JAPAN NUCLEAR FUEL LIMITED

January 7 1998

Press Release Concerning an Application for Approval of
Modifications to an Application for Off-Site Radioactive Waste
Disposal of Phase III Returned Vitrified Waste


Tokyo Electric Power Company
Kansai Electric Power Company
Chubu Electric Power Company
Kyushu Electric Power Company


As the owners of vitrified waste (60 canisters) scheduled to be returned in the 2nd half of fiscal 1997, the above parties today filed an application with the Director General of the Science and Technology Agency to modify their application for off-site radioactive waste disposal filed on 2 October 1997.

The reason for this modification is to supplement the description of the inspection result of "surface contamination" ( no problem found), which was obtained during inspections conducted at La Hague Reprocessing Plant in France from the middle of October to the beginning of December 1997.

Details of the inspections are shown in Appendix 1 and Appendix 2.

Further information about the above application is available from the Nuclear Cycle Information Booth at Japan Nuclear Fuel Limited in Aomori.


Appendix 1


Results of Vitrified Radioactive Waste Inspection
and Measurement Conducted in France (60 canisters)

 

As the owners of vitrified waste (60 canisters) scheduled to be returned to Japan, the electric power companies concerned conducted inspections and measurements of 60 canisters in France.

Three inspection criteria were applied:

(1) Visual inspection
(2) Leak tightness inspection
(3) Surface contamination inspection

Inspections were conducted three times from October to December 1997. The first extended from 13 October to 20 October 1997, the second extended from 3 November to 10 November 1997, and the third extended from 24 November to 1 December 1997.

The results confirmed that the waste therein met all standards for the 3 criteria.


Appendix 2


Outline of Vitrified Radioactive Waste Inspection Prodedures

 

(1)Visual Inspection

The surface of canisters are visually inspected for noticeable damage.

(2)Leak Tightness Inspection

Canisters are put into an inspection vessel and the air therein is extracted into sampling unit collectors. Radioactive materials (cesium-137, cesium-134, and ruthenium-106) in the collectors are then analyzed to confirm leak tightness.

(3) Surface Contamination Inspection

The surface of the canister is wiped with smear paper while the canister is rotated. The smear paper is then analyzed to assess radioactive material density on the canister surface.

The results confirmed that the waste therein met all standards for the 3 criteria.


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