ML20235P121
| ML20235P121 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 09/29/1987 |
| From: | Brigham Young University, PROVO, UT |
| To: | |
| Shared Package | |
| ML20235P105 | List: |
| References | |
| NUDOCS 8710070182 | |
| Download: ML20235P121 (7) | |
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. --'- Technical Specifications
- 1. Brigham Young University currently possesses a L-77 Research Reactor. The fuel has been removed from the reactor, thus rendering the reactor non-functional.
The L-77 Research Reactor is located in the Reactor Laboratory. This is a dedicated facility with no other active use. Only the Chief of Reactor Operations and the Radiation Safety Officer are currently authorized to enter the building unaccompanied . The reactor fuel has been removed and returned to 00E. The only regularly scheduled
.I operations performed in the reactor facility involve radiation safety surveys on a quarterly basis by the Radia-tion Safety Officer. Since this set of ter.hnical specifi-cations is written in support of a Possession Only license,
. and due to the percent status of the reactor, many of the i normal sections covered by technical specifications will not be applicable in this case.
1.3. Definitions 1.3.1. certified operators - A certified operator is an individual authorized by the chartering or licensing organization to carry out the e duties and responsibilities associated with
.% the position requiring the certification.
1.3.2.
confinement - Confinement means a closure on the overa?1 facility which controls the move- ,
ment of air into it and out through a l g controlled path. l 1.3.3. experiment -
Any operation, hardware, or target (excluding devices such as detectors, "4 foils, etc.), which is designed to investi-
'g i gate non-routine reactor characteristics or which is intended for irradiation within the d
n- pool, on or in a beamport 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.
1.3.4. operable -
Operable means a component or system is capable of performing its intended function.
1.3.5 operating - Operating means a component or system is performing its intended function.
1.3.6 reactor operating - The reactor is operating whenever it is not secured or shutdown.
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I' 1.3.7 ' reactor secured - A reactor is secured when:
- 1) It'contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality unde r.' optimum available conditions or moderation and reflection, or
- 2) A combination of-the following:
a) The minimum number of. neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required- by tech-nical specifications, and b) The console key switch is in the off position and the key is removed from the lock, and c) No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and
'd) No experiments in or near the reactor are being ' moved or serviced that have, on movement, a reactivity worth exceeding the maximum value. allowed for a single experiment or one dollar which-ever is smaller.
1.3.8 reactor shutdown - The reactor is shut down if it is subcritical by at least one dollar in the Reference' Core Condition and the reactivity' worth of all experiments is accounted for.
1.3.9 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 may have provisions for the production of radio-isotopes.
1.3.10 shall, should and may .- The word "shall" is used to denote a requirement; the word "should" to denote a recommendation; and the word "may" to denote permission, neither a requirement nor a recommendation.
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- 2. Safety Limits and Limiting Safety System Settings 2
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l Applicability: .This section covers the L-77 Research Reactor and the reactor facility.
Objectives: To maintain the reactor and reactor facility in i
such a way as to present minimal risk to persons or property.
Specifications: The reactor will remain in a secure state by virtue of the fact that the reactor fuel has been unloaded and shipped off site. The shielding will remain intact until decommissioning with the exception that shielding water will be drained following the removal of the Pu/Be source.
Basis: The safety limit and limiting safety system settings are intended for an operational reactor. The removal of fuel renders all such operating specifications meaningless.
With the removal of the Pu/Be source, very little radio-active residual material will remain in the reactor.
2.1. Safety Limit - Not applicable 2.2. Limiting Safety System Settings - Not applicable
- 3. Limiting Conditions for Operation Applicability: Both the reactor and the reactor facility.
Objectives: To specify operating conditions which would ensure the safe operation of the reactor.
Specifications: Entrance into the reactor f acility will be made only by the Reactor Facility Chief or the Radiation Safety Officer, or by an individual approved and accompanied by one of the two above mentioned. The reactor will remain secured at all times.
Basis: We have set the most stringent possible limiting !
conditions for operation, i.e. no opera tion. This, therefore, seems sufficient. In addition, by strictly limiting access to the building housing the reactor, any potential exposure to facility personnel is minimized.
l 3.1. Reactor Core Parameters - Not applicable '
3.2. Reactor Control - Not applicable 3.3. Coolant Systems - Not applicable 3.4. Confinement or Containment - Not applicable 3.5. Ventilation Systems - Not applicable 3.6. Emergency Power - Not applicable 3
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, 3.7. - Radiation Monitoring Systems and Effluents 3.7.1. Monitoring ~ Systems -
Applicability: The reactor facility.
Objectives: To insure no unsafe exposure to or unauthorized release. of radioactive material .
Specifications: Through TLD monitors - two on the outside wall of the reactor facility and 1 inside the reactor facility will be placed in -such a manner as to maintain an accurate record of the potential, exposure risks posed by the reactor facility.
Basis: . Under the current license, the monitoring requirement is governed by Tech Specs,Section II.D.1 which states, "The reactor building will be monitored by a radiation and air particulate monitor during reactor operation and whenever radioactive materials are being handled in the building".
Since the reactor is permanently secured, no environmental radiation monitoring would be performed under the current license. This proposal then is to increase the stringency of the monitoring ' requirement.
3.8. Experiments - Not applicable
- 3. 9. . Facility Specific LC0 - Not applicable
- 4. Surveillance Requirements 4.1. Reactor Core Parameters.- Not applicable 4.2. Reactor Control and Safety Systems - Not applicable 4.3. Coolant Systems - Not applicable 4.4. Confinement or Containment - Not applicable 4.5. Ventilation Systems - Not applicable 1 4.6. Emergency Power - Not applicable l 4.7. Radiation lionitoring Systems and Effluents i Applicability: The reactor facility.
Objective: To maintain surveillance for potential exposure to radiation by facility personnel.
Specifications: The TLD dosimeters will be checked by a commercial vendor quarterly. The report generated will be reviewed by the Radiation Safety Officer quarterly.
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Basis: For the past five years, the reactor has been in a secured status. The fuel was removed and l returned to the DOE in May, 1987. Due to the present configuration and the proposed operational limitations a more stringent surveillance seems unjustified.
l l 4.8. Experiments - Not applicable 4.9. Facility Specific Surveillance - Not applicable
- 5. Design Features
- 5.1. Site and Facility Description - The L-77 Research Reactor is located in the nuclear laboratory on the l
south end of the Brigham Young University campus. The building is constructed of concrete.
5.2. Reactor Coolant System - Not applicable 1 5.3. Reactor Core and Fuel - Not applicable 5.4. Fissionable Material Storage - Not applicable
- 6. Administrative Controls
6.1. Organization
Level 1 - Jeffrey R. Holland (or John B Stholton, Executive Vice President).
Level 2 - Reactor Administrator Dean Mason (or Edwin Jackson, Radiatic.i Safety Officer).
Level 3 - Reactor Facility Chief Gary Jensen.
Level 4 - No licensed operators.
6.1.1. See figure 1
6.1.2. Responsibility
Responsibility for the safety of the nuclear reactor facility rests with the personnel shown in figure 1.
6.2. Review and Audit The Radiation Safety Committee shall have both review and audit functions with regard to the Reactor Facility.
6.2.1. This committee shall be composed of four members, to include: the Radiation Safety Officer, a faculty member from the Physics Department, a faculty member from the college of Biological Science, and a member from the Campus Safety Office.
6.2.2. The Radiation Safety Committee (RSC) will meet quarterly. 3 of 4 members will constitute a quorum.
The minutes will be recorded and sent to the committee members. The minutes will be read and approved at the start of each meeting.
6.2.3. Any changes in equipment or facilities will be reviewed by the RSC.
6.2.4. Audit Function: The records of safety surveys and deficiency reports will be examined by the Radiation Safety Committee.
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l 6.3. Procedures-The RSC will: review any changes in security Lplans and surveillance performed in' . compli?nce with technical specifications. 'These elements will also be reviewed by the Radiation Safety Officer. 1
.6.4. Experiments Review and Approval - Not applicable -
.6.5, Required Actions - Not applicable 6.6. Reports - Not applicable.
p 6.7. Records 6.7.1. Records of surveillance activities, Radiation ~
Safety Committee meetings, any changes to the equip-ment, or configuration of the reactor will be main-tained for at least 5 years.
6.7.3. Drawings of the reactor will be maintained for the life of the reactor facility. Records of radia-tion exposure to individuals will be maintained in-definitely.
l 7. References l
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FIGURE-I l
Level 1 Unit or Organization Head Jeffrey R. Holland i
i Level 2 l 1
Facility Director or Radiation Administrator Safety Committee Grant W. Mason Review l Audit Radiation Safety Edwin F. Jackson _
Level 3 Facility Chief Gary Jensen ;
. Level 4 Operating Staff None i
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