ML19329C745
| ML19329C745 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/03/1974 |
| From: | Tedesco R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8002190862 | |
| Download: ML19329C745 (2) | |
Text
~
hhh f'\\ h g
~
e ggp 3 1974 Docket No. 50-346 Richard DeYoung, Assistant Director for Pressurized Water Reactors, L DAVIS-BESSE NUCLEAR POWER STATION - SECOND RCUND QUESTIONS Plant Name: Davis-Besse Nuclear Power Station, Unit i Licensing Stage: OL Dockmt Number: 50-346 Responsible Branch:
PWR 44 Project Leader:
I. Pe'. tier Requested Completion Date: September 6,1974 Description of Response: Additional Inforsation Required Review Status: Cceplete We have reviewed the amended FSAR for Davis-Besse Nuclear Power Station, Unit 1, and find that the analysis of the effect of liquid radwaste component failure is missing.
Enclosed is the infor:aation we will need to complete our evaluation.
We will need the additional information by December 6,1974 to meet our schedule.
, venal igtel by:
n.Aert I. TM Robert L. Tedeaco, Assistant Director for Containment Safety Directorate of Licensing
Enclosure:
As stated Dis. ibution:
Docket File n
cc: w/o encicsure L Reading A. Giambusso CS Reading Dj
(\\[ g;
,, -N.
W. Mcdonald ETSB Reading
\\
\\
y Qgng,\\ju;L>y ETSB Staff n
n \\\\ g\\
w/ enclosure S. Hanauer
- 7. Bemaroya F. Schroeder J. Kastner O O A. Schwancer W. Burke E. Thompson J. Glynn I. Peltier FDE G. Knighton
- ETS4_,
ETSBp AD/CS. g's_
.,,.c.,
iC$urIe:ks VBenarofa_
RLTedesc'o 3...,
9/J /74_
._9/1. G.4 9/3/74 r.,..src.3u
,n,..+....srcs ozm
- -a ca ' ' " " + ' " * * "
8002190 862
//
~ ~. - -
- =. _. -.
d A
i ROUND TWO QUESTIONS FOR DAVIS-BESSE NUCLEAR POWER STdION, UNIT 1 l
DOCKET No. 50-346 i
01.0 EFFLUENT TREATMENT l
01.1 Provide an analysis indicating the radionuclide concentra-l (15.24) tions which could occur in both 1) the nearest potable water supply, and 2) the nearest surface water in an i
unrestricted area as a result of leakage based on single failures of components located outside realtor contain-ment containing radioactive liquids.
Assume 1% of the operating fission product inventory is released to the 1
primary coolant, failed tanks release 80% of their design capacity, and all liquids from failed components enter the 4
groundwater; i.e., do not assume liquids are retained by,
1 building foundations.
Credit for radionuclide removal by-i the plant process systems, consistent with the decontamina-tion factors in WASH-1258 should be assumed. List all
. parameters and provide justification for the values assumed in your calculations, including liquid dispersion and transit time based on dis tance, the hydraulic gradient, permeability and effective porosity of the soil, and the assumed decontamination due to ion exchange by the soil.
\\
i i
l
?
e l
i
{
\\
i.
.