ML20246B526
| ML20246B526 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 04/24/1989 |
| From: | Brigham Young University, PROVO, UT |
| To: | |
| Shared Package | |
| ML20246B524 | List: |
| References | |
| NUDOCS 8907070365 | |
| Download: ML20246B526 (7) | |
Text
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x-1 Technical Specifications Ir-77.Researdi Heactxr Bric*== Yourn University 1.
Definitions 1.1. certified operators - A certified operator is an individual authorized by the chartering or licensing organization to carry out the duties and responsibilities associated with the position requiring the certification.
1.2. channel check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. 'Ihis verifica-tion may include cmparison of the channel with other independent channels or methods measuring the same variable.
1.3. confinement - Confinement means a closure on the overall facility ~
i which controls the movement of air into it and out through a controlled path.
1.4. experiment - Any operation, hardware, or target (excluding devices such as detectors, foils, etc.), which is designed to investigate non-routine reactor characteristics or which is intended for irradiation on or in a beam port or irradiation facility and which is not rigidly secured to a core or inner shield structure so as to be a part of their design.
1.5. operable - Operable means a component or system is capable of performing its intended function.
1.6. operating - Opem. ting means a component or system is performing its intended function.
l 1.7. reactor operating
'Ibe reactor is operating whenever it is not secured or shutdown.
1.8. reactor secured - A reactor is secured when:
1.8.1. It contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum available conditions of moderation ard l
reflection.
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1.9. reactor shutdown
'Ihe reactor is shut down if it is subcritical by at least one dollar in the Reference Core Condition arx1 the reactivity worth of all experiments is accounted for.
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'1.10. research reactor - A research reactor is defined as a device o
designed to support a self-sustaining neutron chain reaction for research,
- development, educational, training, or experimental purposes, and which may have provisions for the production of radio-isotopes.
1.11. shall, should and may - The word "shall" is used to denote a-requirement; the word "should" to denote a raemmandation; and the word "may" to denote permission, neither a requirement nor a r+>-. ardation.
2.
Safety Limits.and Limiting Safety System Setting Safety Limit - Not applicable. The reactor shall remain secured.
- 3. -
Limiting conditions for Operation Not applicable. The reactor shall remain secured.
1 4.
Surveillance Requirements Specified surveillance actions shall be performed in accordance with the following schedule.
4.1. -Control and 'afety system.
4.2. Applicability
The reactor facility.
4.2.1. Objective
7b maintain surveillance for potential exposure to radiation.
4.2.2. Specifications
4.2.2.1. TLD Mmaters will b3 checked by the comercial vendor quarterly. The report generated will be reviewed by the Radiation Safety Officer quarterly.
4.2.2.2.
Portable radiation survey instruments will have a channel check semiannually, and calibration annually.
4.2.3. Bases. Periodic quality assurance s u utures should insure confidence that measurements and observations are cvuec-t.
4.3.
Reactor Area.
4.3.1.
Applicability. This specification pertains to the reactor facility.
4.3.2.
Objective. Ib assure the radiatiou safety of the reactor area.
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4.3.3.
Specifications.
4.3.3.1.
S e fire alarm test frequency (NFPA 72d priority s!gnaling systcms) will be on a biannual basis in accordance with NFPA # 73E. Testing will be performed by personel from Physical Facilities.
4.3.3.2.
%e door locks shall be inspected quarterly.
4.3.3.3.
S e shield water level shall be visually inspected l
annually. 21s will be accomplished by removing the metal
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access plate located on top of the shield water tank and placing i
a one foot ruler flush with the top and p rpendicular to the top of the tank and visually checking to insure that the bottom of the ruler is imersed in water. 'Ihis requirement will be void once the plutonium / beryllium source is removed from the reactor.
l 4.3.3.4.
The Radiation Safety Officer shall make a radiation l
survey of the area semiannually, 'Ihis survey will irclude an exposure rate determination as well as a contamination survey.
Expcsure rate will be determined by placing an ionization chamber within two inches of each closed port and recording the resultant exposure in mrem /hr. 'Ibe survey will be conducted using a GM tube with thin window and scanning four one foot square areas. Survey areas will be chosen from the top of the reactor, the side of the reactor and the floor immediately l
adjacent to the reactor.
4.3.3.5.
Two TLD dosimeters shall be placed in the nuclear laboratory and one TID dosimeter shall be placed immediately 1
outside the nuclear facility in order to maintain a record of potential exposure levels inside and immediately adjacent to the facility.
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4.3.4. Basis
'Ihe fuel has been renoved, and the power to the f
reactor has been cut. In addition the beam ports have been locked.
'Ihe only persons allowed unam,nied access to the facility are the Radiation Safety Officer and the Facility Chief. Currently the building housing the reactor is occupied less than five hours per quarter. Under th conditions the rate of exposure would have to be in excess of 200 mrem / hour in order to cause those individuals most heavily exposed, to accumulate more than 1.25 rem / quarter. 'Ihe highest rate of exposure recorded by TLD Ionitors in the reactor facility during 1988 was 23 mrem / quarter. 'Ihe radiation exposure instrunent currently used in surveys is a Victoreen 470 ionization chamber. 'Ihis instrument is capable of detecting exposures of as low l
as 0.1 mrem /hr which is approximately three orders of magnitude less the the exposure rate necessary to produce an overexposure to the most frequent evv'p'nt.
'Ihus it is reasonable to suppose with the l
current static condition of the facility that, first no significant exposure can occur in the facility unless there is physical 3
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manipulation of the Pu/Be source, and second if there were a change in status that change would be readily detectable well below the level at which serious exposure would be anticipated with the current monitoring system.
I 5.
Design Features:
5.1. Reactor
2 e reactor is an L-77 research reactor. The fuel has been removed and shipped off site.
5.2. Reactor Facility: The reactor is located in the Nuclear Tahnratory.
This is a dedicated facility located on the scuttreest portion of the Brigham Young University campus. The building is of wcud.e and masonry I
construction. The beam ports have been locked. Unaw m,vded access is limited to the Radiation Safety Officer and the Reactor Facility Chief.
Any other access must be under the supervision of one of the above two named individuals.
5.3.
Anticipated changes in configuration. Under the Possession Only License the major anticipated configuration change would be the removal of the plutonium / beryllium source. Until the source is renoved the shielding
(
I water will be maintained at a level no less than one foot below the top edge of the shieldirg tank.
6.
Administrative Contro]s:
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6.1. Organization
(see figure 1) 6.1.1.
President. The president is the Chief Administrative Officer responsible for the University. As such he has ultimate responsibility for the operation and management of the nuclear reactor.
6.1.2.
Executive Vice President (EVP). The Executive Vice President reports directly to the President and has been given direct responsibility for the reactor.
6.1.3.
Radiation Safety Officer. The Radiation Safety Officer (RSO) is appointed by the Executive Vice President with the advice of the Chairman of the Radiation Safety Committee. He is responsible to the EVP for the day-to-day administration of the radiation safety pgam arxi serves as the Secretary of the Radiation Safety Committee. He prepares the University's Radiation Safety Manual. The Radiat. ion Safety Officer is also responsible for preparirxJ, for the signature of the Chairman of the Radiation Safety Committee, reports of all reportable occurrences to the awwpriate regulatory agency and for ensuring that appropriate follow up action is taken.
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b 6.1.4.
Training Requirements. At least one raember of the Radiation Safety committee will have a PhD in physics with experience in Nuclear Physics. The Radiation Safety Officer will have a minimum of three years experience in working with radiation and radiation safety.
6.1.5.
Radiation Safety Commi*. tee. The members of this cc mittee are appointed by the Executive Vice President. This committee shall be composed of four members, to. include: the Radiation Safety Officer, a faculty rulur from the Itlysics Department, a faculty member from the college of Biologicd Science, and a ruuber from the Campus Safety Office. The Radiation Safety Committee (PSC) will meet quarterly. 3 of 4 ruduts will constitute a quorum. The minutes will be recorded and sent to the committee h *s.
"he minutes will be read and approved at the start of each meeting. The RSC repcrts directly to the Executive Vice President.
The Radiation Safety Committee shall have both review and audit functions with regarti to the Reactor Facility. The RSC will advise the Reactor Administrator as well as level one management on all matters pertaining to reactor facility safety.
6.1.5.1.
Any changes in equipnent, sucslures, or facilities will be reviewed by the RSC.
6.1.5.2.
Audit Function: The records of safety surveys and deficiency reports will be examined by the Radiation Safety Committee. Audits will be perfomed on an annual basis.
6.1.5.3.
The RSC will review any changes in security plans and surveillance performed in compliance with technical specifications. These elements will also be reviewed by the Radiation Safety Officer.
6.2.
Required Actions:
6.2.1.
Action to be taken in the event of an occtures.e defined in Section 6.3.2.1.
6.2.1.1.
Corrective action shall be taken to return conditions to nomal.
6.2.1.2.
All rmch ooatutsaxs shall be promptly reported to the Invel 2 authority or designated alternates.
6.2.1.3.
All such occurrences including action taken to prevent or reduce the probability of a rectutum shall be reviewed by the Radiation Safety Cammittee.
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s.
'6.3.
Reports. All written reput.s shall be sent within the g h ibed interval to the NRC, Washington, D.C. 20555, Attention:. th'mant Control ~
Desk, with a copy to the Regional Administrator, Region IV.
6.3.1.
Operating Reports. Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be sutstitted to the agavsiate NRC office by March 31 of the subsequent year. :'lhe following information will be included in the report.
6.3.1.1.,
Tabulation of major preventive and uaractive maintenance operations having safety significance.
6.3.1.2.
Tabulation of major changes in the reactor facility s uc.mdares.
6.3.1.3.
'Ibe results of any environmental surveys performed outside the facility.
6.3.1.4.
A sumary of radiation exposures received by facility peumcausi and visitors in any one year including the dates and times of significant exposures (above 500 mrem).
6.3.1.5.
A sunnary of any effluents or discharges from the reactor facility.
6.3.2. Special Reports. Special reports which may be required by the NRC shall be sutznitted within the time period specified for each report.
6.3.2.1.
Prmpt Notification with Written Fbilow up. 'Ibe types of events listed below shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mailgram, or facsimile transmission to the Director of NRC Region IV or his designated representative no later than the first work day following the event, with a written follow up report within-two weeks. Information provided shall contain narrative material to provide empleted explanation of the circtmsus surrounding the event.
6.3.2.1.1.
Unanticipated releases of radioactivity to the environment exceeding 500 times the limits specified for such materials in Appendix B, Table II of 10 CPR part 20.
6.3.2.1.2.
Exposure of pen w ual exceeding the limits as stated in 10 CPR 20.403 (b) 1.
6.3.2.1.3.
Damage to, or theft of the sealed source.
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!l 6.3.3. Reports Within 30 Days. 'Ihe types of events listed below shall be reported to the Director of NRC Region IV or his designated i
representative within 30 days of their occurrence.
6.3.3.1.
Permanent changes in the facility organization structure.
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6.3.3.2.
An observed inadequacy in the implementation of I
administrative or procedural controls such that the inadequacy causes or could have caused an unsafe condition with regards to i
reactor maintenance.
6.4. Records
Records of the following activities shall be maintained aM retained for the period specified below. The records may be in the form of logs, data sheets, or other suitable forms. 'Ihe required information may be contained in single, or multiple records, or a combination thereof.
6.4.1.
Records to be Retained for a Period of at least five years.
6.4.1.1.
Normal reactor facility operations.
6.4.1.2.
Principal maintenance operations.
6.4.1.3.
Reportable occurrences.
6.4.1.4.
Surveillance activities required by the Technical Specifications.
6.4.1.5.
Reactor facility radiation and contamination surveys where required by applicable regulations.
6.4.1.6.
Special Nuclear Material inventories, receipts, and shipmnts.
6.4.1.7.
Approved changes in operating procedures.
6.4.1.8.
Records of meeting and audit tuputts of the Radiation Safety Committee.
6.4.1.9.
Sealed source leak test results.
6.4.2.
Records to be Retained for Five Years or for the Lifetine of i
the Reactor Facility whichever is Greater (Note: Annual suputLs may be used where applicable as records in this section).
1 6.4.2.1.
Gaseous an:1 liquid radioactive effluents released to the environment.
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