ML040360709
Jump to navigation
Jump to search
| ML040360709 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/04/2004 |
| From: | NRC/NRR/DLPM |
| To: | |
| References | |
| TAC MC1763 | |
| Download: ML040360709 (1) | |
Text
REACTOR COOLANT SYSTEM BASES 3/4.4.7 DELETED 3/4.4.8 SPECIFIC ACTIVITY I
The limitations on the specific activity of the reactor coolant ensure that the resulting 2-hour doses at the SITE BOUNDARY will not exceed an appropriately small fraction of 10 CFR Part 100 dose guideline values following a steam generator tube rupture accident in conjunction with an assumed steady-state reactor-to-secondary steam generator leakage rate of 1 gpm. The values MILLSTONE - UNIT 3 B 3/4 4-5 Amendment No. 204 Corrected by letter dated February 4, 2004.