Press Release

Press Release

Regarding the Application for Confirmation of External Disposal of Returned Vitrified Waste

January 07, 2014
Chubu Electric Power Co.,Inc.
The Kansai Electric Power Co., Inc.
The Chugoku Electric Power Co., Inc.
Shikoku Electric Power Co., Inc.
Kyushu Electric Power Co., Inc.

Chubu Electric Power, The Kansai Electric Power, The Chugoku Electric Power, Shikoku Electric Power, and Kyushu Electric Power have made application today to the Incorporated Administrative Agency Japan Nuclear Energy Safety Organization for confirmation of external disposal of waste in connection with the return from overseas of vitrified waste in accordance with the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors (hereafter, Act on Regulation of Nuclear Reactors, Etc.).

This application relates to the scheduled transport of a total of 132 canisters of returned vitrified waste to waste-management facilities belonging to Japan Nuclear Fuel Limited in Rokkasho-mura, Aomori Prefecture, in fiscal year 2014. The application is made by the electric power companies that are the owners of this shipment in order to obtain confirmation of the necessary security measures that need to be observed when placing vitrified waste in storage.

The details of the application are as given in Attachment 1.

The electric power companies have had measurements and observations made of the vitrified waste to be returned at the Sellafield reprocessing plant of Sellafield Ltd in the United Kingdom from May to November of last year. The canisters have also been confirmed to be in good condition in terms of their external appearance and so on. The substance and results of measurement and observation in the United Kingdom are as shown in Attachment 2.

The vitrified waste being transported for return is scheduled to arrive in Japan around April 2014.

Attachment

Attachment1

Regarding the Application for Confirmation of External Disposal of Returned Vitrified Waste

1. Position of the Application for Confirmation of External Disposal of Waste

Japan's nine electric power companies and the Japan Atomic Power Company have contracted the reprocessing of spent fuel originating at nuclear power stations to Areva NC of France and to NDA in the United Kingdom. Radioactive waste that is generated in the course of reprocessing is returned to Japan in accordance with their contracts.

When the imported radioactive waste (hereafter, imported waste) is to be disposed of at waste-management facilities in Japan, the licensee of reactor operation and other such parties that are seeking to dispose of the imported waste are required by the provisions of the Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors to receive confirmation from the Incorporated Administrative Agency Japan Nuclear Energy Safety Organization regarding compliance with the necessary measures for security as provided in Article 2 of the Regulations Concerning the Disposal of Nuclear Fuel and Other Such Materials Outside Plants or Business Establishments.

2. Matters to be Confirmed

Before the electric power companies and other such companies dispose of imported waste at waste-management facilities belonging to Japan Nuclear Fuel Limited, they must receive confirmation of the following items from the Incorporated Administrative Agency Japan Nuclear Energy Safety Organization.

(1) When imported waste is to be disposed of, the measures necessary for security in the next and subsequent items are to be taken and the waste is to be disposed of at a waste-management facility.

(2) Imported waste is to conform to the following criteria:

  • The waste is to be enclosed in containers for prevention of radiation hazard or solidified in containers.
  • The particulars (including dimensions, weight, strength, and calorific value) and quantities are to be such that the waste is manageable by the waste-management facility concerned.
  • The radioactive concentration of each type of radioactive substance is to be such that the waste is manageable by the waste-management facility concerned.
  • The waste is to be such that radioactive substances will not readily be dispersed or leak.
  • The waste is not to be significantly damaged.

(3) When imported waste is to be disposed of at a waste-management facility, documents are to be prepared recording matters related to the imported waste concerned and these documents are to be submitted to the waste management company that established the waste management facility.

(4) The imported waste is to be marked with a reference number in a prominent location on its surface made by a display method that is not readily removed.

(5) The radiation dosage received by individuals involved in the disposal is not to exceed the level specified by the Nuclear Regulation Authority.

3. Overview of Application Form Entries

(1) Application date:January 07, 2014

(2) Applicants and quantities:

Chubu Electric: 28rods

Kansai Electric: 28 rods

Chugoku Electric: 20rods

Shikoku Electric: 28rods

Kyusyu Electric: 28rods

(3) Party that conducted enclosure or solidification of the imported waste:  Sellafield Ltd

(4) When produced:  2001 - 2008

(5) Content and other particulars of the imported waste

  • Content of imported waste:    High-level radioactive liquid waste generated in the reprocessing of spent fuel, solidified using borosilicate glass and stored in stainless steel containers.
  • External appearance:  Satisfactory
  • Containment:  Satisfactory
  • Container materials:  UK standard BS1501 Pt3 309S16 (corresponds to JIS SUH 309)
  • Container thickness:  Approximately 5 mm
  • Source of high-level radioactive liquid waste:Uranium fuel used in light-water reactors and fuel other than uranium used in light-water reactors
  • Method of enclosure or solidification of imported waste:
    Atelier de Vitrification de Marcoule (AVM) method
  • Dimensions of imported waste: Outside diameter approximately 430 mm, height approximately 1,340 mm
  • Weight of imported waste:    439 kg - 494 kg
  • Strength of imported waste:   Satisfactory
  • Calorific value of imported waste (at time of application): 0.9 - 1.3 kW/canister
  • Radioactive concentration of each type of radioactive substance contained in imported waste (at time of application):
  • Radioactive substances emitting alpha rays:   1.3 × 1014 - 2.0 × 1014 Bq/canister

(Concentration of radionuclides) 238Pu: 5.2×1010 - 4.9×1011 Bq/canister

239Pu: 4.7×109 - 2.4×1010 Bq/canister

240Pu: 1.3×1010 - 6.9×1010 Bq/canister

241Am: 8.9×1013 - 1.3×1014 Bq/canister

242Cm: 1.9×103 - 8.9×107Bq/canister

243Cm: 1.7×1012 - 3.8×1012 Bq/canister

244Cm: 2.5×1013 - 5.7×1013 Bq/canister

 

  • Radioactive substances not emitting alpha rays:   1.1×1016 - 1.6×1016 Bq/canister

(Concentration of radionuclides) 90Sr: 1.8×1015 - 2.7×1015 Bq/canister

90Y: 1.8×1015 - 2.7×1015 Bq/canister

106Ru: 2.5×109 - 6.1×1011 Bq/canister

106Rh: 2.5×109 - 6.1×1011 Bq/canister

125Sb: 0.0×100  - 1.9×1012 Bq/canister

134Cs: 8.0×1011 - 8.2×1012 Bq/canister

137Cs: 3.0×1015 - 4.7×1015 Bq/canister

137mBa: 2.9×1015 - 4.4×1015 Bq/canister

144Ce: 1.4×108  - 1.6×1011 Bq/canister

144Pr: 1.4×108  - 1.6×1011 Bq/canister

154Eu: 2.2×1013 - 5.3×1013 Bq/canister

155Eu: 3.3×1012 - 1.4×1013 Bq/canister

  • Reference number labeling method: Engraved on side of container body

(6) Attached documents

1. Detailed explanation of content of imported waste

2. Detailed explanation of method of enclosure or solidification of imported waste

3. Explanation of method used to determine strength of imported waste

4. Explanation of method used to determine calorific value of imported waste

5. Explanation of method used to determine radioactive concentration of imported waste

6. Explanation of containment of radioactive material in imported waste

7. Explanation of waste-management facility where imported waste is to be disposed of

Attachment2

Results of Measurement and Observation in the United Kingdom

The electric power companies that are the owners of the 16th return shipment of vitrified waste, having first confirmed that the surfaces of the vitrified waste had been polished and wiped off, had measurements and observations made (external appearance, containment, surface contamination) of the vitrified waste for return (132 canisters) in the United Kingdom. These confirmed that there were no problems in terms of the examination criteria.

1. Measurement and observation period

May 09, 2013 to November 14, 2013

2. Measurement and observation items and results

(1) External appearance

a. Measurement and observation method

Confirm visually and by other means that there is no significant damage to the vitrified waste.

b. Measurement and observation results

The results were satisfactory, with no significant damage to any of the vitrified waste.

(2) Containment

a. Measurement and observation method

Following placement of the vitrified waste in containers for measurement and observation, a blower was used to pass air through the containers into devices (filters and ruthenium-collecting materials) to collect radioactive materials. The radioactive materials (volatile radioactive cesium and radioactive ruthenium) in the filters and ruthenium-collecting materials were analyzed, and it was confirmed that the levels of radioactive cesium and radioactive ruthenium met the criteria (radioactive cesium leakage no more than 4.5 Bq/3 canisters/h; radioactive ruthenium leakage no more than 2.2 Bq/3 canisters/h), thus confirming the soundness of the vitrified waste containment.

b. Measurement and observation results

The results are satisfactory, with all the vitrified waste satisfying the criteria.

(3) Surface contamination

a. Measurement and observation method

Rotate the vitrified waste and wipe its surfaces with filter paper. Analyze the filter paper to confirm that the density of surface contamination by radioactive substances satisfies the criteria (less than 4 Bq/cm2).

b. Measurement and observation results

The results are satisfactory, with all the vitrified waste satisfying the criteria.

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