ML19326A403
| ML19326A403 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/02/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19326A401 | List: |
| References | |
| NUDOCS 8002030206 | |
| Download: ML19326A403 (4) | |
Text
.
m rS s
\\_)
Davis Besse Q Questions p
Offsite Radiological Monitoring 11.6.3 TLD will be' used to measure off-site radiation levels at 18 locations. The applicant states that there are three dosimeters at each location which will be changed monthly, quarterly and annually. This implies the use of one dosimete read out at each station for each specified time interval.
The Staff's position is that 2 or 1 dosimeters should be used and read out for each station at each interval to provide more reliable data for statistical analysis.
The milk sa=pling frequency should be changed frem =onthly to weekly'Alsoduring the seasons that milking animals are on the limits of sensitivity for '##! should pasture.
be at 0.5 pC1/ liter at the time of sampling, instead of 2.0 pCi/11ter' as cindiMeed -iFTab'le IT '57.'
.~.,y.
..y.
As pointed cut in the FES, the Environmental Mtnitoring Program omitted aquatic plants that are part of the food chain. The staff reco=nended monitoring the smartweed in marsh area and the applicant was advised of this require =ent.
State the reason for the caission in the FSAR.
Shielding 12.1.1 (1)'
The applicant states that the shielding is designed to ensure that during normal operations the exposure :o opera-tions personnel will not exceed the limits of 10 CFR 20.
In section 12.3.3, he also alludes to the fact that station personnel will be monitored to assure that they do not exceed the linits of 10 CFR 20. Although table 12-4A shows that the expected annual man-rem based on operating plant data will
'.n fact be less than the limits of.10.CFR 20.
the applicant should state his management policies regarding as low as practicable doses as specified in 10 CFR 20 Section 21.0(c), his methods of achieving these doses, and the persons responsible for their implementation and enforce-ment.
N 1
8 o 0 2 o 3 0SOk 4
.m 2
12.1.2.1.4 Fig. 12-11 " Isomeric at Control Room" shows a 2' concrete shield. What is the shield thickness on the roof of the control room?
Table 12-2 shows the. principle nuclides in process equipment.
The maximum total activity in the Miscellanious Waste Evaporator Storage Tank is listed as greater than 5000 curies of high energy ga=ma radiation. A detailed description and drawings of the shielding around this compartment as well as other compartments containing high levels of high energy gamma radiation should be included in the FSAR.
Fig. 12-1 is not of sufficient detail to determine the adequacy of the shielding in pertinent areas.
If shield design in an area is based on access requirements in that
..,..g.....
ate..the par.a. meg source strengt.h, d.ose rate g.
. ters (i.e.,
area, st
..c.;
... <, ; e, ;... :.....,,
v u
_~
thickness, etc.) used in the design of specific shields to achieve the desired accessibility in the area.
Area Monitorine 12.1.4 Recording of background dose rates allows one to note an inadvertant increase in radiation levels below the alarm point.
It also provides a permanent reco'rd of radiation lev &ls in the area of interest.
Zxplain why there are no automatic recording functions on any of the area radiation instrumentation.
Estimates of Exposure 12.1.6.1 The applicant shculd either identify the reactors labeled A, B, C, D.... in Table 12-5A, or provide a reference for the tabulated data.
Ventilation 12.2.1 The applicant states that the maximum expected concen-tration of radioactivity on the station site will be within the limits of 10 CFR 50 Appendix I "for all areas outside the station structure but within the site pgyndary". Doe s this meaf5 )a t estagjonwillmaintain t
t I eggcentration or, 10 j Ci/cc and KR concentrations of 10 sgC1/cc within the site boundary?
e
m 12.2.4 In their airborne radioactivity monitoring program, the Davis Besse station monitors the fuel handling and radweste areas, and the penetration and control rooms in the ventilation system. The staff therefore requires a diagram that shows the location of the sa=pling heads in the ventilation system with respect to each area being monitored. Also, describe the airborne radio-act v ty m gjg ring system that will {etect particulate y s Ci/cc in a matter and I at levels of 1 x 10 v
background of 10 mr/hr (see table 11-50).
o Provide information on frequency of sample changing of filter papers and charcoal cartridges at each sample location.
- 3.,.n..
.c..<.,.
..12.2.5.3.. - v. Wiiac"is.the~ frequency: of. collection of hi-vol grab samples for area surveillance for alpha, beta, ga==a activity analysis to establish the levels of airborne contamination.
Contamination Control 12.2.5.4 Explain why tritium is not monitored on a continuous basis at Davis Besse. The applicant statgs that when the tritium concentration exceeds 2 x 10 jjCi/ce, supplied air masks are worn. What areas are monitored for tritium and at what frequency is it monitored?
What method is used for tritium monitoring? Describe the bionssay program for critium uptake during noc=al operations
and anticipace'd operational occurrences.
Estimation of Inhalation Dose 12.2.6 A statement such as "No significant dose is expected from iodine" is ambiguous. What is a significant dose?
What records will be kept on airborne radioactivity measurements including noble gases and critium?
Health Physics 12.3 Who is responsible for writing radiation safety proceduces?
What level of =anagement reviews and signs off on these procedure s?
i 4
h
.m,.
-%em.
_ L.. ~...
n
-4d t
12.3.2.2.1 Describe the procedure for calibrating the neutron survey meters for fast neutrons.
Who maintains and calibrates the survey instruments?
What is the inspection schedule of instruments insofar as preventive maintenance is concerned. Are instrument maintenance records kept and are these records auditable?
~
12.3.2.2.3 Describe the test facilities and fitting procedures for respirator equipment. What procedures will be used for decontamination of respirators after use in a contamination incident.
Technical" Soec'ifications 16. 0.... --.. Provide the techg.al specifications on the Radiation and nic
. g.g gg y; 393 gg-v..
VI H of the Standard Format and Content of SAR Reports.
P s
e s
-s..
s i
_