Additional materials on the safety assessment for the 24 CANFLEX-NU bundle demonstration irradiation at Wolsong-1 generating station as the answers on the KINS's second questions

This report describes the additional materials on the Safety Assessment for the 24 CANFLEX-NU Bundle Demonstration Irradiation at Wolsong-1 Generating Station, which is the answers on the KINS's first questions as a result of the review of the Safety Assessment report. The additional materials cover : 1) Subjects on CANFLEX-NU fuel channel and the selection criteria, 2) Subjects on the evaluation of the discharge fuel with respect to the purpose of the DI, 3) Subjects on the planning of report of the DI results, 4) Subjects on the integrity evaluation of the CANFLEX-NU fuel bundles in the reactor, 5) Subjects on the thermal-hydraulic compatibility of the CANFLEX-NU fuel with the existing 37-element bundles, 6) Subjects on the Input variables of CATHENA code used in the safety analyses, 7) Subjects on the loss of forced circulation, 8) Subjects on the CANFLEX-NU fuel element power under condition of non-LOCA, 9) Subjects on the loss of reactivity control, 10) Subjects on the LOCA. The additional materials are made on the basis of the Safety Assessment for the 24 CANFLEX-NU Bundle Demonstration Irradiation at Wolsong-1 Generating Station(H. C. Suk et. al, KAERI/TR-1864/2001, 2001.6) and Operational Procedure of the Wolsong-1 Generating Station, and so on