ML20244D000
| ML20244D000 | |
| Person / Time | |
|---|---|
| Site: | 07000025 |
| Issue date: | 12/31/1988 |
| From: | Remley M ROCKWELL INTERNATIONAL CORP. |
| To: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 89RC-01028, 89RC-1028, NUDOCS 8904210094 | |
| Download: ML20244D000 (7) | |
Text
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l Rocketdyne Division REGION V I
Rockwell international Corporation Rockwell 6633 Canoga Avenue Canoga Park, California 91304 InternadOn81 Telex: 698478
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ROCKETDYN CNPK l
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January 19, 1989 In reply refer to 89EC-0102u Mr. John B.
Martin, Administrator Region V Office U.
S.
Nuclear Regulatory Commission 1450 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 for the period f rom July 1 to December 31, 1988.
Two copies of the report are enclosed f or your inf ormation and use.
Sincerely
- ours, M.
E.
Remley, Director Nuclear Safety & Licensing Enclosures as noted (2 copies) cc: w/ enclosure Director, Inspection and Enforcement, U.
S.
Nuclear Regulatory Commission, Washington, D.
C.
20555
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8904210094 881231 PDR ADOCK 07000025 C
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ROCKOYNE DIVISION EFFLUENT MO$0 RING REPORT a
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 R & NRC Special Nuclear Material License SNM-21, and under State of California 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 to license conoitions regarding releases of such materials to the environment For comparison with regulatory limits i
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.
A.
FACILITY DESCRIPTION 1.
Santa Susana 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 i
examination of reactor components.
Only atmospheric emissions are released f rom the f acility to unrestricted areas.
No radioactive liquid waste is released f rom the facility 'to unrestricted areas.
The atmospheric emissions may contain particulate material, as well as radioactive gases, depending on the operations being perf ormed and the history of the irradiated fuel or other material being processei The chemical form 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 unencapsulated form in Building 020 during the last half of 1988 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 last half of 1988 involved clean-up and decontamination of examination cells, removal of surplus equipment, and general f acility maintenance.
The I
distance from the point of atmospheric release to the nearest site boundary is about 302 meters and is
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O O
approximately 1900 meters to the nearest offsite structure.
L Nearest ' of f site boundary ground-level concentrations would be lowered by a.f actor of at least 20000 under the Pasquill 3.
Type. B : moderate instability
- category, which is
. representative of the'SSFL site.
Bi. TREATMENT AND HANDLING Waste' streams discharged to unrestricted areas are limited,.
'inTall 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-ef ficiency.' pa'r ticulate air (BEPA) 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 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
~f or filtering ' gaseous emissions are certified to be 99.97%.
efficient for removal of
- 0. 3 tm 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'17, 1988, was 99.996% particulate removal efficiency.
The semiannual average concentration' and total radioactivity in gaseous emissions f rom NRC licensed facilities discharged
' to unrestricted areas during the last-half of 1988 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 facility.
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ROCKEgNE DIVISION EFFLUENT MONgRING REPORT SPtrIAL NUCLEAR MATERIAL LICENFE SNM-21 l
f Effluents which may contain radioactive material are generated at Rocketdyne facilities as the result of operations performed under contract to the U. S. DOE, under R & NRC Special Nuclear Material License SNM-21, and under State of California 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 to license conditions regarding releases of such materials to the environment For comparison with regulatory limits 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 f or this period were below 1% of the applicable MPC.
A.
FACILITY DESCRIPTION 1.
Santa Susana Site, SSFL a.
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 unrestricted areas.
No radioactive liquid waste is released f rom the f acility to unrestricted areas.
The atmospheric emissions may contain particulate material, as well as radioactive gases, depending on the operations being perf ormed and the history of the irradiated fuel or other material being processed.
The chemical form 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 unencapsulated form in Building 020 during the last half of 1988 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 contautination f rom the previous SEFOR and EBR II reactor fuel decladding operations.
The major effort conducted at the RIHL during the last half of 1988 involved clean-up and decontamination of examination cells,. removal of surplus equipment, and general f acility mMntenance.
The distance from the point of atmospheric release to the nearest site boundary is about 302 meters and is
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.y approximate 1y'1900 meters ~to the nearest offsite structure.
Nearest ' of f site - 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.
B.
TREATMENT AND_ HANDLING Waste streams discharged to unrestricted' areas are limited,,
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 discl.arge.
The emissions are sampled for entrained
-particulate radioactive materials by means of continuous stack emission samplers installed at the point of releast In addition, the continuous stack exhaust monitor installed at Bui.1 ding 020.has an automatic ' alarm capability in the event of a release of radioactivity.
The HEPA filters used for filtering gaseous emissions are certified to be 99.97%
efficient for removal of
- 0. 3 um diameter particles.
viltration 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 17 ',
1988, was 99.996% particulate removal ef ficiency. -
The semiannual average concentration and total radioactivity in gaseous emissions f rom NRC licensed facilities discharged to unrestricted areas during the last half of 1988 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 r adioactiv ity in the ambient air.
Unfiltered ambient air is mixed with the HEPA filtered
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i exhaust air as needed to control differential pressures within the various areas of the facility.
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