Press Release Back Number(2006)

Request to confirm off-site disposal of returned solid-glass waste and notice of revisions in text of request to confirm off-site disposal

January 18, 2006
Hokkaido Electric Power Co., Inc.
The Tokyo Electric Power Company, Inc.
Chubu Electric Power Co., Inc.
The Kansai Electric Power Co., Inc.
Kyushu Electric Power Co., Inc.
The Japan Atomic Power Company

The following six companies are to return a total of 164 rods of solid-glass waste in the second half of the 2005 fiscal year: Hokkaido Electric Power Co., Inc.; the Tokyo Electric Power Company, Inc., Chubu Electric Power Co., Inc.; the Kansai Electric Power Co., Inc.; Kyushu Electric Power Co., Inc.; and the Japan Atomic Power Company. Since 144 of these 164 rods will be returned from overseas pursuant to Nuclear Reactor Regulation Law, the six companies today applied to the Japan Nuclear Energy Safety Organization for approval of off-site disposal. The six companies also submitted a notice of revisions in the text of a request to confirm off-site disposal. The request was submitted on November 24, 2004 for 20 rods from the Tokyo Electric Power Company.


Through this request, the electric power companies are seeking to address various issues, including mandatory safety measures involving storage of the 144 rods of solid-glass waste to be delivered during the second half of the 2005 fiscal year to the waste-management facility of Japan Nuclear Fuel Ltd. in the village of Rokkasho, Aomori Prefecture. The notice is intended to update various specifics, such as the dates on which confirmation is requested for the 10th return of solid-glass waste, comprising 20 rods, from the Tokyo Electric Power Company, for which shipment has been delayed.


Appendix 1 addresses the details of this request. Appendix 2 provides a summary of the notice.


In addition, from late August through early December 2005, each electric power company has assessed the returned solid-glass waste at the La Hague reprocessing plant of France's COGEMA to confirm the adequacy of various aspects, including external appearance. See Appendix 3 for details and results of the measurements undertaken in France.


The returned solid-glass waste is to be shipped according to the following tentative timetable: Shipments are to depart port around February 2006 and to arrive around March 2006.


Appendix 1:
Concerning request to confirm off-site disposal of returned solid-glass waste

Appendix 2:
Summary of notice of revisions in text of request to confirm off-site disposal

Appendix 3:
Assessments carried out in France



Appendix 1

Concerning request to confirm off-site disposal of returned solid-glass waste

1. Significance of request for off-site disposal confirmation


Japan's nine electric power companies and the Japan Atomic Power Company subcontract the reprocessing of spent nuclear power plant fuels to COGEMA of France and British Nuclear Fuels Limited (BNFL) (now British Nuclear Group Sellafield [BNGS]). The radioactive waste generated in the reprocessing is returned to Japan, in accordance with the terms of the relevant agreements.

Under Nuclear Reactor Regulation Law, nuclear power plant operators planning to import and dispose of imported radioactive waste at waste-management facilities in Japan are required to have the Japan Nuclear Energy Safety Organization 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. Matters to be confirmed


Before disposing of imported waste at the Japan Nuclear Fuel Ltd. waste-management facility, the electric power companies ask the Japan Nuclear Energy Safety Organization 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:
    • A. Waste has been solidified in containers to prevent harmful radiation.
    • B. Waste parameters (including dimensions, weight, strength, and heat generation) and quantities are suitable for management at the subject waste-management facility.
    • C. The radioactive density of each type of radioactive substance is appropriate for management at the subject waste-management facility.
    • D. The radioactive substances will resist leakage or dispersal.
    • 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 issued 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 labeling method not easily removed
  5. (5) That the volume of radiation to which individuals involved in the disposal may be exposed will not exceed values specified by the Minister of Economy, Trade and Industry

3.Summary of request


1) Date of request:

January 18, 2006


2) Applicants and quantities:

Hokkaido Electric Power Co., Inc.: 6 rods

The Tokyo Electric Power Company, Inc.: 22 rods

Chubu Electric Power Co., Inc.: 20 rods

The Kansai Electric Power Company, Inc.: 63 rods

Kyushu Electric Power Co., Inc.: 10 rods

The Japan Atomic Power Company: 23 rods


3) Party responsible for solidification of imported waste:

COGEMA


4) Years of manufacture:

1993 - 2002


5) Detailed description of imported waste

  1. (1)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 SUH 309)
    • • Container thickness: approx. 5 mm
    • • Source of high-level radioactive liquid waste: uranium fuels used in light-water reactors, or both uranium fuels and non-uranium fuels used in light-water reactors

  2. (2) Solidification method used for imported waste: AVM (Atelier Vitrification de Marcoule) method
  3. (3) Dimensions of imported waste: Outside diameter: approx. 430 mm; height: approx. 1340 mm
  4. (4) Weight of imported waste: 472 kg - 516 kg
  5. (5) Strength of imported waste: satisfactory
  6. (6) Heat generated by imported waste (at the time of the request): 1.3 kW/rod - 1.8 kW/rod
  7. (7) Radioactive density of each type of radioactive substance included in the imported waste (at the time of the request)
    • • Radioactive substances emitting alpha rays:1.51014 - 2.91014 Bq/rod
      (radionuclide density) 241Am:7.31013 - 1.31014 Bq/rod
      244Cm:5.71013 - 1.91014 Bq/rod
    • • Radioactive substances not emitting alpha rays: 1.61016 - 2.01016 Bq/rod
      (radionuclide density) 90Sr: 2.71015 - 3.61015 Bq/rod
      90Y: 2.71015 - 3.61015 Bq/rod
      106Ru: 3.41010 - 5.21013 Bq/rod
      106Rh: 3.41010 - 5.21013 Bq/rod
      125Sb: 7.01011 - 2.71013 Bq/rod
      134Cs: 9.61012 - 4.41014 Bq/rod
      137Cs: 4.21015 - 5.61015 Bq/rod
      137mBa: 4.01015 - 5.31015 Bq/rod
      144Ce: below detectable levels - 2.51013 Bq/rod
      144Pr: below detectable levels - 2.51013 Bq/rod
      154Eu: 5.71013 - 1.61014 Bq/rod

  8. (8) Reference number display method: imprinted on container lid

6) Attached documents

1. Detailed description of imported waste

2. Detailed description of solidification method for imported waste

3. Description of method of determining strength of imported waste

4. Description of method of determining heat generated by imported waste

5. Description of method of determining radiation density of imported waste

6. Description of sealing of radioactive materials in connection with imported waste

7. Description of waste-management facility for disposal of imported waste




Appendix 2

Summary of notice of revisions in text of request to confirm off-site disposal

1.Date of original request:

November 24, 2004


2.Date of notice:

January 18, 2006


3.Applicant and quantity:

The Tokyo Electric Power Company, Inc.: 20 rods


4.Specifics of revisions:

Revisions in text of request to confirm off-site disposal

Requested dates of confirmation:

Before: November 24, 2004 - March 31, 2006
After: November 24, 2004 - May 31, 2007


Revisions in Appendix to request for off-site disposal confirmation

Note added to clarify that the external appearance of the solid-glass waste is to be confirmed once again following the request to confirm off-site disposal.


5.Reason for change:

Revision to shipment schedule and reconfirmation of external appearance of the solid-glass waste carried out in France



Appendix 3

Assessments carried out in France

Each electric power company owning the solid-glass waste returned in this 11th return has measured in France the solid-glass waste subject to return (164 rods), confirming that the related measurements present no problems with regard to 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.Periods of measurements:

  • • August 22 - 25, 2005
  • • September 5 - 9, 2005
  • • September 26 - 28, 2005
  • • October 10 - 14, 2005
  • • November 2 - 4, 2005
  • • November 14 - 17, 2005
  • • November 30 - December 2, 2005

2.Measurement items and results

(1) External appearance

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


(2) Sealing

  • a. Assessment method
    Following placement of the solid-glass waste in containers for measurement and the application of a blower to pass air through the containers into devices (filters and Ruthenium-collecting materials) to collect radioactive substances, radioactive materials in the filters and Ruthenium-collecting materials (volatile radioactive cesium and radioactive Ruthenium) were analyzed, it was confirmed that the volumes 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). Also confirmed was the adequacy of the sealing of the solid-glass waste.
  • b. Assessment
    All solid-glass waste was deemed satisfactory and to meet the evaluation criteria.


(3) Surface soiling

  • 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
    All solid-glass waste was deemed satisfactory and to meet the evaluation criteria.