ML20246B188
| ML20246B188 | |
| Person / Time | |
|---|---|
| Site: | 05000262 |
| Issue date: | 03/17/1988 |
| From: | Brigham Young University, PROVO, UT |
| To: | |
| Shared Package | |
| ML20246B183 | List: |
| References | |
| NUDOCS 8907070232 | |
| Download: ML20246B188 (11) | |
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TECHNICAL SPECIFICATIONS L-77 RESEARCH REACTOR L
BRIOHAM 70UNG UNIVERSITY l
l 1.
Introduction 1
1.1.
Definitions 1
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l 2.
Safety Limits and Limiting Safety System Setting 1
l 3.
Limiting Conditions for operation 2
4.
. Surveillance Requirements 2
4.1.
Control and safety system.
2 4.2.
Reactor Area.
2 5.
Design Features 3
5.1.
Reactor.
3 5.2.
Reac+or Facility 3
5.3.
Anticipated changes in configuration.
3 6.
Administrative Controls 3
6.1. Organization
3 6.2.
Training Requirements 4
6.3.
Radiation Safety Committee.
4 6.4.
Required Actions 5
- 6. 5. -
Reports 5
6.6.
Records 6
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TBCHNICAL SPECIFICATIONS L-77 MmRARCH ERACTOR BRIGBAM YOUNG ONIVERSITI 1.
Brigham Young University currently possesses an 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 l
Operations and the Radiation Safety. Officer are currently authorized to -
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enter the building unaccompanied.
The reactor fuel has been removed and returned to DOE. The only regularly scheduled operations performed in the reactor facility involve radiation safety surveys on a quarterly basis by the Radiation Safety Officer.
Since this set of technical specifications is written in support of a Possession Only license, and due to the present status of the reactor, many of the normal sections covered by technical specifications will not be applicable in this case.
1.1. Definitions 1.1.1.
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.
A channel check is a qualitative 1.1.2.-
channel' check verification of acceptable performance by observation of channel behavior. This verification may include comparison of the channel with other independent channels or methods measuring the same variable.
1.1.3 confinement - confinement means a closure on the overall facility which controls the movement of air into it and out through a controlled path.
1.1.4.
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 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.
1.1.5.
operable - Operable means a component or system is capable of performing its intended ibnetion.
Operating means a component or system is 1.1.6.
operating performing its intended function.
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reactor operating - The reactor is operating whenever it is not' secured or shutdown.
141.8.
3 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 under optimum. available conditions of moderation and reflection.
1.1 9.
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.
1.1.10.
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.
1.1.11.-
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.
2.
Safety Limits and Limiting Safety System Setting L
Safety Limit - Not applicable. The reactor shall. remain secured.
3 Limiting Conditions for Operation Not applicable. The reactor shall remain secured.
4.
Surveillance Requirements Specified surveillance actions shall be performed in accordance with the following schedule.
4.1. Control and safety system.
4.1.1. Applicability
The reactor facility.
4.1.2. Objective
To maintain surveillance for potential exposure to radiation.
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4.1 3. Specifications:
4.1 3.1. TLD dosimeters will be checked by the commercial vendor quarterly. The report generated will be reviewed by the Radiation Safety Officer quarterly.
4.3.1.2. Portable radiation survey instruments will have a channel check semiannually, and calibration annually.
4.1.4. Bases.
Periodic quality assurance procedures should insure confidence that measurements and observations are correct.
4.2. Reactor Area.
4.2.1. Applicability.
This specification pertains to the reactor facility.
4.2.2. Objective.
To. assure the radiation safety of the reactor area.
4.2.3. Specifications.
4.2.3.1 The fire alarm shall be tested on an annual basis.
4.2.3.2 The door locks shall be inspected quarterly.
4.2.3 3 The shield water level. shall be visually inspected annually.
This ' requirement will be void once the plutonium / beryllium source is removed from the reactor.
4.2.3.4. The Radiation Safety officer shall make a radiation survey of the area semiannually.
4.2.3 5. Two TLD dosimeters shall be placed in the nuclear laboratory and one TLD dosimeter shall be placed immediately outside the nuclear facility in order to maintain a record of potential exposure levels inside and immediately adjacent to the facility.
i S. Design Features 5.1 Beactor.
I The reactor is an L-77 research reactor.
The fuel has been removed and shipped off site.
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i 5.2. Reactor Facility I
The reactor is located in the Nuclear Laboratory.
This is a dedicated facility located on the southwest portion of the Brigham i
Young University campus.
The building is of concrete and masonry
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construction. The beam ports have been locked. Unaccompanied 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 changes include removal of the plutonium / beryllium source following which the shielding water will be tested for chemical and radiological contamination.
In the event the shielding water is found to be within point source guidelines under the Clean Water Act; and is also found to have radiation counts not exceeding 50 cpm above the background level of Provo city culinary water the water shall be discharged into the sanitary sewer.
5.3.1.
Chemical contaminants will be checked by a State approved laboratory.
5.3.2. Radioactive contamination will be tested using both liquid and solid scintillation counters. Water will not be discharged if either of the counting methods have a mean counting rate greater than 50 dpm above that of Provo City Culinary water.
6,, Administrative Controls
6.1 Organization
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 (RS0) 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 program and serves as the Secretary of the Radiation Safety Committee.
He prepares the University's Radiation Safety Manual. The Radiation Safety Officer is also 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.
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Figure 1
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Reactor Organization Chart
. Level 1
,---------+
President
+---------e
. Executive Vice President a__
....a Level-2
..___.4_.____.,.
,......___A.
,.....____A__________,
Radiation Safety 't.
Reactor
- Radiation Safety :
. Officer, Administrator :
Committee 2.........__
..___.__1 t...____._,__ -_.._1 2_..
___............ 1 4....
- Level.3
-Facility Chier A........__.__..
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6.2-Training Requirements. At least one member 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.
6.3. Radiation Safety Committee.
The members of this committee are
. appointed by the Executive Vice President. 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 n
Safety Office.
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 membetrs.
The minutes will be read. and approved at the start of each meeting '
The RSC reports directly to the Executive'Vice President.
The. Radiation Safety ' Committee shall have both review and audit functions. with regard to the Reactor Facility.
The RSC will advise the Reactor Administrator as well as. level one management on all mi,ters pertaining to reactor facility safety.
6.3.1.'Any changes in equipment or facilities will be reviewed by the RSC.
6.3.2. Audit Function:
The records of safety surveys and deficiency reports will be examined by the Radiation Safety Committee.
-6.3.3. The RSC will review any changer in security plans and surveillance performed in compliance with technical specifications.
These elements will also'be reviewed by the Radiation Safety Officer.
6.4 Required Actions 6.4.1. Action to be taken in the event of an occurrence defined in Section 6.5.3.
6.4.1.1. Corrective action shall be taken to return conditions to normal.
6.4.1.2. All such occurrences shall be promptly reported to the Level 2 authority or designated alternates.
6.4.1.3. All such occurrences including action taken to prevent or reduce the probability of a recurrence shall be reviewed by the Radiation Safety Committee.
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6.5. Reports. ? A11 written reports shall.be sent within the
_ Washington, D.C. - 20555, Attention: ' prescribed interval to. the.' NRC, Document-Control Desk, with a copy to the Regional Administrator, Region IV.
6.5.1. Operating Reports.
.Rou. tine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the' appropriate NRC office -
within three months following the end of each prescribed year.
The first such report under these specifications will be filed for the year 1988 on or before March 30, 1989.-
Each annual operating report shall include the following information:
6.5.1.1. Tabulatio n of major preventive and corrective maintenance operations having' safety significance.
6.5.1.2. Tabulation of major - changes in the reactor; facility procedures.
6.5.1.3. - The results of any ' environmental surveys performed outside the' facility.-
6.5.1.4. A summary of radiation exposures received by facility personnel and visitors in any one year including the dates and times of significant exposures (above 500 mrem)..
6.5.2. Special Reports.
Special' reports which may be required by the NRC shall be submitted within the time period specified for each report.
6.5.3. Reportable Occurrences.
Reportable occurrences such as increases in radiation levels or physical degradation of the facility, including causes, probable consequences, corrective actions, and measures te prevent recurrence, shall be reported to the NRC.
'6.5.4. Prompt Notification with Written Follow up.
The 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 completed explanation of the circumstances surrounding the event.
6.5.4.1. Unanticipated releases of radioactivity to the environment.
6.5.4.2. Unanticipated exposure of personnel.
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6^.5.4.3. An. observed ' inadequacy in the implementation of administrative or procedural controls such that the
-i inadequacy ~ causes or could cause an unsafe condition with regard to facility maintenance.
'6.5.5. Reports Within 30 Days.
The - types of events listed below shall be reported to the Director of NRC Region IV or. his des 1 nated representative within 30 days of their occurrence.
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' 6.5.5.1. Permanent changes in the facility organization structure.
6.5.5.2. An observed inadequacy in the - implementation of administrative or procedural controls such that the inadequacy causes or could have caused an unsafe condition with regardn to reactor maintenance.
r, 6.6.'. Records. Records of the following activities shall be maintained and retained for'the' period specified below.
The records may be in the form of logs, ' data sheets, or other suitable forms.
The required -
'information may. be contained in single, or multiple records, or a combination thereof.
6.6.1.
Records to be Retained for a Period of at least five years.
6.6.1.1. Normal reactor facility operations (including scheduled and unscheduled shutdowns).
6.6.1.2. Principal maintenance operations.
6.6.1.3. Reportable occurrences.
6.6.1.4. Surveillance activities ' required by the Technical Specifications.
6.6.1.5. Reactor facility radiation' and contamination surveys where required by applicable regulations.
6.6.1.6. Special Nuclear Materials (SNM) inventories, i
receipts, and shipments.
6.6.1 7. Approved changes in operating procedures.
6.6.1.8. Records of meeting and audit reporte of the Radiation Safety Committee.
6.6.1.9. Sealed source leak test results.
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6.6.2-Records to be Retained for Five Years or for the Lifetime of the Reactor Facility whichever is Greater i
I (Note: Annual reports may be used.where applicable as records in this section).
6.6.2.1. Gaseous and liquid radioactive effluents released to the environs.
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'T Thib. is - a:;11st. of key Brigham Young. University employees' involved-in
- decommissioning the L-77 research reactor.
1 Edwin Jackson'(RS0)
' Safety Office 801-378-6882 CBMH BYU Provo, Utah 84602 The RSO has primary responsibility for ' generating plans and reports, ar.,
performing surveys.
He serves.on the' Radiation. Safety Committee.
He woulc be the primary' contacti for information regarding the present status of the l..
. reactor and' decommissioning plans.
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l 1-Dr.! Gary Jensen.-
Physics Dept 801-378-220S 296 ESC BYU Provo, Utah 84602-Dr. Jensen serves as Facility Chief and President of the Radiation Safety Committee. During the time the reactor was in use Dr. Jensen was - an operator.
John B.':Stohlton
.B-346 ASB.
801-378-5625 BYU Provo, Utah 84602 l
President Stohlton is the Executive Vice President. He has been designated as the primary Level 1 executive responsible for the reactor.
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