ML20138C237
| ML20138C237 | |
| Person / Time | |
|---|---|
| Site: | 07000267 |
| Issue date: | 09/27/1985 |
| From: | Alexander Adams NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| 25846, NUDOCS 8510220383 | |
| Download: ML20138C237 (93) | |
Text
m l
i l0 F
76-247 BMRC BUFFALO MATERIALS RESEARCH CENTER September 27, 1985 RETURN TO 396-SS PD /L o
x c
RECbb
. 9 3
SEP 3 0 ess >e
_1 tyc Mr. W. T. Crow
{
gettp
-Q Acting Chief CCQy,3 Uranium Fuel Licensing Branch
,,j stau y,
a Nuclear Material Saf ety and Safeguards _ _
v United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Crow:
Docket 50-57 SNM License 273 Enclosed are six (6) copies of our renewal application for Special Nuclear Materials License 273. If I can be of-any as'sistance in this matter, please feel free-to call me.
~
Very truly yours, kh y
e,
,y
- - -Reactor' Engineer _ p.
Alexander Adams, watn
- 2. -
amf usnRC - -
-~
~
~
6-2 SEp 3 0 W r
-3 g
gss pottG tlIFA 7
V en 0
h;m%8 wmvua,1gyh3#'
3
., u s-851022o383 850927 V0 0W L' O PDR ADOCK 07000267 C
PDR 03At3333
/
SUNY-BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE (716) 831-2826
s.
l 76-247 p
BMRC BUFFALO MATERIALS RESEARCH CENTER September 27, 1985 RETURN TO 396-SS PDIL o
n o
S RECBC cEp 3 0 ngs > 3 u.
gy s Mr. W. T. Crow
{
hyttIA%(fg
'lJ Acting Chief ccj,g3 Uranium Fuel Licensing Branch
,,f wte f,
Nuclear Material Safety end Safeguards
/
4 United States Nuclear Regulatory Commission
~
Washington, D. C.
20555
Dear Mr. Crow:
~
' Docket 50-57 SNM License 273 Enclosed are six (6) copics of our renewal application for Specici Nuclear Materials License 273. If I can be of-any as' istance in
~
s this matter, please feel free to call me.
Very truly yours,
]4gg e,
y
. ~.....
Alexander Adams, r.
- -' - Reactor Engin~eer cocxOED of gage _ _.
g..
6 d
ggp 3 0 G85
- r js,s.. _ _ g c, :
-g ootwac#
7
'c3 c
e, y rd'
!!'lHTME j3 g
n 8510220383 950927 V0.0W. L' O PDR ADOCK 07000267 C
PDR 03M3333
/
SUNY-BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE (716) 831-2826
\\'
r f
'?d-26 7 caC ar no.
E7/54
~
co m ot so.
DATE OF DOC.
O//
/[
DATE RCVD.
[
8h [d reuFa/
90 7 #
FCAF LPDR k?f I&E REF. L IN SAFEGUARDS FCTC OTIIER DESCRIPTION:
A9/LAsss V bW vh'Nwud 'y- (/LNn1C MB/85~~uuruu.0/46
'/
/
. - e
.f 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.
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. (BHR),
a private company, manages operation of the reactor and its support facilities.
- The BMRC maintains a close working relationship with SUNY through the Office of the Vice President for Research.
It is with this office that 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 Radiation 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.
e h-
i
> 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 ' hat committee. The NSC consists of a minimum of six (6) t 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 Dep'artment 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 BHRC 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 generated by grants, medical radioisotope production, and industrial 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 above, 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 mainta in 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 attached to this application as Appendix 4.
This page provides applicable information regarding the current University Officers, SUNY Central Administrative staff, and the SUNY Board of Trustees.
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.
1
f
> 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 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 utilizatica occurs within the confines of the BMRC.
Isotopic neutron sources (Pu-Be) may, however, I,e 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 below.
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.
I f
. i 4.2 Radiation Safety Officer t
a)
Ph.D. in a field of nuclear science and three (3) years of l
experience in radiation protection.
or i
b) MS degree in nuclear science and~five (5) years of experience in radiation protection.
t
[
or t
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.
j i
4.3 Reactor Engineer f
i BS degree in nuclear engineering or a closely related field.
[
and j
a) Five (5) years experience in the field of re~ actor physics or nuclear engineering.
l or a
b) Three (3) years of experience with the BMRC.
4
,In either case (a) or (b), the Reactor Engineer must obtain and possess
[
j for three (3) years, or have previously possessed for three (3) years.
a Reactor Operator or Senior Reactor Operator license for the BMRC l
reactor. An MS degree may be substituted for two years of experience under option (a) or (b).
l 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 least two (2) of the three years must be in a reactor operations supervisory position.
i or.
1 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.
l 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 l
visory position.
i 1
r-J
4 e
. 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 subcritical reactor tank.
5.
ICA-4:
The balance of the facility, including the hot cell, and approved campus laboratories.
6.
ICA-5H Howe Building Transfer of SNh between ICA's is documented as specified in the Accountability Manual.
s A physical inventery, 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.
Floor plans of BMRC and Howe Building have been included with this application as. Appendix 6.
6.
Storage and Utilization Facilities The following is a brief description of the facilities available at 2
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).
1
~
, l 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-Be sources may be used or stored within the tank.
Transfer i
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.
i 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 (or vice-versa) in such a manner as to prevent flooding of the cell, and n
with a minimal amount of radiation exposure.
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 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.
I
1
. 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 iostopic neutron sources.
7.2 Uranium,235 7.2.1 Up to one gram contained in fission counters.
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.
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 c: the response characteristics of neutron detectors, boron determinations, studies of the neutron transmission characteristics 4
of materials, and effective shielding thickness determinations.
l 1
. The Pu-Be sources are normally used within the c 1 Ci sources may be loaned to other University donfines of the BMRC.
The Officer, for use in RPS approved radiochemical l bappro epartments with the a
on Safety vided with equi of the sources.pment deemed by the RPS to be adequate for safe utilizatio A metal rod, wire, or nylon line is attached to e means for source handling and transfer which minimiach source to provide a experiment er.
individual source is based on the experiment l fThe choice of the p to be used.
n are used as deemed advisable by the RPS.Use of additional safety devi a
andling tools In general, moderated devices such as water or paraffin-fill d hthe source sembly or in specially fabricated equipment.
owitzers, aquaria or e
devices when not in active use if the device cThe sources may be stored in these when not in use, an be locked. Otherwise, All laboratories in which the sources are used a dth container.
ng or storage tainers and devices used for source storage will n all con-with the requirements of 10 CFR 20 and the New York Soe labeled in accordanc Part 16.
be locked when not occupied, unless materials are othAll lab rage will erwise secured.
The gamma and neutron dose rates from a one (1) and Written procedures for all experiments involvingsource wit a ten (10) curie PuBe ovided in Appendix 7.
'by academic users shall be approved by the O use of Pu-Be source (s) be maintained on file for inspection by the NRCperating Committee, and shall 8.3
_ Uranium-235 Possession of up to 1 gram of uranium-235 contain d i requested.
Fission counters are utilized in conjunction withn fission counters is e
experimen t s.
the counters will not become appreciably actiAs a result of the low ne suberitical n such use, represent a health and safety factor.
vated and do not, therefore, performed in view of the low inherent hazard of the matRoutine leak tests will not b counters may be stored in either the suberitical ass erial. The fission storage room.
be locked in place.When not in active use the suberitical assemblyembly or in the f cover is to Possession of up to 9 grams of uranium-235 in any in any enrichment up to 93.48 per cent U-235 is reqchemical or physical form and development programs.
uested for research performed in accord with written procedures provided by thExperime and approved by the BKRC Accountability Officer and th e experimenter e RPS. Au tho riza tion
a e
a 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 Monitors 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 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): Stcrage area (s) shall be surveyed monthly by the BMRC Health Physics Department. Personnel entry to the fuel vaults is closely monito' red for security reasons.
Each entry is therefore documented.
If, in a g'iven 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.
r g
8 10.2 Contamination Action Levels Action levels for surface contamination shall be specified in the table below:
RADIOACTIVE SURFACE CONTAMINATION LIMITS A
Application Alpha (dps/100cm )
Beta /Gammat 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.
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 MeasureC at 1 cm from the surface.
t N
2
.D. -- non-detectable.
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 Licenses for' Byproduct, Scurce, or Special Nuclear Materials", published by the USNRC Division of Fuel Cycle and Material Safety.
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 act' ion' levels.alone.
If decontamination cannot proceed immediately, (i.e., if appropriate personnel or equipment is not iraediately available), immediate steps will be taken to control and isolate the contamination. This would entail such steps as posting, barr.icading, encapsualting in paper or plastic, etc.
8 10.3 Leak Tests
^
The Pu-Be sources'sh'411 be leak tested by BMRC Health Physics at six-month intervals. A smear of the source will be taken and analpzed, using an appropriate counter.
1
. 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 Special, clearly 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 perfor- :d by the BMRC Director or his designee.
The Director (or his designee: anall review procedures and activities involving SNM twice a year. Any recommendations shall be presented to the Operating Committee. The scope of the audit shall be commensurate with the level of activities performed within the context of this license.
10.7 Training Program All persons 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 an authorization, an individual must demonstrate adequate training, either by in-house training, or documented past experience. The in-house training is accomplished through completion of the reactor operator 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 staff member, or by a teaching assistant authorized by the-Operating Committee.
1 i
f o
12 -
10.8
' Ventilation' Control and Monitoring N i 10.8.1 Ventilction System 7
4
-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 $6" 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 travels to the main heating plant behind BMRC and exhausts at a height of 50.7 mete'rs.
Air pressure in the stack duct is maintained.at-negative pressure relative to the containment.
1 All air. leasing BMRC-is passed through profilters 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.D 10.8.2' Ventilation Effluent Monitoring 10.8.2.1
- Building Air Monitoring A sidestream of air is drawn from the duct shortly before it exits the roof. JThe stream first enters the fixed filter building 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 th.e concentration of radioactive material in the l
sample tank.
Signals are fed to rate meters'and' transmitted to follow meters and a chart recorder in the control room."7 Local and remote alarms are provided.
y 10.8.2.2 -Stack Monitoring t
A.sidestream _ of air is -d'rawn from the s ack duct shortly before it exits the. building.
It is, passed. thriugh a s' lied filter, and then to a sample tank identical to the' building air 'iav A Geiger tube (and window)' coa,t 4)f % nitors activity, collected on the fixed. filter, and sends jits sigt,41 to ratemeter.
A< signal is also sent to a follow meter and chart recorder.in the control room.
s.
s.
+-
i
$k k
a
. 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.
A1. arm 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 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 estimated 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.
e N
b
Appendix 1 e
s2 W
I
!3 num emm a l
I I
L-I I
d i
i g
=
4~I 2
3 I
3 I
e x
g 3
.2 C
a 2
E 2
3.:-[
he' e:
2
..M a
B a
w1 3
48 j
s
.=
.J.
e
-e
=
i-j 131 il Il c
.i a
1 8
ye 3
3
.al 5-3
.3 i
b s
t
i i
Appendix 2 e
p m e_
m W M N
W -
WWW ENEW I
I I
1
]'.
l j
I 3
J i
l l
I I
I I
i 2
q J
g, i
i I
E g
I r
E I
J-3 3
i j
L__. ____.__ __ _ _ __ __l l
3 l
g._
_ __ q i
I I
t l
i 1
I.
1 E
E I.
i I
I E
\\
e i
i j
}
5, 5
i a
_t I
l 8
S.
o E_
I I
3 i
=
l t
r i
I.
L _. ___ __ __. __ ___ __
l i
I.
I
_m...-.
. -. e _.===. = = =. - - = = =
I i
I
~
I z
~r m.
}
l.
l l
l I
e 3
]
I s
1
-l 2
1 v
i i
=
i I
]
=
i 1.
3 a-i I
1.,_._
_ _ _ - l l
I l
i l
P l
APPENDIX 3 NUCLEAR SCIENCE AND TECHNOLOGY FACILITY STATE UNIVERSITY OF NEW YORK AT BUFFALO NUCLEAR SAFETY COMMITTEE CONSTITUTION ARTICLE I: NAMs r
The official name of the committee shall be the " Nuclear Safety Committee of the State University of New York at Buf falo", hereinaf ter i
L referred to as the "NSC".
I t
ARTICLE II: PURPOSE f
I The purposes of the NSC are:
l I
(a)
To periodically review and advise the Director. in regard to the radiation and nuclear safety programs at the Nuclear Reactor Facility located on the Main Street campus (hereinafter referred to as the " Facility").
(b)
To review and approve experiments referred to it by the Operating Committee f
L (see By-Laws), because of the degree of hazard or unusual nature of the l
experiment.
(c)
To review and approve proposed changes to Facility licenses, changes to
[
i i
technical specifications, and experiments or changes made pursuant to i
(d)
To review reportable occurrences.
(e)
To carry out duties as may be prescribed by licenses, specifications, and manuals.
P
.-+
e.
. mee - 6 m
...+ "
- . s* "-
",, ' ~ '
~
(
t
r e
g
. A. reportable occurrence shall be any of the following:
(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 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.
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 Of ficer (RS0). The committee shall elect from its membership a chairman and a secretary.
ARTICLE IV: MEETINGS r
(a)
The NSC shall meet twice per year, and more often as required.
i (b)
Meetings may be called by any member.
(c)
Minutes of all meetings shall be distributed to all members.
ARTICLE V: CONSULTANTS The. committee shall solicit the advice or recommendation of consultants or experts as required, befora approving any experiment, or reactor or license mod'ification, for which the committee members do not possess suitable knowledge- - -
l l
or expert'ise.
l
_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 staf f members is also required.
ARTICLE VII:
BY-LAWS The committee shall establish By-Laws which will be the rules of 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.
e
[
j i
i
~
R 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 Of ficer (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 Com=ittee, 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.
~'
1 L
i
APPEND 1X 4 804810mboll Tower.................. Dione Wood G48 Forber................. Geroldine D. Friedoy OFFICE OF THE CNANCELLOR 138 Forter..................... :..Jornes J. Rosso Clifton R.Whorton, Jr Chancenor l
158 Forbw.................... l... Louro A Kdos -
r I
124 K!mboll Tower......... Reno N State UnbrsHy W New York State UnkrsNy Plaza i
Amherst Compus Locollons Albony, RY. 12246.................. (518) 4 736 j
l 103 Center for Tomorrow............. Donna Cross 103 Center for Tomorrow........Giorlo K-c,4 CENTRAL ADMINISTRATION 1
108 Nortori..................... Judith Dingeldey SW UnbrsNy Plazo 581-L Spoulding Quod. Bldg. 5... Winifred Saubert Albany. RY. 12246 * " " " * " " " " " (518) 47M060 1
10s Crofts Hon.......................Erleen Anton i
i 434 Crofts Hall................. Fronces R. Stonton NEW YORK CITY OFFICE l
202 Crofts Hall.................. Beverty Hughes Dr. George Biolr Assistant to the Chancellor
- 206 Crofts Holl..................,... Arlene Broun State University of New York g
206 Crofts Holl................. Donlei A Podolic 60 East 42nd St Rrn 3318 L
i 224 Crotts Holl........................ Gerry Kisker New York. RY. 10165................ (212) 68 7 314 Crotts Hon............... Mor i
3300 Crofts Hoti.....'.............guertte Reddien
.... Ullion Sitek 434 Crofts Hall.................. Frances Alspough SUNY CONSTRUCTION PUND Bissell Hall...................... Florence Pliocki Dr. W R Mmon, Genwol Monocer and Mce 102 John Boone Center.........
Chcs.c E, for Capital Focilities Bissell Ha!!...............s........ Donoid M. rov Morton Gossmann, Monoger of Program Planning.
Bissen Holl........................... John Greio
%gn and Construction Desi
...Dione 6tolorsid l
B!ssell Holl..............
406 Copen....................... Kurt Herrmann State Univwiny Ploro
.......Delores Korczynski Samuel Helm B!dg..............Wotter R.10yczek po m 94 Albany, RY. 12201.................. (518) 4 73 1134 Ridge ino Compus 4240 Ridge Leo................... Doris Milholland Buffalo Hold Office: see departmental listings Mrnpus Mns SUNY RESEARCN FOUNDATION Educational Opportunity Center Jerome & Komisor, President 465 Woshington Ave.............. Bowrty J. Do" John F. Buckhoff, Executta Mce President 5
Educationo! Opportunffy Center Mail Address-465 Woshington Ava. - o o o o o ChrisHne SuHer State Unkrsity Ploro Albony. RY. $1746................"., (518) 434-7015 Educational Opportunity Center 465 Woshington Ave............. ' Iris Tc.;;;, "4er c, t Erte County Medico! Center SUNY PRESS r
Rm. 2iSC.7,ce 8 dg WilliamEastmon Director Medical 0
................... Marsha Stroubinger State Unbralty Plazo l
Erie County Medical Center Albany. RY. 12246.................. (518) 4 72-5000 BB Annex. Rrn 201............ Glorlo A Landsman.
i S"A E U N VE7SITY
.U \\llVERS TY O: N 9N YORK AT BU:FALO l
l BOARD OF' TRUSTEIS.
STATE UNIVERSITY OF NEW YORK THE COUNCIL j
Donald M. B!Inkeri Chairman Mrs. Judith D. Moyers. Mce Chairman Ay gyyyAgo
{
George L Corans. Jr., MD.
M. Robst Koren Chairman D. Clinton Dominick Wiluom C. Baird. Chairman Emerttus Mrs. Judith L Duken Seymour R % Chairman Emmttus Arnold B. Gardner Robert i Millonzt Chairmon Emerttus John LS. Hollomon, Jr., M.D-Frank N. Cuomo Mrs. Non Johnson Mrs. Harriet W. Fogari Ederd V. Mele John F. Kopezynsid Sr.
i 1
Ms. Suscn 'Ntoy l
Edgar A Sandman t
James F, Phillips. M.D.
Ms. Joon K. Robinson i
l Thomas Von Arsdale Mrs. Rose H Sconlas j
DorMn R. Wales John RWolsh, til i
)
Philip & Wels. M.D.
3 oppointments pending JoseptiSorkis StudentRepresentative X
APPENDIX 5 3-I GRAMD k
\\
1 ISLA ND '
^
\\(
k i
\\\\
9
_.=
N
,k g(\\
gN s,
/
e l
w 1
- eo 29 0
gtsbv*7 r,
1 du ggiet*
9 4,V n
,o q
t.A KE ERIE
/
s,**e 33 e
/
5 Ce
,*e, n
2 9
,/
e, 9
e r*.y
/
6
/
/
Os Ne e
[
stre**
o gato N*In c
e-I
- e i
N.y l
\\
- 4,
V e
e S
STATE UNIVERSITY
- y
++,
5 4
0F NEW YOE 6
g AT PUFFAID j
g Ot e
il L.
APPENDIX 5
?g g "g; f
'?t 3
4k
)
q,
(
- s
{::l1 3
-~. ; b;\\:(.;khf.
7 4
Gw.:.
i q~ -
p.
3
,'ap a -,
.) ; 1 87Q
. },I:.;
,..j:. s. y
~
^
df,'*l?f.d; ';
'9,..s W
. ~..., -
[-
S T48 y
lh%
(.
flEl i.:
,?
sg
~
f 3.w
..kij'<
..s y -
~:gy,
[ $c,.,;
j6(hs>
h;.{9v' &if ~'
l
..,1(:;f9s;
?~
c y hF'" ^ bi i
lf [
$(W!;i%@l l ki B
v) 9s
- 1 q q h tu O i TO1 l
4 -.J
=
LWIRI 6 $ Y 'i $
$5 5 *~
8 f, 7E l
APPENDIX 5 A
.1 L
M r
Abbott Library 37 Farber H 318 - 24 M c hagLf tal, 26.
Acheson Hall 13 Farber A - 22 CEdiear Desearch Center 14 ]
Acheson A 12 Foster Hall - 36 Pa'a er Ha' 10 Anren A - 28 Goodyear Hall 30 Pa ker Arren - 11 Annen B 27 Harriman Hall 41 Pr tchard Ha'l - 33 Aden Ha!! 34 Hayes Hall 1 nap-d Traas.t Stat >on 42 Deck Hall - 9 Hayes A 4 Rota v F.e, ! 20 Cary Ha.!
23 Hayes 0 3 Semce Ua ung - 16 Centra + Heating Piant 15 Hayes C - 5 Se wce Center Oah1og 17 C: ark Ha:I-19 Hayes 0 - 2 Schce '=op' Han 31 Clement Hal - 29 Howe Research Laboratory - 18 S* e ma, Hall 21 l
Crosby Hail - 38 Kimball Tower 32
, p e H a n 3 5 O>e'endorf Hall 39 Macdonald Hall 25 Tca" send Ha4 8 Die'endorf A - 40 Main St. Library 6 Mnce Hail 7 l
f:
g i
n pse o= 3 kThes"7 i
g i
e s
Ul..
f sp l
asiE 4
~
l ra N
s' l
s t
i l
e G
{
i h
i, l
cs s.. -
e 3
e
{
9
<r,
I (g
j j
~
s un;g
~
s kl
- fS l
f
%ifi(%;
i o
4 ee W
j
~
g,
)
l A
~
8 N\\//'
Main Street Camp.us
/
.. e H.-
o
.e. c e e.
Q 2
s.
.um 2s Aa.se. a 3
Mos es 8 29 Anim A f.
/
4
- t av es A 30 Clement Haat t
aaves C 3
Gaed,e.e Neu
'/
6 Priv s.c al Sc.eace L.tn eev 32 Schoeitope Here Hochseestee Hele 33 Stock ton Towee Heia
.f/
f] ' j G
Towresend Hase 34 Coote Hart
[g 9
06d F aculty Club 35 Ba.ed Heft 0*
5 f -
Parnee Eng.neeruse Build.n 36 F ottee A 10 Ct,.ee co.. g.e.e.e..,g. o
.e.g n
oe toe. H a.,
il 12 Acheson A 38 Fostee Hase 17 I
13 Acheson Hets 39 Lockwood L. bee *v
^
) 14
%ciese fleweech Centee 40 Crosby Hat
/'.
s e yf
[/
15 Centwaa Heating Ptant 41 Lockwood Lebearv A
/
yh '
[3 16 Seewce Build.ng 42 0.efendorf Hart O
1' See..co Centee Bu.sd.ng 43 Deetendoef A h' %9'#
20 Motary Fie et y.
- k'. ' *)
IS Carbon Reseech Laboestory 44 Have.ma.i Lhaev g
,s 19 Cia t Gy m L
a o_
g v
-}
ll gj,.
j y7 s
22 Caoen A 7
g'
?l O'E 8 E'e00m 87/ -
, f,
'g 21 Sherman Hate A,
6_i g
e omearies u
" ' v" 14 !
4\\
23
.tes.sh Sc.ence Sw.id.ng i
I l'eff.'.. -
M, 4, {
,4 24 c oe
'4 a
si s
-p
\\
25 Ntacdonald Heel y
.g 9;g-8W *ee.st l,s 26 Mechae4 Hast 3
C**^8 L LOT b
m
)
cart se Lot Lf4 i
/
4'5a'*""8 1_,,1r 1
i,en.r s.e.t.
.u m_
11 pammt.
g
- l 1-U-
s 7
__, h__ =;_4 g' f_
,_h1 [.. l N
f LOT m
.. j t '5e.=== a soe(j
'2 f. 26 -
25 -
. p
_.e.;_yy res 4 _g J.[
.i' f" "(,1dnE6M ifisd
- ' ' mo v
[
s io.
. k.e. v.L:.=.._3.;;n i e u,1,4.,o 2
x gr p gny/
q
.a....
/
s.a Q3,
.,,,lq.......,_\\..
. -&s
_e A
. 2.
a ti r >e r
M s.-.
y m, -
_r y
- -. -. Q
~qt5$
s V
cooov. a. Lo, x.. (av
,j l 35
<- (f
} g,""*""*7"g j.
[
a ia-#,-:.e n e
- g oua town,sg,,o to, 46 a
f.;
j
'0I k
0 g\\
g naa sa lev LOT x
[s
,,.t, p
.}
2 e a.ao tot g\\
y,,
.m
__._...i._
L)_
Q-
. _ _ _ _ ( L g
Y 1
af T"
a 7
APPENDIX 6 Floor Plans of BMRC and Howe Building (RPS)
O I
i
_f
-)
ak a c n
mm e o
aD rk l6' 3
G t ce saD LN T
3 NE U
]
M
?
N IAT pg NO C
RO T
U
{
s N
C O
A l
I E
o T
R r
C t k E
nc S
oe CD J
W E
S R
E L
[
V k
k S
rc rc N
i o i o A
T m
1 r
o o
D r
k o
c o
u i.
l l
r F
l T
t e
s
~
r 1
i p
F g
kc k
e c
D e
D n
o y
l a
r N
o n
t O
rk u
m u
/
I t c a
e T
J ne C
N C
S oD E
E C
I S
I r
R o
h L
O o
A T
l N
A F
I R
D O
t U
B n
T A
e I
L m
C e
N s
D O
a L
B
/
ggu
\\
\\
o
, 4.
\\
l an mm ru 1
l-el r
h o e
ij I
.i i1l
!!t iIl i
iTC l
i a
r T
-C
(
8
- l i'
4 I
ff!
il I
I fI
}/
t l
K~
I u
C
)
a E
V D
k N
p n
O U
aT R
(
d T
U ik p
E bn U
N
~
a l
T d
6 l
1 o
I N
6 1
[\\ - N p
U h
K
(
C l
E at pm D
cn mo i e uo N
n m PR O
a p R
hi m
\\
T c uo U
e qo
'[Y MER EN h
r gni m P
no U
oo i R l
t ll d n it N
ne O
om l
I Cp n
T te A
en l
i ru D
ln iq N
nu AE U
$T O
F
~
tb
~
b oa a
HL L
R KC c
E K
tl D
CR k"
ol r
UO A
RO He o0 C
WE M
TD M
1 A
C b
k u
c I'
oL n
em p
a i t J-b r
r Ps a
i e
yr y
G L
A ut l
co mS NR n
nt a
r E
UW ea el in o
gr t e OO ot OT in li re S n C
t e at en n
l cu u e ou pm m
ib DC
/. {T T,,
i dnio ri s
t r
/
ouR ct%
a Cq es iI A3 ey E
li
/, ',
ra r
ED AW i
U)f A
~
r 7
fo r t
~
e u
'[l tii e
l t h l1 lili' ip l
eS il n
l j1 M(
g il il ho b
i ill ch a
i aS L
il M
ll g
iti T
J.i iI j
1 PU!
t n r
D I
p U
R O
m OL o
i.
F R
K T
t C
N n
E E
e
(
b D
a m
D L
p A
S i
i A
u C
B n
q
?A i
E l.
e C
t g
v l a ar n
a i
C ce t
il t e n
rc u
~
ec o
VA C
a l
.I' l
P U
ig!
l l
lI li1 i
t l
ec i
f l
f
- o O
r 4
e o
c C
i f
f f
ke
'-p O
cl eo DH e
K s
l C
u E
o l
c D
H l
i e
rp CQf L
n o
t o O
a o
ch
['
R F
t R
eS T
o l
N H
E OC g
k.
//
M ro ao Dg J
r a
ir A
o t
gl mr KC g
n o
E o
f D
i t
t a a
L pe l
7 O
er P
_. g_ u_ "D W
R cA N
T e
/
N R
O 1
n C
h.e g
I
~
e l
am
'e
~:tI g
no i
ii eo f
R ti i
MR fO
{
O s
g O
Il
~
. Df p
{
L F
e T
f' c
S I
~
(
n R
e I
r F
e f
Q b
n a
o 3
l C
/
b
)
e m
c I
i f
fO n
g o
liat e
ca i r c
i t e f
rl ee fO vcc 1
A -
,Du 3
r Lb l
e l
I l
lI i
I a
M I
r k
I T
t i~
I
1 RADIATION PROTECTION DEPARTMENT 4
Radioactive Wasta Barrel Storage Area l
j r
6 i
f I
e Trap Door spiral stairs 1
I 1
l Transformer i 10015 l
l l
l l
w-ww w --- - -
,--,s-,-------e m ye-
,--- <- - - -y-----
---e
+w-
-n.
-+s=
w-
%em+
-g--*-----
y wy---
w
.-7-'
- g-w
--y-ew
--r
-w ew
-. - - - --w
--m-w---
"**----a--M
APPENDIX 7 Pu-Be Source Dose Rates 1 Ci Pu-Be Source 6
1.85x10 n/sec a.
Unmoderated Source Distance Neutrons, arem/hr Cansna, mr/hr Contact 100 50 6"
20 5
12" 10 0.75 24" 3
0.5 36" 1
0.5 b.
Moderated (1 cm Water)
Distance Neutrons, mees /hr Cansna, 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)
Distance Neutrons, ares /hr Canna, mrM Contact 25 8.5 6"
15 2.5 12" 6
1.75 24" 2
1.25 48" 1
1 G
L
=
APPENDIX 7 Pu-Be Source Dose Rates 10 Ci Pu-Be Source a.
Unmoderated Source Distance Neutrons, uran /hr Cama, mr/hr Contact 1000 260 6"
300 46 12" 110 17 24" 50 5
36" 18 2
b.
Moderated (1 cm. Water)
Distanee Neutrons, mran/hr Gamma. mr/hr Contact 800 200 6"
300 40 12" 110 15
- ~24" 45 5.2 48" 12 1.3 Moderated (5 cm Water) c.
Distance Neutrons, ares /hr Gamma, mr/hr-Contact 500 100 6"
200' 23 12" 80 12 24" 30 3.8 48" 8
1 L
Appendix 8 i
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 interlock prevents implosion of the N-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 LS3s and SLs are adequate.
3.3 Radiation Monitoring Systems 3.3.1 Fixed Area Monitors Apolicability:
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 one.,of the.three monitors on the neutron deck may be out of servi'ce at a given time.
(b) The hoboceLL,moni. tor.may.be out of service for extended periods-pro-l vided the key-to=the= cell-is-administratively-controlled; l
9
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 weactor power level is not increased during that outage.
(d) Any, monitor may be temporarily replaced by a portable unit that pro-vides equivalent functions.
Bases:
Specification 3.3.l(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 monitor system without shutting down the reactor.
3.3.2 Ef fluent Ponitors and Primary Coolant Monitor 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 coolant monitor system.
ll Specifications:
(1) The normal cor.tingent 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.
(2) The alarm points for the two gaseous effluent monitors shall be clearly stated in a facility cperating procedure.
The alarm points for the pri-mary waten 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-ticulate 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 being, conducted 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 mor.itors are operating.
The*ftack') articulate monitor may be out of ser-vice for periods not exceeding.one week, provided that the fixed filter is evaluated daily.
The pecorder may be out of service for periods of time not to exceed,48-hours _.as_long as the effluent _ monitor values are logged m
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 when 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.
Spec fication 3.3.2(2) provides for the unambiguous establishment of alarm set-i 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 Applicability:
These specifications apply to the facility containment vessel and its associated airlocks and ventilation system.
1 Objective:
The' objective of these specifications is to control the release of airborne radioactivity from tle facility under both normal and off normal conditions.
Specifications:
The reactorwill not be operated unless the following condi-tions-are satisfied:
. ( 1)
ThS truck door sh'all be closed and sealed, one door in each of two air-spis shall be closed and sealed, and all other' penetrations other than ventila'. ion ducts shall be sealed.
i (2) The stack-fan in the university steam plant shall be operating and the fan inethe* building air-duct shall be' operating.
(3)
The pressure in the containment vessel shall be= negative with respect to
~
the outside atmosphere, i
l (4)
The damper.s in the contailment ventilation ducts must be operable and be capable of closing in=6..sec. or lesA.
They must close automatically in l
I l
l l
l L
l TABLE I EFFLUENT MONITORS ALARMS MONITOR LOCATION SENSOR RANGE PURPOSE FUNCTION LOW HIGH PRIMARY PUMP GM TUBE 10-10 PRIMARY INSTRUMENT 10,000 CPM NONE WATER ROOM CPM WATER FAILURE ACTIVITY BUILDING FAN 36" UHAUST INSTR N 1,000 CPM WIH 3
AIR ROOM 2 GM TUBES 10-10 DUCT GAS FAILURE BRIDGE o
x co S
5 BUILDING FAN GM TUPE 10-10 36" EXHAUST INSTRUMENT 100 CPM NONE O
[
PARTICULATE ROOM CPM DUCT FAILURE PARTICULATE ACTIVITY OUND 5
STACK MECHANICAL 2 GM TUBES 10-10 EXHAUST INSTRUMENT 2,500 CPM NONE CAS 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 l
ROOM ACTIVITY PARTICULATE
s APPENDIX 9 Summaries of Worker Exposures 1980 through 1984 O
i l
4 s
I NSTF EXPOSURE
SUMMARY
1984 i
Total Whole Body General Investi-Dose (REM)
Processorg 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
'O O
s d
s
.250
.500 1
2 6
0 0
0
.500
.750
-0 1
0 0
0 0
.i
.750 - 1.000 3
3 0
0 0
0 1-2.
0 1
0 0
0, 0
l 2.-
3 0
0 0
0 0-O t
j.
468
.49 4
24 39 369 l
i
)
e i
l 1
4.
I k
i 1
,\\
n
.,,~,
s-
,, - ~, - ---
t NSTF EXPOSURE
SUMMARY
- 1983 i 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-
.250
.500 1
4 3
0 0
0
.500
.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 2.000 - 3.000 0
0 0
0 0
0
> 3.000 0
0 0
0 0
0 4
23' 29 442 351 49 4
9
- y
-m-
=
o e.
e
]
I.
9 T
NSTF Personnel External Radiation Exposure Summarn Calendar Year 1982 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 1
0 4
51 592 564 Measurable <O.100 2
0 7
2 O
O x
O.100 - 0.250 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
> 3.000 0
0 0
0 0
0 TOTAL No. Reported 17 4
11 53 592 564 TRAINING The RPD participated in the annual Reactor Requalification prosram.
A lecture on Radiation Control and Safety was presented and questions drawn from the lecture provided 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 11/17/62.
RELEASES TO THE ENVIRONS.
Tables 2-A and'3-A represent the steady-state and tfansient releases of radioactive materials to the air from the NSTF's Buildins Stack and Power House Stack.
Arvon-41 is produced as a result of neutron interaction with naturally occurrins vases 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 facilitier (such as the Pneumatic Conveyor System and the in-core Isotope 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
Tcble 1-A oummarizoo NSTF Porocnnol-outornal rediction exposures.
TABLE 1-A NSTF Persnnnel 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 O
O O.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 O.750 - 1.000 1
O O
O O
O 1.000 - 2.000 O
1 O
O O
O 2.000 - 3.000 O'
O O
O O
O
> 3.000 O
O O
O O
O TOTAL No. Reported 20 4
8 57 827 721 TRAINING The RPD Participat'ed.in the annual Reactor Regualification Prosram.
A lecture on Radiation Control and Safety Was Presented and questions drawn from the lecture Pr'ovided for the final exam.
The RPD also provides trainins to maintenance workers, students and new staff members when needed.
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 natural 1Y occurrins sases dissolved in the reactor Pool Nater.
Cesium-138 is a Particulate fission Product' arisins from the decay of was'eou.s Xenon-138.
Their conc-entration is a function of reactor operation.
Power level, and time.
The remainins nuclides represent losses from radioisotope Produ'ction and experimental irradiation facilities (such as the Pneumatic Conveyor System and the in-core Isotore Facility).
All s'ubstantially 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 buildine.
They are c'ollected in waste holdins-tanks and assaved Prior to discharse to the sewer.
The levels are.substantially below maximum release values..both in total quantity and concentration.
(<'
l l
I O'
w
L-s D
t t
/
/
f NSTF Personnel Faternal Radiation Exposure Summary - Calendar Year 1980
___ NUMBER OF INDIVIDUALS IN EACH RANGE Public ltotepe Annual Whole Body Doso Range NSTF_
Preduction Special Safety Staff Staff Projects Officers Visitors Tours (Rems) 14 64 908 150 10 No Measurable Exposure 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 2.000 - 3.000 Greater than 3.000 30 4
15 73 908 150 Total number of Individuals Reported
'**%im_
t 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 scaled sources in storage need not be Icak 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.
Proc edure :
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 RIMOVE 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 contamination 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 f rom 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.
l l
l L_
l l
-3 t
t f
APPENDIX 11 i
s Emergency Procedures i
?
k 1
i l
l l
l L_.
T presy-ym---99-e-w+ev m w r Nwt-e Fe--ry' ww - r e m = ewe-
y ja 4
EP #1 (formerly OP #51) 2/85 PULSTAR REACTOR (R-77)
EKERGENCY PROCEDURE Staff General Emergency Procedure I.
Introduction This procedure provides rules and information which, if utilized, will minimize hazards to NSTF staff members in the eveat of an emergency.
This procedure presents an overview of_information presented in the j
NSTF Emergency Plan and Emergency Procedures Manual.
Reactor operatoro and members of the NSTF Emergency Staff must be familiar with the l
aforementioned procedures and plan. For such personnel, this procedure I
serves as a summary review. Other members of the NSTF staff are not required to maintain familiarity with other emergency procedures or the Emergency Plan. They are required, however, to be familiar with this procedure.
II.
Scope
.Two. problem categories are addressed by this procedure; Soilding evacuations and medical emergencies.
Evacuations are further segregated into fire and non-fire situations. Three levels of building occupancy are addressed:
{
l.
Daytime working hours, when a comparatively large number of people occupy the building.
2.
Evening and nighttime hours, when typical' occupancy is two-reactor ope,rators.
i 3.
Weekends and holidays, when no one is regularly scheduled to' be in l
the building. On such occasions, one or more staff members may be present for non-routine maintenance, repair, or research activities.
III. Medical Emergency A.
During Daytime Working Hours 1.
Administer first aid as you are able.
If someone more qualified in first aid is available, try to obtain assistance from such p'erson(s).
2.
Obtain medical assistance by calling University Public Safety (security) at "2222".
Request medical assistance.
Speak slowly and clearly.
If no radiation exposure or contamination i
is involved, tell the dispatcher right away.
be--
g s
EP #1 (2/85)
Page 2 3.
Notify the receptionist that a medical assistance team is on the way.
If a staff member is available, have him or her wait in the reception area for the medical team. This person should guide the team to the location of the victim (s) within the building.
4.
Do not delay the medical team by requiring them to sign in.
They must be escorted at all times.
Issue dosimeters only if a radiation emergency exists. Whoever notifies the receptionist should indicate whether dosimeters will be required.
B.
Evening and Night Working Hours
/
1.
Administer first aid as you are able.
2.
Notify the reactor operator on duty (if reactor is in operation) via intercom "7".
The reactor operator should shut down'the reactor if necessary, in order to lend assistance.
3.
Obtain medical assistance as in A.2.
4.
If no one is available, inform Public Safety'that they will have to escort the medical team to the location of the victim (s).
Otherwise, station an escort at the front door to admit and direct the medical team to the victim (s).
5.
Issue dosimeters if appropriate (as specified in A.4.).,
6.
When time allows, notify the Operations Manager.
C.
Weekends and Holidays e
- 1.,If you are alone in the building, call Public Safety.
Be sure to indicate your location within the building.
2.
If more than one person,is present in the building, proceed as in section B.
IV.
Evacuation of the Building A.
General TherearemanyforeseeablesituationswhichwodIdmakeprompt evacuation of the facility prudent, in the interest of safety.
This would include fires, high radiation levels, severe contamination, airborne radioactive materials, toxic fumes, gas leaks, earthquakes, bomb threats, etc.
~
- ~--"
I t
I lL
-+
e i
EP #1 (2/85)
Page 3 i
i Such evacuations can be initiated in three ways:
1.
The building fire alarm system.
l There are pull stations and klaxons located throughout the i
building.
These alarms.should be used only in true emergency situations. An automatic response by the Buffalo Fire Department 4
is triggered. Once initiated, the response can not be averted.
3 Fire Department personnel will risk their lives to get here.
The Fire klaxons produce a constant tone for three minutes, and then shut off automatically.
- 2. - The building evacuation alarm.
l The building evacuation alarm is to be used for non-fire evacuation situations.
It is activated by a switch on the radiation monitor panel in the control room. Use of this alarm
[
should be backed up by a P.A. announcement.
Indicate the.
reason for evacuation. Warn personnel away from hazardous
[
areas. No outside agencias are automatically summoned by this l
4 alarm.
If assistance is required, call Public Safety. The.
d evacuation alarm activates intermittent klaxon horns. This alarm must be turned off manually.
1 h
3.
P.A. announcement.t.
{
The P.A. system is used as a backup to the evacuation alarm, or may be used in lieu of the alarm if the activating switch is j
inaccessible. It may also be used in limited evacuation situa-tions, such as the evacuation of one or more' decks of the i
containment only. Microphones are located in the control room f
and in the reception area.
Speak slowly and clearly, and repeat information several times.
The proper' response in any evacuation is to leave the building immediately. Do not delay.
If possible,-leave via the front door.
j If the path is blockad, leave by any available exit. Hang up telephones. If possible. close windows, secure air conditioners,
[
]
leave lights on, and close doors behind you.
I If possible, pick up respirators or portable radiation monitoring i
equipment on the way out.
Do not go out of your way to obtain them.
The reactor operator on duty should scr:1 the reactor, and take the
{
~
log book with him if able.
[
t Once you have exited the' building, do not leave the area.
Report I
immediately to'the loading dock inside the-Howe Research Building.
Do not eat, drink, or. smoke until you have been monitored for-
[
contamination.
i N
t I
i
-=, _ _..,. - _.
-. m
e' EP #1 (2/85)
Page 4 B.
Fire In The Facility If you hear a fire alarm, evacuate the building as per the afore-mentioned guidelines.,If you discover a fire, you must quickly choose one of two alternatives:
1.
If the fire is small, and does not involve radioactive material (such as a fire in a wantebasket or instrument chassis), and if the appropriate fire extinguisher is readily available, fight the fire if you are able.
If you attempt to fight the fire and cannot control it quickly, turn in a fire alarm.
2.
If any of-the above three conditions are not met, do not fight the fire.- Turn in an alarm.
If in doubt, turn in an alarm!
C.- Other Evacuation Situations If you hear the evacuation horn, or a P.A. announcement, evacuate as per the aforementioned guidelines.
If you discover a situation which you feel may warrant an evacuation, proceed as follows:
1.
Verbally alert any other personnel in the immediate area.
2.
During working hours, if the reactor is operating, notify the control room (intercom 7).
The operator on duty will investigate or initiate action as appropriate.
If the reactor is not operating, notify the shift supervisor.
3., During-weekends and holidays, notify the senior staff member in
-the building.. The senior staff member will take action as appropriate.
If you are alone, notify Public Safety at "2222".
Inform the dispatcher that.you are proceeding to Howe Research Building.
Go to Howe and await assistance.- Do not leave the area.
D.. Special Considerations 1.
During Business Hours In an emergency, an " Emergency. Director" will take charge, a.
as specified in the NSTF Emergency Plan.
b.
If you evacuated the building by an alternative exit, make your presence known to. the Emergency Director.
EP #1-(2/85)
Page 5 1.
c.
The receptionist (if one is on duty), upon hearing an evacuation signal, should wait and observe who leaves the building, for a maximum of two minutes. The receptionist should then leave, taking along the visitor log and any name tags from the IN/0UT board that are still in the IN position.
The crash bar on the front door must be locked on the way out, to prevent any unauthorized re-entry. A spare key is located in the left end of the cabinet housing the visitor film badges.
d.
If no receptionist is on. duty, the first person to reach the reception area assumes the duty of the receptionist.
The front door must be locked to prohibit any entry to the building (such as a mailman, or a staff member who was out of the building).
2.
Weekends and Holidays Initial response to an emergency shall be by members of the Public Safety Department.
Make your presence known to the officers responding.
3.
Fires The Emergency Director must account for all personnel. When the Fire Department arrives, approach the senior officer and provide all available information. The Fire Department will not enter the building without a staff escort, unless it is a lifesaving situation. All persons must be accounted for.
s OPERATING COMMITTEE APPROVAL:
Administration M
0 Operations Uf sf.
~
'g f
E4 Radiation Protection l
l 1
- EP #2 (formerly OP #52) 2/85 PULSTAR REACTOR (R-77)
EMERGENCY PROCEDURE Medical Emergency Procedure I.
Introduction The purpose of this procedure is to facilitate prompt and proper treatment of medical emergencies at the Nuclear Science and Technology Facility.
It may foreseeably be implemented 'in a " stand alone" situation or in conjunction with other emergency implementing procedures.
It would be absurdly foolish to attempt to address specifically all foreseeable emergency scenarios.
It would be equally foolish to assign specific duties to specific individuals, since one cannot know in advance which individuals would be available when the emargency occurs.
This procedure is therefore written in a generic sense, and encompasses five crucial aspects of emergency response: Assessment; Notification; Preparation for transport; Transport; Contamination control.
It will be the responsibility of the Emergency Director to ensure that the provisions set forth in this procedure are carried out.
He may assume or
' delegate specific duties to personnel.on hand, at his discretion.
II.
/.ssessment Medical emergencies at NSTF will require two initial assessments:
an assessment of medical severity, and an assessment or radiological severity.
A.
Medical Assessment NSTF and Radiation Protection Services (RPS) staff members are not trained medical personnel. Any medical assessment should therefore be backed up as soon as possible by representatives of the University Health Services Department. Pending this backup, however, an initial assessment must be made, and if possible, first aid should be supplied (CPR, compresses, etc.).
Life-saving first aid should and must be given top priority in a medical emergency. Other considerations, such as contamination control, are secondary.
~w*~eo-w~
e
, s.o.
i i
t
Page 2 EP #2 (2/83)
B.
Radiological Assessment The following categories of medical emergencies are addressed by this procedure:
1.
Injury or sickness not involving radiation exposure or radioactive contamination.
2.
Severe radiation exposure (estimated more than 25R), and no contamination.
3.
Injury or sickness involving radioactive contamination and/or radia-tion exposure.
Classification of a situation into one of these categories shall determine which emergency organization and individuals shall become involved in response. A classification assessment must therefore be made promptly by the Emergency Director or his designate.
Methodologies by which such an assessment will be performed will vary, depending on the particular situation, and hence cannot be rigorously set forth in this procedure.
Basically, however, the following two aspects should be considered:
1.
Contamination The likelihood of contamination will vary, depending on the series of events by which the injury or sickness came to be.
If there is any reason to suspect contamination, a thorough cb.ck should be made, using portable survey instruments and standard techniques.
2.
Dose Estimate All persons at the NSTF are issued radiation dosimeters. These should be read as soon as possible if exposure is' suspected ~.
It is possible, however, that said dosimeters may be off scale or rendered inoperable.
In such situations, estimate exposure by determining as_well as possible, radiation dose rates and victim stay times.
III. Notification Communications is an important aspect of response to medical emergencies.
It is imperative that proper channels be followed to avoid duplicate or conflicting calls, and to ensure that the correct individuals and organizations are contacted.
$P #2 (2/85)
Page 3 Emergency medical response will involve a combination of the following organizations:
1.
University Public Safety Department.
2.
University Health Services.
3.
Ambulance service (s).
4.
Veterans Administration Medical Center.
5.
Roswell Park Memorial Institute.
6.
University Environmental Health and Safety Department.
The first call should always be to the Public Safety Department dispatcher at '2222'.
Speak slowly and clearly, and state "I wish to report an emergency at the Nuclear Facility.".
The dispatcher will then request the following information:
1.
Is immediate medical assistance requested? Ie an ambulance requested?
Extent and number of injuries?
2.
What is the cause and general nature of the emergency?
3.
Caller's name and affiliation.
Name of the Emergency Director.
Phone number (s) and location (s) for call back.
After supplying the above information, hang up and await response.
A Public Safety officer (s) and a doctor and nurse should arrive within minutes.
If possible, station someone at the back door
- to admit and escort them.
Victims of. severe radiation exposure with no contamination are to be trans-ported to Roswell Park. All other persons who require hospitalization (at the discretion of Health Service personnel) shall be transported to the 1
V.A. Medical Center. Calls should be placed to the Office of the Director at V.A. Medical Center so that the Emergency Room may prepare to receive patients.. (See Appendix A.)
It is the responsibility of the Emergency Director to ensure that these calls are made.
As completely as possible, supply the following information to the hospital:
1.
Number of patients.
2.
Estimated amounts and types of exposure for each patient.
~
3.
Extent or nature of injuries for each patient.
4.
Estimated time of arrival at hospital.
5.
Caller's name and number for call back.
If v.ictim(s) are not at the NSTF (i.e., at Howe or elsewhere), indicate this to the dispatcher, and station a person in.the appropriate location.
W
l 1
EP #2 (2/85)
Page 4 I
The following staff members should also be notified if they are not on site:
e 1.
Facility Director.
i 2.
Radiation Safety Officer.
3.
Operations Manager.
The Emergency Director shall ensure that these persons are notified, as time allows.
i s
IV.
Preparation for Transport I
Once Health Services personnel reach the scene, they shall assume responsibility l
for medical treatment. ~NSTF and/or RPS staff members will maintain responsibility for radiological control.
If medical conditions allow, decontamination of any contaminated victims will be performed at the scene.
Shower facilities and supplies are available at NSTF and at Howe.
[
t For serious injuries or illness, cover the victim with a blanket and tag the blanket or stretcher as " contaminated".
If time allows, attach a radiation accident victim tag to the victim or i
stretcher, completing as much of the tag as possible.
(See Appendix B).
l Patients with severe injury (injuries) or who have received severe exposure should be immobilized as much as possible, and should be moved via stretcher r
to avoid unnecessary exertion, i
V.
Transport Transport shall be via ambulance. Public Safety will obtain the ambulance upon request.
If resources allow, a representative of the Radiation Pro-i tection Services or the NSTF Operations Department shall accompany the transported victim (s). He shall maintain eadiological control until the emergency vehicle reaches the hospital.
The victim (s) should remain in the vehicle until authorization for transfer into the emergency room is granted
~
by hospital representatives (if victims are centaminated).
If contaminated victims have been transported, the driver and the vehicle shall not be released back to service without authorization by the V.A. Medical Center.
Once victims are transferred into the emergency room, responsibility for their care transfers to the hospital. University employees shall remain available, however, for assistance or to provide information as-needed.
i I
I A
L
EP #2 (2/85)
Page 5 VI.
Contamination Control In the event of a medical emergency involving radioactive contemination, all reasonable measures should be taken to preclude ingestion, inhalation, absorption, or spread of the radioactive material.
Such measures, however, should not compromise essential medical treatment.
In cases of minor illness or injury, decontamination should be performed on site. Routine procedures and methodologies shall be employed.
If all
)
contamination cannot be removed, contain the residual by use of tape, and plastic bags, cloth, or paper.
For severe injuries or illness, do not delay transport and/or treatment by attempting to decontaminate. Control the spread by:
1.
Remove or cut away contaminated clothing if time allows.
2.
Cover victim with a blanket, and tag as contaminated.
3.
If hair is contaminated, place a surgical cap on victim.
4.
Segregate any equipment or supplies used. Do not return to normal service until checked for contamination.
5.
If time allows, personnel should wear protective clothing, including respirators if there is a likelihood of airborne contamination.
6.
.All personnel who handle or treat the victim are considered contaminated until a check proves otherwise.
OPERATING COMMITTEE APPROVAL:
i e
Administration ase225 m
.Q v'
Operations
+.
.f Radiation Protection 4t b
~
=
APPENDIX A.
MEDICAL EMERGENCY CALL LIST UNIVERSITY:
Public Safety Department - 2222 Health Services - 3316 Environmental Health and Safety - 3301 Radiation Protection Services - 3281 RPS STAFF:
Mark Pierro - 3281/691-7844/Pager 696-0039-10 second Don Sherman - 3281/839-2678 messageo NSTF STAFF:
Louis Henry - 2826/773-3186/Pager 886-1743 6903896)
- Philip Orlosky - 2826/684-8585/Pager 696-2553 Robert Kerns - 2826/731-3810 A. Adams - 2826/877-1884 Jim Griffin - 2826/652-3139/Pager 881-8017 Nancy Hutchison - 2826/875-0905 HEALTH SEb' VICES:
Answering Service - 884-3100 Dr. Marie Kunz - 3316/836-5419 V. A. MEDICAL CENTER:
Emergency Room - 834-9200, Ext. 3608 Dr. J. Steinback - 834-9200. Ext. 3635 home - 688-7913 Dr. Gona - 834-9200, Ext. 2687 home 434-1883 Lockport Mr. W. Quain - 838-5250 or 838-3266 home - 627-3738
'Miss J. Dudkiewicz - 834-9200, Ext. 2685 home - 631-9176 ROSWELL PARK MEMORIAL INSTITUTE:
Admissions - 834-5734 Emergency Room - 845-5178, 3534 Dr. R. Johnson - 845-2300 Dr. E. Henderson - 845-3221
- 1.
Call the Dispatch number 886-1743.
2.
Tell the person who answers at this number that you wish to activate pager No. 6903896.
3.
Tell the person "I wish to display No. 'xxx-xxx" where xxx-xxxx is the phone number you would like me to call (usually your own number).
4.
Await my call.
L_
l l
1 i
j i
APPENDIX B
{
s.
i i
i i
..f.
Tk,
,(
.:y,
- h.eq/
- c..
' ' 'WJ _
% irk at Buf6alo
.i i-..
.,.. y??".',,y,h.
3<>;,
' f Q.
- 3..
1
!.;lj
' ~~
g j
p..,.
,y y,
t t.'lr
./
,{.
[
d)Eh l
a>
p
.. W
- h ;u,, G4.Q?l
- l :.. h
/r
- 4. W. -
e s.
t N
^'
'e t
,1; i.f' t
, 3 !. i -
Rea I)
,o 5 :.
e s 3)
Other;(
)
Reni (som of 1, 2,3 above) f t
^^
7,
....y x s..
- .3 r i; r.....
(
- t. n
.. F i
p>,
s
,k' fP
- (s
- $3'[ '
.5
.'il.
gecord
- 'i.
, i
'){.*ff1, '
_. -.. % M',s',.'l;. t f *k v k i; W k5 y.
i t * *"i
- i g,y,.) -
toch N
it '..!.
kth '
4( ',c#:,A 6
. s' 54E,
a. - c.A eeR..
)?, 4...;y' p % d>
drM,.t *,'
3'..
.:.7.
. n.4..
1; 0
y
.< *. i,
,).
[
i.
't
! 'j' { i r g e WM i J f.r m n.
J.
Nf@ h 1;fg i
M
- .ht a we,
,o,, w >. w. g.#.u..
.qf.
.p m.
Psi
. : {&I.ai?,y in donemel % w& & m ? W i " Y p.,.,;4.vw um.
',,..,.'rr-c..w... :.,!
' l' E.8.. [., h) d,kY f','T.[,'.,'*7,a.;.
.j
.e i
-)!'e '
.d u.s.
x.r.ua..-
=,t
..., e e
- J E'
say 0, APPENDIX C ENVIRONMENTAL llEALTH AND SAFETY 3
3 POLICIES AND PROCEDURES 1
o
%s 4P
'8 oArt: September 10, 1973 0rpSt0' susject: NEDICAL ENERGENCY - S0tTIH CAMPUS FILE: Emergency Procedure (Safety Manual)
Any person at the scene of an accident or onset of serious personal illness may obtain medical, nursing, ambulance and campus security aid by dialing one number - 4747 (831-4747).
This number has twenty-four (24) hour service in the Office of Campus Security. When this number is called, the following measures will be taken:
Caller should state, "I WISH TO REPORT A MEDICAL EMERGENCY,
1.
Campus Security Dispatcher Should Ask:
a.
Location:
Bldg.
Floor Room b.
Extension for call back c.
Who is calling d.
Nature of emergency e.
Name of victim (if known) f.
Is an ambulance required 2.
Campus Security Dispatcher (af ter receiving report):
a.
Dispatch a patrol to scene (Patrol #1) b.
Notify Uhiversity Health Service - extension 3316 (dispatcher relay details of incident) c.
Dispatch a patrol to Health Service (Patrol #2)
(dispatcher relay details of incident) d.
Call ambulance if deemed necessary 3.
Patrol #1 (goes directly to scene):
a.
Confirm condition - report to dispatcher b.
Render appropriate first aid c.
Request physician if needed (only nurse will respond with second patrol unless otherwise directed) d.
Request ambulance if needed and not already called or cancel if not required
^
2 b
4.
Patrol #2 (goes directly to Health Service):
a.
Driva directly to Health Service: Entrance - north end Michael Hall b.
Assist nurses by loading emergency equipment I
c.
Transport nurses and/or physician to scene.
(If scene is close to Health Service building, nurses and physician may proceed directly to scene. Patrol #2 should check to see if additional assistance in required.)
d.
Patrol #1 should remain at scene until nurses certify that the emergency is under control.
j e.
Patrol #2 may proceed to other assignment if assistance is I
not required.
5 5.
Calls for Ambulance:
The Campus Security dispatcher, patrols or University Health Service personnel may call for an ambulance. All calls will be coordinated to avoid duplicate calls, i
i
?
y t
t I
f r
i i
I i
REH:jlv 1
-t..
y
'i
,2 APPENDIX D
m BEEMENCY HANDLING OF RADIATION ACCIDBff CASES VETERANS ADMINISTRATION HOSPITAL 3495 Bailey Avenue Buffalo, New York 14215 e
4 e
i
- e i
.l
-.-.. -.... - -,. _,........-_--..-.-~..._...__...:_--.,
4, l
_j r
L_
-s c
[
c I
i h
Teu& MWan f
.F,,agg
s 1.
Definition of Radiation Accident Cases 2
t 2.
Esely Management Prior to Arrival in Hospital 4
i 3.
Instructions to Referring Agency / Person 5
i t
4.
Instructions to Energency Room Clerk 7
l 5.
Ins tructions to Rescue Squad 8
i e
i i
6.
Instructions to Emergency Room Physician l
and Nurse 9
j i
7 Instructions to Radiation Control Personnel 11
/
8.
Radiation Eastgency Notification Report Form 12 r
l t
f f
I i
L l
l t
l E
?
9
~~ *
~
~'=
l e
me e
e
, +-
-w-
-w.
e m-
l i
~ j
.Definitiori of Radiation Accident Cases _
l I
There are four types of radiation accident patients.
t 1.
_ Radiation expos _ur_e_ - The individual who has received whole or j
partial body external radiation may have received a lethal dose of radiation i
but he is no hazard to attendants, other patients, or the environment. He
(
is no different than the radiation therapy or diagnostic x-ray ;attent.
I 2.
Internal contamination - Such contamination results from inhalation
[
or ingestion of radioactive material.
Such a person is no hazard to attendants, other patients, or the environment. Following cleansing of minor amounts of contaminated material deposited on the body from airborne exposure, this person should be handled similarly to a case involving exposure to a chemical poison such as lead. His body wastes should be i
collected and saved in ceder that measurements of amount of radioactive i
materials present can be made as an assist in determining appropriate j
therapy.
3.
External contamination - External contamination of body surf ace f
and/or clothing by radioactive liquids or by dire particles presents a type of case with problems similar to vermin infestation. Surgical isolation i
techniques to protect other patients and the hospital environment must be i
employed in order to confine and remove any potential hasard.
I 4
Contaminated wounds - When external contamination is complicated
{
by a wound, care mus t be taken not to cross-contaminate surrounding surfaces r
r from the wound and vice versa. The wound and surrounding surfaces are I
cleansed separately and sealed of f when clean.
r These radiation and/or contamination problems may or may not be complicated j
t by injury, I
Radiation accidents may occw principally u' der the following conditions:
i 1.
During handling of unsealed radioactive materials and fissionable materials (such as in a Reactor).
2 Exposure to radiation emitting devices.
Wherees under the first category (1) all previously described radiation accident's may occur external contamination is unlikely in the second (2) l j
l category.
s l
.If the patient is radioactive, this may be due to either contamination I
or induced activity.
Induced radioactivity from neutron exposure has never presented any hazard to those caring for the patient and it adds little to i
the patient's dose.
Radioactivity from contamination can be a serious l
hazard to patient and personnel and must be dealt with rapidly.
~
- * ^
" ' ~ * * * * - - =
..-si._
t
[
~
3 i
Review of previous cecidents suggests that some patients have auf fared because relatively uninformed personnel were too concerned about i
small amounts of induced radioactivity. There is no record that anyone ever received an intolerable dose of radiation by caring for a radiation accident victim in a first-aid station or hospital. The possibility <. f j
a doctor or paramedical person receiving a dangerous radiatfor. dose an a radiation accident arises only if they must enter the radiation field in rescue attempts.
i t
i f
I i
i r
f l
t l
e l
t
+
f l
l h
i I
l l
i l
t l
l
_~
f h
l l
r.
l 4
Early Management and General Priorities of Radiation Accidents PRIOR to
_ Arrival in the Hos pita l
- 1.
Resove patient from high-dose radiation field, or turn off or shield source.
2.
Deal with any traumatic hesorrhage and respiratory obstruction.
~
3.
Measure patient's radioactivity - decontaminate if necessary.
4.
Establish radiation dose by biological and physical means -
estimate degree of injury and modify management accordingly.
5.
Notify hospital, and other authorities such as Department of Health, police, etc.
6.
Transfer to Emergency Room.
i
- The above are dealt with extensively and in detail in.various esanuals i
at plants which are likely to develop such accidents; for example, the SUNYAB Reactor.
/
t I
f l
i i
i i
i f
L i
t E
t 1
l
W Instructions to Persons Referring Radiation Accident Patients to the Buff alo Veterans Administration Mosoital A.
As soon as it is suspected that a radiation accident case (s) may be referred to the Buf falo VA Hospital, notify the Emergency Ibom and provide the following information:
1.
Identification and affittation.of person making the call 2
Number of persons to be admitted and suspected of having:
l a.
Injury but no radiation expo'sure or contamination b.
Radiation exposure l
c.
Internal contamination l
d.
External contamination, and e.
Contaminated wotmde 3.
Identification of patient (s)' if known l
i 4
Nature of accident, radiation, or radioactivity source, if known 5.
Location, name, type of f acility at which accident occurred 6.
Persons in charge of radiation eval intion
{
I 7
Whetter or not patients will.be:
s a.
Surveyed for contamination l
b.
Decontaminated before arrival at hospital P.
Expected time of arrival at hospital B.
Deliver patient to emergency entrance. '
f l
C.
Upon arrival at hospital, provide medical and. Radiation Control l
personnel with,information on:
{
l 1.
Details about the accident j
i
- 2..The radiation or radioactive sources involved 3.
Exposure estimates l
4 Surveys made l
S.
Decont amin ation ' performed i
t I
+
l
?
r-l
^'
~
4-When the accident has occurred at a facility where radiation sources or radioactive materials are regularly used, the Radiation Safety Officer, the supervisor, co-workers, and the patient should be able to inform the hospital of the nature of the accident, type of radiation exposure or radioactive contamination inw1ved, and possible body areas that may be affected.
%.s e
e e
G 0
9 l
l l
t
)
i
i
=..
Instructions to Emertenev Room Clark On receipt of notification of the momentary arrival of a case involving radiation exposure or contamination:
A.
While still in contact with the perood making the notification enter available data on a Radiation Emergency Notification form and then:
%.g B.
Notify:
1.
Ensegency Roon physician and nurse 2.
The Hospital A&ninistrator on call VAH Phone Home Phone _
3.
Dr. J. Steinbach (Physician)
- 380, 632-1987 4
Dr. G. Donoghue (Physician) 381 689-9613 5.
Mr. U. Quain (Realth Physicist) 838-5250 627-3738 6,
Miss J. Dudkiewicz (Nuclear Medicine Technologist) 381 688-5605 h
l l
l i
l a
l
.g.
l Instructions to Rescue Souad Adulance-Rescue Squad personnel are usually the first persons of the medical team to see the case of radiation exposure or radioactiv,e con tamination.
Their first acts will vary in degree whether they evacuate i
the patient (s) from a nuclear-energy plant or from a university or medical group regularly working with nuclear material or from a road transporation accident. Trained, knowledgeable co-workers, supervisors or health physicists i
are usually on hand at the plant but,not at the road site.
l When the accident has occwred at a plant, the health physicist, super-visor, co-workers and the patient (s) should be able to inform members of the l
rescue squad of the nature of the accident, number of patients, and type of radiation exposure or radioactive contandnation involved and possible body areas that may be affected. A gross measurement of the amount of radiation involved may be available; such information is most helpful.
It is the responsibility of the Rescue Squad to:
1 For the patient:
1.
Give lifesaving emergency assistance if needed i
2 Secure pertinent information including rcugh measurement from th3se in attendance 3.
Determine if physical injury or open wund are invclved. Cover wound with clean dressing; use elastic' bandage to hold wound-
~
cover in place; do not use adhesive 4
Cover stretcher, including pillow, with open blanket; wrap victim in blanket to limit spread of contamination 5.
Notify hospital by radio or telephone of available information For Rescue Squad personnel
/
6.
Perform survey of clothing, ambulance, etc., on arrival at hospital before undertaking further activity 7
if contiminated, discard clothing in container marked " Radioactive -
Do Not Discard." Cleanse self by washing and/or showering, as appropriate.
8.
If in contaminated crea, rescue squad personnel must be surveyed by radiation survey meter; measurements must be recorded.
Cleansing mus t continue until responsible physician indicates person may leave.
l
Instructions for Physteien and Nurse in Charme of Emerxency Room l
'A., Upon initial notification:,
4 1.
Make sure that as much data is available as possible (see page 5) 2.
Notify Radiation Emergenc.y Team (see page 7)
I 3.
Prepare Emergency Room for receiving of contamination patients:
s.
Restrict Emergency Room area only to essential personnel l
b.
Designate transportation route and cover it with absorbent paper c.
Cover designated room with absorbent paper. Area should j
be adequate' for stretcher cart, disposal haopers and working space for professional attendants d.
Energency Room personne1~ should wear protective clothing l
and gloves 4
Obtain survey meters located in 3bom 416A B.
Upon arrival of patient:
1.
Assist the Radiation Control representatives in checking patient for contamination (preferable as stretcher is removed from the j
ambulance) by use of a survey meter.
R.
If seriously injured, give emergercy lifesaving assistance immediately.
3.
Handle contaminated patient and wound as one would in a surgical l
proc edures, i.e., gown, gloves, cap, mask, etc.
l 4
If possible excet. sal contaminacion is involved, save all clothing i
i l
and bedding from mobulance.
If possible _ internal contamination or neutrop exposure is involved save all blood, urine, stool, l
and vomitus.
If possible neutron exposure is involved, save L'
'all metal objects (e.g., jewelry, belt buckles, dental plates,
.etc.).
Label with name, body location, time and date. Save each in appropriate containers; mark containers clearly l
(Radio active - Do Not Discerd).
l l
l 5.
Decontamination should ' start, if medical status permits, with cleansing and scrubbing the area of highest contamination first, i
If only an extremity is involved, the clothing may serve as an i
effective barrier and only the affected limb may.need to be scrubbed and cleansed.
If the body as a whole is involved or if the clothing is generally permeated by contaminated material, j
l l
^
1
=
m y
v
-r--,-,-
'c
- showering and scrubbing will be necessary. Give special attention to hair parts, body orifices and body folds.
Rameasure with a survey. ins trument and record measurement after each washing or showering.
If wound is involved, prepare and cover the wound with a self-adhering disposable surgical drape. Cleanse neighboring surface of skin. Seal off cleansed areas with self-adhering disposable drapes.
Remove wound covering and irrigate wound with sterile water, catching the irrigating fluid in a basin or. can, mark and handle as described in 4 above. Each step in the decontamination should be preceded and followed by radiation monitoring and irecording of the location and extent of contamination.
6 Save the physicians', nurses' and attendants' scrub or protective clothing as described above for patients.
Physicians, nurses and attendants must follow the same monitoring and decontamination routine as the patients.
7 The physician in attendance in the Emergency Room, if confronted with a grossly contaminated wound with dirt particles and crushed tissue, should be prepared to do a preliminary simple wet debride-ment. Further measurements may necessitate sophisticated wound counting detection instruments supp1'ied by the radiation control consultant who will assist in determining if further definitive debridement is necessary.
C.
Upon completion of EmerRency Room Procedures Patient should then be handled according to the following guidelines:
1.
Decontaminated and no injuries requiring hospitalization - discharge.
2.
Decontamiested and injured - admit to a nursing floor.
3.
Irradiated - admit to intensive care.
4 Serious radiation exposure, serious internal contamination, and/or 4
external and wound contamination not responsive to decontamination admit to nursing floor with special contamination control procedures.
l
11
' Instructions to Ra'diation Control Personnel The Radiation Control officer on duty will be notified by the VA Hospital Ensegency. Room clerk of an impending admission of a radiation emergency case.
A.
Upon receivina initial notification :
1.
Obtain as much information as possible from the Emergency Room about the nature of accident and the likelihood of contamination.
~.
2.
Notify additional Radiation Control personnel if the aveilable information seems to warrant this.
3 Pick up any additional supplies or instrumente suggested necessary by the available information.
4 Proceed to the Emergency Room.
B.
4 the Easraency Room:
1.
Assist Emergency Room personnel in instituting contamination control procedures of the radiation emergency admission.
i 2.
Establish a chsckpoint and monitoring station for entry and exit from the contamination control area.
3 Survey patients and advise physician in charge on external radiation levela to personnel and on patient contamination.
l 4.
Survey personnel, equipment and facilities and designate those that must be restricted for decontamination.
5.
Supervise decontamination of personnel and f acilities and release areas that are not contaminated.
l 6
Direct handling of radioactive waste.
-7 Arrange for whole-body counting and radioassays of clothing, l
axcreta, etc., as required.
l 8.
Other duties as dictated by responsibilities of the Radiation Control Office.
l i
i h
(
i L
I f
i
. ' l.'.. t.
12-RADIATION EMEICDICY NOTIFICATION _ REP 0_RT To be used by Emergency Room Clerk to enter available data when a notification is received of the impending senission of a case involving radiation exposure or contamination.
A.
PERSON MAKING ICTIFICMION:
NAME _ _
DATE TIT E AFFILIMION ADDRESS TELEPHONE B.
PATIENTS TO BE ADMITTED total NIDSER g
INJURY BUT NO INTERNAL EXTERNAL CONTAMIN-RADIATION OR RADIATION CONTAMIN-CONTAMIN-AliD CONTAMINATION EXPOSURE ATION
_ATION WOUNDS 1.
2.
3.
4 5.
C.
WILL PATIENTS BE:
SURVEYED FOR CONTAMINATION 7 DECONTAMINATED 7 D.
NATURE OF ACCIDENT: TYPE RADIATION SOURCE OTHER DETAIIS:
E.
PERSON IN CHARGE OF RADIATION EVAIDATION F.
EXPCEL TIME OF ARRIVAL AT BUFFAID VA HOSPITAL G.
NOTIFICKrION TAKEN BY o
e e
e
. ~
i d
t i
y 1
l State University of New York at Buffalo Nuclear Science and Technology Facility 831 2826/831 3281 RADIATION MEDICAL EMERGENCY TAG -
Patients Name Estimated Radiation Exposure:
1)
X, Beta or Gamma REM 2)
Neutron REM.
3)
Other (
)
REM TOTAL ESTIMATED EXPOSURE REM (aum of 1,2,3 above) 5 Was Patient checked for Removable Contaminationi i
(
) ya
(
) no If yes, record contamination levels below:
LOCATION CONTAMINATION LEVEL (com) 1 I
+
i 5
ii Survey pehormed by:
t f
Time:
Date:
1 I
6
._3 l
EP #3 (formerly OP #53) 2/85 PULSTAR REACTOR (R-77)
EMERGENCY PROCEDURE High Level of Loose Radioactive Surface Contamination I.
Introduction The purpose of this procedure is to describe personnel actions required during periods when high-level loose radioactive surface contamination is present or is suspected to be present.
Loose radioactive surface contamination can be proven to exist in several ways; by known spills of radioactive materials; from results of con-tamination surveys; from evidence of personnel contamination; from airborne radioactivity surveys; etc.
When dealing with radioactive surface contamination, the item of utmost importance is to prevent the ingestion, inhalation, or absorption of radioactive materials. A secondary, but nonetheless important, considera-tion is to minimize spreading of-the con'tamination.
The following procedure sets forth personnel actions required to confine the spread of loose radioactive surface contamination to the smallest possible area.
Radioactive contamination is generally not life-threatening.
Life-threatening hazards such as medical emergencies, gas leaks, fire,
~
toxic gases, severe external radiation, etc., should be given top priority if coincident with high-level loose contamination.
In such situations, the procedures established herein may not be practicable, and deviation may be prudent.
II.
Known Spill of Radioactive Materials 1
1.
All personnel in the affected area shall stop work and restrict their movements in order to limit spread of the contaminant.
2.
Personnel outside but in proximity to the spill area shall be advised of the spill.
3.
If possible, confine the spilled material.
(For a liquid spill, absorb excess liquid with suitable absorbent.
For a dry spill, cover excess dry material with clean beaker, paper, etc.)
4.
If airborne contamination is suspected, all personnel shall vacate the area, and notify Health Physics.
5.
One individual shall proceed to the closest location where that individual is able to notify the Health Physics Department.
1 I
i LL-2
'EP #3 (2/85)
Page 2 6.
The individual indicated in step 5 shall remain at that location until monitored and consulted by the Health Physics Department.
7.
Health Physics will inform the Control Room (if manned), then proceed to the spill area to perform the following steps:
a) Evaluate the possibility of airborne contamination.
b) Determine magnitude and extent of contaminated area by suitable
- methods, c) Cordon off contaminated area.
d) Prescribe necessary protective clothing for decontamination of area.
e) Evacuate personnel from contaminated area.
f) Direct decontamination of personnel and facilities, g) Based on the results of surveys, allow unrestricted access to the affected area when appropriate.
III.
Loose Radioactive Surface Contamination Discovered by Health Physics Department Survey Results 1.
Instruct personnel in the affected area to stop work and to restrict their movements in order to limit spread of the contamination.
2., Inform personnel in the affected area and the' Control Room.
3.
Verify that the contamination has not spread to other areas.
4.
Cordon off the affected area.
1 5.
Direct the removal, survey, and decontamination of personnel within the affected area, using established radiation protection techniques.
6.
Prescribe required protective clothing for decontamination of area.
7.
Direct decontamination of affected area.
8.
Based on results of surveys, allow unrestricted access to the affected area when appropriate.
l 9.
When possible, interview all individuals in the Facility to determine l
if they have passed through the affected area.
Survey and decon-taminate, as appropriate.
_ J I
w-
EP #3 (2/85 )
Page 3 IV.
Loose Radioactive Surface Contamination Discovered by Personnel Survey Results.
(Surveys conducted for personnel contamination; 1.e., G.M. frisker survey).
1.
Immediately notify Health Physics via shortest possible route.
2.
Stay where you are.
3.
Health Physics will proceed to the contaminated individual (s) and perform the following:
Direct individual to nearest area for decontamination, using a.
established radiation protection techniques.
b.
Direct decontamination of individual.
Interview individual to determine areas where the person encountered c.
the contamination.
d.
Direct surveys of appropriate areas to determine extent of contamination. Proceed with Part II of-this procedure as appropriate.
V.
Documentation of Incident The Operating Committee shall convene to review any incident described in this EP and determine preventative measures.
OPERATING CO}DfITTEE APPROVAL:
Administration M
rr x e L c.r.ti -
br Radiation Protection L
a.
EP #4 (formerly OP #54) 4/85 PULSTAR REACTOR (R-77)
EMERGENCY PROCEDURE Reactor Loss Of Coolant Accident I.
Introduction A Loss Of Coolant Accident (LOCA) for the NSTF PULSTAR reactor poses potential hazards far.less severe than those associated with power reactors.
Significant off-site hazard is not considered credible.
Residual heat decay levels are insufficient to produce fuel melting.
Several accidents have been postulated which could lead to the loss of primary coolant from the reactor tank. The major accident scenarios involve significant mechanical shocks or stresses (such as dropping heavy objects) to the in-tank coolant pipes, fuel assemblies, and core support structures. Many events which would compromise the primary coolant boundary could also compromise fuel cladding integrity, thereby releasing into the reactor tank and into containment, gaseous and particulate radioactivity.
The cogent personnel and environmental hazards, therefore, include high levels of " direct shine" and airborne radio-activity. Proper and prompt implementation of this procedure is necessary to limit radiation exposures to the staff and public, and releases of radioactive materials to the environment.
II.
Potential Leaks A.
Minor Leaks Minor leaks from the primary coolant system include:
- pool liner leaks.
- leakage past primary coolant return and outl'et pipe penetrations.
- siphon leaks through pneumatic conveyor tubes, experiments, or other such tank penetrations.
- excessive leakage past the primary pump seals.
- leakage through the heat exchanger tubes.
- leakage from the cleanup demineralizer system.
- leakage through the minor. pipe penetrations, such as for pressure gauges or temperature sensors.
- leakage past isolation or bypass valve stems / packings.
Minor leaks such as the above do not pose a significant hazard, since they may be compensated for, using the routine pool water addition system, the emergency pool fill (EPF) system, or by other means.
,a y
w 4
--a v
-"4
e EP #4 (4/85)
Page 2 B.
Major Leaks A major leak could potentially uncover the reactor core.
Some major leaks are isolable.
This would include any leak in the primary coolant loop between the core outlet pool isolation valve and the core return pool isolation valve. Non-isolable leaks would include:
- beam tube ruptures (cover plate removed).
- major leaks in the core outlet and return lines in-board of the pool isolation valves.
- major loss of pool liner integrity.
Beam tubes which are not in use are normally flooded, and sealed by
~
a cover plate and gasket at the outer face of the biological shield.
Major leaks are therefore not anticipated from such beam tubes.
However, beam tubes which are in use, generally will contain collimators, and will be shielded at the outboard end.
Major leaks are therefore credible which could uncover the reactor core (to the level of the' tube) in as little as ten minutes. The presence of collimators and shielding makes sealing off of the leak unlikelv.
Flooding (via the EPF system) of the neutron deck will likely be necessary.
It'will take approximately thirty hours to fill the vessel to a depth of three feet above the core. Once water levels exceed this depth, leakage outward through the ventilation ducts will occur, and reflood should be stopped.
Major non-isolable leaks in the coolant outlet or return pipes.could 3
occur via cracking or fracture of the pipe, flanges, or valve, or from compromise of the cover plate penetrations. Again, repair is unlikely, and flooding the neutron deck will be necessary.
Major leaks in the pool liner will also require flooding.
III. Hazards Associated with LOCA A.
R'adiological Under normal conditions, primary coolant activities are quite low and not life threatening. Contamination and direct radiation levels associated with major leaks, or major leaks which have been isolated without severe reduction of the water level above the core, pose only a minor threat, and 'can be adequately addressed via routinely implemented methodologies.
If the core has been uncovered, severe direct radiation levels will be encountered. Dose rates at the top of the' tank can be greater than 2 x 10" R/hr.
If the fuel cladding integrity has been compromised, airborne radio-activity levels in excess of MPC will likely occur. This would include gaseous and particulate radioactive materials.
e
-e 3
y----o-y w
w m-+c
.=m y
-g
<--e pur
,s--
p.
-r y-7e yy
-4w-t---wwv g
ni-e
(
we-m-r -
+yriwy s--g
i i
EP #4 (4/85)
Page 3 B.
Electrccution Any significant loss of coolant can potentially generate an electrocution hazard.
If the reactor tank were to drain to core level onto the neutron deck, the level of water on the neutron deck would be about ten inches. As more water is added via the EPF system, the AC power circuits will short out.
Similar hazards would exist with a major leak in the pump room.
IV.
Operator Response A.
Loss of Flow A loss of flow accident (without leakage) could be caused by failure of the primary pump, complete or partial loss of AC power, or severe obstruction of coolant channels or the primary circulation loop. Operator response to a loss of flow situation is:
1.
Back up the flow scram--take the key.
2.
Turn off the primary pump.
3.
Turn off the secondary pump.
4.
Turn off the demineralizer pump.
5.
Verify that the plenum flapper valve has opened.
6.
Verify that the rods are seated.
7.
Inspect the reactor core.
8.
Notify the shift supervisor or senior operator on call.
B.
Minor Leaks 1.
Notify shift supervisor or senior operator on cail, and request immediate instructions.
If possible, isolate the leak.
If necessary, add water to the pool.
2.
Notify the highest available Emergency Director candidate.
C.
Major Leak Which is Isolable
'1.
Scram the reactor--take the key.
2.
Turn off the primary pump.
3.
Turn off the secondary pump.
4.
Turn off the demineralizer pump.
5.
Close pool isolation valves.
6.
Announce the situation over the P.A.
Evacuate unnecessary personnel, if appropriate.
7.
Survey radiation levels in proximity to the reactor pool.
8.
If necessary, activate the EPF system. Do not allow the pool to overflow.
9.
Post-off the airlocks and/or the machine room door, as appropriate.
10.
Notify the highest available Emergency Director candidate.
i
.4 EP #4 (4/85 Page 4 D.
Major Leak Which is Non-Isolable 1.
Scram the reactor--take the key.
2.
Turn off the primary pump.
3.
Turn off the secondary pump.
4.
Turn off the demineralizer pump.
5.
6.
Initiate building evacuation.
7.
Open the EPF valve and leave containment.
8.
Close the N-deck trench drain valve.
9.
Close the remaining primary system isolation valves.
10.
Notify Public Safety, request all available personnel to respond to the facility and stand-by.
11.
Survey evacuated personnel for contamination.
12.
Survey for gamma radiation at the air locks and outside the building.
Erect barricades and restrict access as necessary.
Re-survey frequently.
13.
Notify the highest available Emergency Director candidate.
OPERATING COMMITTEE APPROVAL:
Administration e5
/
Operations.
f) m _.
I f
Radiation Protection
(
) lQ h
e
4 f
- s
~
l EP #5 (formerly OP #55) 4/85 PULSTAR REACTOR (R-77)
EMERGENCY PROCEDURE.
Reactor Fuel Failure Accident I.
Introduction Loss of fuel integrity is generally considered one of the most serious reactor accidents. Although the~ probability of a major failure is i
extremely remote for our reactor, it is the one event that could affect personal health and safety beyond the facility boundary. The con-sequences of such a failure are highly dependent on proper operator response and the performance of engineered safety systems.
It is therefore important that operators understand the mechanics of possible failure modes and their probable consequences. The follosing sections describe failure modes, consequences of failure, and appropriate operator responses.
This procedure does not address the problems of finding the failed fuel, pool cleanup, etc.
II.
Operator Responses A.
Small Leaks 1.
If a leak is suspected on the basis of pool water analysis only, then the analysis should be repeated and the results presented
. to the Operating Committee. Once a leak has definitely been established, the reactor must be shut down and the leaking pin found.
2.
Primary water monitor increase only. The operator should inform his supervisor. The instrument channel should be tested for proper operation.
If the channel is opetating properly, a water analysis should be performed.
3.
Increase in building air or particulate monitor only.
Refer to OP #26B.
If no other cause for the increase is evident, perform a pool water analysis.
4.
Significant and simultaneous increases in primary water monitor and building air or particulate monitor.
Shut down the reactor.
Note monitor responses as a result of shutdown.
Notify the Operations Manager.
W EP #5 (4/85)
Page 2 B.
Major Leaks 1.
If there is a large and simultaneous increase in the primary water monitor and the building air monitor, especially if in conjunction with other indicators such as increases in N-16, bridge monitor, or knowledge of events--then the following steps should be taken:
a)
Scram the reactor.
b) Turn off the primary pump.
c)
d) Evacuate the containment.
e) Notify the members of the Operating Committee, f) Secure cooling systems to the extent able from outside containment.
g) Commence personnel and area monitoring.
h) Do not re-enter containment.without health physics supervision except for life-saving emergencies.
III.
Failure Modes Cladding integrity can be compromised by a number of conditions. They are listed below.
1.
Fabrication defects. This would include defective materials, poor velds, lax inspections, etc.
2.
Corrosion. Corrosion of the zircalloy could occur due to poor water chemistry or foreign material in the pool water.
3.
Forces generated in normal use.
This would include thermal and hydraulic forces, as well as pressure from fission product gases.
4.-
Transient forces. The forces in item 3 alone are increased drastically ddring power transients such as occur as a result of prompt criticality.
5.
Clad melting due to loss of coolant. This could result from foreign material blocking coolant flow channels.
6.
Heavy object falling on core. A large cask or experimental facility dropped on the core could cause clad failure.
~
7.
Sabotage.
Intentional damage must be considered.
The following information explains why each type of failure is unlikely, and what has been done to reduce that probability.
1.
Our fuel was made by an experienced fabricator. They employed elaborate quality controls and testing methods,. audited by NSTF.
Tubing was ultrasonically tested; welds were sampled and destructively tested; all finished pins were helium leak tested..
w_
EP #5 (4/85)
Page 3 2.
Zircalloy is highly corrosion resistant.
It is used in power reactor fuel subject to a much harsher environment than ours.
Inspection of our fuel at 15,000 Mw days /tonn burnup revealed no signs of corrosion. Our technical specifications impose strict limits on water chemistry.
3.
Power reactors subject similar fuels to temperatures, pressures, and burn-ups many times more severe than we encounter.
4.
Our pulsing experience has demonstrated that our fuel will withstand severe transients without damage.
Step insertions of 2% AK/K (3 x 8) were experienced.without fuel failure. Pulses of 1.5% AK/K and 2,000 Mw peak power were routinely conducted.
It should be noted that pulsing fragments the UO2 Pellets. Small fuel fragments would be more easily dispersed in a gross failure accident and would releace more fission product gases.
5.
Loss of flow resulting in melting is very unlikely. An object would have to block nearly all inlet holes in a single fuel assembly.
Doppler and boiling voids in that region would decrease power density.
That, combined with the high melting point of zircalloy (3,365'F.)
would make melting unlikely.
An early natural convection experiment demonstrated that nucleate boiling in the core does not damage the fuel, and does cause power instability that would be recognized by the operator.
6.
Heavy objects are prevented from falling on the core by administrative control. Large casks that were once loaded in the pool are now loaded by dry transfer methods. This is due to a formal policy change.
Few, if any, other objects moved in the pool have suf ficient mass to jeopardize the fuel.
7.
Sabotage, if well executed, could result in the worst possible release of fission products.
Such an act would require some knowledge of the facility. Our defense against such an act is a security system that is significantly more sophisticated than is required.
The " water logging" mode of' pin failure should be understood by operators.
It was once a concern when pulsing was a normal mode of operation.
In steady state mode, it could happen only under a very narrow set of conditions, if at all.
Assume that a very small leak develops in a fuel pin, and water enters the pin during a shutdown such as a weekend. When the reactor is brought to full power, the water in the pin could possibly be turned to steam.
If the steam or water could not escape through the leak fast enough, pressure could build up and rupture the pin.
Since the presence of water in the pin would greatly enhance heat transfer from the UO2 to cladding, and the leak size would have to be just right, this scenario is highly improbable.
- o EP #5 (4/85)
Page 4 IV.
Consequences Of A Fuel Leak A.
Released Isotopes There is obviously a large inventory of fission products in our used fuel.
There is, however, no postulated accident that would melt the UO2 (melting point is 4,5300 F).
Therefore, even during a loss of clad accident, the vast majority of fission products would remain bound up in the solid pellets, including the gases. The only isotopes of concern, then, are those that have a chance of escaping the fuel surface and escaping from the pool. This reduces to the noble gases. krypton and xenon, and the halogens bromine and iodine.
The noble gases are free to escape the pool. However, their impact is limited by the fact that their half-lives are mostly short and thus a small inventory; their radiations are low energy, and they are not retained in the body.
Bremine and iodine are solids at room temperature, but are volatized at moderately elevated temperatures. Both are very soluble in water, chemically reactive, and condense readily on any cool surface.
In our reactor, it is not likely that the halogens would escape the pool unless very violent boiling occurred with no flow, a chemical explosion (sabotage) occurred, or there was somehow simultaneous loss of fuel integrity and gross loss of pool water.
B.
Detection Methods Cladding failure would become evident in a number of different ways, depending on the size of the leak.
A very small leak might show up as an increase above normal in the building air monitor or building particulate monitor (Cs-138).
Small leaks that allowed leaching of fission products into the water would show up in the weekly gross beta count or the quarterly spectral analysis of pool water.
Larger leaks would cause an increase above normal on the primary water monitor, as well as the above-mentioned indicators.
Leaks large enough to allow fuel particles to enter the coolant stream would cause an increase in the N-16 channel signal and possibly on the bridge monitor.
~
4-L
e EP #5 (4/85).
Page 5 Reactor Fuel Failure Accident i
f OPERATING COMMITTEE APPROVAL:
t Administration J
[
Operations
~
d,f,_
Radiation Protection 1
l l
t
)
r 3,
e L
f N
I 6__
t EP #6 (formerly OP #56) 2/85 PULSTAR REACTOR (R-77)
EMERGENCY PROCEDURE Fire in the Facility I.
Introduction The purpose of this Emergency Procedure is to describe the fire-fighting devices and alarm mechanisms in use in this Facility, and how to use them effectively.
II.
Reporting of Fires An employee who spots a fire in the area must-decide quickly what action to take.
This can be influenced by:
1.
The size of the fire. A small fire which can be controlled quickly with an appropriate extinguisher, should be fought by the employee.
2.
The availability of an appropriate extinguisher in the immediate area.
3.
Origin of the fire. A fire involving radioactive materials means air-borne radioactivity, which is a serious hazard and calls for evacuation and help immediately.
If either of the first two conditions do not prevail, and/or the fire involves radioactive materials, the nearest alarm box should be pulled, and.the area evacuated.
If in doubt, turn in an alarm.
III.
Location of Alarm Boxes Fire alarm boxes are painted red, and are located throughout the Facility.
The following is a list of alarm box locations:
Control Room (behind console).
Control Deck (near airlock).
Gamma Deck (near airlock).
Neutron Deck (at base of stairs).
Office Wing Lower Hall (near machine shop).
Office Wing Upper Hall (near conference room).
Fan Room (basement).
General Building Evacuation (in electrical equipment room).
Outside, on side of office wing (this alarm will call the Fire Department, but will not alarm in the building.)
EP #6 (2/85)
Page 2 To sound the fire alarm, simply pull down the lever.
Some areas of.the Facility are protected by ceiling-mounted flash fire sensors.
These devices are located in Rooms 114, 118, and labs 215, 213, 103, 104, end 108.
They trip the nearest alarm box to their location.
IV.
Types of Extinguishers 4
Throughout the Facility, fire extinguishers are disbursed. The locations are shown on Figures 1, 2, and 3.
The extinguishers are mounted conspicuously, and contain full and clear instructions on their use.
The University Environmental Health and Safety Department routinely checks each unit to ensure its reliability.
V.
Response To A Fire Alarm When a fire alarm box is pulled, the Buffalo Fire Department-and University Public_ Safety Department will automatically respond. Once set in motion, their people will risk their lives to respond as quickly as possible.
Do not use the fire alarm as a substitute for the building evacuation alarm.
The fire klaxons will sound for three minutes and then automatically turn off.
In response to the fire klaxon, leave the building immediately.
Be sure to close windows, hang up phones, turn off room fans, turn off all electrical and gas appliances. Leave the lights on.
Close doors on your way out.
The preferred route is via the front door, but if this exit is blocked, leave using any available exit. The control room operator should not scram the Pratt dampers.
The first person to reach the reception area should account for people leaving the building.
In most cases, the receptionist on duty will perform this task. Please remember to push your name out on the IN-0UT' board.
Do not leave the area, but go to the Howe Research Building.
Do not eat,
' drink, or smoke until you have been monitored for contamination.
Be sure to avoid areas downwind of the fire.
The senior staf f member present shr uld address the following items:
1.
Make sure that all the people that were in the building are accounted for. Do not release excess (non-essential) staff until they are cleared by Radiation Protection or Health Physics.
2.
Alert senior staff not on-site when time permits.
3.
Arrange for escort of firemen into controlled areas when they arrive.
NSTF staff responsibility is to provide health physics coverage. Air packs anc monitoring instruments are kept with the emergency kits in Howe.
The Fire Department will not enter controlled areas unescorted' unless it is a lifesaving operation.
The units most likely to respond have some health physics training.
m i
g-EP #6 (2/85)
Page 3 4.
Issue dosimeters,'and record the firefighters' names, if possible.
5.
Use Public Safety to keep the public away from.the area as much as possible.
6.
After the situation is secured, do not release the firefighters or any of their equipment until checked and approved by Radiation Protection or Health Physics.
OPERATING COMMITTEE APPROVAL:
Administration M
[
u Operations
.6 f-
?
e Radiation Protection k.
~
{/
A e
a e
L-
)
1/84 I
o n.
NUCLEAR FACILITY FIRE EXTINGUISHER DATA I
Type Class Size Location i
i CO, B-C 5#
Control Room
[
CO 5-C 15#
Phys-Chem Lab
{
2 1
l Dry Powder A-B-C 5.5#
Near air lock (control deck) l CO B-C 5#'
Outside Elect ronic Shop j
2 Dry Powder A-B-C 5.5#
Near air lock (gamma deck)
I
)
CO B-C 5#
NEN office (gamma deck) f 2
CO B-C 5#
Outside A.A. Lab (gamma deck) 2 CO B-C
-15#
Base of stairs (neut ron deck) l 2
r j
CO B-C 15#
Under_ Hot Chem Lab (nctit ron deck) 2 i
)
CO B-C 15#
Inside airlock (gamma deck) 2 j
CO B-C 58
-Opp. Machine Shop (lower hall) 2 CO B-C 150 Fan room (basement) 2 Dry Powder A-B-C 10#
Opp. Rest Rooms '(upper liall)
CO B-C 5#
Trailer (inside door) 2 i
i Halon ABC 9#
Control Room l
Halon ABC 9#
Counting Room i
?
4 l'
i 1
l I
i l
t l
_----.-.-~._.-,-.;-.---....-..,--- -.. - - - - _-.
d
)
b p
A's l
\\
KC E
t D
)
u N
j a
O V
R T
k U
(
p n
E U
a N
T d
l k p
on U
H aT d
6 l
1 o
H N
6 1
[(
N p
U I
K 1
C F.
l
(
E O
at R
cn U
N i e pm G
O n m mo I
R a p u o F
T hi m PR U
c uo
\\
Et
[
MER eqo h
L 0c r
gn o
p i m U
no oo iR t
i t N
)1 d n O
ne I
l om T
te C p A
en n
i D
ln ru N
nu i q U
$T AE O
F re hs x i o u B gn m ir t
a x l E A Ek l
l
b 4
e tb b
oa a
HL L
E egnr E ao h o CR C
~l K
E K
D CR t l um UO ol r o A
RO H e oo M
TD C
WR NA
]
C b
p k
b co J
L' en 8
pe r
it e
P s ut yr y
co sS P
n
[
l b
nt a
in e a el ot gr t e i n l
r e S n i m m c
l en n
t e a
a e ou d po i
_l/ 'TT nio
't ouR te*~
N c
Cq v )f N)I
- y E
f a r
l AW i
E l,
A
_;~
r_~
f o
i t
cS l
1 r u 1
t h il 111 J
- 1 p
i (
l1 o
1 t
\\
li11 h
U l1
{
baL l
1 S
l 1
Pi
- N/
l l1 l
l IlI 1
e E
I1 L
n l
AA R
Y, ec f@
i OOL f
F
)
O K
T t
N 2
C N
n E
E e
b r
E D
M m
a r
o R
E p
L e
t U
A S
j i
h c
t A
u C
m B
n q*
s x e I
i o t
E F
A i
9 e
u B e
C t
l a g
v g
D n*
a n m ar i
C i r t
ce t
t a a i l t e n
x l
e E A H rc u
ec o
VA C
1 hkh
\\
P U
l h
l Ul I I
A
)
rl 8
4' s
oo t r 4
ct m ano
\\
eoo RCR e
~
c i
k e f
cl f
%H eo O
e DH K
s C
u E
o l
D l
L c
n l
O a
i e
K' CO f R
F rp T
o t o N
o ch t
R eS O
[
o C
l H
E l
k m ro ao k
DR f
E b
a L
^
K 3
E
~
C m
D r
E 1
n o
R L
o f
i U
O t
I T
t a C
R a
p e l
er F
N P
7 O
cA l
e C
hVK
/
1 R
5 lI
)
3 R
n k
D L
se e
I!
sm 3I!
i no c
i 1II d
eo f
R
[
II MR f
O gpl UN j
d O
O L
I-F i [l R
t
[
T o
E S
f s
e c
1 I
n a
[A F
l e
bh P
re T
f a
n L
b.
o C
bh h
Y a
e L
c i
f f
r r
o O
r o
lf e
t at h
c M
s x e ca e
i o t
ir t e c
u B e
i rl g
D ee f
n m f
i r t
V c O
t a a c
A x
l e
g E A H
)
$ h
%. k[h r
ll e
lf l
Il i
ll a
d l
r d
i T
Il lI s