File 315 is only for the ENDF-6 format version. In the ENDF-5 format, the fission product yields are given together with cross section data of fissioning nuclei.
NUCLIDE MAT RECORDS
1 90-TH-232 9040 3313
2 92-U -233 9222 4948
3 92-U -235 9228 4948
4 92-U -236 9231 1673
5 92-U -238 9237 3312
6 93-NP-237 9346 1673
7 94-PU-239 9437 4948
8 94-PU-240 9440 1672
9 94-PU-241 9443 3310
10 94-PU-242 9446 1672
11 95-AM-241 9543 69
12 95-AM-243 9549 69
TOTAL = 31607 RECORDS