ML20210R940
| ML20210R940 | |
| Person / Time | |
|---|---|
| Site: | 07000267 |
| Issue date: | 11/15/1985 |
| From: | Glenn J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Alexander Adams NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| Shared Package | |
| ML20210R873 | List: |
| References | |
| 25847, NUDOCS 8610070498 | |
| Download: ML20210R940 (1) | |
Text
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g>a naCog UNITED STATES Nw EAR REGULATORY COMMISSION
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$31 PAR K AVENUE KING OF PRUSSI A, FENNSYt.VANI A 19406 November 15, 1985 State University of New York Nuclear Science and Technology Facility ATIN: Alexander Adams, Jr.
Reactor Engineer Rotary Road Buffalo, New York 14214 Docket No.
070-00267 License No.
SNM-273 Control No.
25847
SUBJECT:
LICENSE RENEWAL APPLICATION Gentlemen:
This is to acknowledge receipt of your application for renewal of the material (s) license identified above.
Your application is deemed timely filed, and accordingly, l
the license will not expire until final action has been taken by this office.
Any correspondence regarding the renewal application should reference the control number specified and your license number.
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Sincerely,
' Original Signed Byf Doris J. Foster John E. Glenn, Ph.D., Chief Nuclear Materials Safety Section B Division of Radiation Safety and Safeguards 8610070498 860813 REG 1 LIC70
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BMRC BUFFALO MATERIALS RESEARCH CENTER September 27, 1985 w
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Nuclear Material Safety and Safeguards N
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United States Nuclear Regulatory Commis'sion
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Washington, D. C.
20555 Docket 50-57
Dear Mr. Crow:
SNM License 273
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Enclosed are six (6) copies of our renewal application for Special Nuclear Materials License 273.. If I can be of any assistance in this matter, please feel free to call me.
Very trily yours,
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o APPLICATION FOR RENEWAL SPECIAL NUCLEAR MATERIAL LICENSE SNM 273 Pursuant to Part 70.21 of 10 CFR, we hereby file this updated application for Special Nuclear Material License SNM 273.
1.
THE STATE UNIVERSITY OF NEW YORK (SUNY)
The State University of New York is a public educational corporation established by Article 8 of the New York State Education Law.
As such, it is exempt from licensing fees under 10 CFR 170.11.
It is an agency of the state of New York, and is responsible for the administration of publicly supported higher education outside of those institutions within N-the jurisdiction of the City University of New York.
1.1 Administrative Structure SUNY is governed by a Board of Trustees.
Its constituent units include university centers, four year colleges, medical schools, and specialized and contract colleges. The State University of New York at Buffalo (SUNY/ Buffalo) is one of the state-operated institutions within the SUNY system.
The State University of New York at Buffalo is the licensee.
The Buffalo Materials Research Center (BMRC) is owned by the State University of New York at Buffalo. Buffalo Materials Research, Inc. (BMR),
a private company, manages operation of the reactor and its support Iacilities.
The BMRC maintains a close working relationship with SUNY through the Office of the Vice President for Research.
It is with this office that
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overall responsibility as the licensee rests. The BMRC Director is assigned direct responsibility for the safe operation of the Center, on behalf of the licensee.
The SUNY/ Buffalo Radiation Safety Officer (RS0) has responsibility for monitoring, planning, and promoting radiological safety at the Center.
The RSO has the authority to stop, secure, or otherwise control as necessary, any operation or activity that poses an unacceptable radiological hazard. University Radiacion Protection Services (RPS),
under the direction of the RSO, provides an independent overview function at the BMRC. The RSO reports to the Director of Environmental Health and Safety, who in turn reports to the Vice President for Finance and Management. The BMR/SUNY at Buffalo organization is shown in Appendix 1.
Responsibility for the routine and day-to-day radiological safety activities rests with the BMRC Health Physics Department.
BMRC organiza-tion is shown in Appendix 2.
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The Nuclear Safety Committee (NSC) reviews matters relating to the health and safety of the public, in accordance with the Constitution and By-Laws of that committee. The NSC consists of a minimum of six (6) persons with expertise in the physical sciences. Permanent members of the committee are the BMRC Director, the SUNY/B Radiation Safety Officer, and the Operations Department Manager.
The Operating Committee is a subcommittee of the Nuclear Safety Committee.
It consists of the Director, the SUNY/ Buffalo Radiation Safety Officer (RS0), and the Operations Manager. The Operating Committee is authorized to act for the Nuclear Safety Committee with regard to routine aspects of BMRC operations.
The responsibilities of the Operating Committee include:
a) review experiments which present no new, significant, safety problems.
b) approve additions to or revisions of any Operating Procedures.
c) review abnormal occurrences.
d) perform Center inspections.
The Constitution and By-Laws of the Nuclear Safety Committee may be found in Appendix 3.
1.2 Financial Structure The Buffalo Materials Research Center (BMRC) and Radiation Protection Services (RPS) receive financial support directly from SUNY/ Buffalo as Organized Activities, a specific budgetary category.
In addition, an Income Reimbursable agreement between BMRC and the University is also in effect.
Under this agreement, the University guarantees payment of additional salaries with reimbursement to the University from income p
generated by grants, medical radioisotope production, and industrial d
services. A similar income reimbursable agreement exists between the University and the RPS to cover costs associated with low level radioactive waste disposal.
In addition to the two mechanisms abova, the BMRC is allowed to generate income directly for its own accounts by providing nuclear services.
The University will provide whatever resources are required to maintain the Center in a condition that poses no threat to the general public or to the environment.
1.3 Foreign Dominance The nature of the State University of New York is all that is implied in its title.
A copy of page X of the University Directory has been I
attached to this application as Appendix 4.
This page provides j
applicable information regarding the current University Officers, SUNY Central Administrative staff, and the SUNY Board of Trustees.
l In view of the above, it is not conceivable that the-State University of New York, or its centers, facilities, or subsidiaries could come under foreign control or dominance.
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, 2.
Site Description The State University of New York at Buffalo, Main Street campus, is located in the northeast corner of the City of Buffalo, New York. The BMRC is located at the southwestern edge of this campus. The RPS is located in the Howe Research Building which is immediately adjacent to the BMRC.
The Amherst campus is located approximately four miles north of the Main Street campus, in Amherst, New York. Maps are provided in Appendix 5.
A more detailed site description, including applicable meteorological data, may be found in the Hazards Summary Report for NRC License R-77, which is on file with the NRC under docket 50-57.
3.
Activities at BMRC
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The major research facility at the BMRC is a 2 Mw PULSTAR research pool reactor, which is operated under NRC license R-77.
The Technical Specifications for R-77 are also on file with the NRC under docket 50-57.
This license is requested to permit possession and utilization of SNM in support of or supplementary to activities licensed by R-77.
This would include academic and commercial service activities, as well as quality assurance activities. Most SNM utilization occurs within the confines of the BMRC. Isotopic neutron sources (Pu-Be) may, however, be utilized in radioisotope laboratories at both the Main Street campus and the Amherst campus. Such use must be approved by the Campus Radiation Safety Officer and the BMRC Accountability Officer.
4.
Key Staff
. The qualifications for key staff positions at RPD and BMRC are presented p
below.
%J 4.1 BMRC Director a) MS degree in physical sciences or related discipline and two (2) years of nuclear experience.
or b)
BS degree in physical sciences or related disciplines and five (5) years of nuclear experience, plus an additional two (2) years experience in the operation and utilization of a research nuclear reactor.
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. 4.2 Radiation Safety Officer a)
Ph.D. in a field of nuclear science and three (3) years of experience in radiation protection.
or b) MS degree in nuclear science and five (5) years of experience in radiation protection.
or c) BS degree in nuclear science and five (5) years of experience in radiation protection, with at least three (3) of the five years in a management position.
4.3 Reactor Engineer BS degree in nuclear engineering or a closely related field, and a) Five (5) years experience in the field of reactor physics or nuclear engineering.
or b) Three (3) years of experience with the BMRC.
,In either case (a) or (b), the Reactor Engineer must obtain and possess for three (3) years, or have previously possessed for three (3) years, a Reactor Operator or Senior Reactor Operator license for the BMRC s/
reactor.
An MS degree may be substituted for two years of experience under option (a) or (b).
4.4 Operations Manager a)
BS degree in engineering or a closely related field, and three (3) years experience as a licensed Senior Reactor Operator at BMRC.
At lease. two (2) of the three years must be in a reactor operations supervisory position.
or b) AAS degree or equivalent in an appropriate curriculum, and five (5) years experience as a Senior Reactor Operator at BMRC. At least three (3) of the five years must be in a reactor operations super-visory position.
or c) Ten (10) years experience as a Senior Reactor Operator at BMRC, at least five (5). years of which are in a. reactor operations super -
visory position.
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. i 5.
Inventory Control Implementation of inventory control of Special Nuclear Material is accomplished via compliance with the BMRC Accountability Manual. This manual is on file with the NRC under docket 50-57.
A brief summary is presented below.
Accountability of SNM is accomplished on an Item Control rather than a Mass Balance basis. The facility is therefore divided into Item Control Areas or ICA's.
They are as follows:
1.
ICA-lC:
The control deck level fuel storage vault.
2.
ICA-lG:
The gamma deck level fuel storage vault.
3.
ICA-2:
The reactor core and pool storage facilities.
4.
ICA-3:
The suberitical reactor tank.
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5.
ICA-4:
The balance of the facility, including the hot cell, and approved campus laboratories.
6.
ICA-5H Howe Building Transfer of SNM between ICA's is documented as specified in the Accountability Manual.
A physical inventory, on a piece count basis, is performed each year by the Accountability Officer or his designee (s).
An approved security plan is on file with the NRC under docket 50-57.
j Floor plans of BMRC and Howe Building have been included with this l
application as Appendix 6.
6.
Storage and Utilization Facilities O
The following is a brief description of the facilities available at BMRC for the storage and/or utilization of SNM.
6.1 Fuel Vaults (ICA-lG and IC)
SNM which does not require special shielding and is not in active use is stored within one of the fuel storage vaults. These vaults are located between the gamma and control deck air lock doors. Security seals on the vault doors are used to detect unauthorized entries. Access keys are controlled by the Operations Manager or his designee (s).
An exemption to the criticality monitor requirements of section 70.24 or 10 CFR 20 was granted on June 19, 1964, by the USAEC.
(See section 9.)
Materials which are typically stored within the fuel vaults include cold fuel pins and miscellaneous nuclear materials such as uranium oxide powders and pellets of varying enrichments, and nuclear instruments (primarily fission chambers).
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. 6.2 Reactor Tank (ICA-2)
Routine reactor start-ups are accomplished using a regenerable antimony-beryllium source. After prolonged periods of shutdown, a Pu-Be source may be needed to provide start-up source neutrons. The source is removed from the reactor core area while at low power, to prevent unnecessary neutron activation of the source.
Other special nuclear materials which may be stored or used within the reactor tank include nuclear instruments or detectors such as fission counters or threshold foils.
6.3 Suberitical Assembly (ICA-3)
The subcritical assembly consists of a tank with natural uranium fuel slugs, which is currently located on the gamma deck of the BMRC contain-ment.
For experimental purposes, the tank shall be filled with water, and the Pu-lie sources may be used or stored within the tank.
Transfer of Pu-Be sources into or out of the suberitical assembly is performed by authorized personnel in accordance with the BMRC accountability manual.
When not in active use, the assembly is maintained locked.
6.4 Hot Cell The hot cell is located adjacent to the reactor tank. The cell dimensions are 7.5' wide by 6' deep, by 14.9' high, with a minimum wall thickness of 3' (high density concrete--nominal density 225 lb/ft3).
Normal cell access is through a side door (47.6" opening) or a stepped plug in the cell ceiling (36" opening). Additionally, a six-inch diameter pipe connects the cell with the reactor tank. A system of interlocked valves permits transfer of materials from the reactor tank to the cell
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(or vice-versa) in such a manner as to prevent flooding of the cell, and with a minimal amount of radiation exposure.
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A gamma monitor is located within the cell above the viewing window. An alarm on the monitor inhibits opening the main access door when high radiation is present. The cell is vented to the stack release vent via a 350 CFM blower.
(See Section 10). Whenever unencapsulated* SNM is stored or manipulated within the hot cell, a flow sensing system will be l
functional, in the hot cell exhaust vent.
This system will alarm upon loss of flow from the cell.
- For the purposes of this application, "unencapsulated" shall mean material which is not sealed within an isotopic source or a nuclear detector such as a fission chamber or sealed foil.
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. 7.
Possession Limits The maximum quantities of SNM to be possessed under this license are:
7.1 Plutonium 7.1.1 Up to one gram encapsulated as threshold detectors.
7.1.2 Up to 240 grams encapsulated as Pu-Be lostopic neutron sources.
7.2 Uranium-235 7.2.1 Up to one gram contained in fission counters.
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_j 7.2.2 Up to nine grams in any form for research and development purposes.
8.
Use of Materials The scope of activities for which the above listed nuclear materials is requested, is described herein.
8.1 Plutonium Threshold Detectors These devices are used for measurement of fast neutron fluxes within the BMRC reactor.
The copper encapsulated foils currently in use were manufactured by Monsanto Research Corporation.
(Nuclear Source Numbers MRC-TD-Pu-275, 276, 277, and 278, Drawing No. NS-11.)
. Insertion into the reactor is licensed by R-77.
Irradiation times and flux levels are controlled to produce assay levels of radioactivity, and hence no health or safety hazard is anticipated. When not in use, the foils are stored in a suitable shielded container within a fuel vault.
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8.2 Plutonium as Plutonium-Beryllium Sources These sources are used for educational and research and development activities at BMRC and at approved campus locations. Currently five (5) one curie and one (1) ten curie are in use.
They are stainless steel encapsulated, and were manufactured by Monsanto Research Corporation.
Source identification numbers are: M442, M505, M506, M507, M508, and M873 (10 C1).
Total element and isotope weights are 239.04 grams and 222.51 grams, respectively.
The Pu-Be sources are used in conjunction with courses in Biology, Physics, and Chemistry, and in research and development activities.
Activities in the former category include, in part, use in experiments, demonstrating concepts of half-life, saturation factor, thermalization of neutrons, buckling, neutron shielding, activation analysis, and cross section.
In the latter category, the sources are used, in part, for measurement of the response characteristics of neutron detectors, boron determinations, studies of the neutron transmission characteristics of materials, and effective shielding-thickness determinations.
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O The Pu-Be sources are noreclly used within the confines of the BMRC. The 1 Ci sources may be loaned to other University departments with the approval of the BMRC Accountability Officer and the Radiation Safety Officer, for use in RPS approved radiochemical laboratories which are pro-vided with equipment deemed by the RPS to be adequate for safe utilization of the sources.
A metal rod, wire, or nylon line is attached to each source to provide a means for source handling and transfer which minimizes the exposure to the experimenter. The choice of the particular device attached to an individual source is based on the experimental facility in which it is to be used. Use of additional safety devices such as remote handling tools are used as deemed advisable by the RPS.
In general, the sources are used in the subcritical assembly or in moderated devices such as water or paraffin-filled howitzers, aquaria or specially f abricated equipment. The sources may be stored in these devices when not in active use if the device can be locked. Otherwise, when not in use, the sources will be stored in a locked shipping or storage container. All laboratories in which the sources are used and all con-tainers and devices used for source storage will be labeled in accordance with the requirements of 10 CFR 20 and the New York State Sanitary Code, Part 16.
All laboratories in which sources are in use or storage will be locked when not occupied, unless materials are otherwise secured.
The gamma and neutron dose rates from a one (1) and a ten (10) curie PuBe source with varying amounts of water moderation are provided in Appendix 7.
Written procedures for all experiments involving use of Pu-Be source (s)
'by academic users shall be approved by the Operating Committee, and shall be maintained on file for inspection by the NRC.
8.3 Uranium-235 Possession of up to 1 gram of uranium-235 contained in fission counters is requested. Fission counters are utilized in conjunction with suberitical experiment s. As a result of the low neutron exposure inherent in such use, the counters will not become appreciably activated and do not, therefore, represent a health and safety factor. Routine leak tests will not be performed in view of the low inherent hazard of the material. The fission counters may be stored in either the suberitical assembly or in the fuel Ptorage room. When not in active use the suberitical assembly cover is to be locked in place.
Possession of up to 9 grams of uranium-235 in any chemical or physical form in any enrichment up to 93.48 per cent U-235 is requested for research and development programs. Experiments utilizing such material are to be performed in accord with written procedures provided by the experimenter and approved by the BMRC Accountability Officer and the RPS. Autho rization c
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, to use the material in experiments involving reactor irradiation is not requested under this license.
Such use is covered under Reactor License R-77.
Enriched uranium held under the current license (SNM-273) ranges in enrichment from 1.41 to 93.48 per cent.
The total uranium weight is 27.132 grams with a uranium-235 content of 7.423 grams.
Materials not in use will be stored in a fuel storage vault.
9.
Criticality Monitora License R-77 was amended on June 24, 1977.
(Amendment No. 14, R-77-50-57).
This amendment allows under R-77:
1.
Expansion of vault storage capacity from 8 to 30 fuel assemblies.
2.
Storage of up to 24 fuel assemblies within the hot cell.
An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted for the storage vaults, in a letter from the AEC on 6/19/64.
This exemption remains applicable, as per the cover letter which accompanied amendment No. 14.
The storage geometries for fuel storage in the hot cell and the fuel vaults are quite similar. Nuclear materials possessed under SNM-273 do not have the capability to significantly perturb conditions assumed in the criticality analyses.
It is therefore the judgment of BMRC that no further criticality analyses are warranted or necessary.
10.
Radiation Protection 10.1 Contamination Surveys O
The minimum frequency for contamination surveys shall be as follows:
10.1.1 Pu-Be. sources:
Pu-Be sources shall be leak tested as per section 10.3 of this application.
10.1.2 Material in storage (other than Pu-Be sources): Storage area (s) shall be surveyed monthly by the BMRC Health Physics Department.
Personnel entry to the fuel vaults is closely monitored for security reasons.
Each entry is therefore documented.
If, in a given month, no entry has been made, no survey is required.
Personnel who enter the fuel vault (s) are required to monitor themselves for contamination, immediately upon leaving the vault.
10.1.3 Material in use:
Contamination surveys shall be performed each time non-encapsulated SNM is used.
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. 10.2 Contamination Action Levels Action levels for surface contamination shall be specified in the table below:
RADIOACTIVE SURFACE CONTAMINATION LIMITS Application A
Alpha (dpm/100cm )
Beta /Gammai Total Removable Total Removable (mR/hr)
(dpm/100cm )
2 Controlled area Radioisotope labs, 25,000 Max.
500 1.0 5,000 other designated Radio-5,000 Av.
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isotope working areas Clean area 1,000 100 0.5 1,000 Non-controlled area Skin, personal clothing N.D.2 N.D.2 N.D.2 N.D.2 Measured at 1 cm from the surface.
1 2.D. -- non-detectable.
N Release of equipment or materials from BMRC for unrestricted use shall be in accordance with " Guidelines for Decontamination of Facilities and Equipment Prior to Release for Unrestricted Use or Termination of i
Licenses for Byproduct, Source, or Special Nuclear Materials", published j
by the USNRC Division of Fuel Cycle and Material Safety.
1 If a contamination action level is exceeded, decontamination shall, if possible, commence immediately.
In all cases, clean-up will start within twenty-four hours, once the measured surface radioactivity level exceeds the action levels alone.
If decontamination cannot proceed immediately, (i.e., if appropriate personnel or equipment is not immediately available), immediate steps will be taken to control and isolate the contamination. This would entail such steps as posting, l
barricading, encapsualting in paper or plastic, etc.
10.3 Leak Tests The Pu-Be sources shall be leak tested by BMRC Health Physics at six-month intervals. A smear of the source will be taken and analyzed, using an appropriate counter.
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l 1 l The plutonium threshold foils will be leak tested in the same manner, quarterly.
If the foils have been in storage only (i.e., not used), no leak test is required; but a leak test will be performed before the next utilization. Procedures are shown in Appendix 10.
10.4 Instrument Calibration Portable survey instruments (Geiger counters, ion chambers, etc.) shall be calibrated at six-month intervals by BMRC.
Laboratory instruments shall be calibrated as necessary.
10.5 Waste Disposal 0;ecial, cicarly labeled, waste containers shall be utilized for the disposal of radioactive waste containing Special Nuclear Material.
These containers will segregate the SNM waste from containers used for byproduct material only. Waste containers containing SNM shall be checked for external contamination monthly by Health Physics. Disposal shall be arranged by the RPS in accordance with applicable NRC and DOT regulations. Contamination checks of waste containers shall be accomplished using smears to be counted on a proportional counter.
10.6 Audit Program The management audit function for SNM utilization shall be performed by l
the BMRC Director or his designee. The Director (or his designee) shall review procedures and activities involving SNM twice a year. Any j
recommendations shall be presented to the Operating Committee. The scope 1
f of the audit shall be commensurate with the level of activities performed within the context of this license.
10.7 Training Program All p'ersons who use radioactive materials must be authorized by the Nuclear Safety Committee or by its designee, the Operating Committee, or by the RSO.
In order to obtain such oa authorization, an individual must demonstrate adequate training, either by in-house training, or documented past experien ". The in-house training is accomplished through completion of the reactot,perator license training program, or through a training program provided by the Health Physics Department. The examination and training program requirements may be waived by the RPS for qualified individuals, with documented prior experience.
Students participating in laboratory experiments at BMRC must be supervised by a BMRC staf f member, or by a teaching assistant authorized by the Operating Committee.
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, 10.8 Ventilation Control and Monitoring 10.8.1 Ventilation System The BMRC reactor is housed within a concrete containment vessel.
Negative pressure is maintained in the containment when the reactor is operating, or when radioactive materials are being manipulated which could generate airborne radioactive material.
There are two ventilation release points from the BMRC containment.
The " Building Air" duct is a 36" duct which exhausts through the containment roof. This duct releases general building air and low level fume hoods. High level hoods and experimental facilities exhaust through a second duct referred tto as the " stack".
This duct f'}
travels to the main heating plant behind BMRC and exhausts at a height
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of 50.7 meters. Air pressure in the stack duct is maintained at negative pressure relative to the containment.
All air leaving BMRC is passed through prefilters having an efficiency of 8 to 12 per cent for atmospheric dust, and then through absolute filters with a rated efficiency of 99.97 per cent for particles of 0.3 microns or bigger.
The hot cell exhausts through the " stack" duct. If SNM is utilized within the hot cell, the filter shall be changed semi-annually, or if any discernible damage has been incurred to the filter.
10.8.2 Ventilation Effluent Monitoring 10.8.2.1 ?>uilding Air Monitoring
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A sidestream of air is drawn from the duct shortly before it exits the roof. The stream first enters the fixed filter bizilding particulate monitor, where filter activity is measured by a Geiger tube.
The air then passes through a 30 liter sample tank.
Two Geiger tubes operating in parallel, measure the concentration of radioactive material in the sample tank.
Signals are fed to rate meters and transmitted to follow meters and a chart recorder in the control room.
Local and remote alarms are provided.
10.8.2.2 Stack Monitoring A sidestream of air is drawn from the stack duct shortly before it exits the building.
It is passed through a fixed filter, and then to a sample tank identical to the building air tank.
A Geiger tube (end window) constantly monitors activity collected on the fixed filter, and sends its signal to a ratemeter. A signal is also sent to a follow meter and chart recorder in the control room.
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, Two parallel Geiger tubes inside the sample tank transmit through a rate meter to a follow meter and chart recorder in the control room.
The stack gas and particulate monitors have both local and remote (control room) alarms.
Alarm set points and action levels, as well as maximum allowable release rates, are set by the Technical Specifications of License R-77.
A copy of applicable sections of the current Technical Specifications is attached as Appendix 8.
Amendments to these specifications shall be considered applicable to this license.
10.9 Personnel Exposure S
Personnel who frequent the BMRC are potentially exposed to radiation as authorized by Reactor License R-77. New York State License 1051, or this license.
It is not possible to segregate accurately the exposure attributable to each license. The only credible, significant exposures resulting from the materials authorized by this license are exposures to the Pu-Be sources. Personnel who might manipulate these sources are required to wear dosimetry.
It is estinated that exposure attributable to this license constitutes less than one per cent of the total exposures at the BMRC. Appendix 9 provides summaries of worker exposure for the last five years.
10.10 Emergency Procedures The BMRC has an NRC-approved emergency plan (Docket 50-57).
In
. addition to this emergency plan are the Emergency Procedures, which are attached as Appendix 11.
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APPENDIX 3 NUCLEAR SCIENCE AND TECHNOLOGY FACILITY STATE UNIVERSITY OF NEW YORK AT BUFFALO NUCLEAR SAFETY COMMITTEE CONSTITUTION ARTICLE I: NAME s
The official name of the committee shall be the " Nuclear Safety Committee of the State University of New York at Buffalo", hereinafter O
referred to as the "NSC".
ARTICLE II: PURPOSE The purposes of the NSC are:
(a)
To periodically review and advise the Director.in regard to the radiation J
and nuclear safety programs at the Nuclear Reactor Facility located on the Main Street campus (hereinaf ter referred to as the " Facility").
(b)
To review and approve experiments referred to it by the Operating Committee
()
(see By-Laws), because of the degree of hazard or unusual nature of the i
experiment.
(c)
To review and approve proposed changes to Facility licenses, changes to technical specifications, and experiments or changes made pursuant to 10 CFR 50.59.
(d)
To review reportable occurrences.
(e)
To carry out duties as may be prescribed by licenses, specifications, and manuals, l
-r-I i
O O
2-1 A reportable occurrence shall be any of the following:
i (a)
Operation in excess of a safety limit, as defined by technical specifications.
(b)
Discovery of a Safety System Setting less conservative than th,e limiting value established by technical specification.
(c)
Operation in violation of any condition for operation as established by j
technical specification.
(d)
A safety system component malfunction or other component or system malfunction that could, or threatens to, render the safety system
}
incapable of performing its intended safety functions.
4 j
ARTICLE III: MEMBERSHIP AND OFFICERS The membership of the NSC shall include at least six persons with expertise in the physical sciences, and preferably some nuclear experience.
Members need not be employees of SUNY.
Permanent members of the NSTF are the Facility Director, the Facility Operations Manager, and the Radiation Safety 3
()
Of ficer (RS0).
The committee shall elect from its membership a chairman and a secretary.
ARTICLE IV:- MEETINGS i
(a)
The NSC shall meet twice per year, and more often as required.
(b)
Meetings may be called by any member.
(c)
Minutes of all meetings shall be distributed to all members.
ARTICLE V: CONSULTA!rrS 4
The. committee shall solicit the advice or recommendation of consultants l
or experts as required, before approving any experiment, or reactor or license
'~
modification, for which the committee members do not possess suitable knowledge or expertise.
4
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3-ARTICLE VI: QUORUM A quorum of the NSC shall consist of at least five members, including the chairperson or his or her designee, and the Operating Committee. A majority of individuals who are not NSTF staff members is also required.
{
ARTICLE VII: BY-LAWS The committee shall establish By-Laws which will be the rules of O
procedure.
ARTICLE VIII: AMENDMENTS TO CONSTITUTION Amendments to the Constitution or By-Laws may be proposed by any member of the' committee, and must be approved by a majority of the members.
O e
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NUCLEAR SCIENCE AND TECHNOLOGY FACILITY STATE UNIVERSITY OF NEW YORK AT BUFFALO NUCLEAR SAFETY COMMITTEE BY-LAWS 1.
The Committee Chairperson shall notify the members of the Agenda, not later than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before a regular meeting.
For emergency meetings, the Agenda shall be included with the meeting notice.
2.
Questions before the Committee shall be decided by a vote of the members present, the concurrence of a majority of' the members present being required for approval.
3.
Non-permanent members of the NSC shall be appointed by the Facility Director with the approval of the Radiation Safety Officer (RS0), and the majority consent of the Committee. Appointments are for two years, and can be renewed indefinitely.
4.
The Operating Committee shall consist of the Facility Director, the Facility Operations Manager, and the RSO. The Operating Committee is a subcommittee of the NSC, and is authorized to oversee and approve routine activities and experiments.
Matters shall be referred to the NSC at the discretion of any member of the Operating Committee, or as required by technical specifications or the NSC Con-stitution. The Operating Committee may appoint additional non-voting members to the Committee, with the unanimous approval of the permanent Operating Committee members. These additional members need not be members of the NSC.
Each member of the Operating Committee shall designate a qualified individual to replace him or her when absent from meetings or during prolonged absences from work.
The Operating Committee shall perform the following:
(a) Review experiments which present no new, significant safety problems.
(b) Approve additions to or revisions to Operating Procedures and Emergency Plans.
(c) Review abnormal occurrences.
(d) Perform Facility inspections.
5.
The NSC shall tour the Facility at least once each year.
m O
O APPEND 1X 4 8048 Kimball Tower.................. Diane Wood G-58 Forber................. Geroidine D. Riedoy OFFICE OF THE CHANCELLOR 138 Forber.................... f..Jomes J. Rosso CHflon R.Wharton, Jr., Chancellor 158 Forber................
124 Kimball Tower................ Lauro A; Kotos -
State Universityof NewYoric Rena Browne,Irv+enn State University Plazo Amherst Compus i=*ans Albany, RY. 12246.................. (518) 4 73-4060 103 Center fcr Tomorrow............. Donna Cross i
103 Center for Tomorrow....
CENTRAL ADMINISTR TION 108 Nortori..................... Gloria K-e i
- 39ag,
.... Judith Dogeldey 581-L Spoulding Quad, Bldg. 5... Winifted Soubert Albany, RY. 12246 " " " " * " " " " * (518) 473-4060 108 Crofts Hall.......................Erleen Anton 434 Crofts Holt................ Frances R. Stonton W YORK CITY OFFICE 202 Crofts Holl.................... Bowity Hughes Dr. George Blair,, Assistant to the Choncellor 206 Crofts Hall..................,... Arlene Brown
. State Unhersity of New Yoric 206 Crofts Hall................. Dani 224 Crofts Ho:t........................el A Podolic 60 East 42nd St. Rm. 3318 Gerry Kisker New York. N.Y. 10165................ (212) 6 314 Crofts Hall................Mor 330D Crofts Hall.....'.............guerite Reddien
.... Ullion $ltel(
O 434 Crofts Holi.................. Frances Alspough SUNY CONSTRUCTION PUND 102 John Boone Center..........
Bissell Hall....................... Florence PIlocki Dr. W R Freedmon. General Monoger and Vice Donald M. Roy Chancellor for Copnol FocHMies Bissell Hall...................... :...... John Greio Morton Gossmann, Monoger of Program Plonning.
Bissell Holl...............,......
..Dione 6toiorsid Design and Construction Bissell Hall.................
Construction Fund 406 Copen....................... Kurt Herrmann.
State Uniwrsity Plazo
....Delores Korczynski Samuel Helm Bldg...............Wolter R.10yezeic PO Best 1946 Albany, N.Y. 12201.................. (518) 4 73-1134 Ridge too Compus 4240 Ridge Leo................... Doris Millhollond Buffolo Rold Office see depu.6.60tol listings mmpus locanons SUNY RESEARCH FOUNDATION Educational Opportunity Confer Jerome B. Komisor, President 465 Woshington Ave.............. Beverty J. Dow John F. W, m 6 mt Educational Opportunity Center yog g 465 Washington Am..o o o o n, N SuMer State Unlarsity Plozo Albany. N.Y. 12246................"., (518) 434-7015 Educational Opportunity Center 465 Washington Am............ ' Iris Tc,.a.e0c,.. u Erie County Medical Center SUNY PRESS Medical Of. flee Bld O
Rm. 2iSC........ g..
Williom Eastman. Director
............ Marsha Stroubinger State Uniwrsity Plazo Erle County Medical Center
~
Albany. MY. 12246.................. (518) 4 72-5000 BB Annex. Rm. 201............ Glorio A Landsman.
STATE UN VERSITY
.UNVERSITY OF \\ ~W YORK AT.BUF_ALO BOARD O' TRUSTEES.
THE COUNCIL F
Donald M. Bilnken. Chairman STATE UNIVERSITY OF NEW YORK Mrs. Judith D. Moyers. Vice Chairman AT BUFFALO g
in Do r ick' Williom C. Boird, Chairman Emeritus Mrs. Judith L Duken H
Chairman EmerHus Arnold B. Gordner Robert L Milloruf. Choirman Emeritus John LS, Hollomon, Jr., M.D.
g k Non hson M M W. W i Edwcrd V. Mete John F. Kopezynski. Sr.
Ms. Susan Wray i
James F, Phillips. M.D.
Edgor A. Sondman W h K. Robinson Thomas Von Arsdale ggggg Darwin R. Wales John R Walsh. El Philip B. Wels. M.D.
3 oppointments pencing Josept) Sorkis, Student Representottve f
X
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Acheson Hall 13 Farber A. 22 ar Research Center.
l Acheson A 12 Foster Hall 38 Parker Hall - 10 Annex A 28 Goodyear Hall 30 Parker Annex - 11 j
Annen 8 27 Harriman Hall 41 Pntchard Hall - 33 I
Allen Hall - 34 Hayes Hall-1 Rapid Transit Station - 42 l
Beck Hall - 9 Hayes A 4 Rotary Field - 20 Cary Hall. 23 Mayes B. 3 Service Building - 16 Central Heating Plant 15 Hayes C 5 Service Center Building 17 l
Clark Hall.19 Hayes D 2 Schoellkopf Hall - 31 Clement Hall-29 Howe Research Laboratory 18 Sherman Hall 21 Crosby Hall. 38 Kimball Tower. 32 Squire Hall 35 Diefendorf Hall-39 Macdonald Ha!! 25 Townsend Hall 8 Diefendorf A. 40 Main St. Library 6 Wende Hall. 7 i
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Abbott Library 37 Farber Hall - 24 Michapall,_2&_
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Acheson A - 12 Foster Hall - 36 Parker Hall 10 An7ex A - 28 Goodyear Hall - 30 Parker Annex - 11
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1.85x10 n/sec a.
Unmoderated Source Distance Neutrons, mrem /hr Gama, mr/hr contact 100 50 6"
20 5
0 12" 10 0.75 7.
7
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0.5 b.
Moderated (1 Cm Water)
Distance Neutrons, mrem /hr Gamma, mr/hr Contact 60 24 6"
30 3.5 12" 14 1.6 24" 3
1.25 1.7 1
48".
c.
Moderated (5 Cm Water) i Distance Neutrons, mrem /hr Cama, mr/hr Contact 25 8.5 6"
15 2.5 12" 6
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Unmoderated Source Distance Neutrons, aren/hr Gansna, mr/hr Contact 1000 260 6"
300 46 12" 110 17 24" 50 5
_.. = ~
36" 18
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Distance Neutrons, mran/hr Gamma, mr/hr Contact 800 200 6"
300 40 12" 110 15
~24" 45 5.2 48" 12 1.3 O
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Distance Neutrons, arem/hr Gamma, mr/hr Contact 500 100 6"
200 23 12" 80 12 l
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~
Appendix 8 The Pool Temperature scram ensures that the reactor will shut down if the LS3 for bulk pool temperature is exceeded, as this parameter enters into the thermal-hydraulics safety analyses.
The Recorders Inoperative interlock ensures that the recorders indicating reactor power or startup count rate are operative during startup and operation of the reactor.
The neutron detectors provide assurance that measurements of reactor power or source multiplication are adequately covered at both low and high ranges.
The blade positions indicators ensure that information is available to the operator of the control element positions and, hence, the amount of available negative reactivity.
(]}
The N-16, core AT and primary temperature systems provide a measure of reactor power that is not sensitive to neutron flux distribution.
The suction-valve-closed interic-k prevents implosion of Lhe H-16 delay tank.by primary pump suction.
Specifications 3.2(2) and 3.2(3) ensure that primary control devices are oper-able and that upon exceeding any LS3, automatic protective action will promptly avoid exceeding a safety limit.
These specifications help to ensure that the safety margins between LS8s and SLs are adequate.
3.3 Radiation Monitoring Systems 3.3.1 Fixed Area Monitors Applicability:
These specifications apply to the permanently mounted radiation monitors in the containment building that have readouts and alarms in the con-trol room.
Objective:
The objective of these specifications is to set a minimum level of performance for the. facility area monitor system when the reactor is operating.
Specifications:
(1)
The normal contingent of operating monitors when the reactor is operating shall be (a) neutron deck #1, 2, and 3; (b) reactor bridge; and (c) hot cell.
(2)
The alarm set points for each monitor shall be clearly stated in a facility operating procedure.
(3) Monitors may be removed from service for repair, replacement, or calibra-tion in accordance with the following restrictions:
(a) No more than=oneaofrthe three monitors on the neutron deck may be out of servi'ce at a given time.
(b) The hobc.cel.Lumoniton may.be out of service for extended periods-pro-vided the key-toathe=cellvit-administratively' controlled.~
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~
Appendix 8 (cont.)
(c) The bridge-monitor may be out of service for periods up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, provided.ceactor-power: level is not increased during that outage.
(d) Any monitor may be temporarily replaced by a portable unit that pro-
- v. ides equivalent functions.
Bases:
Specification 3.3.1(1) provides that the neutron deck area monitors alert the operator and experimentors of unusually high radiation levels on the neutron deck; the bridge monitor alerts operators and others of high radiation over the pool, which could conceivably result from low pool water level or experiment transfers; the hot cell monitor warns personnel who may potentially enter the cell that high radiation exists within.
Specification 3.3.1(2) ensures that each monitor will have a clearly defined alarm point that cannot be altered without formal review.
Specification 3.3.1(3) provides for normal repair and calibration of the area mw itor system without shutting down the reactor.
3.3.2 Effluent Monitors and Primary Coolanti onitor Applicability:
These specifications apply to the permanently installed syscams that monitor the airborne radioactivity leaving the facility and also monitor the activity of the primary coolant.
Objective:
The objective of these specifications is to establish a minimum operability level for the effluent and primary coolint monitor system.
Specifications:
(1) The normal contingent of operating monitors when the reactor is operating shalT be the building air continuous monitor, stack air continuous monitor, stack particulate continuous monitor, and primary water monitor.
Ob (2) The alarm points for the two gaseous effluent monitort shall be clearly stated in a facility operating procedure.
The alarm points for the pri-mary water' monitor and stack. particulate monitor shall be posted on the radiation monitor panel in the control room.
(3) The outputs of the building air, stack air, and stack particulate monitors shall be recorded on a strip chart.
(4) Both air monitor systems shall provide fixed filters for evaluating par-
- iculate releases.
(5) One of the two gaseous effluent monitors may be out of service for up to 4* hours'while the reactor is operating, provided that no unusual experi-ments are bei,ng,.copducted and no radioactive chemical processing is being done in the hoods.
The pnimary water monitor may be inoperative for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> while the reactor is operating, provided that both air effluent monitors are operating.
Thr Tthclr) articulate ~ monitor may ba out of ser-vice for periods not exceeding.one week, provided that the fixed filter is
, evaluated daily.
The recordeF may be out of service for periods of time not to exceed.48:hourr ns11ong.as the effluent _ monitor values are logged
._ g
Appendix 8 (cont.)
- at nominal 15-min intervals while the reactor is operating.
The primary water monitor need not be operative in the natural convection mode.
Bases:
Specification 3.3.2(1) provides assurance that adequate operating instrumentation exists to monitor airborne effluents and primary coolant activ-ity wher, the reactor is operating.
The building air and stack air monitors measure the concentrations of gaseous radioactive materials being released to the environs.
The stack particulate monitor measures particulate airborne radioactive materials in the stack exhaust.
These monitors enable the operator to ensure that applicable release limits are not being exceeded and maintain released materials to a level that is as low as reasonably achievable.
The primary water monitor provides indication of unusual levels of radioactivity in the primary coolant that might arise as a result of fuel cladding or experiment failure.
(V Specification 3.3.2(2) provides for the unambiguous establishment of alarm set-
~'s tings for the effluent and coolant monitors.
Specification 3.3.2(3) ensures that a permanent record of effluent releases shall exist.
Specification 3.3.2(4) ensures that a means shall be available to evaluate par-ticulate releases from the facility.
Specification 3.3.2(5) provides for limited inoperability of the monitor equip-ment in order to permit maintenance and calibration of the systems without shutting the reactor down.
3.4 Engineered Safety Features 3.4.1 Rea'ctor Containment Building O
a niicebiiitv:
these specificatioas pair to the r ciiity coat ia eat vessei n
and its associated airlocks and ventilation system.
0bjective:
The' objective of these specifications is to control the release of airborne radioactivity from the facility under both normal and off normal conditions.
Specifications:
The= reactor"will'not be operated unless the following condi-tions are satisfied:
(1) The truck door shall be closed and sealed, one door in each of two air-locks-shall be closed and sealed, and all other' penetrations other than ventilation ducts shall be sealed.
(2) The stack' fan-in the university steam plant shall be operating and the fan in the-building air duct ~shall-be' operating.
(3) The. pressure in the containment vessel shall bemegative with respect to the outside atmosphere.
(4) The.demper.s in the containment ventilation ducts must be-operable-and be capable of closing inab sec.or lesg.
They must close automatically in
i TABLE I EFFLUENT MONITOR 5 ALARMS MONITOR LOCATION SENSOR RANGE PURPOSE FUNCTION LOW llIGH 5
PRIMARY PUMP GM TUBE 10-10 PRIMARY INSTRUMINT 10,000 CPM NONE WATER ROOM CPM WATER FAILURE ACTIVITY 9
\\
BUILDING FAN 36" EXHA!IST INSTRUMENT 1,000 CPM WITH AIR ROOM 2 GM TUBES 10-10 DUCT GAS FAILURE BRIDGE d
CPM ACTIVITY TRIPS E
h DAMPERS x
co 2
k BUILDING FAN GM TUBE 10-10 36" EXHAUST INSTRUMINT 100 CPM NONE PARTICULATE ROOM CPM DUCT FAILUR3 PARTICULATE ACTIVITY e
UNDERGROUND 5
STACK MECHANICAL 2 GM TUBES 10-10 EXHAUST INSTRUMENT 2,500 GPM NONE GAS EQUIPMENT CPM DUCT FAILURE ROOM ACTIVITY GASEOUS UNDERGROUND STACK MECHANICAL GM TUBE 10-10 EXHAUST INSTRUMENT 2,000 CPM NONE PARTICULATE
' EQUIPMENT CPM DUCT FAILURE ROOM ACTIVITY PARTICULATE
O O
APPENDIX 9 Summaries of Worker Exposures 1980 through 1984 0
5 9
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O O
i NSTF EXPOSURE
SUMMARY
1984 Total Whole Body General Investi-Dose (REM)
Processors Staff gators Visitors Tours Security None measurable 0
8 21 369 468 49 None + <.100 0
6 6
0 0
0
.100
.250 0
3 6
0 0
0
-.250 2500. -
-_l
.? --
- Or 0----
0--c-
.500
.750 0
1 0
0 0
0
.750 - 1.000 3
3 0
0 0
0 1-2 0
1 0
0 0,
0 2-3 0
0 0
0 0
0 4
24 39 369 468 49 O
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-, + -.
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NSTF EXPOSURE
SUMMARY
- 1983
- Individuals TOTAL WHOLE BODY NSTF NSTF DOSE (REMS)
Isotope General Investi-Processors Staff gators Visitors Tours Security None Measurable 0
1 18 442 351 49 None Measurable - <.100 0
8 4
0 0
0
.100
.250 0
6 2
0 0
0 j
-~-----_--:.--w=--
'"'~~~-- -
230
~~.300^
l 4
3 0
0 0
..i00
.750 3
0 1
0 0
-0
.750 - 1.000 0
3 1
0 0
0 1.000 - 2.000 0
1 0
0 0-0 4
2.000 - 3.000 0
0 0
0 0
0
> 3.000 0
0 0
0 0
0 4
23 29 442 351 49 O
i i
i l
i i
1 1,
1
_ _. - -. _ _. _. _,. _ _ _,., ~
- _ _. - _ _. - ~.. - _ _.., _ _ - _ _
r'%
fr Q
\\j NSTF Personnel External Radiation Exposure Summary Calendar Year 1982
__==____________-_________________
NUMBER OF INDIVIDUALS IN EACH RANOE
_ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ = - -.
ANNUAL WHOLE BODY ISOTOPE PUBLIC DOSE RANGE (REMS)
NSTF PRODUCTION SPECIAL SAFETY VISITORS TOURS STAFF STAFF PROJ OFFIC.
None measurable 1
0 4
51 592 564 Measurable <O.100 2
0 7
2 O
O O.100 - O.250 3
0 1
O O
O O.250 - 0.500 7
1 O
O O
O O.500 - 0.750 3
0 0
0 0
0 0.750 - 1.000 1
O O
O O
O 1.000 - 2.000 0
3 0
0 0
0
{'
2.000 - 3.000 O
O O
O O
O y.;
._ > 3.000
.O
- _ O. _..
0-O.
n-
--n-TOTAL No. Reported 17 4
11 53 592 564 TRAINING The RPD Participated in the annual Reactor Requalification prosram.
A lecture on Radi4 tion Control and Safety Was Presented and questions drawn from the lecture Peovided for the final exam.
The RPD also provides trainins to maintenance workers, students and new staff members when needed.
RPD also Participated in the NSTF's Annual Emersency Drill held on 11/17/S2.
RELEASES TO THE ENVIRONS
()
Tables 2-A and 3-A represent the steady-state and transient releases of radioactive materials to the air from the NSTF's Buildins Stack and Power House Stack.
Arscn-41 is produced as a result of neutron interaction with naturally occurrins sases dissolved in the reactor Pool water.
Cesium-138 is a Particulate fission product arisins from the decay of saseous Xenon-138.
Their co'ncentration is a function of reactor operation, power level, and time.
The remainins nuclides represent losses from radioisotope Production and experimental irradiation facilities (such as the Pneumatic Conveyor System and the in-core Isotore Facility).
All are substantially beloW Permissible release levels.
Table 4-A represents the release of radioactive material to the sanitary sewer from the drains and sinks in the NSTF containment buildins.
They are collected in waste holdins tanks and assaved Prior to discharse to the sewer.
The levels are substantially below maximum release values, both in total quanti-tv and concentration.
9
__,.,.,.-__m-w
~ -
0 0
Table 1-A nummarizoo NSTF Poroonnol-external radiation exposures.
TABLE 1-A NSTF Personnel External Radiation Exposure Summary Calendar Year 1981
- - - = - __
.=======_
.-----==_________=----
NUMBER OF INDIVIDUALS IN EACH RANGE
===_--
ANNUAL WHOLE BODY ISOTOPE PUBLIC DOSE RANGE (REMS)
NSTF PRODUCTION SPECIAL SAFETY VISITORS TOURS STAFF STAFF PROJ OFFIC.
None measurable 5
0 5
53 827 721 Measurable <0.100 4
0 3
4 0
0 0.100 - 0.250 5
0 0
0 0
0 0.250 - 0.500 3
1 O
O O
O O.500 - 0.750 2
2 O
O O
O 0.750 - 1.000 1
O O
O O
O Os 1.000 - 2.000 O
1 O
O O
O 0--
n-0.~
~ 2.000 -~~3.000 o'
O O
7
> 3.000 O
O O
O O
O TOTAL No. Reported 20 4
8 57 827 721
=---- -
=
TRAINING The RPD Participated.in the annual Reactor Requalification Program.
A lecture on Radiation Control and Safety was presented and questions drawn from the lecture Provided for the final exam.
The RPD also ProVides trai'ning to maintenance Workers, students and new staff m'mbers when needed.
e RELEASES TO THE ENVIRONS Table 2-A represents the routine and non-routine releases of radioactive materials to the air'from the NSTF's.Buildins Stack and Power House Stack.
Arson-41'is Produced as a
result of neutron interaction with naturally occurrins sa'ses dissolved in the reactor Pool water.
Cesium-1'38 is a Particulate fission Product ~arisins from the decay of sas'eou.s Xenon-138.
Their conc-entration is a fonction of reactor operation.
Power level, and time.
The remainins nuclides represent losses.from radioisotope Production and experimental irradiation facilities (such as the Pneumatic Conveyor System and the in-core Isotope Facility).
All substantially below Permissible release levels.
Table 3-A are represents the release of radioactive material to the sanitary sewer from the drains.and sinks in the NSTF containment buildins.
C'ollected in Waste holdins' tanks and assaved Prior to Thev are discharse to the sewer.
The levels are.substantially below maximum release values..both in total-guantity and concentration.
wr
-- - - i m-
---=w pim,*
,n.--c
--m
-w-
.L
./,
(Oi
/
/
/,'
f NSTF Personnel Plternal Radiation Calendar Year 1980 Exposure Summary -
NUMBER OF INDIVIDUALS IN EACH RANGE Pdblic Ipotope NSTP_
Production Special Safety Annual Whole Body Dose Range Staff
.Sta f f Proiects Officers Visitors Tours
((-.-]
(Rems) 14 64 908 150 E
10 No Measurable Ekposuro Measurable Exposure Less 1
9 5
than 0.100 8
0.100 - 0.250 4
1 0.250 - 0.500 1
0.500 - 0.750 1
1 0.750 - 1.000 1
2 1.000 - 2'.000 p()
2.000
~1.000 Greater than 3.000 30 4
15 73 908 150 Total number of Individuals Reported
________c
0 O
Appendix 10 Buffalo Materials Research Center LEAK TESTING OF SEALED SOURCES A sealed source is any radioactive material permanently bonded or fixed in a capsule or matrix designed to prevent release of the material under the most severe conditions likely to be encountered in normal use and handling.
Each beta / gamma source (except for H-3) with a half-life greater than 30 days in any form other than gas and containing more than 100 uCi must be leak tested
()
before initial use and every six (6) months thereaf ter. BMRC sealed sources in
___. ____, storage need not be. leak. tested _as.long as they are tested.when put back in
"~
~~
" service or ~transf ered.
Alpha emitters greater than 10 uCi must be leak tested every three (3) months.
Procedure:
Wipe the source itself using filter paper or cotton swabs moistened with water or alcohol. Do not under any circumstances disassemble the device to be leak tested.
Care must be exercised in the testing as not to damage electroplated alpha sources and other similar sources. DO NOT RUB OVER ELECTROPLATED SOURCES AS THIS MAY REMOVE SOME OR ALL OF THE FIXED ACTIVITY - instead rub areas adjacent to the el,ectroplating. Use remote handling tools for sources of high activity.
For certain. sources where direct contact with the source is not possible (as the case in most gas chromatographs), select a sampling point where one might expect
()
contanination if leakage was present.
Instrumentation used to analyze the smear or swab must be capable of detecting 0.005 uCi or removable activity or 0.001 uCi/24 hours radon gas from radium sources.
If a source is leaking in excess of 0.005 uCi (or 0.001 uCi/24 hrs radon gas from radium), the use of that source must be suspended immediately. Arrangements will be made for the decontamination, repair, or disposal of the source by the Senior Health Physicist.
Record Keeping:
- 1) Analyze raw data using " Raw Data Record Sheet".
- 2) Record all findings in the BMRC Sealed Source Leak Test log book.
- 3) Attach data print out to the Raw Data Record Sheet and file in Leak Test Raw Data File.
O o
APPENDIX 11 Emergency Procedures O
e O
4
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