Press Release Back Number(2007)

Offsite Disposal Confirmation Application for Solid-Glass Waste

January 24, 2007
Tokyo Electric Power Company, Inc.
Chubu Electric Power Co., Inc.
Hokuriku Electric Power Company
Kansai Electric Power Co., Ltd.
Kyushu Electric Power Co., Inc.

The Tokyo, Chubu, Hokuriku, Kansai and Kyushu electric power companies today applied for offsite disposal confirmation from the Japan Nuclear Energy Safety Organization (JNES) to facilitate the return of solid-glass waste from overseas, in accordance with the Nuclear Reactor Regulation Law.

The present application concerns 130 rods of returned solid-glass waste scheduled to ship to a Japan Nuclear Fuel Co., Ltd. waste management facility in Rokkasho, Aomori Prefecture in FY2006. The application seeks confirmation that the electric companies that own the shipment have taken the necessary steps to ensure safety during the storage of the solid-glass waste.

Details of the application can be found in Attachment 1.


From late July to late November last year, the power companies assessed the returning solid-glass waste and examined its external appearance at the Areva NC's La Hague reprocessing plant in France and found that all was in order. Details and results of measurements taken in France are shown in Attachment 2.


The shipment of the returning solid-glass waste is scheduled to depart in February 2007 and arrive in Japan in March.


Attachment 1: Concerning application for confirmation of offsite disposal of solid-glass waste

Attachment 2: Results of measurements in France



< Attachment 1 >

Concerning application for confirmation of offsite disposal of solid-glass waste

1. Background to application for confirmation of offsite disposal

Japan's nine electric power companies and the Japan Atomic Power Company subcontract the reprocessing of spent nuclear power plant fuels to Areva NC of France and British Nuclear Group Sellafield. The radioactive waste generated in the reprocessing is returned to Japan, in accordance with the terms of the relevant agreements.

Under the Nuclear Reactor Regulation Law, nuclear power plant operators planning to import and dispose of radioactive waste at waste-management facilities in Japan are required to have JNES confirm compliance with the safety measures required under Article 2 of the regulations concerning plant or off-site disposal of nuclear fuels and other substances.


2. Items to be confirmed

Before disposing of imported waste at the Japan Nuclear Fuel waste management facility, the electric power companies ask JNES to confirm the following points:


  1. (1) That the imported waste will be disposed of at the waste management facility after first fulfilling the required safety measures listed below.
  2. (2) That the imported waste meets the following criteria:
    1. A. Waste has been solidified in containers to prevent harmful radiation.
    2. B. Waste parameters (including dimensions, weight, strength and calorific value) and quantities are suitable for management at the subject waste management facility.
    3. C. The concentration of radioactivity of each type of radioactive substance is appropriate for management at the subject waste management facility.
    4. D. The radioactive substances will resist leakage or dispersal.
    5. E. The imported waste shows no signs of significant damage.

  3. (3) That, before disposal of imported waste at the waste management facility, documents are prepared on various issues related to the imported waste, and that these documents are submitted to the waste management company that set up the waste management facility.
  4. (4) That a reference number is clearly indicated in a prominent location on the surface of the imported waste by a labelling method not easily removed.
  5. (5) That the level of radiation to which individuals involved in the disposal may be exposed will not exceed the level specified by the Minister of Economy, Trade and Industry.

3. Summary of request

1) Application date:

January 24, 2007


2) Applicant and quantity:


  • Tokyo Electric: 20 rods
  • Chubu Electric: 20 rods
  • Hokuriku Electric: 6 rods
  • Kansai Electric: 75 rods
  • Kyushu Electric: 9 rods

3) Party responsible for solidification of imported waste:

Areva NC


4) Years of manufacture:

1994 - 2002


5) Detailed description of imported waste

• Detailed description of imported waste:

High-level radioactive liquid waste generated in the reprocessing of spent nuclear fuel stored in stainless steel containers, solidified by borosilicate glass.

  • • External appearance:
    satisfactory
  • • Seal:
    satisfactory
  • • Container materials:
    materials comply with French standard Z15 CN24 13 (corresponds to JIS SUH309)
  • • Container thickness:
    approx. 5 mm
  • • Source of high-level radioactive liquid waste:
    uranium fuel used in light-water reactors, or both uranium fuel and other fuel

• Imported waste solidification method:

AVM (Atelier Vitrification de Marcoule) method


• Dimensions of imported waste:

diameter: approx. 430 mm; height: approx. 1,340 mm


• Weight of imported waste:

467 kg - 511 kg


• Strength of imported waste:

satisfactory


• Calorific value of imported waste (at time of application):

1.3 kW - 1.8 kW / rod


• Concentration of radioactivity for each type of radioactive material in imported waste (at time of application)
• Radioactive substances emitting alpha rays:
    1.7×10 to the power of 14st - 2.9×10 to the power of 14st Bq/rod
  (radionuclide density)
  241Am: 7.0×10 to the power of 13st - 1.3×10 to the power of 14st Bq/rod
  244Cm: 5.9×10 to the power of 13st - 1.8×10 to the power of 14st Bq/rod
• Radioactive substances not emitting alpha rays:
    1.5×10 to the power of 16st - 2.0×10 to the power of 16st Bq/rod
  (radionuclide density)
  90Sr: 2.5×10 to the power of 15st - 3.7×10 to the power of 15st Bq/rod
  90Y: 2.5×10 to the power of 15st - 3.7×10 to the power of 15st Bq/rod
  106Ru: 2.9×10 to the power of 10st - 2.8×10 to the power of 13st Bq/rod
  106Rh: 2.9×10 to the power of 10st - 2.8×10 to the power of 13st Bq/rod
  125Sb: 8.9×10 to the power of 11st - 2.7×10 to the power of 13st Bq/rod
  134Cs: 8.9×10 to the power of 12st - 3.1×10 to the power of 14st Bq/rod
  137Cs: 4.1×10 to the power of 15st - 5.4×10 to the power of 15st Bq/rod
  137mBa: 3.9×10 to the power of 15st - 5.1×10 to the power of 15st Bq/rod
  144Ce: 1.6×10 to the power of 9st - 1.0×10 to the power of 13st Bq/rod
  144Pr: 1.6×10 to the power of 9st - 1.0×10 to the power of 13st Bq/rod
  154Eu: 6.1×10 to the power of 13st - 1.5×10 to the power of 14st Bq/rod

• Reference number marking procedures:

Engraving on container lid


6) Attached documents

  1. 1. Detailed explanation of content of imported waste
  2. 2. Detailed explanation of imported waste solidification procedures
  3. 3. Explanation of procedures used to determine imported waste strength
  4. 4. Explanation of procedures used to determine imported waste calorific value
  5. 5. Explanation of procedures used to determine the imported waste's concentration of radioactivity
  6. 6. Explanation of sealing of radioactive materials in imported waste
  7. 7. Explanation of waste management facility in which imported waste will be disposed


< Attachment 2 >

Results of measurements in France


The electric power companies that own the 12th shipment of returned solid-glass waste performed measurements of this waste (130 rods) in France and determined that there were no problems in terms of the evaluation criteria. They have also confirmed that the surfaces of the solid-glass waste have been polished and wiped off in advance.

The Japanese government has confirmed the results of these measurements.


1. Measurement period


  • • July 31 - August 4, 2006
  • • September 11 - 15, 2006
  • • October 9 - 11, 2006
  • • October 23 - 25, 2006
  • • November 6 - 8, 2006
  • • November 20 - 22, 2006

2. Measurement items and results

(1) External appearance


  • a. Assessment method
    Confirm visually and through other means that the solid-glass waste shows no signs of significant damage.
  • b. Assessment results
    All solid-glass waste was deemed satisfactory, with no significant damage.

(2) Sealing in


  • a. Assessment method
    Following placement of the solid-glass waste in containers for measurement and the use of a blower to pass air through the containers into devices (filters and ruthenium-collecting materials) to collect radioactive substances, radioactive materials (volatile radioactive cesium and radioactive ruthenium) in the filters and ruthenium-collecting materials were analyzed, and it was determined that the levels of radioactive cesium and radioactive ruthenium met the evaluation criteria (leakage of radioactive cesium: no more than 4.5Bq/3 rods/h; leakage of radioactive ruthenium: no more than 2.2Bq/3 rods/h), thus confirming the adequacy of the sealing of the solid-glass waste.
  • b. Assessment results
    All solid-glass waste met the evaluation criteria and was deemed satisfactory.

(3) Surface contamination


  • a. Assessment method
    The solid-glass waste was rotated and surfaces wiped with filter paper. The filter paper was then analyzed to confirm that the density of surface soiling of radioactive substances satisfied the evaluation criteria (less than 3.7Bq/cm2).
  • b. Assessment results
    All solid-glass waste met the evaluation criteria and was deemed satisfactory.