ML19332C355
| ML19332C355 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 06/30/1989 |
| From: | Tuttle R ROCKWELL INTERNATIONAL CORP. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 89RC-08857, 89RC-8857, NUDOCS 8911280017 | |
| Download: ML19332C355 (4) | |
Text
p-
- y..:
-3
.i :; 1 ?
i
..e, j
'1
-~
~
. Rocketdyne DMelon -
- ""'""'"*""*'C**'*""
Rockwell' P^ - M 7 6633 Canoga Avenue
~ Carmga Park, California 91304
'IntemedOn81 3
i Telex: 698478 0' "9
' t m kU Th,* { [
ROCKETDYN CNPK
=J
-l July 17,-1989
. In reply refer to 99RC-08857 1
QL Mr. ' John B.
Martin,-Administrator Region ~V Office i
U.
S.
Nuclear ' Regulatory Commission 11450 Maria Lane,' Suite 210 Walnut Creek, California 94596-5368 Dear Mr.. Martin 1
Subjects. Effluent Monitoring Report
'As required in 10 CFR 7 0. 5 9 (a),
we are submitting the Effluent.-Monitoring Report for activities conducted at the Rocketdyne~ Division of-Rockwell International under Special-j Nuclear-Materials License SNM-21 for the period f rom January
- to June-30,-1989.
- Two: copies of the report are enclosed f or your 'inf ormation 4
and use.
-Sincerely yours,-
whx R. \\ J.
Tuttle, Manager
' Radiation land Nuclear Safety Enclosures as noted- (2 copies) a --
cc: w/ enclosure Director,. Inspection and Enforcement, U.
S.
Nu cl e a r Regulatory Commission, Washington, D.
C.
20555
^I
//
\\
j/
/
\\ \\
891128oo17 89063o
[DR.ADOCK 07000023 PDC
- z. :
n 2 -
ROCKETDYNE ' DIVISION' EFFLUENT MONITORING REPORT
- SPECIAL. NUCLEAR MATERIAL LICENSE SNM-21 0
Ef fluenes.which may' contain radioactive material are generated'at Rocketdyne facilities-as the-result of
< operations perf ormed under contract to the U. S.. DOE, under LL S,1NRC Special Nuclear Material License SNM-21, and under State of California Radioactive Material License 0015-70.
The only f acility operating under the PNM-21_ license is identified as Building 020, the Rockwell International Hot JLaboratory (RIHL),
at the Santa Susana Field Laboratories site.
Monitoring of effluent for radioactive materials demonstrates that operations conform to NEC regulations and to 1icense conditions regarding releases of such materiala to the environment.
For comparison with regulatory limits on discharge 6 ~ we have chosen the 'most restrictive maximum
_ permissible concentration (MPC) from 10 CFR 20 for
. radionuc1' ides in use at the ---f acil ity.
All discharges reported f or-this period wsre.below 1% of 'the applicable MPC.
~
^
l-A FACILITY DESCRIPTION-f l
1.
Santa Susnna Site, SSFL Building 020-NRC and California State Licensed Activities Operations at Building 020 which may generate radioactive ef fluents consist of hot cell examination and decanning,.
dismantling, or decladding' of irradiated nuclear fuels and examination of reactor components.
Only atmospheric
~
~
emissions are released f rom ~ the.f acility to unrestricte~d~
^
l-areas.
No radioactive liquid waste is released ffo~m"the
~
f acility to ' unrestrictsd~ areas.
The atmospheric - emissions L
may contain particul"ateTmat~erial,. as well as radioactive ls.
gases, depending on the operations being perf ormed and the l '
history of the irradiated fuel or other material being t'
1
~c/
processed.
The chemical - f orm.of such materials may be metal, oxide, carbide, or other forms,.and may contain mixed fission products and various activation products.
Radioactive material handled in unencapsul ated form in Building 020 during the _first half of 1989 was' limited to residual. radioactive contamination from prototype demonstrations of Fermi f uel decladding processes, fines produced from the' Fermi-fuel shroud removal,.-
and also residual contamination f rom the previous SEFOR and EBR II reactor fuel ' decladding operations.
The major effort conducted at the RIHL during the first half of 1989 involved clean-up and decontamination of examination cells, removal of surplus equipment, and general f acility maintenanca The distance from the point of atmospheric release to the nearest site boundary is about 302 meters and is approximately 1900 meters to the nearest offsite structure.
l l
w.
.L
'i
(.
?
P293?2
, e Nearest offsite boundary' ground-level concentrations would
- be icwered-by a-f actor of. at least: 20000 under the Pasquill j
Type B
moderate-instability category,- which is j
representative of'the SSFL site.
l B.
TREATMENT AND HANDLING Waste streams discharged to unrestricted areas are limited,.
R
- in all cases, to gaseous emissions.
The levels of ~ radioactivity contained in all atmospheric emissions are reduced to the lowest reasonably achievable values by passing the emissions through certified high-efficiency particulate air. (HEPA)- filters prior to di s ch a r g e.-
The emissions,are sampled for entrained p
L particulate radioactive materials by taeans of continuous stack emission samplers installed at the point of releast In addition, the continuous stack exhaust monitor-installed at. Building 020 has-an automatic alarm capability in the event of a release of radioactivity.
The HEPA filters used i
for filtering gaseous emissions are certified to be 99.97%
efficient for removal of
- 0. 3 um diameter particles.
Filtration efficiency increases above and below this
. particle size.
The result for the most recent in-place test of. the Bui'lding 020 main exhaust system performed on November 17, 1988,(was 99.996% particulate removal efficiency.
The semiannual. average-concentration and total radioactivity in gaseous emissione f rom NRC licensed f acilities discharged to unrestricted areas during the first half of 1989 are shown in the appended table.
The value for " Total Radioactivity Discharged" is calculated as the. product of discharge volume and-average radioactivity concentration, which includes naturally occurring radioactivity in the l
ambient air.
l^
L Unfiltered ambient-air is mixed with the HEPA filtered exhaust' air as needed to control differential pressures within the various areas of the f acility.
i p
o
g).
7--.y._.
.x,; -. -,,
1 1
s
- ~
h.a _
v I h '..
y.
,b' c. - Q'.
g.,
b,.3 c
g, 1
y [
GASEOUS EMISSIONS DISCHARGED TO ' UNRESTRICTED AREAS
'FIRST HALF,.1989 January 1 to June-30, 1989 Approximate Release Approximate Lower Point
+/-
Sampling Period Total.
Limit of Average
. Error Maximum Observed Radioactivity-Effluett
. Detection-Concentration Estimate
- Concentration' Discharged Flosfate Activity Building Release Point (m /s)
Monitored (uCi/mll'
.(uCi/ml)
-(uCi/ml)
. (uCi/ml)
(Curies).
T/020 Stack Exit 13 Alpha 3.0 x 10-16
- 0. 3 x 10-15 0.4 ' x 10-15
' 0.9 x 10-15 0.06 x 10-6 Beta 3.1'x'10-16 7.0 x 10-15 6.0 x 10-15 ' - 1. 4 ' x 10-14
- 1. 4 x 10-6 Total:{1.5 x 10-6 Local ambgnt airborne radioactivity cgcentrations' averaged for the rej)orting period.were NOTE:
1.3 x 10-uCi/ml alpha and 2.6 x 10 uCi/ml beta.
The lower limit of detection was calculated for ' single measurements,' using the method of U.. S. NRC Regulatory Guide 4.16. -
The average concentrations are based on arithmetic averages of 25 measurements each for alpha and beta activity, including values below the LLD and below the analytical background (negative values).
i
- -Calculated at the 95% uncertainty level.
t m
-m.sw^e W
m-
--M.
t t
+
g
-g,i
=y-.
u
,w-.
-,s_,_-_,
c
. a t
..f
,mw