ML19319D578
| ML19319D578 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 10/10/1971 |
| From: | Case E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003170747 | |
| Download: ML19319D578 (2) | |
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CRYSTAL RIVER III i
PRDit.RY REACTOR COITAINMENT 1
T The Crystal River III primary containraent has a 1'ree volume of 0 ft.3 and a design pressure of 55.0 PSIG. The applicant has 2.0 x 10 investigated various si:cd primry coolant system breaks and finds that n
tha d.5 ft.' break results in the highest peak containment pressure of 53.4 ?SIG, and thus there is a 9.17. cargin to design pressure.
An coti.. ate of the Crys:cl ?.iver III contairent peak pressura has been radc by the staff utilizing the " straight lice approach".1 This simple =2thod predicts a peak containment pressure of 51.0 PSIG.
Sinca January, li69, all dry WR contatuacuts have been required i
to have at Icast a 10". margin.
Crystal ;uv=r III balcng;; te a group of contain= cats whose pressure margin was approved prior to January, 136i.
HowcVer, based en the applicant's and the staff's calculations, the Crystal River III containment has a design pressure in excess of the peak calculated loss-of-coolant-sceident pressure and an acceptable pressure margin of approximataly 97..
o i
b I raft of Safety Guide
" Design Pressure of Dry WR Containments" -
D From H. Specter, SPS, to E. G. Case, DRS, 12/7/70.
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