ML20012D847

Effluent Monitoring Rept for Jul-Dec 1989

ML20012D847
Person / Time
Site:	07000025
Issue date:	12/31/1989
From:	Tuttle R ROCKWELL INTERNATIONAL CORP.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 9003280468
Download: ML20012D847 (7)

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Rocheldyne Division Rockwell Internettonal Corporation ROCkWe.ll-i 6633 Canoga Avenue Canoga Park, Cahtornia 91303 Inteinational Telex 698478 b

b b.' b ROCKETDYN CNPK '

i February-9, 1990 In reply refer'to 90RC-02174-

'Mr. John B.

Martin,. Administrator Region V Office-U.

S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 Walnut Creek, Calif ornia 94596-5368

Subject:

Effluent ~ Monitoring Report As required in 10 CFR 70.59(a),

we are submitting the Ef fluen_t ? Monitoring ' Report : f or activities conducted at the.

Roc _ketdyneLDivision ofLRockwell International under Special

. Nuclear : Materials License SNM-21 for_ the period f rom July 1 to December 31, 1989.

Two copies of the report are enclosed for your information and use.

-Sincerely yours, l

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>_wA R. : J. Tuttle, Manager-Radiation and. Nuclear Safety l

Enclosures as noted (2 copies) cc w/ enclosure l

Director, Inspection and Enforcement, U.

S.

Nuclear l

Regulatory Commission, Washington, D.

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-ROCKETDYNE DIVISION EFFLUENT MONITORING REPORT SPECIAL NUCLEAR-MATERIAL LICENSE SNM !

p Ef fluents..which may contain radioactive ' material are 4

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 California Radioactive Material License 0015-70.

-The-only f acility operating under the SNM-21 license is identified as Building 020, the Rockwell' Internationt.1 Hot Laboratory (RIHL),

at the Santa Susana Field Laboratories site.

t Monitoring of' effluent for radioactive materials-demonstrates that operations conform to NRC regulations ~and to license conditions regarding releases of such materials j

p to the environment.

For comparison with regulatory 1imits ll H

on discharges, we have chosen the most restrictive maximum l-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 f rom-the facility to unrestricted areas.

Radioactive-material handled in unencapsulated form in Building 020 during the last half of - 1989 - was limited to residual-radioactive contamination from previous operations with reactor fuel materials.

The major effort conducted at the RIHL during the last half of 1989 continued to involve only

. clean-up and decontamination of examination cells, removal of surplus equipment, and general f acility maintenance.

.The distance f rom the point of atmospheric release to the nearest site boundary is about 302 meters and is approximately 1900 meters to the nearest offsite structure.

Nearest offsite boundary ground-level concentrations would be lowered by a factor of at least 20000 under the Pasquill Type B moderate instability

category, which is representative of the SSFL site.

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TREATMENT' AND HANDLING Waste. streams discharged to unrestricted areas are limited,.

j in all cases, to atmospheric emissions.

1 m-The levels of radioactivity contained in all atmospheric

.I emissions are reduced to the lowest reasonably achievable -

I 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-1 particulate. radioactive materials by means of continuous-stack emission samplers installed at the point. of release.

1 4

In addition, the continuous stack ~ exhaust monitor installed i

at Building 020. has an. automatic alarm capability in the event of-a release of-radioactivity.

The HEPA filters used j

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 test of the Bui'1 ding 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-last 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, l

which includes. naturally occurring radioactivity in-the l

ambient air.

Unfiltered ambient air is mixed with the HEPA filtered exhaust air as needed to control -diff erential pressures within the various areas of the facility.

This contributes l

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 than the RIHL effluent during this period.

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ATMOSPHERIC EMISSIONS DISCHARGED TO UNRESTRICTED AREAS.

LAST HALF, 1989 July 1 to December 31, 1989 Approximate Release Approximate

. Lower Point:

+/--

Sampling Period

' Total.

Effluent Limit of Average Error Maximum Observed. Radioactivity Flog /s) ate Activity Detection. Concentration Estimate *'

Concentration'-

Discharged Building Release Point (m

Monitored (uCi/ml)

(uCJ/ml):

(uCi/ml)

(uCi/ml)

(Curies)

T/020 Stack Erit 10 Alpha

. 3.0 x 10-16 0.5 x 10-15 0.4 x 10-15 1.3 x 10-15 0.12 x ' 10*

Beta 3.1 x 10-16 1.1 x 10-14 6.0 x 10-15 3.4 x 10-14

'A.7 x 10-6 Total:'2.8 x 104 NOTE: Local ambgnt airborne radioactivity cgrcentrations' averaged for the reporting period were 1.7 x 10-uCi/ml alpha and 2.8 x 10- 4 uC1/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).

• -Calculated at the 95% uncertainty level.

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ROCKETDYNE DIVISION EFFLUENT MONITORING' REPORT SPECI AL NUCLEARL MATERI AL LICENSEL SNM-21 Ef fluents' which may contain radioactive - material-are~

. generated at.Rocketdyne facilities as the result of I

operations perf ormed under contract to the U. S. DOE, under U. S. 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.

ton 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 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 f rom. the facility to unrestricted areas.

Radioactive material handled in unencapsulated form in Building 020 during the last half of 1989 was limited to residual radioactive contamination from previous operations with

-reactor fuel materials.

The major effort conducted at the RIHL during the last half of 1989 continued to involve only clean-up and decontamination of examination cells, removal of surplus equipment, and general f acility maintenance.

The distance f rom the point of atmospheric release to the nearest site boundary is about 302 meters and is approximately 1900 meters to the nearest of fsite structure.

Nearest. off site boundary ground-level concentrations would be lowered by a factor of at least 20000 under the Pasquill Type B. moderate instability

category, which is representative of the SSFL site.

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' B.= TREATMENT l AND HANDLING

- Waste streams discharged to unrestricted areas are limited, ini-all cases,' to atmospheric emissions.

The levels of-radioactivity contained in all atmospheric emissions are reduced to the lowest reasonably > achievable values by passing t.he_ 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 emission samplers 1 installed at the point of release.

' In addition, the continuous stack exhaust monitor installed l

at Building 020.has an automatic alarm capability in the L

- 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 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.last half cf 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 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.

This 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 than the RIHL effluent during this period.

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ATMOSPEERIC EMISSIONS DISCHARGED TO UNRES**RICTED AREAS LAST. HALF, 1989 July'l to December 31, 1989 Approximate ~

Release

~ Total.

Approximate Lower Point

+/-

_ Sampling Period

~

Effluent Limit of Average Error

. Maximum Observed.. Radioactivity :

Flowg/s) ate Activicy. Detection Concentration' Estimate

• Concentration

Discharged Building Release Point (m

Monitored (UCi/ml)

(uC1/ml)

(uCi/ml)

(uCi/ml)-

(Curies).

T/020 Stack Exit 10 Alpha 3.0. x 10-16 0.5 x 10-1

'O.4 x 10-15' 1.3 x.10-15 0.12 'x 104' Beta

- 3.1 x 10-16 1.1 x 10-14 6.0 x 10-15 3,4

,39-14' 2.7f x 10-6 :

Total: 2.8'x 104' Local ambgnt airborne radioactivity.cgcentrations averaged for the reporting period were NOTE:

1.7 x 10~

uCi/ml alpha and 2.8 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, cincluding values below the LLD and below the analytical background (negative values).

• -Calculated at the 95% uncertainty level.

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