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Main design and engineering solutions on dismantling surface vessels and on SNF and RW management

Kalistratov N.Y., FSUE "EE "Zvezdochka", Russia

1. Stages of life circle of the heavy nuclear powered missile cruiser "Admiral Ushakov"

The leading heavy nuclear missile cruiser "Admiral Ushakov" (hereinafter referred as "the Vessel") was built at the Baltic shipyard and commissioned to the Navy in 1980 according the project of the Severnoye Design Bureau. Her performance characteristics made her the pride of the Fleet. She has been a flagship of the Northern Fleet for many years.

Stages of life circle of the vessel are given in figure 1.

Figure 1 – Stages of life circle of the surface nuclear powered vessel "Admiral Ushakov"

The vessel was delivered to the territory of the FSUE EE "Zvezdochka" (Severodvinsk) in 1999 (figure2). In 2002 the Vessel (figure 3) was decommissioned from the Navy and now is waiting for its dismantlement with nuclear fuel in its reactors.

Figure 2 – Heavy nuclear powered missile cruiser "Admiral Ushakov" at the

embankment of the FSUE "EE "Zvezdochka"

Main performance attributes of the Vessel comparing with NPS are given in table 3.

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Figure 3 – General view of surface nuclear powered vessel of Admiral Ushakov Class

Table 3 – Performance attributes of different types of NPS and surface vessel "Admiral Ushakov" – class.

Attribute "Victor" – class NPS

"Taifun" – class NPS

Surface vessel of Admiral Ushakov –

class Maximal length, m 106,1 172,8 250,1 Maximal width, m 10,8 23,3 28,5 Draft, m 7,8 11,5 11,0 Water displacement (surface/underwater),t

4 780/7 250 23 200/48 000 24 300

Number of compartments

8 20 19

Type of SSP OK-300 OK-650 KH-3 Number of SSP 2 2 2

Comparison characteristics of NPS and surface nuclear vessel of Admiral Ushakov Class are given in figure 4.

Long staying of the vessel without supporting works on maintenance of her systems and mechanisms in operational condition affects their technical condition. The technical condition of systems and mechanisms providing survivability of the Vessel does not meet current regulation requirements. The docking of the vessel, which is required according to the regulations, is not performed because of the lack of funding. The Vessel lacks a full set of equipment including that for firefighting and survivability providing systems.

The influence of corrosion causes the loss of tightness of the isolating valves on out of board pipes, mechanisms and devices, pipes. Corrosion ruins welded components of the hull that may cause emergencies.

Main problems for the dismantlement of the Vessel are:

− Absence of experience of the dismantlement of surface vessels with nuclear power installations in Russia;

− Till now no refuelling operations for the reactors of the Admiral Ushakov Class vessels have been performed;

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− Absence of the developed regulatory, design, technological and organizational documentation for performance of the dismantling procedure;

− The overall dimensions of the cruiser do not allow to put her onto the hard platform at "Zvezdochka" shipyard without prior cutting into sections afloat;

− Absence of experience of unique operations on cutting vessels afloat, as well as equipment and approved technologies of the underwater cutting of the hull;

− Absence of agreed decisions on the way of the long-term storage of the reactor compartment unit;

− Big amount of radioactive and toxic industrial waste produced during dismantlement of the Vessel.

2. Analysis of adequacy of the existing on-shore infrastructure for the possibility of dismantlement of surface vessel with nuclear power installation

A unique infrastructure that has no analogies in the World has been established at the shipyard for the funds of Russia and international technical assistance of the USA, Norway, United Kingdom and Canada for the complex industrial dismantlement of all types of NPSs and future dismantlement of surface vessels with nuclear power installations.

The established infrastructure meets both Russian and international requirements for ensuring nuclear, radiation and environmental safety and allows to solve all problems connected with NPS dismantlement process in complex.

The following main facilities constitute infrastructure for the complex NPS dismantlement at the FSUE EE "Zvezdochka" (figure 5):

− on-shore defueling facility for spent nuclear fuel (SNF) unloading from decommissioned NPS;

− on-shore temporary storage pad for casks with SNF assumed for 60 TK-18, TUK 108/I type casks;

− facility for temporary storage and treatment (conditioning) of liquid and solid radioactive waste;

− special quay;

− cradle-works site including dry-dock and floating dock;

− specialized site for mechanical cutting of the scrap;

− specialized sites for gas cutting of ferrous and non-ferrous scrap;

− electric cable chopping site.

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Figure 4 – Comparison Characteristics of NPS and surface nuclear vessel "Admiral Ushakov"

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Existing production capacities of the shipyard allow:

− dismantle up to 6 NPS per year;

− defuel 4 NPS being dismantled per year by means of on-shore defuelling facility (OSDF);

− ensure SNF handling and its temporary storage;

− perform dismantlement of other kinds of weapons and military equipment;

− reprocess metal scrap with total amount up to 17 thousand tons per year (data for 2004);

− treat up to 1 500 m3 of LRW per year;

− process up to 200 m3 SRW per year.

The following proposals have been developed to get the shipyard ready for the dismantlement of the surface vessel with NPI of Admiral Ushakov Class in order to meet the requirements on ensuring nuclear, radiation and environmental safety at the FSUE EE "Zvezdochka" (figure 6):

− procurement of special equipment for underwater cutting of the Vessel;

− procurement of additional equipment for upgrading of efficiency and ecological safety of the hull constructions cutting under water and metal reprocessing including aluminum alloys;

− remediation of temporary storage facility for solid radioactive waste (bld. 162) for storage of SRW produced and processed during dismantlement of the surface vessels before its shipment to the regional repository site;

− upgrading of the facility for treatment of liquid radioactive waste (LRW) with planned increase of annual amounts of processing from 1 500 m3 to 3 000 m3, and establishing on its basis the regional facility for reprocessing of LRW;

− upgrading of the temporary storage pad for toxic industrial waste produced during complex dismantlement of surface vessels with NPI in accordance with their amount and environmental safety requirements that become stricter annually;

− reconstruction of the incinerator for SRW and additional equipping of the SRW remelting site in order to perform complete closed loop for SRW handling at the shipyard.

3. Options for defuelling of the vessel by means of the on-sore defueling facility and floating technical base (FTB) of the Navy

Design differences of the reactor installation (RI) of the Vessel from those of NPS:

− Reactor diameter is 1.35 times bigger comparing to that of the 3rd generation of NPS;

− height of fuel bearing part is 200 mm higher;

− number of spent fuel assemblies (SFA) is 1.7 times more.

Status of RI of the Admiral Ushakov Class for the 01.05.2005:

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1. General activity of RI – 4.33*1016 Bq (1.16*106 Ci). Including SNF:

− fission products 3.7*1016 Bq (1016 Ci);

− actinides 2.3*1015 Bq (6.2*104 Ci).

2. State of the reactor cores:

− No.1 – normal state (fuel is tight);

− No.2 – acceptable state (part of spent fuel assemblies is leaky).

In 1995 nuclear power installations of the Vessel were switched to "long storage" mode in accordance with "The technological regulations of long-term storage" developed by OKBM. The following measures were taken on switching the nuclear power installations into the "long-term storage" mode:

1. Gas release from the primary circuit equipment of RI;

2. Water chemistry mode of long-term storage was set for the primary circuit in accordance with the OKBM documentation;

3. Mechanical blockage of compensating groups (CG) of control rods has been performed at the lower limiters. Argon-arc welding of the gears of CG control rods of control and protection system has been performed in accordance with the documentation. As a result, it is impossible to change the position of compensating groups manually by means of spanner for manual control of compensating grids (CG);

4. Control rods, gears of compensating grids, scram system were switched off the power supply together with disconnection of cables from cable inlets of the reactivity compensation means. As a result, it is impossible to change the position of scram system and compensating groups by means of remote control of the control room.

5. Primary circuit pumps were switched off the power supply;

6. The pressure was brought down in the primary circuits, operating and reserve groups of the high-pressure gas down to the value specified by the design documentation. Transfer system valves were closed and sealed in accordance with "The Technological Regulations…"; high-pressure intercepting valves of the pressurizes were set in the manual control mode and sealed.

7. The control over the primary circuit pressure of NI was arranged;

8. Gears and actuators of control rods were sealed;

9. The possibility for unauthorized use of the key for manual control of compensating grids (CG) is absolutely impossible;

10.The state of the secondary circuit system of the nuclear power installation during long-term storage corresponds to "wet" storage mode of steam generators;

11.The state of the third circuit of the nuclear power installation during long-term storage corresponds to the designed mode of storage when the system is fully filled with water.

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Figure 5 – Production sites, used during dismantlement of surface vessels with nuclear power installations of Admiral Ushakov Class

at the FSUE "EE "Zvezdochka"

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Figure 6 - Measures on preparation of production capacities for dismantlement of surface vessel with nuclear power installations

at the FSUE "EE "Zvezdochka"

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Stage-positional method ensuring performance of works in certain sequence at certain

positions will be taken as the basis for the dismantlement of the Vessel. Defuelling will be the key-stage of the dismantlement process.

Defuelling of the Vessel can be conducted by means of two options at the FSUE EE "Zvezdochka":

I option – by means of the OSDF of "Zvezdochka" (see figures 7 and 9);

II option – by means of floating technical base (FTB) of the Navy (see figure 8).

Stages of the preparation for the defuelling, SNF discharge and its shipment to PO Mayak for further reprocessing are the follows (table 4):

− preparation of the shipyard and the Vessel for defuelling;

− preparation of the OSDF (FTB) for the SNF discharge;

− SNF discharge from reactors;

− SNF temporary storage at the temporary storage pad of the FSUE "EE "Zvezdochka" (during defuelling by means of OSDF) or at the floating technical base - during defuelling by means of FTB);

− loading of the casks with SNF onto a special train and its shipment to the PO Mayak for further reprocessing.

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Table 4 – Stages and main measures for preparation for the defuelling

Stage of preparation Measure Preparation of the Vessel

− assembling works in the reactor compartment and in hardware enclosures of the working areas; assembling of exhaust filter-ventilation equipment for ventilation of hardware enclosures; assembling of additional technological pipes for acceptance and injection of operating and technological mediums; − assembling of additional radiation control equipment; − delivery of technological equipment, including containers for SRW, drums for LRW, etc. in the sanitary protected area; − gas release from the high-pressure gas system in accordance with operating instruction; − reduction of pressure in primary circuit down to the level of the atmospheric pressure and drainage of the preservative solution down to the level of main manifolds of the reactors, or, on conclusion of OKBM, their complete drainage.

Preparation of the shipyard

− development of the shipyard’s and vessel’s defuelling readiness certificate; − development of list of disassembling works and concomitant operations for SNF discharge; − development of documentation and fulfillment of measures ensuring nuclear and radiation safety; preparation of the personnel within certificate’s framework

Preparation of the on-shore facilities and defuelling equipment

− fabrication of required non-standard equipment (containers for screw-down mechanism, special lids for shutting of the hardware enclosure); − preparation of two exhaust filter-ventilation plants to perform ventilation of the hardware enclosures; − assembling of radiation control systems, alarm-, communication- and television control systems between the control room and hardware enclosures of the ship; − checking of the complete-set of recharging equipment, used during SNF discharge and its preparation to work.

Preparation of the floating technical base of the Navy

− development and agreement of the "Instruction on nuclear and radiation safety"; − development and agreement of organizational-technical measures on ensuring nuclear and radiation safety.

Defuelling will take place at a special quay "Zvezdochka" shipyard, the Vessel being moored there.

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Figure 7 – Scheme for SNF discharge by means of

the on-shore defuelling facility Figure 8 – Scheme for SNF discharge by means of the Navy technical floating

base "Malina"

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Figure 9 – Transportation-technological scheme of SNF handling at the FSUE "EE "Zvezdochka" by means of the infrastructure of the on-shore defuelling facility

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Design and operational documentation of the Vessel developed by "Severnoye Design Bureau" and Central Design Bureau "Aisberg" stipulates defuelling by means of the Navy FTB "Malina". This ship was built in 1984 and is located at the water area of Severodvinsk. FTB is equipped with two cranes, cask loading point, cells for "wet" storage of SFA and sufficient for acceptance of SNF from the Vessel’s reactors. One of the problems regarding SNF discharge by means of the Navy FTB is a very busy schedule of its use for the Navy needs.

The following factors should be taken into consideration during defuelling by means of the FTB:

− potential nuclear and radiation risk of defuelling is higher when it is conducted by means of the FTB than that of the OSDF;

− FTB "Malina" requires annual supporting repair to ensure readiness for SNF discharge as well as repeating docking examinations and repairs;

− the crane performing SNF discharge has been in operation for more than 20 years and has lifting capacity of only 16 tons – this is not sufficient for removal of equipment from reactor compartment of the Vessel thus attracting additional equipment (on-shore crane or floating crane).

The on-shore defuelling facility complex was built and commissioned in 2001, it has new modern equipment, trained and certified personnel. Specialists involved in defuelling process undergo annual training at the training base of the FSUE "NIPTB "Onega"; technical staff of the OSDF undergoes special training at the FSUE OKBM (Nizhny Novgorod). Since 2001 six defuelling has been conducted from different types of NPS ("Typhoon", "Delta", Victor-I", "Victor-II", "Victor-III") by the personnel of the OSDF. The crane performing SNF discharge has been in operation less than 5 years and has lifting capacity of 80 tons that is enough for removal of all the equipment from reactor compartment including reactor lids with weight of about 20 tons.

But till now no refuelling operations of surface vessels’ reactors of Admiral Ushakov Class have been done, so defuelling equipment manufactured in 1987 has not been tested yet.

Taking into consideration that for the assessment of appropriate SNF discharge by means of the on-shore facilities it is necessary to develop some design-technological options, a decision about what option should be chosen for the discharge of SNF must be taken at further stages of the development of the dismantlement design of the Vessel.

According to stated above information it is possible to conclude that the OSDF is the most appropriate option for SNF discharge from reactors of nuclear power installations of the surface vessel "Admiral Ushakov" due to following reasons:

− SNF discharge is the most safe during defuelling by means of OSDF due to reduction of risk of accidents comparing to use of FTB performing defuelling afloat;

− it is necessary to perform intermediate operation for taking SNF out of FTB cells into transport casks that additionally increase risk for accidents during SNF handling during defuelling by means of the Navy FTB; during defuelling by OSDF the intermediate operation for unloading of fuel from FTB cells into casks is not required. SFAs are loaded directly into transport casks TK-18 or TUK-108/1. Thus additional risk for nuclear and radiation accident during SNF handling is excluded;

− the existing at "Zvezdochka" shipyard on-shore infrastructure for defuelling and SNF handling allows conduct safe SNF discharge out of the Vessel’s reactors, and place casks

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with SNF at the SNF temporary storage pad, prepare a special train and send SNF to PO "Mayak" by means of the FSUE "EE "Zvezdochka" without attracting additional forces.

During SNF discharge out of surface nuclear powered vessel some operations will have the following peculiarities comparing to NPS defuelling:

− initially low parts of the safety rods together with absorbtion rods after their cutting are subject to temporary dislocation in the reactor holders with their further loading into the peripheral slots emptied from other holders of the reactor’s removable block for long-term storage;

− due to insufficient lifting capacity of the crane of the floating technical base the defuelling, temporary storage, preparation for the repetitive mounting and loading of the reactor lids onto the Vessel is performed by means of portal crane and technical equipment of the on-shore defuelling facility of the shipyard;

− screw-down mechanisms removed from reactors are packed as SRW into special containers located at the floating technical base with their further loading into reactor compartments of NPS being dismantled for long-term storage. It is allowed to put the screw-down mechanisms into the emptied slots of the removable reactor block of the Vessel.

The shipment of discharged SNF by special train is performed at the SNF storage pad of the OSDF at the FSUE EE "Zvezdochka" or at a port of Belomorskaya Naval Base in accordance with technological regulations of VNIPIET.

Transport-technological scheme for SNF discharge and its shipment to PO "Mayak" during its discharge by means of OSDF is given in figure 10.

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Figure 10 – Transport-technological scheme of SNF discharge and shipment to PO Mayak by means of the on-shore defueling facility of "Zvezdochka" shipyard

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4. Principal design and technological approaches on dismantlement of the surface vessel of Admiral Ushakov Class

Outline of organizational and technological scheme for dismantlement of surface vessels with nuclear power installations is given in figure 11.

Three options of the dismantlement of the Vessel after her defueling were considered while developing technological options for SNF discharge and the Vessel’s dismantlement:

I option (figure 12). Cutting of the hull afloat into 2 blocks up to seizes allowing to perform putting of the hull sections of the Vessel into the dry-dock of the shipyard for further sectional dismantlement and formation of the reactor unit on the hard basement.

II option. Cutting of the hull afloat into 3 blocks and formation of the reactor unit together with adjoining compartments (constructions) and bow and stern blocks.

The following sequence of works is expected to take place for I and II options:

1. Demilitarization of the vessel;

2. Defueling;

3. Storage of casks with SNF at the pad for SNF temporary storage at the FSUE "Zvezdochka". Shipment of SNF to PO "Mayak".

4. Removal, processing and shipment of radioactive waste to storage pads.

5. Removal and dismantlement of the upper hull superstructure of the vessel up to the permeable decks located above waterline, removal of equipment, devices and mechanisms;

6. Preparation of the hull for cutting into blocks afloat (welding of bulks in the area of cutting lines of the hull, acceptance of ballast, etc.).

7. Cutting of the hull afloat along the cutting lines (into 2 blocks according to the I option and 3 blocks according to the II option) according to the design documentation.

Cutting of the hull in its underwater part is possible by two ways:

− using technology of underwater cutting;

− by means of caissons to be installed in the area of the hull cutting lines under water.

8. Preparation of the hull sections to be put into the dry-dock of "Zvezdochka" shipyard.

Note: It is necessary to remove the surface board of the hull up to the 3d deck level thus providing the required width of the hull of 25.0 m to put the hull sections of the vessel into the dry-dock of the shipyard "Zvezdochka".

9. Putting of the hull sections of the vessel into the dry-dock.

10. Disassembling and removal of equipment, mechanisms and devices. Cutting of hull constructions into large-size sections and their further scrapping.

11. Formation of the reactor unit, its preparation for storage afloat. Loading of solid radioactive waste into the reactor unit (if required). Assembling of towing and mooring arrangements, lifelines, connecting bridges, depth marks, signal-side lights and painting. Launching of the prepared reactor unit onto water and its transportation for interim storage site at Sayda Bay (Murmansk Region).

12. Collecting of toxic waste produced during dismantlement of the vessel, reprocessing and storage of hazardous and toxic waste at specialized pads.

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Figure 11 – Organizational and technological scheme of the dismantlement of a surface nuclear powered vessel

of Admiral Ushakov Class

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Figure 12 – Stage-positional method of dismantlement of surface vessels with nuclear power installations into two parts afloat (option I)

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The design peculiarity of surface vessels that distinguish them from submarines during dismantlement process is availability of big amount of aluminum-magnesium alloy (AMg) constructions (table 5). Taking into account a high combustibility of this alloy and big scope of works on cutting of this material, it is necessary to develop measures on organization of these works.

Table 5 – Comparison characteristics of aluminum-magnesium alloy scrap during

dismantlement of NPS and a surface vessel of Admiral Ushakov Class, tons

Type of the ship

Material Victor-II Delta-III Oscar Taifun Surface vessel

with NPI of Admiral

Ushakov ClassAluminium-magnesium

alloys (AMg) 26.0 28.0 34.8 24.0 600.0 (*)

(*) – roughly

Comparison characteristics for the output of ferrous and non-ferrous materials during NPS and the Vessel dismantlement are given in table 6.

Table 6 – Comparison characteristics for the output of ferrous and non-ferrous materials from NPS and a surface vessel of Admiral Ushakov Class, tons

Characteristics Victor-II Delta-I Oscar Surface

vessel with NPI (*)

Approximate output of materials:

ferrous 1631.0 3063.0 5830.0 8900.0

non-ferrous 301.6 377.8 753.9 2300.0 (*) – roughly.

Figure 13 shows the correlation of the scrap output during dismantlement of different types of NPS and surface vessels with nuclear power installations.

Another peculiar feature of dismantlement of the surface vessel with nuclear power installation "Admiral Ushakov" is a great scope of works done at height that will also demand the development of measures on organization of this type of works and corresponding equipment.

A big amount of hull constructions, equipment and materials is removed during dismantlement operations and needs to be stored at the territory of the shipyard. Analysis of Zvezdochka shipyard capacities on amounts of the reprocessed scrap produced during NPS dismantlement (table 7) for 5 years confirms the readiness of the shipyard to reprocess scrap produced during the Vessel’s dismantlement.

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Figure 13 – Correlation of metals output during dismantlement of different types of NPS

and surface nuclear powered vessels

Table 7 – Zvezdochka shipyard capacities for amounts of the reprocessed scrap produced during NPS dismantlement

Year Number of dismantled NPS per year

Total amount of the reprocessed scrap*

2000 2 14 902 t 2001 1 8 398 t 2002 1 10 225 t 2003 2 10 576 t 2004 5 17 156 t

5. Analysis of nomenclature and amounts of radioactive and toxic waste produced during dismantlement of NPS and surface vessels

Main objective of RW handling during the process of dismantlement is reduction of radiation influence upon personnel, public and the environment down to the reasonably achievable minimum taking into account sanitary standards, economic and social factors. During dismantlement of surface vessel with nuclear power installation at Zvezdochka shipyard this objective will be reached by taking a complex of special measures forming a sequence of the following phases:

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a) handling of gaseous radioactive waste (GRW):

− purification by means of filters in order to reduce activity down to levels stipulated by RSN-99 (radiation safety norms) allowing discharge of radioactive substances (if required);

− discharge into atmosphere;

b) LRW and SRW handling:

− collecting in places of production;

− shipment within the territory of the shipyard to temporary storage facilities;

− temporary storage;

− treatment of LRW and SRW;

− temporary storage of secondary SRW;

− loading of SRW into reactor compartments of NPS being dismantled or transfer of secondary SRW to repository.

All procedures on RW handling during surface nuclear powered vessel dismantlement at Zvezdochka shipyard will be performed according to the technological scheme (figure 15) thus allowing meeting the following conditions:

− quantity (amount, mass) and activity (activity concentration, specific activity) of RW to be minimal;

− all requirements on ensuring radiation safety to be met.

Correlation of LRW produced during dismantlement of surface nuclear powered vessels and different types of NPS (primary coolant and technological fluids of the third circuit) is given in figure 14. The categories and quantity of SRW produced during dismantlement of different types of NPS and surface nuclear vessels are shown in table 8.

Handling of RW produced during the Vessel’s dismantlement is performed in accordance with schemes and instructions existing and acting at the shipyard taking into account quantitative and qualitative composition of RW produced during the Vessel’s dismantlement. RW are subject to reprocessing at special facilities of the FSUE EE "Zvezdochka" (figure 16). In accordance with the requirements of managing directives SRW after their preparation are collected into containers and partially loaded for long-term storage into the reactor compartments of NPS being dismantled or prepared reactor compartment unit of the Vessel. SRW partially are stored at the temporary storage pad of the shipyard until they are shipped to the regional SRW repository facility. The controlling record of production, handling and shipment of all categories of RW during the process of dismantlement will be conducted by the Nuclear and Radiation Safety Department of the shipyard.

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Figure 14 – Correlation of LRW produced during dismantlement of different types of NPS and surface nuclear powered vessels (primary coolant and technological fluids of

the third circuit)

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Figure 15 – Technological scheme of RW handling at the FSUE "EE "Zvezdochka"

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Table 8 – Categories and amounts of solid radioactive waste produced during dismantlement of NPS and surface nuclear powered vessels

Type of the vessel

Solid radioactive waste Victor-III Delta Taifun Oscar

Surface vessel with nuclear powered unit

(*) Reactor equipment (metal constructions, pipes, etc)

6.0 6.0 10.0 10.0 15.0

Insulation coating, means of individual protection, cork, asbestos cloth, etc.

3.0 8.0 8.0 5.0 10.0

Cable waste, drainage hosing of "contaminated" water, rubber coating, elastron, etc.

20.0 30.0 30.0 20.0 30.0

Total: 29.0 44.0 48.0 35.0 55.0

Note: (*) Composition and amount of RW produced during the Vessel’s dismantlement will be specified during the development of the documentation set for the Vessel’s dismantlement.

SRW produced during defuelling and preparation of the reactor compartment unit for long-term storage as well as those accumulated during the Vessel’s operation (equipment and reactor elements to be changed during refit) can be located inside the reactor compartment unit in much the same way according to requirements RD95.10548-2000 "Solid radioactive waste. Disposal in the reactor compartments of NPS being dismantled. General engineering requirements". This document needs further development with respect to surface vessels with nuclear powered unit. NIKIET plans to make the corrections of the document.

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Figure 16 – Scheme of usage of special complex for SNF and RW handling at the FSUE "EE "Zvezdochka" during dismantlement of surface

nuclear powered vessels

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During the Vessel’s dismantlement liquid, solid and gaseous materials containing toxic waste and being hazardous for public and the environment: atmosphere, water reservoirs, soil will be produced. Approximate amount of toxic industrial waste produced during the Vessel’s dismantlement is given in table 9.

Table 9 – Approximate amount of liquid and solid toxic industrial waste (according to

categories of danger) produced during dismantlement of a surface nuclear powered vessel of Admiral Ushakov Class, tons

Category of danger

Waste 1 abnormally dangerous

2 highly

dangerous

3 moderately dangerous

4 low-

dangerous

5 practically

not dangerous

Liquid (standard operating mediums, rinsing waters with oil products and remnants of operating mediums, household sewage waters from production shops and sites involved in dismantlement)

- 5.0 192 - -

Solid (special rubber, glass-fiber-reinforced plastic materials, insulation materials, cable, polymer materials, asbestos bearing materials, tar, adsorbents, dry hardened paintwork materials, gasket materials, cloth)

- - 360.0 2 242 2 084

Solid (luminescent lamps), items 11 415 - - - - Note:

1. The 1st category of danger is considered to be the most dangerous one. The 5th category of danger is allowed to be sent to disposal facilities (GOST 12.1.007 "System for labour safety standards. Harmful substances. Classification and general safety requirements").

2. Category of waste is defined in accordance with the "Sanitary rules on defining of the category of danger for toxic waste in production and consumption" SP 2.1.7.1368-03.

3. Composition and amount of toxic industrial waste produced during the Vessel’s dismantlement will be specified during development of the set of documentation required for the dismantlement of the Vessel.

The FSUE EE "Zvezdochka" is responsible for safe temporary storage of toxic

materials at the territory of the shipyard and performs removal of toxic materials from the territory of the shipyard to regional sites for their storage and demolition.

The record of production, handling and transportation of toxic materials of all kinds is performed at the shipyard under the supervision of the Environmental Protection Department.

Standard operating mediums of the Vessel, rinsing waters containing oil products and remnants of operating mediums, household sewage from production shops and facilities engaged into dismantlement process are the source of production of liquid toxic waste. Standard operating mediums include oil products (diesel fuel, different types of oil), different types of lubricants (petrolatum, paraffin, ceresin), acids, alkalis, frother, and chladones.

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Rinsing oil-bearing waters are purified from the oil at the purifying facilities of the shipyard and are subject to biological purification prior their discharge into water reservoir. Spent oil products are combusted at the boiler-plant of the shipyard. Acids, alkalis, frother are neutralized at the purifying facilities of the shipyard. Hydraulic fluid, chladones need special technological approaches and equipment. At present time there is a process of accumulating of these materials and their temporary storage in watertight flasks at the territory of the shipyard.

The approximate amount of liquid toxic waste during dismantlement of NPS, surface vessels with nuclear powered plant and nuclear powered vessels of technical maintenance is given in figure 17.

Figure 17 - Approximate amount of liquid toxic waste during dismantlement of NPS,

surface vessels with nuclear power installations and NPS and nuclear service ships

Solid toxic waste are special resin and fiberglass plastic materials, insulation materials, cable, luminescent mercury bearing lamps, polymer materials, asbestos bearing materials, tars, adsorbents, dry hardened paint work materials, gasket materials, cloth. As a rule there are mixed of inseparable materials, compositions or mixtures with remnants of glue, paintwork materials and metallic dust.

The organized collection of solid toxic waste at special pads, loading into watertight containers and further disposal at solid industrial waste storage facility will be performed in order to avoid pollution of soil. The approximate amount of solid toxic waste produced during dismantlement of different types of NPS, surface vessels with nuclear powered unit and nuclear powered vessels of technical service is given in figure 18.

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Figure 18 - Approximate amount of solid toxic waste produced during dismantlement of

different types of NPS, surface vessels with nuclear power installations and nuclear service ships

Conclusion and findings Dismantlement of heavy nuclear powered missile cruiser "Admiral Ushakov" is the

stage ending the life circle of the vessel after its being in operation and includes a set of organizational and technological measures on preparation for dismantlement, defuelling, SNF storage, and shipment to PO "Mayak", cutting and reprocessing of hull construction and equipment of the Vessel, formation of reactor compartment unit and its transportation to the long-term storage facility.

For the time being the works on dismantlement of surface nuclear powered vessels of this type have not been conducted in our country, however, taking into account existing modern and meeting all the safety requirements infrastructure for NPS and surface vessels dismantlement at the shipyard, and experience of implementation of projects for dismantlement of NPS and surface vessels with power installations using organic fuel, it is possible to state that this task can be done by means of the FSUE "EE "Zvezdochka".

Despite the fact that dismantlement of the cruiser "Admiral Ushakov" is a task that is technically new and technologically complicated, all scope of works can be divided according to the "standard" scheme into the following stages:

− development of feasibility study of defueling and dismantlement options in order to choose the most optimal one;

− development and agreement of design organizational documentation for the Vessel’s dismantlement, EIA development; obtaining of conclusion of the State ecological expertise;

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− modernizing of existing infrastructure at the FSUE "EE "Zvezdochka";

− procurement of necessary special equipment including that for underwater cutting;

− SNF discharge; temporary storage of casks at "Zvezdochka"s storage pad and shipment of casks with SNF to PO "Mayak";

− collecting, processing and shipment for storage of RW and toxic waste;

− cutting of the Vessel afloat into sections, putting of sections into dry dock of the shipyard;

− dismantlement of bow and stern ends of the Vessel;

− formation of the reactor compartment unit, its transportation for long-term storage facility.

The given above scheme will allow dividing a complicated task into several stages for accurate planning of the preparation of the production and organization of works on the Vessel’s dismantlement.

In January 2005 the Italian company "Sogin" within the frames of the "Agreement between the Government of Russian Federation and the Government of Italian Republic on cooperation in the area of decommissioned nuclear powered submarines dismantlement and safe handling of radioactive waste and spent nuclear fuel" signed on November 6, 2003 in Rome expressed its agreement for funding of the initial stages of complex dismantlement of this Vessel:

− Development of feasibility study of options of defuelling and dismantlement of the Vessel;

− Development of design and organizational documentation for the dismantlement of the Vessel;

− Discharge of SNF.

It is feasible to arrange cooperation of several donor-countries for the implementation of this scale pilot project.

One of the distinguished examples of cooperation of donor countries headed by coordinator of work – Rosatom – is remediation of nuclear and radiation hazardous facilities in Andreeva Bay in the Murmansk Region.

Dismantlement of the heavy nuclear powered missile cruiser "Admiral Ushakov" will allow to solve one of the most difficult task on ensuring safety of the North-western region of Russian Federation and greatly mitigate the risk of nuclear, radiation and ecological accidents connected with the presence of nuclear fuel aboard the decommissioned vessel located in the town with the population of more then 200 thousand people.

It would be useful to know opinion of every participant of CEG on this problem. In our opinion it would be very reasonable to organize a meeting of international experts in July of this year in Severodvinsk in order to work out principal approaches on looking at the possibility of cooperation of donor-countries and distribution of their involvement in the project on dismantlement of the heavy nuclear powered missile cruiser "Admiral Ushakov" at the FSUE "Zvezdochka".