ML20063B899
| ML20063B899 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 01/27/1994 |
| From: | Oregon State University, CORVALLIS, OR |
| To: | |
| Shared Package | |
| ML20063B898 | List: |
| References | |
| NUDOCS 9402030152 | |
| Download: ML20063B899 (6) | |
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Attachment B .)
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PDR ADOCK 05000243 :1 P PDR ((
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i 3.6 RADIATION MONITORING SYSTEM i
3.6.1 Radiation Monitorina Eauioment ;
Acolicability. This specification applies to the radiation monitoring information which must be available to the reactor operator during reactor operation.
Obiective. The objective is to assure that sufficient radiation monitoring information is available to the opertor to assure safe operation of the reactor.
Soecification. The reactor shall not be operated unless the radiation monitoring l channels listed in the following table are operable. Each channel shall have a
! readout in the control room and be capable of sounding an audible alarm which
! can be heard in the reactor control room.
Radiation Monitoring Channels
- Number l Area Radiation Monitor 1 Continuous Air Particulate Radiation Monitor 1 l Exhaust Gas Radiation Monitor 1 i
l Exhaust Particulate Radiation Monitor 1 t When maintenance to the radiation monitoring channels I is required, the intent of this specification will be satis-
! fied if they are replaced with portable instruments of appropriate sensitivity having their own alarms, or which shall be kept under visual observation.
Basis. The radiation monitors provide information to operating personnel regarding routine releases of radioactivity and any impending or existing danger from radiation. Their operation will provide sufficient time to evacuate the facility or take the necessary steps to prevent the spread of radioactivity to the surroundings.
l 3.6.2 Radiation Release Limits l Acolicabilitv. This specification applies to the release rate of argon-41 from the {
l Oregon State TRIGA reactor facility.
Obiective. The objective is to ensure that the concentration of the argon-41 in the unrestricted areas is consistently well below the applicable effluent concen-tration value in 10 CFR 20.
I Specification. The annual average concentration of argon-41 discharged into the unrestricted area shall not exceed 4 x 10-8 microcuries per milliliter at the point of discharge.
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'. I Basis, if argon-41 is continuously discharged at 4 x 10 4 Ci/mi, calculations using the current guidance show that the maximum annual average ground concentration of argon-41 in unrestricted areas would be only 3% of the applicable effluent concentration value of 1 x 10~8pCi/ml found in 10 CFR 20. l Consequently, the annual total effective dose equivalent to an individual exposed to this concentration would be less than 3 mrem. This is significantly !
less than the annual public dose limit of 100 mrem. Similarly, if argon-41 is discharged at 4 x 10-epCi/ml under the worst-case short-term weather condi-tions, the maximum total effective dose equivalent rate would be less than 0.02 mrem /h. Therefore, a person exposed under these conditions would receive a dose much less than the public limit of 2 mrem in one hour.
3.7 ENGINEERED SAFETY FEATURES 3.7.1 Ventilation System Acolicability. This specification applies to the operation of the facility ventila-tion system.
Obiective. The objective is to assure that the ventilation system is in operation to mitigate the consequences of possible releases of radioactive materials resulting from reactor operation.
Specification. The reactor shall not be operated unless the facility ventilation system is operating. In the event of a substantial release of airborne radioactiv-ity, the ventilation system will be secured automatically.
Basis. During normal operation of the ventilation system, the annual average ground concentration of argon-41 in unrestricted areas is well below the applicable effluent concentration limit in 10 CFR 20. In addition, the worst-case maximum total effective dose equivalent rate is well below the limit for individu-l al members of the public. In the event of a substantial release of airborne radioactive material, the ventilation system will be secured automatically.
Therefore, limiting the operation of the reactor to only those items when the ventilation system is operating ensures the maximum designed control over releases of airborne radioactive material. 1 3.7.2 Reactor Pool Water.
Acolicabilitv. This specification applies to the level and bulk water temperature-of the reactor pool.
Obiective. The objective is to assure that there is an adequate amount of water in the reactor tank for fuel cooling and shielding purposes, and that the bulk temperature of the reactor pool water remains sufficiently low to guarantee reactor tank integrity.
Specification. The reactor shall not be operated if:
- a. The pool water level is less than 14 feet above the core.
- b. The bulk pool water temperature exceeds 120 F (49 C).
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i Basis. The minimum height of 14 feet of water above the core guarantees that there is sufficient water for effective cooling of the fuel and that the radiation levels at the top of the reactor are within acceptable levels (SAR). The bulk water temperature limit is necessary, according to_the reactor manufacturer, to ensure that the aluminum reactor tank maintains its integrity and is not degrad-ed.
3.8 LIMITATIONS ON EXPERIMENTS Acolicability. This specification applies to experiments installed in the reactor and its experimental f acilities.
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Obiective. The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.
Specifications. The reactor shall not be operated unless the following condi-tions governing experiments exist:
- a. Non-secured experiments shall have reactivity worths less than 1 dollar.
- b. The reactivity worth of any sing!c experiment will be less than 2.55 l dollars.
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- c. Total experiment worth of all experiments will not exceed 3.00 dollars.
I d. Explosive materials, such as gunpowder, TNT, nitroglycerin, or PETN, in l quantities greater than 25 milligrams shall not be irradiated in the reactor or experimental facilities. Explosive materials in quantities less than 25 milligrams may be irradiated provided the pressure produced upon detona- ,
tion ci the explosiv's has been calculated and/or experimentally demon .
strated to be less tnan the design pressure of the container. EXCEPTION:
Explosive materials not exceeding 0.014 lbs. equivalent of TNT may be irradiated in the laboratory area adjacent to the end of the OSTR tangen-tial beamport for the purpose of neutron radiography.
- e. Where the possibility exists that the failure of an experiment (except fueled experiments) under (1) normal operating conditions of the experi-ment or reactor, (2) credible accident conditions in the reactor, or (3) possible accident conditions in the experiment, could release radioactive gases or aerosols to the reactor bay or the unrestricted area, the quantity and type of materialin the experiment shall be limited such that the airborne concentration of radioactivity in the reactor bay and the unre-stricted area will not exceed the applicable regulatory concentration limits in 10 CFR 20, assuming 100% of the gases or aerosols escape from the j experiment.
- f. In calculations pursuant to e., above, the following assumptions shall be l used:
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- 5. A brief description, including.a summary of the safety evaluations of
! changes in the facility or in procedures and of tests and experiments I carried *st pursuant to Section 50.59 of 10 CFR Part 50.
- 6. A summary of the nature and amount of rsdioactive effluents re-leased or discharged to the environs beyond thr effective control of '
the licensee as measured at or prior to the point of such release or -
discharge.
Liauid Waste (summarized on a monthly basis)
(a) Radioactivity discharged during the reporting period (1) Total estimated quantity of radioactivity released (in - l curies). .. ;
(2) An estimation of the specific activity for each detectable radionuclide present if the specific activity of the released material after dilution is greater than:1 x 10-7 micro . ,
curies /ml.
(3) Summarv of the total release in curies of.each nuclide- ..
determined in (2) above for the reporting period based on !
representative isotopic analysis. ,
(4) Estimated average concentration of the released radio -
active material at the point of release for each month in ;
which a release occurs, in terms of microcuries/mi and - '
fraction of the applicable concentration in 10 CFR 20.
(b) Total volume (in gallons)'of effluent water (including diluent) ,
released during each period of release.
Gaseous Waste (summarized on a monthly basis)-
(a) Radioactive discharged during the reporting period (in curies) -
(1) Total estimated quantity of radioactivity released (in l curies) determined by an appropriate. sampling and count- .
ing method.
(2) Total estimated quantity (in curies) of argon-41 released during the reporting period based on data from an appro-j priate monitoring l system.
(3) Estimated average atmospheric diluted concentration of.-
l argon-41 at the point of release for the reporting period,'
in terms of microcuries/mi and fraction of the' applicable -
effluent concentration value.
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(4) Total estimated quantity of radioactivity in particulate form with half lives greater than eight days (in curies) released during the reporting period as determined by an appropriate particulate monitoring system.
(5) Average concentration of radioactive particulates with half lives greater than eight days released in micro-curies /ml during the reporting period.
(6) An estimate of the average concentration of other signifi-cant radionuclides present in the gaseous effluent dis-charge in terms of microcuries/mi and fraction of the applicable effluent concentration value for the reporting period if the estimated release is greater than 20% of the applicable effluent concentration.
Solid Waste (summarized on an annual basis)
(a) Total amount of sold waste packaged (in cubic feet).
(b) Total activity in solid waste (in curies)
(c) The dates of shipment and disposition (if shipped off site)
- 7. An annual summary of the radiation exposure received by facility l personnel and visitors in terms of the average radiation exposure per individual and greatest exposure per individual in the two groups.
- Each significant exposure in excess of the limits of 10 CFR 20 shall j be reported including the time and date of the exposure as well as i the name of the individual and the circumstances leading up to the exposure.
- 8. An annual summary of the radiation levels and levels of contam-ination observed during routine surveys performed at the facility in
- terms of the average and highest levels.
- 9. An annual summary of any environmental surveys performed outside the facility.
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