has been made to allow for automatic
-flooding of the containment shell of the reactor to prevent its collapse
-in deep waters. The flooding valves are designed to close upon pressure
-equalization so that containment integrity will be maintained even after
-sinking. Salvage connections have been installed to allow containment
-purging or filling with concrete in case of sinking in shallow water
-where recovery or immobilization of the reactor plant seems advisable.
-
-Besides the very latest in navigation and communication equipment,
-including true motion radar, the ship is equipped with antiroll
-stabilizers. Located outside the hull amidships, the stabilizers are
-operated hydraulically by a gyro system capable of sensing sea
-conditions and providing counter-forces to reduce the roll. Each
-stabilizing fin has a lift of approximately 70 tons at 20 knots speed.
-
-
-RADIATION SHIELDING
-
-One of the most important features of the SAVANNAH is her radiation
-shielding. The main sources of radiation during operation of the
-SAVANNAH’s power plant are the reactor itself and the primary coolant
-loop lines. The primary coolant which passes through the reactor core is
-irradiated, and itself becomes a source of radiation. Both the reactor
-and the coolant emit neutrons and gamma rays. There are also radiation
-sources of lesser magnitude including process piping, hold-up tanks,
-pumps, and demineralizers.
-
-The objective of radiation shielding on the SAVANNAH is twofold: First,
-it limits the radiation dose outside the containment to prescribed safe
-levels, and second, it reduces the activation of structure within the
-containment shell by reactor core neutrons. The latter consideration is
-necessary in order that the reactor plant be accessible for maintenance
-within 30 minutes after shutdown.
-
-The shielding is divided into a primary shield, which surrounds the
-reactor itself, and a secondary shield, which surrounds the entire
-containment shell.
-
-
-PRIMARY SHIELDING
-
-The primary shield, immediately surrounding the reactor pressure vessel,
-consists of a 17-foot-high lead-covered steel tank that surrounds the
-reactor vessel with a 33-inch water-filled annulus. The tank extends
-from a point well below the active core area to a point well above it.
-The active core height within the reactor is only 60 inches. Constructed
-of carbon steel, the primary shield tank is covered with a layer of lead
-varying in thickness from 2 to 4 inches. When the tank is filled with
-water, the dose rate outside the primary shielding from core gamma
-sources and activated nuclei will not exceed 200 mr per hour 30 minutes
-after shutdown. This is sufficiently low to permit entry into the
-containment vessel for inspection or maintenance.
-
-
-SECONDARY SHIELDING
-
-The containment shell completely surrounds the primary (reactor) system,
-and serves not only to confine spread of radioactivity in the event of a
-rupture of the system but to support the hundreds of tons of lead and
-polyethylene of the secondary shield.
-
-
-CONTAINMENT SHELL
-
-The primary function of the containment shell is to surround the primary
-system and provide complete containment of any radioactive matter that
-might escape from the system. The design pressure of the vessel was
-determined by postulating the instantaneous release and expansion of the
-entire contents of the primary system. This approach is highly
-conservative because of the improbability of a large rupture.
-
-A study has been made concerning the penetration of the vessel wall by a
-piece of debris in an explosion. An analysis of the penetrating power of
-high-speed components indicated that the shell would contain the largest
-missile that could be expected.
-
-The shell is cylindrical in shape, 35 feet in diameter by 50.5 feet
-long, and is centrally located on the ship’s bottom.
-
-The containment shell is sealed at all times during plant operation.
-Entry to the shell will be made only after the reactor has been shut
-down, the shell purged with air, and the radiation level has dropped
-below 200 mr per hour.
-
-The bottom half of the shell rests in a cradle of steel surrounded by a
-48-inch-thick wall of reinforced concrete.
-
-The top half of the containment shell is covered by a 6-inch layer of
-lead plus a 6-inch layer of polyethylene. During normal power operation,
-this reduces the radiation level to less than 0.6 mr per hour at the
-nearest point of access by the crew.
-
-
-CONTAINMENT SHELL AIR CONDITIONING
-
-This system maintains a constant maximum ambient temperature of 140° F.
-and a maximum relative humidity of 72 percent inside the containment
-shell. The system operates in conjunction with the intermediate cooling
-water system, using 95° F. water.
-
-During normal operation, the containment shell is sealed and no outside
-air will enter or leave the vessel. Ambient conditions will be
-maintained by regulating the cooling water flow as required according to
-instrument readings on the control panel.
-
-In all areas where crew members have unlimited access, radiation levels
-will be less than 5 rem integrated dosage per year, the recommended
-maximum annual exposure of workers in the atomic energy field. Assuming
-that passengers would move about the ship, and on the basis of their
-calculated average distance from the reactor, the average exposure of a
-passenger remaining aboard for a year would be under 0.5 rem, i.e. ¹/₂₀
-of the occupational value.
-
-The 5 rem area is relatively small and not in general use. No crew
-member will be aboard ship or in the 5 rem area continuously for a full
-year, and it is doubtful that any crew member will actually receive an
-integrated dose of more than 0.5 rem in a year.
-
-
-ELECTRICAL SYSTEM
-
-This system supplies power to the reactor system and its auxiliaries and
-is designed to operate with a high degree of reliability to assure
-reactor safety during all phases of operation and shutdown.
-
-It includes all load control and protective devices, containment wiring,
-metering, interlocking and alarms associated with electrical loads for
-the reactor system. Power for the system normally is supplied by two
-turbine-generators, each rated at 1,500 kw, 0.8 pf, 450-volts, 3 phase
-and 60 cycles. For increased reliability, a double bus type arrangement
-is used. In the event of a bus fault, an automatic transfer of all vital
-loads to the other bus will occur. During normal operation, a circuit
-breaker ties the two busses together.
-
-
-RADIATION MONITORING
-
-The radiation monitoring system of the SAVANNAH keeps a constant check
-on the intensity of radiation at various points within the reactor
-system as well as areas remote from the power plant. This system is
-divided into two areas for this description. They are power-plant
-monitoring and health physics monitoring. The latter is covered under
-its own heading.
-
-
-POWER-PLANT MONITORING
-
-Through keeping track of the radiation level at various points in the
-reactor system, any abnormalities in operation can be quickly detected
-and corrected.
-
-A leak in the heat exchangers, for example, would show up on a radiation
-monitor located in the blowdown line from each of the heat exchangers.
-
-The intermediate cooling system, which includes cooling water from the
-primary pumps, shield water cooler, containment air cooler, and other
-components not directly in the primary loop, is monitored at five
-locations. Leakage of primary loop water into the secondary water is
-possible only from the pumps and letdown coolers, because of differences
-in pressure. Consequently, radiation monitors are located downstream
-from the letdown coolers and in each of the return lines from the pump
-cooling coils.
-
-The demineralizers are also monitored. When the resin bed is
-functioning, the flow downstream (effluent) will have negligible
-radioactivity. Consequently, a monitor signal at this point will
-indicate when to switch to a new demineralizer. The monitor in the
-influent (water entering the demineralizer) measures the activity level
-in the primary loop.
-
-The fission product monitor keeps track of fission product activity in
-the primary (reactor) system. The monitor consists of a cation and anion
-column, an amplifier, and an indicating system. This monitor is located
-in the primary coolant flow system.
-
-
-TANKS HOLD LIQUID WASTE
-
-Power plant liquid wastes are collected in tanks for storage prior to
-discharge into a specially designed servicing vessel in port. The liquid
-waste collection tanks are monitored. Gaseous wastes will normally be
-disposed of at sea through the radio mast, which contains two detectors
-for monitoring purposes. They are an air-particle monitor and a
-radio-gas monitor, and operate at all times so that gas is vented to the
-atmosphere. If gaseous radioactivity should rise above specified limits,
-the gas will be diluted to below the limit before being discharged to
-atmosphere.
-
-The above monitor stations are the principal ones involved in reactor
-system operation. The monitors operate through a system of separate
-channels, with each channel responsible for a pre-selected range of
-activity. All detectors relay their readings to the main panel in the
-control room, where automatic recording and visual observation
-instruments are located.
-
-    [Illustration: Surrounded by steel, wood, concrete, the N.S.
-    SAVANNAH reactor is safe against any credible accident.]
-
-  STABILIZING BRACKET PORT AND STARBOARD
-  POLYETHYLENE
-  “C” DECK
-  STEEL & REDWOOD COLLISION MAT
-  WOOD PAD
-  “D” DECK
-  CONCRETE
-  WATERTIGHT BULKHEAD
-  REACTOR COMPARTMENT
-  STIFFENING RINGS
-  LEAD
-  CONTAINMENT VESSEL
-  COMPARTMENT BULKHEAD
-  CONCRETE
-  INNER BOTTOM
-  FOUNDATIONS
-  FORWARD
-
-Portable monitoring equipment, samplers, and other health physics survey
-equipment are provided for access, survey, and maintenance monitoring.
-
-
-REACTOR CONTROL AND SAFETY SYSTEMS
-
-The design of the control system is such that a malfunction which leads
-to an abnormal withdrawal rate of the rods will not result in a
-dangerous condition. Studies indicate that the minimum reactor period
-resulting from maximum withdrawal of the rods is not less than 30
-seconds. The control system is designed to maintain the _net_ reactivity
-insertion always less than the delayed neutron fraction.
-
-The entire reactor system is protected by the safety system. This system
-causes the reactor to terminate power production if a dangerous
-operating condition exists. The safety system also contains interlocks
-which prevent actions which would otherwise jeopardize the reactor
-system.
-
-The control and safety systems are capable of protecting the reactor
-system from damage due to any credible accident except a major leak in
-the primary loop.
-
-The reactor will “scram” (shut down) automatically from any of seven
-causes: (1) shorter than a safe reactor period, (2) excessive power, (3)
-excessive rise or fall in reactor pressure, (4) excessive reactor outlet
-pressure, (5) loss of flow, (6) loss of power to safety circuits, and
-(7) loss of power to control rod drives.
-
-
-INSTRUMENTS DOUBLE CHECKED
-
-The nuclear instrumentation system provides maximum reliability and
-safety, yet minimizes erroneous readings or signals from the monitoring
-channels. This is done by using two or more measuring channels in each
-operating range, and then interlocking the circuits so that at least two
-of them give the same signal of abnormal operating conditions before
-initiating a reactor “scram.”
-
-Increased reliability is obtained by using “solid state” instruments or
-magnetic amplifier units rather than electron tubes and relays.
-
-
-REACTOR SAFETY SYSTEM
-
-This system constantly monitors signals from the nuclear and non-nuclear
-instrumentation, and when necessary takes corrective action. Corrective
-action will be either in the form of “fast insertion” of the control
-rods, or in the form of reactor “scram.” Fast insertion takes place at a
-rate of 15 inches per minute, while a scram is achieved in 1.6 seconds.
-
-Fast insertion consists of moving all control rods to the full down
-position at the fastest rate possible through the electromechanical
-drives. For reactor “scram,” all rods are driven to full down position
-under the force of a net hydraulic pressure of 1,250 psi.
-
-
-SHORTER THAN A SAFE PERIOD
-
-The reactor period is a measure of the rate of reactor power increase;
-the shorter the period the faster the rise. Ten neutron-measuring
-channels, covering the full range from source level to 150 percent of
-maximum power, measure neutron intensity (flux level) and its rate of
-change. These data are continuously transmitted to the reactor operator
-and the automatic control and safety system. Too fast a rate of change,
-or shorter than a safe period, will automatically “scram” the reactor.
-
-
-EXCESSIVE POWER
-
-The amount of power produced is a function of the neutron flux and its
-resultant heat generation in the primary loop. The temperature selected
-to produce automatic “scram” is 540° F. This temperature “scram” circuit
-provides an independent backup to the neutron flux “scram.”
-
-
-EXCESSIVE RISE OR FALL IN PRESSURE
-
-Too low a pressure could result in boiling of the primary coolant, while
-too high a pressure could result in poor heat transfer as well as
-placing unnecessary stresses on the reactor’s fuel element core
-structure. There are a number of causes for either condition, all of
-which would relay a “scram” signal to the operator and to the automatic
-safety system.
-
-
-EXCESSIVE OUTLET PRESSURE
-
-In addition to protection against rapid rate of change in pressure, a
-scram circuit is provided to prevent any steady excessive outlet
-pressure that could result in damage to the core and related equipment.
-
-
-LOSS OF FLOW
-
-This condition would result from a mechanical failure in the primary
-loop pumps, piping, etc., or by accidentally stopping the pumps when the
-reactor is at power, or by loss of power to the pumps. When a single
-pump fails to operate for any reason, an alarm is sounded to warn the
-operator. If all four pumps fail to operate for any reason, a signal is
-sent to the reactor safety system to “scram” the reactor.
-
-
-LOSS OF POWER TO SAFETY CIRCUITS
-
-The hydraulic drives that operate the “scram” mechanism require reserve
-pressure to keep them in the “ready” position for “scram” condition and
-are an integral part of the safety circuitry. A power failure in the
-safety circuits would automatically put the hydraulic drives into
-operation to “scram” the reactor.
-
-
-LOSS OF POWER TO CONTROL ROD DRIVES
-
-Each of the 21 control rods has its own drive mounted vertically on the
-upper reactor head. Of these, 9 are servo controlled and 12 are of the
-nonservo type. The 9 servo rods have variable speed drives and operate
-in two groups in a synchronous manner, according to demand signals from
-the reactor system. The 12-rod group can be operated manually or in
-groups according to predetermined conditions. All of these operate at a
-speed determined by their gearing.
-
-The safety considerations are as follows:
-
-1. Each servo loop contains a monitor that will sound an alarm and
-initiate a fast insertion if the rod fails to follow its command signal.
-
-2. Another circuit monitors all nine servo monitors, and should any of
-the servo monitors malfunction, an alarm will sound and appropriate
-corrective action will be taken through the automatic safety system.
-
-3. “Scram” action starts in the safety system and is independent of
-operator control. Once started, a “scram” action cannot be stopped.
-
-4. For conditions that do not warrant “scram” action, a fast insertion
-serves to reduce power and permit the operator to correct the condition
-without a complete shutdown. A manual fast insertion can be made by the
-operator.
-
-The electrical circuits controlling the reactor control rods are
-monitored, and an electrical failure in one or more circuits will result
-in a fast insertion or “scram” action. Should electrical power to the
-control rod drives fail completely, the hydraulic drives will be
-actuated.
-
-
-WASTE STORAGE AND HANDLING
-
-This system drains and collects, until safe for removal, all drainage
-from the reactor system that might be radioactive. Drainage may result
-from a leak, or be part of the normal drainage accumulation during
-initial fill and testing, normal startup, operation and shutdown, and
-decontamination.
-
-The drainage and storage system consists of two pumps, valves, piping,
-containment drain tank, and four waste storage tanks. The total capacity
-of the tanks is 1,350 cubic feet. This is approximately 80 percent more
-than the maximum operational leakage and drainage for a 100-day period.
-Provisions are made to take samples from any of the five tanks at any
-time.
-
-After sampling indicates sufficiently low level of activity, the fluid
-will be pumped to special dock facilities for transfer to inland waste
-disposal sites. No waste will be discharged at sea under present
-operating plans.
-
-A special 129-foot vessel, the NSV ATOMIC SERVANT, will service the
-Savannah’s reactor and handle the radioactive wastes.
-
-The majority of the potentially radioactive gases vent into a central
-manifold. Here they are monitored, diluted by fan-driven air and
-discharged up the radio mast after passing through a series of filters.
-During normal operation, the manifold is vented continuously. However,
-if the radiation monitor indicates activity levels too high for
-satisfactory dilution, the gases can be diverted into the containment
-shell.
-
-
-GAS FILTERED, MONITORED
-
-The region between the containment vessel and the secondary shielding is
-ventilated with a 4,000 cfm fan which discharges about half way up the
-radio mast. This gas is not expected to be radioactive but as an added
-precaution it is monitored to determine if radioactivity is present.
-
-All gases released through the radio mast are filtered to remove
-particulate matter.
-
-The containment shell air is purged with fresh air periodically at sea
-and prior to entry by the ship’s engineering crew. During normal
-operation the only radioactive gas in the shell is argon-41, at a
-concentration less than the maximum permissible level for continuous
-occupational exposure. The only potential sources of activity in the
-containment air above tolerance levels would be fission products and
-these are not present during normal operation. However, as previously
-described, prior to purging, air samples will be analyzed to ascertain
-the activity levels.
-
-
-HEALTH PHYSICS MONITORING SYSTEM
-
-This system provides radiation protection to crew and passengers through
-constant monitoring for any abnormalities in radiation levels that might
-occur. This is accomplished through a system of 12 radiation detector
-units in the following locations: A-deck, outside doctor’s office;
-B-deck, aft passageway; B-deck, port passageway; C-deck, port
-passageway; C-deck, aft passageway; D-deck, starboard passageway;
-D-deck, both fore and aft bulkheads and at tanktop level, the port,
-starboard, fore and aft passageways.
-
-These 12 monitor units feed their readings into 2 channels, with 6
-monitors on each channel according to a predetermined sequence. A
-manually operated detector permits switching to any one monitor to allow
-observation and study of that station for as long as desired. By means
-of a recorder on each channel, a permanent record of the 12 monitoring
-stations can be obtained.
-
-The detectors are calibrated and maintained periodically by operating
-personnel using a standardized cobalt-60 source.
-
-Ionization chambers located at the points of entry into the containment
-vessel will determine when it is safe to enter the vessel. In addition,
-anyone entering the vessel will carry a portable monitor to determine
-the dose rate at the point he will be working.
-
-In addition to the installed detectors, there is a full complement of
-portable equipment to make any specific investigations required. The
-equipment is used to check decontamination results and to monitor
-contaminated spaces during maintenance. Health physics personnel,
-equipped with portable equipment, accompany all groups working any area
-that might contain radioactivity.
-
-The health physics laboratory aboard the ship is outfitted for all tests
-required during the operation of the reactor plant.
-
-
-AUXILIARY SYSTEMS
-
-_Sampling System._ This system provides a means for removing liquid
-samples from the primary loop to determine the effectiveness of the
-purification system. Samples will be taken from both the inlet and
-outlet flow of the primary demineralizers.
-
-_Intermediate Cooling System._ The primary function is to provide clean
-cooling water to the various reactor system components. A secondary
-function is to maintain water in the annular primary shield tank.
-
-The system consists of two separate flow circuits: a sea water circuit
-and a fresh water circuit. Each of these circuits contains two pumps and
-two coolers, plus other necessary components. The pumps and coolers are
-arranged in parallel, permitting either pump to supply water to either
-cooler.
-
-In the sea water circuit, inlet temperature is 85° F and outlet
-temperature is 106° F. The fresh water enters its coolers at 143° F and
-leaves at 95° F.
-
-Components outside and inside of the containment vessel are cooled by
-one or the other of these intermediate cooling circuits.
-
-
-EXTRA EMERGENCY POWER
-
-Two auxiliary 750-kw diesel generator sets are on standby to provide the
-following: (1) Power to the main bus for operating those loads needed to
-supply cooling for decay-heat removal after a scram or shutdown, (2)
-emergency “take-home” power should the nuclear power plant become
-inoperative, (3) power for reactor startup, and (4) spare generating
-capacity for normal operation should a turbine generator become
-inoperative.
-
-In the event of a reactor “scram,” these generators will automatically
-start and synchronize on the main bus bar to supply and distribute power
-to the components used for reactor cooling.
-
-A 300-kw emergency diesel generator is also available to supply power to
-the 450-volt emergency switchboard. This source will operate in case
-both the main turbine generators and auxiliary diesel generators do not.
-Loads connected to the emergency switchboard include lighting, low speed
-windings of the primary coolant pumps, and the emergency cooling system.
-
-A battery protected source will also provide power to those loads that
-require an especially dependable power source with no interruption due
-to loss or switching of auxiliary power.
-
-
-TAKE-HOME POWER
-
-As mentioned, in the electrical system there are two 750-kw diesel
-generator sets installed in the engine room. If any emergency
-“take-home” power is required, either diesel generator can be used to
-operate a 750-hp wound rotor motor, which is connected to the ship’s
-propeller, through the reduction gears.
-
-Each diesel generator is sized to furnish adequate power for reactor
-decay heat removal, lighting, and necessary ship service.
-
-
-N.S. SAVANNAH MANNED FOR SAFETY
-
-To assure that the first nuclear-propelled merchant ship will be
-completely safe, it is manned by well-trained, competent personnel whose
-duty and responsibility it is to operate the ship safely and
-efficiently.
-
-Every mechanical and electrical safety device of modern navigation is at
-the disposal of the SAVANNAH’s crew to insure the safety and integrity
-of the ship.
-
-The men who will handle the SAVANNAH ashore and afloat will have had the
-advantage of the specialized and extensive training program conducted by
-the Atomic Energy Commission, the Maritime Administration, and the
-private contractors who built the N.S. SAVANNAH and her reactor.
-
-The ship’s master and officers are men of long experience on the sea
-whose backgrounds assure sound and stable assessment and judgment under
-all possible conditions.
-
-All of the factors herein discussed make it possible for the United
-States Government to say of the N.S. SAVANNAH, as she ushers in the
-atomic age on the world’s essential trade routes, that this unique and
-wonderful vessel is unquestionably one of the world’s safest ships.
-
-
-THE NUCLEAR SHIP SAVANNAH IS DESIGNED AND BUILT TO THESE SAFETY
-REQUIREMENTS
-
-_APPLICABLE CODES OF_:
-
-  1. U.S. Coast Guard
-  2. American Bureau of Shipping
-  3. Maritime Administration
-  4. U.S. Public Health Service
-  5. American Institute of Electrical Engineers Marine Code
-  6. U.S. Atomic Energy Commission
-
-_SAFETY REVIEW BY_:
-
-1. AEC Advisory Committee on Reactor Safeguards
-
-_DESIGN REVIEW BY_:
-
-  1. U.S. Coast Guard
-  2. Maritime Administration
-  3. AEC
-    (A) Oak Ridge National Laboratory
-    (B) Electric Boat Company
-  4. American Bureau of Shipping
-
-                       U.S. GOVERNMENT PRINTING OFFICE: 1960    O—562017
-
-    [Illustration: The N.S. SAVANNAH’s construction meets ultimate
-    standards of health and environmental safety.]
-
-  PASSENGER DINING ROOM
-  CREW QUARTERS
-  MAIN LOUNGE
-  PASSENGER STATEROOMS
-  REACTOR HATCH
-  REACTOR AUX. HATCH
-  CREW QUARTERS
-  CARGO HOLD
-  MACHINERY CONTROL CENTER
-  ENGINE ROOM
-  SHIP’S PROVISIONS
-  STABILIZER SPACE
-  CARGO HOLD
-  REACTOR CONTAINMENT VESSEL
-
-    [Illustration: The N.S. SAVANNAH—world’s first atomic merchant
-    ship—pride of the American Merchant Marine—model of maritime
-    safety.]
-
-
-
-
-                          Transcriber’s Notes
-
-
-—Silently corrected a few typos.
-
-—Retained publication information from the printed edition: this eBook
-  is public-domain in the country of publication.
-
-—In the text versions only, text in italics is delimited by
-  _underscores_.
-
-
-
-
-
-
-
-End of the Project Gutenberg EBook of The Nuclear Ship Savannah, First
-Atomic Merchant Ship, by Anonymous
-
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