ML19324B623
| ML19324B623 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 11/01/1989 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19324B621 | List: |
| References | |
| R-109-A-002, R-109-A-2, NUDOCS 8911070197 | |
| Download: ML19324B623 (13) | |
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UNITED sTATss j
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NUCLEAR REGULATORY COMMISSION c-j K
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_BRIGHAM YOUNG UNIVERSITY DOCKET NO d 262 i
AMENDMEJLTAFACJLELLICMSE
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Amendment flo. 2 License No. R-109 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
i A.
The applir.ation for amenoment filed by Brigham Young University i
(the licensee), dated May 22, 1987, as supplemented on September 29, 1987, March 17, 1988, April 24, 1969, and June 12, 1989, complies with the standards and requirerents of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations as set forth in 10 CFR Chapter 18 j
i B.
The facility will be maintained in conformity with the application, the provisions of the Act, and the regulations of the Comission; j
C.
There is reasonable assurance:
(1) that the activities authorized by this atendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be t
conducted in compliance with the Comission's regulations set forth l
in 10 CFR Chapter it t
D.
The issuance of this amendrent will not be inimical to the comon defense and security or to the health and safety of the public; i
E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirenents have been satisfiedt and
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r F.
Publication of notice of this amendment is not required since it does not involve a significant hazards consideration nor anendment of a l
license of the type described in 10 CFR Section 2.106(a)(2).
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2.
Facility License No. R-109 is hereby amended in its entirety to read as follows:
l A.
This license applies to the homogeneous solution research reactor, i
designated as the Atomics International Type L-77, owned by Brigham Young University (hereinaf ter, 'the-licensee"), and l
located on the campus in Provo, Utah, and described in the licensee's application to possession-only status conversion f
dated May 22, 1987 as supplemented on September 29, 1987, March 17 1988, April 24, 1989, and June 12,1989 (hereinaf ter 'the application").
t B.
Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Brigham Young University:
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1.
Pursuant to Section 104c of the Act and 10 CFR Part 50,
' Domestic Licensing of Production and Utilization i
Facilities," to possess, but not operate, the facility in accordance with the procedures and limitations set forth in this license.
2.
Pursuant to the tct and 10 CFR Part 70, ' Domestic Licensing of $pecial Nuclear Material
- to possess a l
0.5 curie (15 grams) plutonium-beryllIumneutronsource.
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3.
Pursuant to the Act and 10 CFR Part 30, " Rules of General l
Applicability to Domestic Licensing of Byproduct l
Material " to possess, but not to separate, such byprMuct i
material as may have been produced by operation of the
- reactor, t
C.
This license shall be deemed to contain and is subject to the i
conditions specified in Parts 20, 30, 50, 51, 55 70 and 73 of 10 CFR Chapter 1, to all applicable provisions of the Act, and i
to the rules, regulations and orders of the Commission now or l
hereafter in effect, and to the additional conditions specified below:
1.
Operation The licensee shall not operate the reactor nor install fuel or experimenti, within the reactor core or core area.
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 2The licensee shall n.re hereby incorporated in a
the license.
aintain the facility in accordance with the Technical Specifications.
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i 3.
This license amendment is effective as of the date of issuance.
D.
The license shall expire on August 24, 2007.
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FOR THE NUCLEAR REGULATORY COMMIS$10N Gary. Holahan Acting Directo Divis pn of Reactor Projects - !!, IV, V and Special Projects Office of Nuclear Reactor Regulation j
Enclosure:
i Appendix A Technical Specifications Date of Issuance:
November 1, 1989 i
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i APPENDIX A i
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TECHNICAL SPECIFICATIONS l
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FOR THE l
L.77 NUCLEAR REACTO,R i
FACILITY LICENSE NO. R-109 BRIGHAM YOUNG UNIVERSITY i
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June 1989
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Included in this document are the technical specifications and the basis for I
technical specifications. These basis, which provide technical support for the individual technical specifications, are included for information purposes only. They are not part of the technical specifications and do not constitute limitations or requirements to which the licensee must adhere.
i 1.
Definitions j
3.1. certified operators - A certified operator is an individual j
authorized by the chartering or licensing organisation to carry out the duties and responsibilities associated with the po6ition requiring the ce r tif ica t ion.
[r 1.2. channel - A channel is the combination of sensor line, amplifier.
and output devices which are connected for the purpose of measuring the value of a parameter.
1.3. channel check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior.
This verifica-tion may include comparison of the channel with other independent channels or methods measuring the same variable.
1.4. channel calibration - Calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values i
of the parameter which the channel measures.
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1.5. operable - Operable means a component or system is capable of performing its intended fonction.
1.6. operating - Operating means a component or system is performing its intended funct ion.
1.7. reactor operating - The 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 optinua available conditions of moderation and reflection.
l 1.9. research reactor - A research reactor is defined as a device designed to support a self-sustaining neutron chain reaction for research, development. educational, training, or experimental purposes, and which i
any have provisions for the production of radio-isotopes.
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1 Amendment No. 2
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i 1.10. shall, should and may - The word "shall" is used to denote a requirement; the word "should" to denote e recommendation; and the word i
"may" to denote permission, neither a requirement nor a recommendation.
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2.
Safety Limits and Limiting Safety System Setting Safety Limit - Ik,t applicable. The reactor shall remain secured.
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3.
Limiting Conditions for Operation Bot applicable. The reactor shall remain secured.
4 Surveillance keguirements Specified surveillance actions shall be performed in accordance with the following schedule.
I 4.1.
Control and safety system.
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4.2. Applicability
The reactor facility.
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4.2.1. Objective
To me.intain surveillance for potential exposure to rediation.
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4.2.2. Specifications
4.2.2.1. TLD dosimeters shall be checked by the commercial vender quarterly. The report generated shall be reviewed by the Radiation Safety Of ficer (R50) guarterly.
t 4.2.2.2.
Portable radiation survey instruments shall have a semiannual calibration.
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4.2.3. Bases. Periodic quality assurance procedures should insure l
confidence that measurements and observations are correct.
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4.3.
Reactor Area.
t 4.3.1.
Applicability. This si,ecification pertains to the reactor facility.
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4.3.2.
Objective. To aerure the radiation safety of the reactor area.
4.3.3.
Specifications.
i 4.3.3.1.
The fire alara test frequency (NFPA 72d priority signaling systems) shall be on a biannual basis in accordance r
2 Amenoment No. 2 g
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l with NFPA i 73E. Testing shall be performed by personnel fres l
Physical Facilities.
4.3.3.2.
The door locks and alarm systems shall be checked l
quart erly.
l 4.3.3.3.
The shield water level shall be visually inspected i
annually.
This requirement aball be void once the i
plutonium / beryllium source is removed from the reactor.
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4.3.3.4 The RSO shall conduct an annual visual inspection of the reactor structure for water leakage. This requirement i
shall persist as long as the shield tank is filled with water.
i Any leakage, corrosion, or damage shall be corrected.
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4.3.3.5.
The Radiation safety of f.icer or his designated representative shall make a radiation survey of the area semisanus11y.
i 4.3.3.6.
Two 7LD dosiosters shall be placed in the nuclear laboratory and one TLD dosiaster shall be placed immediately i
outside the nuclest f acility in order to maintain a record of potential exposure levels inside and immediately adjacent to i
the f acility.
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4.3.4. Basis
The fvel has been removed, and the power to the reactor has been cut. The only persons allowed unaccompanied access l
to the f acility are tt.e Radiation Safety Officer and the Facility
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Chief. Currently the building housing the reactor is occupied less i
than five hours per quarter. Under these conditions the rate of i
expceura would have to be in excess of 200 ares / hour in order to e
cause those individuals most heavily exposed, to accumulate more than
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1.25 res/ quarter. The highest rate of exposure recorded by TLD sonitors in the reactor f acility during 1988 was 23 area / quarter.
The radiation exposure instrument currently used in surveys is a Victcreen 470 ionisation chamber. This instrument is capable of detecting exposures of as low as 0.1 area /hr which is approximately three orders of magnitude less than the exposure rate necessary to produce an overexposure to the most frequent occupant. Thus it is reasonable to suppose with the current static condition of the f acility that first. no significant exposure can occur in the f acility unless there is physical manipulation of the Pu/Se source, i
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.
5.
Design Featurest
5.1. Resctor
The reactor is an L-77 research reactor. The fuel has been removed and shipped of f site and the power to the reactor has been cut.
The beam ports shall be locked except upon approval of the Raciat wn Saf ety Amendment No. 2 i
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l Committee (RSC) to conduct measurements pursuant to decommissioning activities.
5.2. Reactor Facility: The reactor is located in the Nuclear Laboratory.
l This is a dedicated fecility located on the southwest portion of the Brigham Young University campus. The building is of concrete and masonry I
construttion.
Unaccompanied access is limited to the Radiation Safety i
Officer tad the Resctor Facility Chief or University Police. Any other access shall be under the supervision of the RSO or the Facility Chief.
l The doors shall remain locked sad the alarm engaged whenever there are no l
occupants in the building.
5.3.
Anticipated changes in configuration: Under the Possession Only License the major anticipated configuration change may be the removal of i
the plutonium / beryllium source. Until the source is removed, the shielding unter shall be maintained at a level no less than one foot below the top edge of the shielding tank.
6.
Administrative Controle 6.1.
Organisations (see figure 1) 6.1.1.
President. The president is the Chief Administrative Officer i
responsible for the University. As such he shall have ultimate responsibility for the operation and management of the nuclear i
reactor.
6.1.2.
Executive Vice President (EVP). The Executive Vice President reports directly to the President and shall have direct l
responsibility for the reactor.
i 6.1.3.
Radiation Safety Officer. The Radiation Safety Officer (RS0) shall be appointed by the Executive Vice President with the advice of the Chairman of the Radiation Safety Committee. He shall be responsible to the EVP for the day-to-day administration of the radiation safety program and serves as the Secretary of the Radiation Safety Committee. Be prepares the University's Radiation Safety Manual. The Radiation Safety Of ficer shall also be responsible for preparing, for the signature of the Chairman of the Radiation Safety Committee, reports of all reportable occurrences to the appropriate regulatory agency and for ensuring that appropriate follow up action is taken.
l 6.1.4.
Training Requirements. At least one member of the Radiation Safety committee shall have a PhD in physics. The Radiation Safety Of ficer shall have a minimum of one year experience in working with radiation and radiation safety.
6.1.5.
Radiation Safety Commit tee. The members of this commit tee shall be appointed by the Executive Vice Presideut. This c ommit t e e r
shall be composeo of four members, to includes the Radiation Safety Of ficer, a f aculty member from the Physics Department, a f aculty member from the College of Biological Science, and a member from toe 4
Amendment No. 2
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Campus Safety Office. The Radiation Safety Consittee (RSC) shall meet quarterly. 3 of 4 members shall constitute a quorum. The misstes shall be recorded and sent to the consittee members. The misstes shall be read and approved at the start of each meeting. The p
RSC reports directly to the Rzecutive Vice President.
l The Radiation Safety Committee shall have both review and audit functions with regard to the Reactor Facility. The RSC shall advise the Reactor Administrator as well as level one management on all matters pertaining to reactor f acility safety.
L 6.1.5.1.
Any changes in equipment, procedures, facilities or license including these technical specifications shall be reviewed by the RSC.
6.1.5.2.
Audit Function: The records of safety surveys and deficiency reports shall be examined by the Radiation Safety committee. Audits shall be performed on an annual basis.
6.1.5.3.
The RSC shall review surveillance performed in compliance with technical specifications.
6.2.
Proc edure s Procedures shall be adequate to assure both the safety and adequate security of the reactor.
Substantive changes to the procedures shall be made only with approval of the RSC. Temporary changes to procedures which do not change their original intent may be made by the RSO. All such temporary changes shall be documented and submitted to subsequent review by the RSC. Procedures shall be in ef fect for the following items:
6.2.1. Pmergency. proc edures.
6.2.2. Security.
6.2.3. Calibration.
6.2.4. Surveys.
6.2.5. Surveillance.
6.3. Required Actions:
6.3.1.
Action to be taken in the event of an occurrence defined in Section 6.4.2.1.
6.3.1.1.
Corrective action shall be taken to return conditions to normal.
6.3.1.2.
All such occurrences shall be promptly reported to the Level 2 authority or designated alternates.
5 Amendment No. 2
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6.3.1.3.
All such occurrences including action taken to prevent or reduce the probability of a recurrence shall be reviewed by the Radiation Safety Ccomittee.
i 6.4 Feports. All written reports shall be sent within the prescribed interval to the NRC, Washington, D.C. 20555, Attentina Docratat Control I
Desk, with a copy to the Regional Administrator, Region IV.
j 6.4.1.
Operatirs Reports. Routine annual reports covering che activities of the reactor f acility during the previous calendar year shall be submitted to the appropriate NRC of fice by March 31 of the subsequent year. The following information shall be included in the report..
6.4.1.1.
Tabulation of major preventive and corrective l
maintenance operations having safety significance.
l 6.4.1.2.
Tabulation of major changes in the reactor f acility proc edure s.
6.4.1.3.
The resulta of any environmental surveys performed outside the facility.
l 6.4.1.4.
A summary of radiation exposures received by facility 7
penonnel and visitors in any one year including the dates and times of significant exposures (above 500 mrem).
6.4.1.5.
A summary of any ef fluents or discharges from the
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reactor f acility.
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6.4.2. Special Reports.
6.4.2.1.
Prospt Notification with Written Follow up.
The types of events listed below shall be reported as expeditiously as possible by telephone and confirmed by telegraph, mail-gram, or f acsimile 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 to the Document Control Desk and the Regional Adminittrator.
Information provided shall contain narrative material to provide completed explanation of the circumstances surrounding the event.
6.4.2.1.1.
Unanticipated releases of radioactivity to the environrient exceeding 500 times the limits specified for such materials in Appendix B. Table II of 10 CFR part 20.
6.4.2.1.2.
Exposure of personnel exceeding the limits as stated in 10 CFR 20.403 (b) 1.
t>. 4. 2.1. 3. Damage to, or theft of, the sealed source.
6 Amendment No. 2
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l 6.4.3. Reports Within 30 Days.. The types of events listed below shall bo reported to the Document Control Desk and the NRC Region IV Administrator or his designated representativa within 30 days of their occurrence.
r 6.4.3.1.
Any change in the facility organisation.
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6.4.3.2.
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 l
to reactor maintenance.
6.5. Records
Records of the following activities shall be maintained and retained for the period specified below. The records may be in the form 8
of logs, data sheets, or other suitable forms. The required information may be contained in single, or multiple records, or a combination thereof.
6.5.1.
Records to be Retained for a Feriad of at least five years.
6.5.1.1.
Normal reactor f acility operations.
6.5.1.2.
Principal maintenance operations.
l 6.5.1,3.
Reportable occurrences.
6.5.1.4.
Surveillance activities required by the Technical i
Specifications.
6.5.1.5.
Reactor f acility radiation and contamination surveys f
where required by applicable regulations.
6.5.1.6.
Special Nuclear Material inventories, receipts, and l
shipments.
6.5.1.7.
Approved changes in operating procedures.
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Records of weeting and audit reports of the
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Radiation Safety Committee.
6.5.1.9.
3ealed source leak test results.
6.5.2. Records to be Retained for Five Years or for the Lifetime of the Reactor Facility whichever is Greater (Note: Annual reports may be used where applicable as records in this section).
6.5.2.1.
Gaseous and liquid radioactive ef fluents released to the environment.
7 Amendment No. 2
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1 FiTure 1 j
organisation Chart j
University President Executive Vice-President (Level 1) j Radiation Safety Radiation Safety Officer Committee j
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i Reactor Administrator i
Dean of the College j
of Physical and Mathematical Science (Level 2)
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Tacility Chief j
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i Amendment No. 2 9
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