ML20058H293
| ML20058H293 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 06/30/1990 |
| From: | Tuttle R ROCKWELL INTERNATIONAL CORP. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 90RC-09976, 90RC-9976, NUDOCS 9011150147 | |
| Download: ML20058H293 (7) | |
Text
____________
7, RECEl';ED l.'R C Mocheldyne Divleton R{Gfgy gr Rockwell internettonal Corporation Rockwe11 i
canasE cE*lE$
InternationaC l.'.; 13 fil ll: 04 Telex 698478 ROCKETDYN CNPK July 31, 1990 In reply refer to 90RC-09976 i
Mr. John B.
Martin, Administrator Region V Office U. S. Nuclear Regulatory Commission 14 50 Maria Lane, Suite 210 Walnut Creek, California 94596-5368 Dear Mr. Martin
Subject:
Effluent Monitoring Report As required in 10 CPR 7 0. 5 9 (a),
we are submitting the Effluent Monitoring Report for activities conducted at the Rocketdyne Division of Rockwell International under Special Nuclear Materials License SNM-21 f or the period f rom January 1 to June 30, 1990.
Two copies of the report are enclosed f or your inf ormation and use.
Sine rely yours, icrm_
R.
J. Tuttle, Manager Radiation and Nuclear Safety Enclosures as noted (2 copies) cca w/ enclosure
- Director, Inspection and Enforcement, U.
S.
Nuclear Regulatory Commission, Washington, D. C. 20555
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i ROCKETDYNE DIVISION EFFLUENT MONITORING REPORT SPECIAL NUCLEAR MATERIAL LICENSE SNM-21 Effluents 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 U. S. NRC Special Nuclear Material License SNM-21, and under State of Calif ornia Radioactive Material License 0015-70.
The only facility operating under the SNM-21 license is identified as Building 020, the Rockwell International Hot Laboratory (RIHL),
at the Santa Susana Field Laboratories site.
Monitoring of effluent for radioactive materials demonstrates that operations conform to NRC regulations and t
to license conditions regarding releases of such materials i
to the environment.
For comparison with regulatory licits on discharges, we have chosen the most restrictive maximum permissible concentration (MPC) from 10 CFR 20 for radionuclides in use at the facility.
All discharges reported for this period were below 1% of the applicable MPC at the release point.
A.
FACILITY DESCRIPTION
- 1. Santa Susana Site, SSFL a.
Building'020.
Only atmospheric emissions are released f rom the f acility to unrestricted areas.
No radioactive liquid waste is. released from the facility to unrestricted areas.
Radioactive material handled in unencapsulated f orm in Building 020 during the first half of 1990 was limited to residual radioactive contamination from previous operations with reactor fuel materials.
The major effort conducted at the RIHL during the first half of 1990 continued to involve only I
clean-up and. decontamination of examination cells and support facilities, removal of surplus equipment, and general facility maintenance.
L The distance f rom the point of atmospheric release to the l
nearest site boundary is about 302 meters and is approximately 1900 meters to the nearest of f site structure.
Nearest offsite boundary ground-level concentrations would be lowered by a f actor of at least 20000 under the Pasquill Type B
moderate instability
- category, which is representative of the SSFL site.
i
.i.
W
r Page 2 B. TREATMENT AND HANDLING Waste streams discharged to unrestricted areas are limited, in all cases, to atmospheric 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 (H E P A) filters prior to discharge.
The emissions are sampled for entrained particulate radioactive materials by means of continuous stack emiasion samplers installed at the point of release.
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 for filtering atmospheric emissions are certified to be 1
99.97% ef ficient f or 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 Building 020 main exhaust system performed on November 8,
- 1989, was 99.995%
particulate removal efficiency.
The semiannual average concentration and total radioactivity in atmospheric emissions from NRC licensed facilities
. discharged to unrestricted areas during the first half of 1990 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 ambient air.
Unfiltered ambient air is mixed with the HEPA filtered exhaust air as needed to control differential 1"essures within the various areas of the facility.
Tbis contributes a significant amount of natural radioactivity to the effluent.
It should be noted that ambient air contained more than twice the concentration of long-lived radioactivity then the RIHL effluent during this period.
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AT"OSPEERIC EMISSIONS DISCHARGED TO UNRb mICTED AREAS First Half, 1990 January 1 to June 30, 1990 Approximate Eelease Approzirtate.
Lower-Point
+/-
Sampling Period Total Effluent Limit of Average Error Maximum Observed Radioactivity Flowfate Activity Detection Concentration Estimate
- Concentration Discharged (m /s)
Monitored (UCi/ml)
-(uCi/ml)
(uCi/ml)
(uCi/ml)
(Curies)
Building Release Point' 4
10-15 0.33 x 10 T/020 Stack Exit 10 Alpha 3.0 x 10-16 1.5 x 10~15 0.4 x 10-15 3.6 x
Beta 3.1 x 10-16 8.6 x 10-15 6.0 x 10-15 3.0 x 10-14 2.0 x 10-6 4
Total: 2.3 x 10 Lccal ambjent airborne radioactivity cgcentrations averaged during the reporting period were NOTE: 1.3 x 10~ " uCi/ml alpha and 1.6 x 10~
uCi/ml beta.
S. NRC Regulatory Guide 4.16.
The lower limit of detection was calculated for single measurements, using the method of U.
The average concentrations are based on arithmetic averages of 26 measurements each for alpha and beta activity, including values below the LLD and below the analytical background (negative values).
- -Calculated at the 954 uncertainty level.
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ROCKETDYNE DIVISION EFFLUENT MONITORING REPORT SPECI AL NUCLEAR MATERI AL LICENSE SNM-21 Effluents 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 U. S. NRC Special Nuclear Material License SNM-21, and under State of Calif ornia Radioactive Material License 0015-70.
The only facility operating under the SNM-21 license is identified as Building 020, the Rockwell International Hot Laboratory (RIHL),
at the Santa Susana Field Laboratories site.
i Monitoring of effluent for radioactive materials demonstrates that operations conform to NRC regulations and to license conditions regarding releases of cuch materials to the environment.
For comparison with regulatory limits on discharges, we have chosen the most restrictiv'e maximum l
permissible. concentration (MPC) from 10 CPR 20 for i
radionuclides in use at the facility.
All discharges reported for this period were below 1% of the applicable MPC at the release point.
A.
FACILITY DESCRIPTION
- 1. Santa Susana Site, SSPL
- a. Building 020.
Only atmospheric emissions are released f rom the f acility to unrestricted areas.
No radioactive liquid waste 'is released L
from the-f acility to unrestricted areas.
Radioactive i
material handled in unencapsulated f orm in Building 020 during the first half of 1990 was limited to residual radioactive contamination from previous operations with reactor fuel materials.
The major effort conducted at the RIHL during the first half of 1990 continued to involve caly clean-up and decontamination of examination cells and support facilities, removal of surplus equipment, and general facility maintenance.
The distance f rom the point of atmospheric release to the nearest site boundary is about 302 meters and is i
approximately 1900 meters to the nearest of f site structure.
Nearest of f site boundary ground-level concentrations would i
be lowered by a tactor of at least 20000 under the Pasquill Type B
moderate instability
- category, which is representative of the SSPL site.
l
Page 2 B. TREATMENT AND HANDLING Waste streams discharged to unrestricted areas are limited, in all cases, to atmospheric 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 discharge.
The emissions are sampled for entrained particulate radioactive materials by means of continuous stack emission samplers installed at the point of release.
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 for filtering atmospheric emissions are certified to be 99.97% ef ficient f or removal of 0.3 um diameter particles.
Filtration efficiency increases above and below this particle size.
The result for the most recent in-place tost of the Building-020 main exhaust system performed on November 8,
- 1989, was 99.995%
particulate removal efficiency.
The semiannual-average concentration and total radioactivity in atmospheric emissions from NRC licensed facilities discharged to unrestricted areas during the first half of 1990 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 ambient air.
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.
This contributes a significant amount of natural radioactivity to the effluent.
It should be noted that ambient air contained I
'more than twice the concentration of l ong-li v ed j
radioactivity than the RIHL effluent during this period.
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. i ATMOSPEERIC EMISSIONS DISCHARGED TO UNRESTRICTED AREAS First Half, 1990 January 1 to June 30, 1990 Approximate Release Approximate-Lower Point
+/-
Sampling Period Total Flowgate
. Activity.
Limit of Average Error Maximum Observed Radioactivity' Effluent Detection Concentration Estimate
- Concentration Discharged Building Release Point-(m /s)
Monitored (uCi/ml) ~
(uCi/ml)
(uCi/ml)
(uCi/ml)
(Curies) 3 T/020 Stack Exit 10 Alpha 3.0 x 10-16 1.5 x 10-15 0.4 x 10-15 3.6 x 10-15 0.33 x 104 Beta 3.1 x 10-16 8.6 x 10-15 6.0 x 10-15 3.0 x 10-14 2.0 x 10-6 4
Total: 2.3 x 10 Local amb{ent airborne radioactivity c,gcentrations averaged during the reporting period were NOTE:
1.3 x 10- 3 uti/ml alpha and 1.6 x 10 uCi/ml beta.
The lower limit of detection was calculated for single neasurements, using the method of U. S. NRC Regulatory Guide 4.16.
The average concentrations are based on' arithmetic averages of 26 measurements each for alpha and beta activity, including values below the LLD and below the analytical background (negative values).
- -Calculated at the'95% uncertainty level.
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