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{{#Wiki_filter:UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERJuly 20, 2015U.S. Nuclear Regulatory | {{#Wiki_filter:UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERJuly 20, 2015U.S. Nuclear Regulatory Commission Attention: | ||
Document Control DeskMail Station P1-37Washington, DC 20555-0001 | |||
==REFERENCE:== | ==REFERENCE:== | ||
Docket 50-186University of Missouri -Columbia Research ReactorAmended Facility License No. R-103 | |||
Docket 50-186University of Missouri | |||
-Columbia Research ReactorAmended Facility License No. R-103 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Written communication as specified by 10 CFR 50.4(b)(1) requesting U.S. NuclearRegulatory Commission approval to amend the Technical Specifications appended toAmended Facility License No. R-103 pursuant to 10 CFR 50.59(c) and 10 CFR 50.901.0 Introduction The University of Missouri Research Reactor (MURR) is requesting a change to the facility Technical Specifications (TSs) in order to produce the radiochemical sodium iodide (1-131). | |||
There are currently nocompeting modalities for its use as a therapy for thyroid dysfunctions and no current supplier within theU.S. This Amendment would allow MURR to continue to perform a key role in the supply of criticalmedical radioisotopes, both domestically and internationally. | |||
2.0 General Description of Proposed Experiment The proposed 1-131 experiment will include target irradiation; | |||
==References:== | ==References:== | ||
: 1. MURR Reactor Utilization Request 440,' -To Produce 1-131"2. MURR Technical Specifications | |||
: 3. IAEA-TECDOC-1340, "Manual for Reactor Produced Radioistopes" | |||
: 4. MURR Project Authorization RL-76, "Production of 1-131 Radiochemical Sodium IodideSolution" | |||
: 5. ALMO 6 Operating Manual (G-M Radiation Monitoring System)6. Camfil Activated Carbon Filters7. Flanders High Efficiency Gas Adsorber (HEGA) Filters8. MicroShield 8.02 -Computer program used to estimate dose rates due to a specific externalradiation source28 of 29 | |||
: 9. Comply -Computerized screening tool for evaluating radiation exposure from atmospheric releases of radionuclides | |||
: 10. Regulatory Guide 1.109, '.'Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I."11. Regulatory Guide 2.2, "Development of Technical Specifications for Experiments in ResearchReactors" (November 1973)12. M1URR Emergency Plan13. MURR Emergency Plan Implementing Procedures (TOC- 107)14. Letter from MURR to the NRC, dated February 15, 1977, requesting a change to the Technical Specifications in order to increase the iodine inventory limit in a fueled experiment | |||
: 15. Letter from MURR to the NRC, dated September, 1977, responding torequest for additional information in support of the February 15, 1977 request to change the Technical Specifications | |||
: 16. Letter from MURR to theNRC, dated January 20, 1978, in support of the February 15, 1977request to change the Technical Specifications | |||
: 17. Letter from the NRC to MURR, dated | |||
==Background:== | ==Background:== | ||
Counts in case of radialirradiation (Cs 137)approx. 25 counts / minuteapprox. 4 counts/s/tSv/ | |||
Counts in case of radialirradiation (Cs 137)approx. 25 counts / minuteapprox. 4 counts/s/tSv/h Radiation axial:Temperature range:with cap:without cap:Operation: | |||
Storage:only y-radiation a-, 03- and y-radiation | |||
-30'C to + 60'C-40'C to + 70'COutside air:Housing:Dimensions: | |||
500-1300 hPa, influence cannot be determined inpractical use. Transport in planes up to a height of3000 m: Changes in air pressure have to be performed slowly.Aluminum sleeve, red anodized40 mm0 x 110mmWeight:approx. 150 gIf Geiger-Mueller probes are connected, the unit can no longer be changed toBq/m3.Page 58Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 Dresden}} |
Revision as of 22:46, 30 June 2018
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Site: | University of Missouri-Columbia |
Issue date: | 07/20/2015 |
From: | Butler R A, Fruits J L Univ of Missouri - Columbia |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML15203A883 | List: |
References | |
Download: ML15203A867 (87) | |
Text
UNIVERSITY of MISSOURIRESEARCH REACTOR CENTERJuly 20, 2015U.S. Nuclear Regulatory Commission Attention:
Document Control DeskMail Station P1-37Washington, DC 20555-0001
REFERENCE:
Docket 50-186University of Missouri
-Columbia Research ReactorAmended Facility License No. R-103
SUBJECT:
Written communication as specified by 10 CFR 50.4(b)(1) requesting U.S. NuclearRegulatory Commission approval to amend the Technical Specifications appended toAmended Facility License No. R-103 pursuant to 10 CFR 50.59(c) and 10 CFR 50.901.0 Introduction The University of Missouri Research Reactor (MURR) is requesting a change to the facility Technical Specifications (TSs) in order to produce the radiochemical sodium iodide (1-131).
There are currently nocompeting modalities for its use as a therapy for thyroid dysfunctions and no current supplier within theU.S. This Amendment would allow MURR to continue to perform a key role in the supply of criticalmedical radioisotopes, both domestically and internationally.
2.0 General Description of Proposed Experiment The proposed 1-131 experiment will include target irradiation; target disassembly; 1-131 separation; andQuality Control (QC) testing of the product.A double encapsulated target will be placed in a predetermined graphitereflector region irradiation position.
M-URR Reactor Utilization Request (RUR) 440, 'M -To Produce 1-13 1" (Ref. 1), documents the safety evaluation performed for this target, whichincludes satisfying all of the applicable experimental specifications of Section 3.6 of the MvURR TSs (Ref.2). The RUR has been reviewed and recommended for approval by the Reactor Safety Subcommittee (RSSC), a subcommittee of MURR's Reactor Advisory Committee (RAC) (TS 6.1 .c). The mass of thetarget is limited to which can theoretically produce ý of 1-131 at a peak flux ofi=In actuality,
ý of 1-131 is a conservative overestimation of activity based on a maximum value for flux, greater than normal irradiation time1513 Research Park Drive Columbia, MO 65211 Phone: 573-882-4211 Fax: 573-882-6360 Web: www.murr.missouri.edu Fighting Cancer with Tomorrow's Technology (typical weekly reactor run time is 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> or less), and the discountingof any self-shielding effects ofthe target material.
Based on the typical values of flux and irradiation time, and data from low activityexperimental
- testing, a target will produce approximately
ý of 1-131 at the end ofa typical = irradiation.
The following is a basic description of the overall process for producing 1-131:a. An irradiated M target will be delivered to the Handling Hot Cell (also designated as HHC orHC-I IA) where the target will have its encapsulation removed.
The target material will then beplaced in ý and transferred to the Processing Hot Cell (also designated as PHC or HC-1 IB) via a pass-through between the cells.b.is contained in a sealed casing, or containment vessel, with a filtered exhaust asdescribed below. This provides the first barrier against a release of 1-131 to the hot cell.c. The bulk product solution will be sealed in a suitable transfer vial and transferred via a pass-through from the PHC to the Dispensing Hot Cell (also designated as DHC or HC- I1C) forformulation into final product solution.
It will then be dispensed according to customerrequirements into vials suitable for shipping.
An aliquot will be taken from the bulk solution andremoved from the DHC for QC analysis.
The ý time to release 1-131 gas from the target matrix is .Theexpended target material (waste) will be sealed in a can within the PHC for interim storage and eventualprocessing as radioactive waste. After multiple processes, and when the can is full, it will be allowed todecay for a sufficient time and then it will be moved via the pass-through to the HHC for additional decayand storage.Figure 1 is a vendor drawing of the basic components designed for the to produce1-131 from irradiated M .The irradiated
= is placed in ý which are thendescribed in IAEA-TECDOC-1340, "Manual for Reactor Produced Radioistopes" (Ref. 3).2 of 29 Figure 1 -Vendor Drawing of Processing Equipment Processing within the hot cells will be performed under MURR Project Authorization RL-76, "Production of 1-131 Radiochemical Sodium Iodide Solution" (Ref. 4). The Project Authorization has been reviewedand recommended for approval by the Isotope Use Subcommittee (IUS), a subcommittee of the RAC.3.0 Hot Cell Design Considerations The 1-131 processing facility contains three adjoined and inter-connected hot cells which are located onthe building grade level (see Figure 2). The H-C and the PHC have 200 mm (7.9 inches) of vertical leadshielding and the DHC has 100 mm (3.9 inches) of vertical lead shielding.
The area to the rear of thecells, labeled the cask loading area (Room 299U), is where cell support facilities and equipment arelocated and where most cell inputs and outputs of targets, equipment and supplies occurs. Table 1provides the lead dimensions of all of the hot cell components in millimeters.
The area in front of the hotcells, labeled the operator area (299T), is where the cell windows, manipulators and controls are located.3 of 29 Figure 2 -Iodine-I 3 1 Processing Area4 of 29 The design philosophy for the hot cells is to provide adequate personnel shielding and containment of the1-13 1, precluding or minimizing any potential release from the individual cells to the reactor facility or toany unrestricted area. The design of the hot cell shielding and filtration is based upon a 200 Curie 1-131process;
- however, the proposed TSs will only request a limit of 150 Curies. This is consistent with ourcurrent fueled experiment TS limit (TS 3.6.a) on the inventory of iodine-131 through -135 perexperiment.
As explained above, a ý target can theoretically produce of 1-131(conservative overestimation of activity based on a maximum value for flux, greater than normalirradiation time, and the discounting of any self-shielding effects of the target material).
Based on thetypical values of flux and irradiation time, and low activity
- testing, a target will produceapproximately
ý of 1- 131 at the end of a typical M irradiation.
Table I -Hot Cell Lead Shielding (in millimeters)
HC-1IA HC-11B HC-11CFront, Rear Walls 200 200 100Ceiling 150 150 100Bottom (Table) 100 100 100Side Wall 200 N/A 100Partition 100 N/APartition N/A 100Bottom Channel (U-Shaped) 100 N/AExhaust Air 100Inlet Air 50Material Lock (HSB to HC-11A) 150 N/AMaterial Lock (HC-11C to HSB) N/A 1 50The three (3) cell hot cell processing system also incorporates a six (6) detector radiation monitoring system (ALMO-6) designed to provide radiation dose level information to the process operators (Ref. 5and Attachment 1). Three of the detectors (G-M) are located at the operator's work station where the hotcell manipulators are located and used during the process.
These detectors provide real time dose rateinformation to the operators when they are performing a process.
The remaining three detectors (G-M)are situated next to the first in a series of charcoal filters located in each of the bays above the three (3)hot cells. These are designed to give the process operators real time information related to the captureand loading of 1-131 onto the first charcoal filter in each external bank of the individual cells. This allowsthe process operators to monitor the condition of the charcoal filters and will alert them of the need tochange to a bank of alternately available filters.3.1 Handling Hot Cell -Design FeaturesThe Handling Hot Cell (HHC or HC-1 A) is designed for two principal purposes:
(1) to receive irradiated targets and house support equipment to remove the target encapsulation, and (2) to store process waste for5 of 29 an interim period of time. This cell has a floor access port to allow entry of irradiated targets from atarget transfer cask designed to seal with the cell floor port. Within this cell the target encapsulation isremoved and the irradiated=
material is placed in crucibles and transferred via a pass-through to thePHC.The cell is designed to have process waste materials from the PHC returned via a pass-through chamberfor interim storage.
The pass-through has a door at each side and is sized to hold any object that will bemoved to and from the PHC. The waste material from the PHC (e.g., expended target material, contaminated used equipment) will be placed in containers with press-seal lids.The volume of the cell is designed to hold the process waste for approximately 10 half-lives of the 1-131(about 80 days) after which time the cans may be moved to longer term shielded storage.
As noted above,the cell has 200 mm (7.9 inches) thick vertical lead shielding with a stainless steel liner and two master-slave-manipulators (MSM) penetrating the cell from the operator side. This cell also has a sealable glovebox for entry of items such as product vials and processing equipment.
3.2 Processing Hot Cell -Design FeaturesThe Processing Hot Cell (PHC or HC- 11 B) is where the processing of the = targets isperformed.
This cell has 200 mm (7.9 inches) thick vertical lead shielding with a stainless steel liner andtwo MSM which penetrate the cell from the operator side of the cells. The sodium iodide productsolution will be moved from the PHC to the DHC in a sealed vial through a pass-through.
Note: Thesystem is also designed where the sealed vial may be passed back into the HHC through the pass-through for transfer from the HHC to the DHC via a shielded cask.The PHC, during processing, provides three barriers to prevent the release of radioactive material to theenvironment:
(1) the processing equipment itself, (2) an additional inner containment for the separation furnace within the PHC with a dedicated filtration system (as described in Section 2.0), and (3) the PHCcontainment provided by an exhaust system that includes high efficiency charcoal filters.
The process isdesigned to contain 1-131 within the process equipment; therefore, there should be minimal, if any,release of airborne radioactivity to the hot cell.3.3 Dispensing Hot Cell -Design FeaturesThe Dispensing Hot Cell (DHC or HC-1 IC) is designed to receive the bulk 1-131 in solution from thePHC via a pass-through.
The bulk sodium iodide radiochemical will then be dispensed in quantities tomeet customer order requirements.
This cell will also have a sealable glove box for entry of items such asproduct vials, lead pigs, and dispensing equipment.
The dispensing cell has 100 mm (3.9 inches) thick of vertical lead shielding and two MSM penetrating the cell from the operator side.6 of 29 4.0 Facility and Hot Cell Ventilation Systems4.1 Facility Ventilation Supply SystemFresh air is supplied to both the laboratory and reactor containment buildings through louver dampers onthe north and south facades of the reactor building east tower. Most of the supply air entering the easttower is diverted to the laboratory building; a smaller portion is for make-up air to the containment building.
Outside air is preheated, as necessary, by a steam coil and then filtered before entering the laboratory building via the laboratory building supply fan (SF-1). The supply air is then directed to two receiving plenums (hot and cold decks), each containing an independent coil system. Steam is supplied to the hotdeck to heat the supply air; chill water from the air-conditioning system is supplied to the cold deck tocool the air. The heated and conditioned air from these plenums is then circulated throughout thelaboratory building via a double duct air distribution system. A ceiling register and mixing box in eachlaboratory and office allows the hot and cold air from the distribution system to be combined andcirculated within that space to create a suitable environment for personnel comfort and equipment cooling.Additional fresh air is supplied to the laboratory building (also to the laboratory building expansion, known as the MURR industrial building) through roof top air handlers (RTAH). Each RTAH has aheating and a cooling coil to heat and/or condition the supply air before its discharge into the laboratory building through registers in the ceilings of these corridors.
4.2 Facility Ventilation Exhaust SystemExhaust air from both the laboratory and reactor containment buildings is combined in an exhaust plenumprior to being discharged to the atmosphere.
Since air from both buildings is never mixed until this point,potentially contaminated air is diluted by mixing with uncontaminated air, resulting in minimumconcentrations of radioactive gases being released to the environment.
The ventilation exhaust system for the laboratory building is divided into four quadrants, each servicing approximately one quarter of the building.
The ventilation exhaust system also services the MURRindustrial building and mechanical equipment room 114. Each quadrant consists of a stainless steel filterhousing containing a bank of pre-filters and a bank of high efficiency particulate air (HEPA) filters.
Airis ducted from the quadrants to an exhaust plenum located in the reactor building west tower. Facilityventilation exhaust fans EF-13 and EF-14, located within the exhaust plenum, discharge the air throughthe facility exhaust stack to the atmosphere.
The top of the exhaust stack is approximately 70 feet (21 m)above grade level of the containment building.
One exhaust fan is always in operation while the other isin standby.
This condition is indicated by a green light on the fan failure alarm panel located in thereactor Control Room. Any condition other than one fan in "fast speed" and the other in "stand-by" willde-energize the green light and indicate an abnormal condition.
Malfunction of the operating fan willautomatically start the standby fan and de-energize the green light indicating a loss of the operating fan.Failure of both exhaust fans, or significantly degraded flow, actuates a pressure switch which initiates an7 of 29 audible alarm in the reactor Control Room. EF-13 and EF-14 are powered from the Emergency Electrical Power System; therefore, on a loss of normal electrical power, the operating fan will continue to operate.It should be noted that a facility ventilation exhaust fan is always in operation, whether the reactor isoperating or not. The standby feature is checked every week during the normally scheduled maintenance day and the fans are swapped to even runtime.
EF-13 or EF-14 shall be in operation when processing, asrequired by the proposed TSs.Figures 3 through 7 depict the facility ventilation system (8.5-inch x 14-inch versions are also included asAttachments 2 through 6). Specifically, Figure 7 shows the ventilation system for the iodine-131 hot cellsincluding the filtration systems.
The 1-131 hot cell filtration system is described in greater detail below.4.3 Hot Cell Ventilation and Filtration SystemsThe ventilation supply and exhaust system for hot cells HC-I IA, HC-I lB and HC-I IC consists of acombination of HEPA and charcoal filtration systems.
The supply and exhaust systems for each cellcombine to form a common header, but each hot cell has its own independent filtration system. Air issupplied to each hot cell from a common header (suction located in an area above room 299T) through aHEPA and charcoal filter at a rate of approximately 17 cubic feet per minute (cfm). Air is exhausted fromeach hot cell through an internal parallel set of charcoal filters (Bank No. 1) (Ref. 6 and Attachment 7),then through a (selected) external parallel charcoal filtration bank (Bank No. 2: one set of two in service -the other set in standby)
(Ref. 6 and Attachment 7), a second (selected) external parallel charcoal filterbank (Bank No. 3: one set of two in service -the other set in standby)
(Ref. 6 and Attachment 7), andthen through a (selected) parallel charcoal filter (Bank No. 4: one filter on service -one in standby)
(Ref.7 and Attachment
- 8) into the facility main ventilation exhaust system at a flow rate of approximately 50cfm. Air is removed from the hot cells at a rate of approximately 10 air changes per hour (ACPH).There are two glove boxes mounted to the hot cells; one on the north end of HC-1 1A and one on the southend of HC-1 1C. These gloves boxes provide the means of introducing or removing items from the hotcells. Each glove box also has its own independent supply and exhaust system. Air is supplied to eachglove box at a rate of approximately 1.7 cfm through a combination HEPA/charcoal filter. Air isexhausted from each glove box through a charcoal filter and then a HEPA filter. The exhaust ducting foreach glove box connects to the hot cell common exhaust header downstream of the hot cell filtration systems.As described in Section 3.0 above, a six (6) detector radiation monitoring system (ALMO-6) designed toprovide radiation dose level information to the process operators is incorporated into the three (3) cell hotcell processing system (Ref. 5 and Attachment 1). Three of the detectors (G-M) are positioned next tocharcoal filter Bank No. 2 in each bay of the three (3) hot cells. These are designed to give the processoperators real time information related to the capture and loading of 1-13 lonto the first charcoal filter ineach bank of the individual cells. This allows the process operators to monitor the condition of thecharcoal filters and will alert them of the need to change to a bank of alternately available filters.8 of 29 1J TC)cn0I-bnI -- -.--- ----r -- -- -- -- h10 7 -- ---ln ----------
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- 11 -000I-L_____ 2ub'___ ___ __< C/OtC- r_< cco m1: .5 5.0 Radiation Monitoring Equipment There are three (3) separate radiation monitoring systems that can monitor the effluents from the 1-131processing hot cells: (1) the facility Off-Gas Radiation Monitoring System, (2) the 1-131 Processing Laboratory Exhaust Duct Monitor, and (3) the ALMO-6 Hot Cell Dose Rate Radiation Monitor.Air exiting the MURR facility through the ventilation system exhaust stack is continuously-monitored forairborne radioactivity by the Off-Gas Radiation Monitoring System (TS 3.4.a -Stack Radiation Monitor).
The monitoring equipment of this system consists of a three (3) detector radiation detection systemdesigned to measure the airborne concentrations of radioactive particulate, iodine, and noble gas in thefacility exhaust air which is sampled by an isokinetic probe located in the ventilation exhaust plenum.The radiation detection equipment is a self-contained unit consisting of a fixed filter monitored by a betascintillation
- detector, a charcoal cartridge monitored by a gamma scintillation
- detector, and a gas chambermonitored by a beta scintillation detector.
The output from each radiation detector is displayed on a localmeter in counts per minute (cpm) and on a strip-chart, three-pen recorder mounted on the instrument panel in the reactor Control Room. An audible and visual alarm alerts the operator to high activity orabnormal air flow through the radiation detection equipment.
As can be seen by Figure 6 (lower sectionof drawing),
two (2) of these systems are installed for redundancy;
- however, only one is required by theTSs. The facility Stack Radiation Monitor shall be in operation when processing, as required by theproposed TSs.The 1-131 Processing Laboratory Exhaust Duct Monitor consists of a radiation detection system designedto measure airborne concentrations of radioactive iodine in the exhaust air that is sampled by a shroudedprobe in the ventilation ducting immediately downstream of all of the 1-131 hot cell and room filtration systems.
The system is capable of measuring real-time exhaust flow rate as its basis for releaseconcentrations.
A pitot tube measurement device and flow transmitter provides input to the system. Theradiation monitor can be seen in the upper section of Figure 6.The ALMO-6 Hot Cell Dose Rate Radiation
- Monitor, as described in Section 3.0, consists of a six (6)detector radiation monitoring system designed to provide radiation dose level information to the processoperators (Ref. 5 and Attachment 1). Three of the detectors (G-M) are located at the operator's workstation where the hot cell manipulators are located.
These detectors provide real time dose rateinformation to the operators when they are performing a process.
The remaining three detectors (G-M)are located next to the first in a series of charcoal filters (Bank No. 2 and No. 3) located in each of thebays above the three (3) hot cells. These are designed to give the process operators real time information related to the capture and loading of 1-131 onto the first charcoal filter in each external bank of theindividual cells. This allows the process operators to monitor the condition of the charcoal filters and willalert them of the need to change to a bank of alternately available filters.
The ALMO-6 radiation monitorshall be in operation when processing, as required by the proposed TSs. It is referred to as the "Iodine-131 Processing Hot Cells Radiation Monitor" in the TSs.6.0 Evaluation of an 1-131 release in the Processing Hot cellThe PHC will have the highest possible content of volatile 1-131. This peak content would occur duringthe approximately when the = targets are14 of 29 The 1-131 evolved during this.For this conservative evaluation of a potential release during processing it willbe assumed that 150 Curies of 1-131 are released within the PHC. This is a very conservative assumption for the following reasons:1. The 1-131 is evolved over about aAny indication of leakage from the processequipment into the hot cell (e.g., malfunction of the process equipment) would cause staff toimmediately secure the furnace resulting in the 1-131 evolution to be reduced and then to cease,evolving only a small fraction of the total target inventory; 2.and3. Theoretical 1-131 yield from a ý is ý based on a conservative overestimation offlux, greater than normal irradiation time, and the discounting of any self-shielding effects of thetarget material.
Based on the typical values of flux and irradiation time, and data from lowactivity testing of target material, a target will produce approximately of 1-131 at the end of a typical M irradiation.
In addition to the dose consequences from a 150 Curie target that are provided below, dose consequences from a release of of 1-131 are also provided for a more realistic comparison.
5.1 Dose Consequences in the Restricted AreaThe following analysis is specific to determining exposure rates from the ventilation exhaust system to aworker assuming a non-credible, total loss of the 1-131 inventory within the PHC (the same filtration mitigation features exist on all three (3) hot cells; therefore, the analysis applies to any of the three cells).The analysis assumes the following three (3) separate quantities of 1-131 activity:
= and 150 Curies.As stated previously, 150 Curies represents the maximum allowable iodine inventory for any fueledexperiment conducted at MIURR (TS 3.6.a) and was chosen as the starting point for analysis of offsitedose consequences for 1-131 release,
ý represents an overestimated theoretical yield, and *represents the typical processing yield.No credit was taken for the plating of iodine within the hot cells and ventilation ducting.
Radiation exposure calculations are broken down into two scenarios:
(1) exposure rates from the installed charcoalfilters, and (2) exposure rates from the ventilation ductwork assuming complete filter failure.
Whilecalculating exposure rates from the installed filters several adjunct calculations were also performed.
The15 of 29 below sequence illustrates the calculation methodology of radiation exposure rates from a loaded charcoalfilter.In order to calculate the activity deposited on a filter and subsequent filters in a series, the following equation was used:(Eq. 1) A(x) = (A(e)/D-1) -(A(e)/(DF)x)
Where:A(x) = Activity deposited on filter "x";A(e) = Activity entering the first filter of the series;DF = Decontamination Factor (must be common between all filters);
andX = The sequential number of the filter bank in a series starting with 1.Using Equation 1, Tables 2, 3 and 4 present activities that were determined to be deposited on each of thefour (4) installed charcoal filter banks using a Decontamination Factor (DF) of both 100 (99.0%efficiency) and 1000 (99.9% efficiency) for all three (3) processing activity amounts and assuming afailure of one (1) of the installed filters.
To model the greatest potential for worker exposures, Filter BankNo. 1 was assumed to fail. The failure of Filter Bank No. 1 represents a greater exposure to workersbecause this filter is housed within the PHC and shielded with the greatest amount of lead. Filter BankNo. I failure would create the largest magnitude of activities external to the PHC and the largest potential of exposure to workers.Table 2- 150 Curies of 1-131Activity on Filters Post Release (Ci)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 1.4985E+02 1.4985E-01 1.4985E-04 1.4985E-07 Mitigated (3 of 4 filters -DF 1000) 0.OOOOE+00 1.4985E+02 1.4985E-01 1.4985E-04 Mitigated (4 of 4 filters -DF 100) 1.4850E+02 1.4850E+00 1.4850E-02 1.4850E-04 Mitigated (3 of 4 filters -DF 100) 0.OOOOE+00 1.4850E+02 1.4850E+00 1.4850E-02 Unmitigated 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Table 3 -f of 1-131Activity on Filters Post Release (Ci)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 8.7912E+01 8.7912E-02 8.7912E-05 8.7912E-08 Mitigated (3 of 4 filters -DF 1000) 0.OOOOE+00 8.7912E+01 8.7912E-02 8.7912E-05 Mitigated (4 of 4 filters -DF 100) 8.7120E+01 8.7120E-0l 8.7120E-03 8.7120E-05 Mitigated (3 of 4 filters -DF 100) 0.OOOOE+00 8.7120E+0l 8.7120E-01 8.7120E-03 Unmitigated 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 16 of 29 Table 4 -of 1-131Activity on Filters Post Release (Ci)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 5.4945E+01 5.4945E-02 5.4945E-05 5.4945E-08 Mitigated (3 of 4 filters -DF 1000) 0.0000E+00 5.4945E+01 5.4945E-02 5.4945E-05 Mitigated (4 of 4 filters -DF 100) 5.4450E+01 5.4450E-01 5.4450E-03 5.4450E-05 Mitigated (3 of 4 filters -DF 100) 0.0000E+00 5.4450E+01 5.4450E-01 5.4450E-03 Unmitigated 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Calculation of exposure rates for each of the filters was performed using the computer programMicroShield 8.02 (Ref. 8 and Attachment
- 9) with an Annular Cylinder
-External Dose Point geometryfor Filter Bank No. I through 3 and a Rectangular Volume geometry for Filter Bank No. 4. Thesegeometries most accurately represent the designs of each filter according to the manufacture specification sheets. Also, each filter is designed with surrounding lead shielding.
This shielding was included in thegeometry model and used in the exposure rate calculations for each filter. Filter shielding thicknesses aredescribed in Table 5.MicroShield 8.02 is a product of Grove Software and is a comprehensive photon/gamma ray shielding and dose assessment program that is widely used in the industry for designing shields.Table 5 -Filter Shielding Thickness (in centimeters)
Filter Bank Lead Thickness No. 1 10No. 2 10No. 3 10No. 4 0.635An exposure rate calculation for each case as seen in Tables 2, 3 and 4 was performed in MicroShield andresulted in the associated exposure rates in Tables 6, 7 and 8 below. A summary of each MicroShield calculation is attached for review; however, in some cases the calculated exposure rates were scaled froma previous calculation by a ratio of the activities.
To be conservative, a one (1) foot distance from eachfilter was selected as the dose point distance.
Workers are not expected to come within four (4) feet of afilter during normal work activities.
17 of 29 Table 6 -150 Curie Target Exposure Rates Due to Shine from Filters at 1 Foot(in mR/hr)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 5.15E-03 9.72E-06 9.72E-09 1.42E-05Mitigated (3 of 4 filters -DF 1000) 0.OOE+00 9.72E-03 9.72E-06 1.42E-02Mitigated (4 of 4 filters -DF 100) 5.1OE-03 9.64E-05 9.64E-07 1.41E-02Mitigated (3 of 4 filters -DF 100) 0.OOE+00 9.64E-03 9.64E-05 1.4 1E+00Table 7 -ý Target Exposure Rates Due to Shine from Filters at 1 Foot(in mR/hr)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 3.02E-03 5.71E-06 5.71E-09 8.34E-06Mitigated (3 of 4 filters -DF 1000) 0.OOE+00 5.71E-03 5.71E-06 8.34E-03Mitigated (4 of 4 filters -DF 100) 2.99E-03 5.66E-05 5.66E-07 8.26E-03Mitigated (3 of 4 filters -DF 100) 0.OOE+00 5.66E-03 5.66E-05 8.26E-01Table 8 -ý Target Exposure Rates Due to Shine from Filters at 1 Foot(in mR/hr)Bank No. 1 Bank No. 2 Bank No. 3 Bank No. 4Mitigated (4 of 4 filters -DF 1000) 1.89E-03 3.57E-06 3.57E-09 5.2 1E-06Mitigated (3 of 4 filters -DF 1000) 0.OOE+00 3.57E-03 3.57E-06 5.21E-03Mitigated (4 of 4 filters -DF 100) 1.87E-03 3.54E-05 3.54E-07 5.17E-03Mitigated (3 of 4 filters -DF 100) 0.OOE+00 3.54E-03 3.54E-05 5.17E-01Tables 6, 7 and 8 indicate that the highest exposure rate is expected to be from Filter Bank No. 4 at 1.41mR/hr with three (3) of four (4) filter banks in service during a 150 Curie process and filter DFs of 100.The reason for the highest exposure rates being seen on Filter Bank No. 4 is due to the substantially thinner lead shielding thickness installed around this filter as compared to Filter Bank No. I through 3.A second potential scenario for the ventilation exhaust system to create exposure rates near a worker isthat of an unmitigated release resulting in a high activity concentration volume of air moving through theventilation system. In order to calculate the activity concentration of the air within the facility ventilation exhaust system, the following assumptions were made:1. 100% of the available iodine inventory is instantaneously released into the hot cell volume freespace. In reality it is expected the iodine activity would be released from a target over one (1)hour allowing for greater dilution than is considered by this assumption; 18 of 29
- 2. 50% of the entire hot cell volume is considered as free space. 50% is a large underestimation ofthe available free space within a hot cell; however, this results in a conservative determination ofairborne activity concentrations and increases the calculated exposure rates; and3. 100% efficiency of the air to be turned over in the hot cell in the minimum time possible.
Inreality it is not expected that 100% air turn over efficiency will be achieved;
- however, for thepurposes of calculating exposure rates this assumption will result in a conservative determination of air activity concentrations within the facility ventilation exhaust ducting.Also, the following parameters were used to calculate the activity concentration of the air within thefacility ventilation exhaust system:1. Hot cell dimensions of 152.5 cm x 152.5 cm x 122 cm (H x W x D); and2. Hot cell flow rates of: HC-1 1A = 15 cfm; HC-1 lB = 11 cfm; and HC-1 IC = 10 cfm (determined by flow measurements documented in Work Package No. 15-3918, May 4, 2015).In order to calculate the activity concentration of the air entering the facility ventilation exhaust ducting, adetermination must first be made of the hot cell air volume turnover time. Equation 2 was used todetermine hot cell air volume turn over time.(Eqn. 2) T(x) = V(x)/F(x)
Where:T(x) = Air volume turn over time for hot cell "x" in minutes;V(x) = Volume of hot cell "x" in cubic feet; andF(x) = Flow of air exiting hot cell "x" in cfm.Using Equation 2, the following turn over times listed in Table 9 were calculated for the 1-131 processing hot cells.Table 9 -Hot Cell Turnover Time(in minutes)Hot Cell Turnover TimeHC-11A 3.34HC-I lB 4.55HC-I1C 5.01Next a calculation was performed to determine the concentration of activity within the hot cell. Thebelow equation was used to calculate the activity concentrations listed in Table 10.19 of 29 (Eqn. 3)C(x) = A(x)/V(x)
Where:C(x) = Concentration of airborne activity in hot cell "x";A(x) = Activity instantaneously entering hot cell "x"; andV(x) = Volume of hot cell "x".Table 10- Hot Cell Air Concentrations (in pCi/ml)Process Activity Air Concentration 150 Ci 105.7462.03-38.77From the hot cell, a conservative assumption is made that all of the activity instantaneously introduced into the PHC escapes the hot cell and enters the ventilation exhaust system within approximately five (5)minutes.
As stated previously, this assumption will conservatively calculate activity concentrations of theair and hence result in conservative exposure rate values.In order to calculate expected activity concentrations throughout the facility ventilation exhaust system aratio of ventilation flow rates was determined and used to ratio the expected activity concentrations.
Table 11 lists the flow rates used for the activity determinations and Equation 4 describes the methodused to ratio the activity concentrations.
Table 11 -Ventilation exhaust Flow Rate(in cfm)Location Flow RateHC-11B 116-inch Ductwork 4716-inch Ductwork 1000(Eqn. 4) A(x) = C[Fo/F(x)]
Where:A(x) = Activity concentration at location "x";C = Activity concentration in the hot cell;F, = Flow rate from the hot cell; andF(x) = Flow rate at location "x".Using Equation 4, the following activity concentrations listed in Tables 12, 13 and 14 were determined atvarious locations of the ventilation exhaust system. Also, in the tables are the calculated exposure rates20 of 29 resulting from the associated activity concentrations.
The exposure rate calculations were performed inMicroshield 8.02 using a 100 cm line source geometry with a dose point at a distance of one (1) foot fromthe source. A summary of each MicroShield calculation is attached to this document (Attachment 9).Table 12 -150 Curie Target Exposure Rates Due to Shine from Ventilation at 1 FootHot Cell 6-inch 16-inchDuctwork Ductwork DuctworkActivity Concentration (gCi/ml) 1.0574E+02 2.4762E+01 1.1632E+00 Unmitigated Exposure Rate (mR/hr) 1.6330E+01 3.8230E+00 1.7960E-01 Table 13 -ý Target Exposure Rates Due to Shine from Ventilation at 1 FootHot Cell 6-inch 16-inchDuctwork Ductwork DuctworkActivity Concentration (gCi/ml) 6.2032E+01 1.4527E+01 6.8242E-01 Unmitigated Exposure Rate (mR/hr) 9.5770E+00 2.2430E+00 1.0540E-01 Table 14 -Target Exposure Rates Due to Shine from Ventilation at 1 FootHot Cell 6-inch 16-inchDuctwork Ductwork DuctworkActivity Concentration (pCi/mi) 3.8770E+01 9.0796E+00 4.2651E-01 Unmitigated Exposure Rate (mR/hr) 5.9860E+00 1.4020E+00 6.5850E-02 As expected, the highest exposure rate from an unmitigated release is from the hot cell ductwork at 16.33mR/hr assuming the 150 Curie process activity is instantaneously released into the hot cell.After review of the expected exposure rates from an unmitigated and mitigated
- release, external dosehazards to personnel are minimal and within regulatory compliance for process activities up to 150Curies.5.2 Dose Consequences in the Unrestricted AreaTwo analyses were performed for potential offsite dose consequences of a failed = target andsubsequent release of 1-131 to the surrounding environment that was produced in the target duringirradiation.
The first analysis was performed using the Environmental Protection Agency (EPA) and U.S.Nuclear Regulatory Commission (NRC) accepted computer code COMPLY -a computerized screening tool for evaluating radiation exposure from atmospheric releases of radionuclides for calculating doses tothe public for offsite air effluent radionuclide releases (Ref. 9). In fact, MURR currently uses this codefor determination of air effluent offsite dose consequences on an annual basis for regulatory compliance.
Updated wind rose data used for this analysis was obtained from the Columbia Regional Airport (CRA)for the time period of 1984 to 1992. The doses calculated are based on the dose to the nearest permanent resident located approximately 760 meters north of MURR in a residential neighborhood and uses thefrequency distribution of wind directions around MURR. CRA is located approximately 13 miles SE of21 of 29 MURR and the wind data used as noted above is the most readily available and recent wind rose datafound published in the available literature.
As previously stated, the following three (3) activities of 1-131 were used in the analysis:
(1) 150 Curiesrepresents the maximum allowable iodine inventory for any fueled experiment conducted at MURR (TS3.6.a), (2) ý represents an overestimated theoretical yield, and (3) ý represents the typicalprocessing yield.The second analysis utilized the Pasquill-Guifford (P-G) dispersion model methodology for atmospheric dispersion of contaminants.
This model has been used for years in the nuclear industry and is the basisfor subsequent atmospheric modeling methods developed throughout the late 20th century.
The "D"stability class and a southern wind direction was chosen for this analysis as they provide the mostconservative (highest) concentrations of effluents at the point of interest with regards to offsite dosecalculations and is the most prominent wind direction in central Missouri, respectively.
Additionally, thewind direction is assumed to come from the southerly direction the entire two (2) hours of the releaseevent. The above stated three (3) activity amounts were also used in this analysis.
Table 15 presents the dose consequences of the three (3) 1-131 unmitigated (no filtration or plating)release scenarios to the environment whereas Tables 16, 17 and 18 show the expected offsite doseconsequences, presented in a matrix of four separate filter status scenarios, for a mitigated release.
Thiscalculation is repeated three times to reflect the COMPLY code output and two separate calculations forwhole body (WB) and thyroid dose utilizing the P-G methodology.
Table 15 -Offsite Dose Consequences
-Unmitigated (no Filtration)
COMPLY1 Pasquill-Guifford Model2'3 Pasquill-Guifford Model2'3Activity Released (Whole Body) (Whole Body) (Thyroid)
(Ci) (mrem)Nearest Residence Emergency Planning Zone -150 meters150 124 13.1 7616I 73 7.7 446845 4.8 2793Table 16 -Offsite Dose Consequences
-Mitigated (Filtration)
(COMPLY Model -Nearest Residence)
Activity 1 Filter Bank 2 Filter Banks 3 Filter Banks 4 Filter BanksReleased Method(Ci) (mrem)150 COMPLY' 1.24 0.01 1.24E-04 1.24E-06(WB -Nearest 0.73 0.01 7.27E-05 7.27E-07* Residence) 0.45 0.01 4.55E-05 4.55E-0722 of 29 Table 17 -Offsite Dose Consequences
-Mitigated (Filtration)
(P-G Model2'3 -Whole Body at Emergency Planning Zone)Activity I Filter Bank 2 Filter Banks 3 Filter Banks 4 Filter BanksReleased Method(Ci) (mrem)150 0.13 0.01 1.31E-05 1.31E-07P-G Model2'3 0.08 0.01 7.70E-06 7.70E-08-* 0.05 0.01 4.80E-06 4.80E-08Table 18 -Offsite Dose Consequences
-Mitigated (Filtration)
(P-G Model2'3 -Thyroid at Emergency Planning Zone)Activity I Filter Bank 2 Filter Banks 3 Filter Banks 4 Filter BanksReleased Method(Ci) (mrem)150 76.16 0.76 7.62E-03 7.62E-05P-G Model2'3 44.68 0.45 4.47E-03 4.47E-05(Thyroid
-EPZ)S_ 27.93 0.28 2.79E-03 2.79E-051Dose from COMPLY is to the nearest residence, 760 meters north.2Dose conversion factors for the two P-G Models are from NRC Regulatory Guide 1.109, "Calculation of AnnualDoses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR50, Appendix I" (Ref. 10).3Doses for the two P-G models are assumed to be received at the EPZ,. 150 meters north over a two (2) hour period.No correction for dispersion of the cloud is made at the site of the recipient, i.e. the cloud is assumed to be uniformover the entire two (2) hour scenario post release.The initial offsite doses were calculated assuming a total release of the available iodine inventory with nofiltration or capture used (unmitigated) and were generated using the COMPLY code. The second andthird scenarios were calculated using the P-G model and assumed the dose would be received by a personsituated at the Emergency Planning Zone (EPZ) boundary of 150 meters due north of MURR (alsohighest dose location).
The first set of dose calculations are for WB doses due to exposure of 1-131 at theEPZ boundary.
The second set of dose calculations are doses to the thyroid at the same point. Both setsof calculations show the effects of 1 through 4 banks of charcoal
- filters, assuming a 99% collection efficiency (DF 100) for 1-131, used to mitigate offsite dose. Again, the scenario assumes that no 1-131would plate out in the hot cell or ductwork prior to being released from the facility.
Furthermore, thedose calculations assume that a person is located at the EPZ for the entire two (2) hour post-accident period prior to being evacuated from that area (Ref. 11). This assumes that the air concentration isconstant at the calculated values during the accident and that no credit is taken for the prevailing wind todisperse the 1-131 laden air.MURR is situated on a 7.5-acre lot in the central portion of Research
- Commons, an 84-acre tract of landapproximately one mile southwest of the University's main campus (Figure 8). Approximate distances tothe University property lines (site boundary) from the reactor facility are 2,400 feet (732 m) to the north(Stadium Boulevard);
4,800 feet (1,463 m) to the east of Providence Road; 2,400 feet (732 m) to the south23 of 29 (MU Recreational Trail); and 3,600 feet (1,097 m) to the west (MKT Nature and Fitness Trail). MURR'sEPZ lies completely within the site boundary and individuals can easily be evacuated from within thisarea in two (2) hours. The area within the site boundary is owned and controlled by MU and may befrequented by people unacquainted with the operation of the reactor.
The Reactor Facility Director hasauthority to initiate emergency actions in this area, if required (Ref. 12 and 13).'NFigure 8 -MURR Emergency Planning Zone and Surrounding Site Area24 of 29 Providence Road crosses MU property separating University Research Commons from another MU-owned tract of land lying to the east. The road runs north and south with the closest point of approachbeing approximately 400 meters east of the facility.
MU has the authority to determine all activities including the exclusion or removal of personnel and property and to temporarily secure the flow of trafficon this road during an emergency.
For comparison
- purposes, the dose consequence matrix calculates offsite doses for scenarios where one,two, three and four banks of activated charcoal filters are available to capture released 1-131 gases. Thefilters are assumed to be 99% efficient in capturing elemental iodine, which is a factor of lOx lower thanstated values provided by the filter manufacturers.
Thus the offsite doses can be easily compared using avariety of scenarios ranging from having no filtration up to the maximum amount designed into thesystem of four (4) separated banks of activated charcoal filters.In conclusion, the above analysis demonstrates that only one (1) in four (4) filter banks is required to befunctional in order to keep offsite dose below the 10 CFR 20 limit for occupationally exposed workersthat require monitoring and two sets of functioning filters would keep doses below 10 mrem to the thyroidand thus below any dose limits applicable to the general public.6.0 Comparison to Current Fueled Experiment Technical Specifications There are currently two specifications regarding radioisotope limits for conducting fueled experiments atMURR. Both are based on the total inventory of iodine-131 through iodine-135 and strontium-90 produced by the experiment:
3.6.a "Each fueled experiment shall be limited such that the total inventory of iodineisotopes 131 through 135 in the experiment is not greater than 150 Curies and themaximum strontium-90 inventory is no greater than 300 Millicuries."
3.6.o "Fueled experiments containing inventories of Iodine 131 through 135 greater than1.5 Curies or Strontium 90 greater than 5 millicuries shall be in irradiation containers that satisfy the requirements of specification 3.6.i or be vented to theexhaust stack system through HEPA and charcoal filters which are continuously monitored for an increase in radiation levels."TS 3.6.a was proposed by MURR in a letter to the NRC dated February 15, 1977, specifically to supportan experiment in the reactor thermal column which utilized "unclad" fission plates to irradiate large rollsof thin polycarbonate film material (Ref. 14).TS 3.6.o was proposed by MURR in its September 23, 1977 letter to the NRC (Ref. 15). This letter wasone in a series of letters in support of an Amendment request to allow TS 3.6.a fueled experiment limits tobe increased from 1.5 Curies of 1-131 through -135 and 5 millicuries of Sr-90 to 150 Curies of 1-131through -135 and 300 millicuries of Sr-90, which are currently the radioisotope limits for fueledexperiments stated in TS 3.6.a. This increase was requested in order for the MURR to perform thespecific fueled experiment described above. The nature of the experiment, "unclad" uranium fission25 of 29 plates located outside of the reactor pool, required it to be vented to the facility ventilation exhaust systemthrough continuously monitored HEPA and charcoal filters.Additionally, TS 3.6.o provided assurance that any experiment exceeding the limits of TS 3.6.o, and up tothe limits of TS 3.6.a, would be vented to the ventilation exhaust system through continuously monitored HEPA and charcoal
- filters, and it specifically applied to the experiment described in MURR letters to theNRC dated February 15, 1977; September 23, 1977; and January 20, 1978 (Ref. 16).By letter dated February 24, 1978, the NRC issued Amendment No. 8 to MURR facility license No. R-103 to change the limitations on fueled experiments (Ref. 17). Table I of that letter provides the potential dose consequences in the unrestricted area due to a failed fueled experiment as calculated by the NRC.These are the following NRC dose calculations and assumptions directly taken from that table:TABLE IPOTENTIAL CONSEQUENCES OF THEPOSTULATED MURR FUELED EXPERIMENT ACCIDENTDose (Rem)Exposure Location Thyroid Whole Body2 Hours Exclusion Boundary 77 0.5(500 feet)Low Population Zone 20 <0.2(1500 feet)Assumptions:
Meteorology:
Regulatory Guide 1.4 Ground Level ReleaseBuilding Wake Effect (1.6)1.0 x 10-2 sec/m (Exclusion Boundary 0 -2 hours)2.5 X 10-3 sec/m (Low Population Zone, 0 -8 hours)Puff ReleaseNo credit for filterNo credit for plateoutEquilibrium quantities of fission products150 curies radioiodines 131 to 135300 mcuries Strontium-90 The above NRC-calculated (and accepted) doses from an unmitigated release of 150 Curies of 1-131through -135 is the basis for our current MURR facility license and TSs for a fueled experiment.
Forcomparison, the unmitigated dose calculations for the requested license amendment in support ofproducing the radiochemnical sodium iodide for approximately the same distances from the MURRventilation exhaust stack are provided in Table 19.26 of 29 Table 19 -Comparison of Doses from an Unmitigated Release of 150 Curies of IodineNRC-calculated Doses' MURR-calculated Doses2(Rem) (Rem)Location Whole Body Thyroid Location Whole Body Thyroid500 ft (152.4 m) 0.5 77 150 m (492.1 ft) 0.013 7.6161500 ft (457.2 m) < 0.2 20 457 m (1499.3 ft) 0.002 1.066'Doses as calculated for a ground release by the NRC for failure of a fueled experiment in support of LicenseAmendment No. 8, dated February 24, 1978.2 Doses as calculated for an elevated release by MURR for a complete release of 150 Curies of 1- 131 in support ofrequest to amend facility operating license R-103 to produce radiochemical sodium iodide.Therefore, the scale of the 1-131 experiment proposed by MURR in this request is well within the currentsafety analysis for fueled experiment TSs 3.6.a and 3.6.o that was approved by the NRC in 1978 for an"unclad" experiment using uranium material.
8.0 Proposed Technical Specifications Attached are the proposed TS pages (revised and new) that will allow MURR to safely produce theradiochemical sodium iodide (Attachment 10).New Specifications 3.6.p and 3.6.q are based on, and worded very similar to, the current fueledexperiment TSs 3.6.a and 3.6.o -a 150 Curie limit on 1-131 and requiring the experiment to be vented tothe exhaust stack through charcoal filtration which is continuously monitored for radiation levels.New Specification 3.11 provides the Limiting Conditions for Operations (LCO) for the ventilation
- exhaust, charcoal filtration and radiation monitoring equipment needed to safely produce 1-131.American National Standard ANSI/ANS-15.1-2007, "The Development of Technical Specifications forResearch Reactors" (Ref. 18), specifically Sections 3.5 and 3.7, was used to determine the LCOs for thisexperiment.
New Specification 5.7 provides the surveillance requirements for the new LCOs. Once again, Reference 18, specifically Sections 4.4 and 4.7, were used to establish these requirements.
Based on the vendorrecommendation of three (3) years for both the Camfil and Flanders charcoal
- filters, filter efficiency measurements will be performed biennially.
Regulatory Guide 1.52, "Design, Inspection, and TestingCriteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants" (Ref. 19), will be used as guidance tomeet this specification.
Additionally, based on the installed radiation monitoring equipment, filtersmaybe replaced at shorter intervals should an increase in radiation levels or activities be detected.
9.0 Conclusion
Based on the onsite and offsite dose calculations for unmitigated and mitigated 1-131releases and theproposed changes to the TSs, MURR can safely produce the radiochemical sodium iodide. Since there27 of 29 are currently no competing modalities for its use as a therapy for thyroid dysfunctions and no currentsupplier within the U.S., this Amendment would allow MURR to continue to perform a key role in thesupply of critical medical radioisotopes, both domestically and internationally.
Additionally, as discussed in Section 6.0, the unmitigated MURR-calculated dose consequences for thisexperiment are much lower than the NRC-calculated dose consequences of a fueled experiment containing 150 Curies of 1-131 through -135 and 300 millicuries of Strontium-90.
The same safetyequipment and instrumentation
-exhaust ventilation, charcoal filtration and radiation monitoring
-willbe used for this experiment that is currently required for fueled experiments (TS. 3.6.o), as was always theintent.If there are questions regarding this request, please contact me at (573) 882-5319.
I declare under penaltyof perjury that the foregoing is true and correct.ENDORSEMENT:
Sincerely, Reviewed and ApprovedJohn L. Fruits Ralph A. Butler, P.E.Reactor Manager Directorxc: Reactor Advisory Committee Reactor Safety Subcommittee Dr. Garnett S. Stokes, ProvostDr. Henry C. Foley, Senior Vice Chancellor for ResearchMr. Alexander Adams, U.S. Nuclear Regulatory Commission Mr. Geoffrey Wertz, U.S. Nuclear Regulatory Commission Mr. Johnny Eads, U.S. Nuclear Regulatory Commission
References:
- 3. IAEA-TECDOC-1340, "Manual for Reactor Produced Radioistopes"
- 5. ALMO 6 Operating Manual (G-M Radiation Monitoring System)6. Camfil Activated Carbon Filters7. Flanders High Efficiency Gas Adsorber (HEGA) Filters8. MicroShield 8.02 -Computer program used to estimate dose rates due to a specific externalradiation source28 of 29
- 9. Comply -Computerized screening tool for evaluating radiation exposure from atmospheric releases of radionuclides
- 10. Regulatory Guide 1.109, '.'Calculation of Annual Doses to Man from Routine Releases of ReactorEffluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I."11. Regulatory Guide 2.2, "Development of Technical Specifications for Experiments in ResearchReactors" (November 1973)12. M1URR Emergency Plan13. MURR Emergency Plan Implementing Procedures (TOC- 107)14. Letter from MURR to the NRC, dated February 15, 1977, requesting a change to the Technical Specifications in order to increase the iodine inventory limit in a fueled experiment
- 15. Letter from MURR to the NRC, dated September, 1977, responding torequest for additional information in support of the February 15, 1977 request to change the Technical Specifications
- 16. Letter from MURR to theNRC, dated January 20, 1978, in support of the February 15, 1977request to change the Technical Specifications
- 17. Letter from the NRC to MURR, dated February 24, 1978, issuing Amendment No. 8 to facilityoperating license R-10318. American National Standard ANSI/ANS-15.1-2007, "The Development of Technical Specifications for Research Reactors"
- 19. Regulatory Guide 1.52, "Design, Inspection, and Testing Criteria for Air Filtration andAdsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems inLight-Water-Cooled Nuclear Power Plants" (September 2012, Rev. 4)Attachments:
- 1. ALMO 6 Operating Manual (G-M Radiation Monitoring System)2. MURR Drawing No. 1125 (Sheet 1 of 5), "Schematic Diagram of Laboratory and Containment Buildings Ventilation System"3. MURR Drawing No. 1125 (Sheet 2 of 5), "MURR Supply Air Schematic"
- 4. MURR Drawing No. 1125 (Sheet 3 of 5), "MURR Exhaust Ventilation Loads"5. MURR Drawing No. 1125 (Sheet 4 of 5), "Schematic Diagram of Laboratory and Containment Buildings Ventilation System Stack Monitors"
- 6. MURR Drawing No. 1125 (Sheet 5 of 5), "MIB East Addition Exhaust Schematic"
- 7. Camfil Activated Carbon Filters8. Flanders High Efficiency Gas Adsorber (HEGA) Filters9. MicroShield 8.02 Analysis for MURR 1-131 Experiment
- 10. New and Revised Technical Specification Pages29 of 29 ATTACHMENT 1ALMO 6Operating ManualNuklear-Medizintechnik Dresden GmbH ATTACHMENT 1
ATTACHMENT 1ALMO 6 Operating ManualContents1. Description and Definition of Project 62. Operation of the Alarm Monitor 83. Operating Elements 93.1. Internal and External Displays 103.1.1. Function of the Quit Button 113.2. Menu Overview 123.2.1. Menu Structure 123.2.2. Menu Operation 134. Measurement Mode 144.1. 6 Probe Display 144.2. 1 Probe Display 144.3. Display as Bar Graph 154.4. Display as Curve Graph or Planar Graph 154.5. Error List 164.6. Alarm Triggering 174.7. Measuring Range Overflow 184.8. Code Entry 194.9. Main Menu 204.9.1. Language 214.9.2. System Parameters 224.9.2.1.
Display 234.9.2.1.1.
Settings for 1-Probe Display 244.9.2.1.2.
Settings for 6-Probe Display 254.9.2.1.3.
Bargraph Settings 264.9.2.1.4.
Display Settings for Curve / Planar Graph 274.9.3. Total Alarm Settings 284.9.4. Data Transmission 294.9.4.1.
Interface Settings 294.9.4.2.
Printer Settings 304.9.4.3.
Data Transfer Settings 314.9.5. Error Display 324.9.5.1.
Error Display ,,No Probe" 334.9.5.1.1.
Error Display ,,No Probe"--Total Alarm Settings 34Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltlthstrasse 14 a, D-0 1277 DresdenPage 3 ATTACHMENT 1ALMO 6 Operating Manual4.9.5.2.
Error Display System Error 344.9.5.3.
Error Display Error Priority 354.9.6. Date and Time Settings 364.9.7. Illumination Settings 374.9.8. Reset System Parameters to Factory Settings 384.10. Probe Settings 394.10.1. Probe Selection 394.10.1.1.
Settings for Probe 1 404.10.2. Alarm Thresholds 414.10.3. Alarm Assignment 424.10.3.1.
Alarm Assignment Total Alarm Settings 434.10.4. Averaging 444.10.4.1.
Statistical Error 444.10.5. Probe Lifetime 474.11. Stored Alarms 484.12. Security Settings 504.13. Traff. Light Relay Check: 514.13.1.1.
Traff. Light / Relay Check Total Alarm 514.13.1.2.
Test Internal Hardware 524.14. Info 535. Transmission Protocol 546. Technical Data 556.1. Technical Data ALMO 6 556.2. Technical Data Probes 566.2.1. y -Low Dose Probe with Nal-Detector 566.2.2. y-Low Dose Rate Probes 576.2.3. Low Dose Probe 18526 D 587. Connector Pin Assignment 597.1. Device View 597.2. Fuses 597.3. Connector Pin Assignment Data Transmission A 607.4. Connector Pin Assignment Data Transmission B 617.5. Connector Pin Assignment Alarm Output Channel 1 -6 627.6. Connector Pin Assignment Total Alarm Channel A and B 63Page 4Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombliithstrasse 14 a, D-01277 Dresden ATTACHMENT 1ALMO 6 Operating Manual7.7. Connector Pin Assignment Pulse Input7.8. Connector Pin Assignment Power Supply8. Maintenance 8.1. Accumulator (rechargeable batteries)
- 9. Accessory
- 10. Service/Customer Service11. EC Declaration of Conformity 64656666677273Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblilthstrasse 14 a, D-0 1277 DresdenPage 5 ATTACHMENT 1I M r- 1) 1ALMO 6 Operating Manual1. Description and Definition of ProjectStationary dose rate measuring systemThe ALMO 6 measuring system can work with up to 6 detectors e.g. Geiger-Miller or NaI-detector to determine the local dose rate.Measuring electronics and display unit are integrated in a plastic housing.
A largeLC display is incorporated into the front panel of the housing.
The values currently measured by the connected detectors are displayed on this LC display (240 x 128pixels).Two freely parameterizable alarm thresholds can be defined for each probe.Parameters are set on various menus. A visual / acoustic alarm is triggered whenever an alarm threshold is exceeded.
Optionally the device can be equipped with an emergency power supply.Depending on the connected components (LED traffic light), the ALMO 6 willcontinue to work for up to 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after power failure.Fields of application
- workplace and room monitoring, e.g. in hot cells" system monitoring, e.g. in isotope production
" ward and/or patient monitoring in nuclear medicine/radiation therapy" monitoring and selection in sorting boxes for radioactive waste" exhaust air monitoring
" monitoring of test facilities in nondestructive material testing" warehouse monitoring, e.g. collection sites for radioactive wastePage 6Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I MCD IALMO 6 Operating ManualPerformance features" lt-controller-based measurement electronics
- digital measurement value information on large-area, illuminated LCdisplay" measurement value display of dose rate in n/[t/mSv/h with autoranging function" membrane keyboard with indication of the switching status of thetraffic light relays" externally connectable detector (GM counter tube, Nal detectors) withintegrated high voltage generation and electronics
" automatic detector identification, calibration data are read out by themeasurement electronics, allowing simple replacement of the detector" detector can be set up in a distance of 100 m from measurement electronics via cable" 2 freely definable alarm thresholds per probe" easy-to-operate measurement system with user guidance" ergonomically shaped housing, desktop or wall version" 8 x 2 switch outputs, 8 x potential-free and 8 x potential-free or 24 Voltsupply (can be set via menu)* 2 (3) interfaces:
o Interface A: USB, RS-232, RS-422 or RS-485 can be selectedvia menu.o Interface B: RS-232, RS-422 or RS-485 can be selected viamenu.o Ethernet (in preparation)
" four languages can be selected:
- English, German, French and Russian" data storage of the last 100 alarms" opional accessory (see chapter 9), options:-various optical/acoustic alarm units can be connected
-emergency power supply-software for continuous dose rate measurement, incl. data storageIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltthstrasse 14 a, D-01277 DresdenPage 7 ATTACHMENT 1ALMO 6 Operating Manual2. Operation of the Alarm MonitorThe alarm monitor has a clear structure and the operating elements are clearly andlogically arranged.
8923 104 115 1267Figure 1: ALMO 6 operating components
- 1. LC display with 240x128 pixels2. LDR sensor for the backlight
- 3. Charge control light4. On/Off switch5. Indicator light: Device on / ok6. Three-stage display of the LED status per probe (channel 1 to 6)7. Blue signal LED's (e.g. indicating malfunctions)
- 8. Operating keys9. Function keys (function is displayed above the key on the display)10. Three-stage display of the LED statuses of both total alarms11. Quit button12. Battery compartment of the optionally available emergency powersupply; fusesPage 8Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblothstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1I M r- D IALMO 6 Operating Manual3. Operating ElementsLC display (1)The LC display is a graphics display with 240x128 pixels.Charge control light (3)In case of monitors with UPS, the rechargeable batteries guarantee a power supplyin case of mains breakdown.
If the batteries are charged, the control light isburning.
The batteries should be full after max. 1 day, otherwise the batteries haveto be replaced.
If the control light is blinking, the batteries are full and the chargingelectronics are switched to power maintenance.
On/Off switch (4)The On/Off switch is designed as a push-button.
Push the button (approx.
1second) to turn the device on/off.Alarm display (6 and 10)The current alarm status is indicated on this display (standard alarm assignment):
- green: no alarm threshold is exceeded.
- yellow: alarm threshold 1 is reached* red: alarm threshold 2 is reachedArrow keys (8)An alarm threshold is changed with these keys, the " keys select the digit to beset.The OU_ keys select a menu item and / or the alarm threshold to be set andincrement or decrement the digit to be set.Enter key (8 center)With this key you select menu items, store entries and change options.Function keys (9)The function of these keys is indicated on the LC display.Menu- Open the menuEnd- Exit the menu structure Back- Return to last menu item and / or return to normal modeStrore- Store changesQuit button (11)If an acoustic warning is triggered when an alarm is exceeded, the acoustic signalcan be reset (turned off) by pushing this button.If the measured value drops below the alarm threshold again, the visual alarm canbe reset by pushing this button once more (only in the quit mode).Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 DresdenPage 9 ATTACHMENT 1I M E D IALMO 6 Operating Manual3.1. Internal and External DisplaysThe device includes the following options to display its current status and toacknowledge errors:* LC display* One LED traffic light and blue LED for each probe* 2 total alarm LED traffic lights and blue LED's (total alarm A and B)* One internal loudspeaker
- One internal quit button (0)* 2 external traffic lights for each probe* 2 external total alarm traffic lights (total alarm A and B)* 2 external total alarm loudspeaker
- 2 external quit buttonsExceeded alarm thresholds will be indicated by the blue LED of the probe thattriggered the alarm which lights up permanently.
- Moreover, if configured on themenu, they can be indicated on the LC display, by the LED traffic light of theprobe that has triggered the alarm, and by the external traffic lights of the probethat has triggered the alarm.Critical probe errors (no probe, unknown probe, end of the lifetime of a GM probe)are indicated by the flashing blue LED of the probe that has triggered the alarm.Moreover, they can be configured on the menu such that they will be indicated onthe LC display and by the respective probe traffic lights.Critical device errors (hardware error and battery voltage too low) are indicated byall blue LED's flashing.
The device also includes two total alarm traffic lights in addition to probe trafficlights. Besides probe traffic lights, exceeded alarm thresholds and error states canbe passed on to these traffic lights. If several errors have occurred, the one with thehighest priority will be indicated on the total alarm traffic lights.For alarm thresholds and also for probe and device errors, the device can beconfigured such that an acoustic signal is triggered.
A 1 second tone with 1 secondbreaks will be created.Page 10 Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1[ý" -7ALMO 6 Operating Manual3.1.1. Function of the Quit ButtonThe device includes an internal quit button (U). In addition, two external quitbuttons can be connected.
These buttons have the following function:
- Push the quit button once to disable the acoustic signal for errors and alarmthresholds which were active at that time." Push the quit button once more to disable the traffic light indication of thepresently active error with the highest priority.
In this case, the next activeerror or alarm with lower priority will be indicated by the traffic lights.Exempted from this are current alarms (if a measured values exceeds analarm threshold).
In this case, the alarm is still indicated.
" Proceed as follows to turn off the alarm display:
set the maximum measuredvalues for all probes equal to the current measured values. If the currentmeasured value is above the alarm threshold, the alarm threshold alarm willbe triggered again immediately.
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltlthstrasse 14 a, D-0 1277 DresdenPage 11 M 11- 1)ATTACHMENT 1ALMO 6 Operating Manual3.2. Menu Overview3.2.1. Menu Structure The program structure of the ALMO6 as a flow graph:Menu items in red are available inthe expert mode (see 4.12) only.Menu items in green can be turnedoff.Page 12Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbllithstrasse 14 a, D-01277 Dresden ATTACHMENT 1iALMO 6 Operating ManualMenu Operation The system includes a membrane keypad with 8 keys + On button for operation ofthe ALMO6. The two E1 buttons below the LC displays are function keys. Theirfunctions are displayed above the respective button in the bottom row of thedisplay, with bright letters on a dark background.
To open the menu, push the right function key Gl (Menu). You can navigate insidethe menu using the keys !__Ui and the ENTER key "".Push the left function key E1 (Back) to return to the higher menu level. The rightfunction key E1 has two different meanings:
If one setting has been changed on themenu, the changed setting is stored permanently in the EEPROM after you havepushed the right function key (following a confirmation prompt).
If no setting hasbeen changed, you can exit the menu by pushing the right function key and returnto the probe display.To edit values (e.g. alarm thresholds, date/time) select the corresponding entry withthe " I keys and confirm with the ENTER key C. The value can be changedwith the arrow keys OU.Select the digit to be changed with the keys IL right/left.
Push the Enter key El once more to store the changed value.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltthstrasse 14 a, D-0 1277 DresdenPage 13 ATTACHMENT 1I M ED IALMO 6 Operating Manual4. Measurement ModeFive different display modes can be selected to present the measured values.4.1. 6 Probe DisplayThe information shown on the display can be reduced so much that only themeasured value is displayed.
The size of the measured value display will be adapted to the available space.maximum information minimum 1onA horizontal bar graph can be displayed instead of the alarm thresholds.
The bargraph shows the current and the maximum measured value in % relative to thesecond alarm threshold in linear or logarithmic scale.The measuring range is set automatically.
4.2. 1 Probe DisplayThe information shown on the display can also be reduced to one measured value.The size of the measured value display will also be adapted to the available space.The measured values of the other probes are displayed in the column all the way tothe right. The probes can be selected with the 1_ and LA buttons.In case of an alarm for a probe that is presently not displayed, this probe may beswitched as active probe.Page 14Issue 05/2012 E, Subject to technical modifications without noticeMED Nuldear-Medizintechnik Dresden GmbH, Domblflthstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1M r- DALMO 6 Operating Manual4.3. Display as Bar GraphThe bar graph is displayed in % relative to the second alarm threshold.
You canchoose between linear and logarithmic presentation.
The current measured valuecan be displayed as a numerical value above the graph (see screen shot below).Besides the current measured value, both alarm thresholds and the maximum valueare displayed.
The first alarm threshold is depicted by a dotted line ( .........
), thesecond alarm threshold by a dashed line (_ -_) and the maximum value by a solidline (-). The presently measured value is the upper end of the black bar.4.4. Display as Curve Graph or Planar GraphThe time base can be changed between 100s and 1000s using the two arrow keysright (a) / left (L"). The graph shows the measured values of the last 100s or1 000s in percent relative to the second alarm threshold.
The alarm thresholds itselfare depicted as a dotted and dashed line. The maximum value is displayed on theY-axis.Curve graph, time base = 1Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltithstrasse 14 a, D-0 1277 DresdenPage 15 ATTACHMENT 1ALMO 6 Operating Manual4.5. Error ListIf you push the Enter key (C) in the measurement mode, a list of the current errorsis displayed for all 6 probes.The symbols have the following meaning:* i]: active error0 : active error which triggers an acoustic alarm (internal or external)
- El: no active errorPage 16Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltlthstrasse 14 a, D-01277 Dresden ATTACHMENT 1[-!! ý11) ýALMO 6 Operating Manual4.6. Alarm Triggering When the defined alarm threshold is exceeded, the alarm indication and, depending on the setting, the acoustic warning are turned on.In the quit mode, themaximum value is indicated on the display.
It will beindicated until it is reset bypushing the Obutton.The status of theconnected trafficlights is indicated in the LED field.In our example,the second alarmthreshold of probe5 has beenexceeded.
Therefore, trafficlight 5 is switchedto red. In addition, the traffic light ofthe total alarm Bwill also switch tored. The blueLED on channel 5is flashing, which indicates that the quit mode is turned on and an alarm has beentriggered.
The maximum value of the previous alarm was 154 ptSv/h.How traffic light colors are assigned to alarms is described in chapter 4.10.3.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltlthstrasse 14 a, D-01277 DresdenPage 17 ATTACHMENT 1ALMO 6 Operating Manual4.7. Measuring Range OverflowIf the measuring range is exceeded, the display looks as follows:Since the present as well as the maximum measured value are outside themeasuring range of the probe, the message ,,Ofl" (,,overflow")
is displayed insteadof the value. Moreover, this status is indicated through the traffic lights, blue LEDon the device and internal and external acoustic
- signals, as defied on the menuSystem parameters
--> Error display --> Measuring range exceeding.
Page 18Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblfithstrasse 14 a, D-01277 Dresden ATTACHMENT 1I Ffi 1: D IALMO 6 Operating Manual4.8. Code EntryTo avoid that unauthorized persons can change any settings on the device (e.g.change or turn off the alarm thresholds),
access to the menu level can be protected by a code entry.* With the L. and Ia buttons, select the digit to be set. The digit to be set willbe displayed inverted.
- With the 0__ and LAi buttons, increment or decrement the digit to be set.* Push the Enter C key or the right function key to go to the menu level. Withthe right function key 0l (back) you get back to the probe display.The function of the arrow keys is the same throughout the entire menu level.CODE 0000 has been set by the manufacturer.
We recommend that you change this value after you have taken the device intooperation.
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 DresdenPage 19 ATTACHMENT 1ALMO 6 Operating Manual4.9. Main MenuOn this level, the following items can be selected using the Fl2u buttons:* Language, etc: Setting the menu language" System parameters:
Setting the system parameters.
Reset of the device andprobe parameters
" Probe settings:
Setting of the alarm thresholds, assignment of the trafficlight colors to the exceeded alarm thresholds, setting of the averaging procedure, setting of the probe life-time (only for GM probes)* Stored alarms: View and delete stored alarms* Security settings:
Enter new menu code, exit the menu automatically, simplified menus, turning the device off* Traff. light relay check: Checking the internal LED and the external trafficlights and loudspeakers and the external quit button* Info: Information about hard- and software and the manufacturer Page 20Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblflthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M I! DALMO 6 Operating Manual4.9.1. LanguageOn this menu you can select the menu language and the language of the othermessages.
Presently, four languages can be selected:
- English, German, French and Russian.Further languages will follow or can be implemented on request.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltlthstrasse 14 a, D-0 1277 Dresden_ Page 21 ATTACHMENT 1I f/I K 1) 1ALMO 6 Operating Manual4.9.2. System Parameters This menu has a different look, depending on whether Expert mode has beenenabled on the ,,Security settings" (see 4.12) menu or not. The Expert modeincludes two additional items: ,,Data transmission" and ,,Error display".
Expert mode Simple menu" Display:
Settings for various display options" Total alarm settings:
Hardware parameters for total alarm traffic lights,external loudspeaker and external quit buttons" Data transmission:
Settings for printer and data transmission (only in theExpert mode)" Error display:
Assignment of acoustic and visual alarms for various errorcases. Setting of error priorities (only in the Expert mode)* Date / Time: Setting of date, time and daylight saving time and standardtime* Illumination:
LCD background illumination
" LED lights: Brightness of the LED lights on the device* Internal acoustics:
Volume of internal loudspeaker
" LED traffic light check after turn on: Enabling and disabling the turn oncheck of the device-internal LED lights" Relay check after turn on: Enabling and disabling the turn on check of thedevice-external LED lights" Reset system parameters:
Reset the system parameters to factory-set values" Reset probe parameters:
Reset the probe parameters to factory-set valuesPage 22Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblilthstrasse 14 a, D-01277 Dresden ATTACHMENT 1[!!D 71ALMO 6 Operating Manual4.9.2.1.
DisplayOn this menu you can set the display mode and whether you can change thedisplay with the left function key. Moreover, from this menu you go to thesubmenus in which you can set the parameters for different display modes.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-01277 DresdenPage 23 ATTACHMENT 1ALMO 6 Operating Manual4.9.2.1.1.
Settings for 1-Probe DisplayOn this menu you can set the parameters for the 1-probe display, as shown on thescreenshots in chapter 4.2.* The checkbox
,,Alarm thresholds" turns the presentation of the alarmthresholds on the display on and off." If the alarm thresholds are turned on, click on the radio button ,,current" and,,or both" to select if only the currently exceeded alarm threshold or bothalarm thresholds are to be displayed.
If the checkbox
,,Alarm thresholds" isnot ticked, this setting will be ignored.* Tick the ,,Bargraph" checkbox to turn the bar graph on and off.* With the 4 following radio buttons you can choose if the bar graph showsthe current value, the maximum value and the alarm thresholds as absolutevalues or as %-values relative to the second alarm threshold.
- Moreover, youcan choose between logarithmic and linear scale division.
- The checkbox
,,Max. value in quit mode" turns the display of the maximummeasured value on and off, provided the quit mode for this probe has beenenabled (see chapter 4.10.3).* If the checkbox
,,forwards in case of threshold exceeding" is ticked, theprobe whose alarm threshold has been exceeded last will be put forward.Page 24Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1I M 1: 0 1ALMO 6 Operating Manual4.9.2.1.2.
Settings for 6-Probe DisplayThe 6-probe display is shown on the screenshots in chapter 4.1. All 6 probes aredisplayed at once. This display is configured by the settings on the menu:System parameters--Display->Settings for 6-probe display:* The ,,Display alarm thresholds or bargraph" checkbox turns the display ofthe alarm thresholds or the bar graph for each probe on and off." If the ,,Display alarm thresholds or bargraph" checkbox is ticked, you canselect with the radio buttons ifo only the currently exceeded alarm threshold is to be displayed o both alarm thresholds are to be displayed o a bar graph with linear scaling is to be displayed o a bar graph with logarithmic scaling is to be displayed If the ,,Display alarm thresholds or bargraph" checkbox is not ticked, thissetting will be ignored." The checkbox
,,Max. value in quit mode" turns the display of the maximummeasured value on and off, provided the quit mode for this probe has beenenabled (see chapter 4.10.3).Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblllthstrasse 14 a, D-01277 DresdenPage 25 ATTACHMENT 1I M ir 1)ALMO 6 Operating Manual4.9.2.1.3.Bargraph SettingsAn example for a bar graph display is shown on the screenshot in chapter 4.3. Withthis type of display, both alarm thresholds and also the current and maximummeasured value of all 6 probes are displayed as bar graph. This display isconfigured by the settings on the menu:System parameters--Display--*Bargraph settings:
- With the first two radio buttons you can either select linear or logarithmic scaling of the Y-axis" Tick the ,,Display meas. value" checkbox to turn the display of the currentmeasured value above the graph on and off* The checkbox
,,Max. value in quit mode" turns the display of the maximummeasured value on and off, provided the quit mode for this probe has beenenabled (see chapter 4.10.3).Page 26Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblilthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I FA U D IALMO 6 Operating Manual4.9.2.1.4.Display Settings for Curve / Planar GraphExamples for curve and planar graph display are shown on the screenshot inchapter 4.4. In this display mode, a curve or planar graph diagram is displayed below the current measured value; both alarm thresholds and the max. measuredvalue are also displayed.
This display is configured by the settings on the menuSystem parameters-->Display---
Settings for curve/planar graph:" The values in the diagram can either be displayed as absolute values or in %of the second alarm threshold.
This is configured by ticking the radiobuttons ,,Display in % of 2nd threshold" and ,,Display as meas. value"" Either the measured values of the last 1 00s or the measured values of the last1000s can be displayed in the diagram.
Since 100 values are alwaysdisplayed in the diagram, with the setting ,,1000s" each measured value inthe diagram corresponds to an average measured value of 10s. This appliesonly to the diagram.
The measured value above the diagram is still updatedevery second." If the ,,Switch time basis via keys" checkbox is ticked, you can switchbetween both time bases 100s and 1000s by pushing the keys L and I9 inthe diagram presentation.
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblfthstrasse 14 a, D-01277 DresdenPage 27 ATTACHMENT 1ALMO 6 Operating Manual4.9.3. Total Alarm SettingsThe device includes two total alarms: Total alarm A and B. In addition to the LEDtraffic light on the housing, each of these total alarms can be indicated by anexternal traffic light and by an external loudspeaker.
- Moreover, one external quitbutton each can be connected.
The total alarm hardware is configured on this menu" The external traffic light can either be supplied with 24V directly by thedevice or it may have its own power supply. This can be configured with theradio buttons ,,Traffic light: Output: 24V" and ,,pot.free"
" The polarity of the external quit button is configured with the radio buttons,,Low-active" and ,,High-active"
" With the radio buttons ,,Quit via: internal",
,,external" and ,,both" you canconfigure if the external quit button is equivalent to the internal one (setting,,both"),
or if one of them is disabled" The external loudspeaker, just like the external traffic light, can be suppliedwith power by the device or it can have its own power supply.Caution:
Before the 24 Volt are switched to the traffic light or to theadditional relay and the acoustics, you have to check if the connected components are designed for these voltages.
If the relays are switched potential-free, max. 24 Volt 1 Ampere may beswitched per relay.In case of a 24 Volt supply of the components by the device, the totalpower consumption must not exceed 500mA.If this is disregarded, the device or the connected components may bedestroyed.
Page 28Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbiithstrasse 14 a, D-01277 Dresden ATTACHMENT 1ALMO 6 Operating Manual4.9.4. Data Transmission The device includes 2 interfaces which can be configured as RS-232, RS-422 andRS-485 interface.
- Moreover, interface A can also be configured as USB interface.
Interface A can only be used for data transmission, but a printer (seetings see4.9.4.2) may be connected to interface B.For every interface, the settings regarding baut rate, data bits etc. can be configured in a submenu.With the setting ,,Address for RS-485" the device can be assigned to an address, sothat several devices can be connected to one PC interface and can be queried by thePC software.
The settings for data transmission regarding send mode and layout are made in asubmenu (see 4.9.4.3).
4.9.4.1.
Interface SettingsSince the possible configurations for interface A and B are the same, only thesubmenu for interface A is described here.You can set the baut rate, the number of data bits, parity and number of stop bits.Make sure that the settings of the communication partner are the sameIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblolthstrasse 14 a, D-0 1277 DresdenPage 29 ATTACHMENT 1ALMO 6 Operating Manual4.9.4.2.
Printer SettingsBesides the option to transfer current measured data to the PC, the device can alsosend information on alarm threshold exceeding through interface B to a printer.Any time an alarm threshold is exceeded, a row containing the following information is printed out:" Start time of the alarm" End time of the alarm" Probe number (I to 6)" Probe type" Max. measured valueAn alarm printout of probe 3 may look as follows:13.05.08 09:50--13.05.08 09:54 3 18550 CE Max:303 pSv/hThe following parameters can be configured on the menu:" Headline with printout:
This row is printed at the top of a page. Its contentscan be changed.
To do this, select it with the [iJ key, move the cursor withthe L and [9 keys to the character you want to edit and push the !n and Ulkeys to select a new character.
" Lines per page: Number of alarm printouts after which a new page will bestarted, not counting the headline.
" New page: This function sends a signal to the printer to start a new page andsets the current line number to 0.The current line number cannot be changed; it is displayed only for the user'sinformation.
Page 30Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I 1A r- 1) 1ALMO 6 Operating Manual4.9.4.3.
Data Transfer SettingsSend Mode 0Volatile setting.
Device sends until nextPowerdown Permanent Setting.
Device will send after rnextpowerupMessage Format:short 0 (only current value)long 01 1111 12 If 'Send Mode' is activated, the data are transmitted till the unit is turned off,provided that data transmission (see 4.9.4.3) is activated.
If the unit is turned onagain, the send mode is not active anymore.
Changes cannot be stored when usingthe 'Send Mode'.If 'Continuous Send Mode' is activated (necessary to store), the data are transmitted also after turning the instrument off and on again.You can define if the transmission format has to be long and all values (see chapter5) have to be transmitted.
If you select the short transmission format, only themeasuring value is transmitted.
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblfithstrasse 14 a, D-01277 DresdenPage 31 ATTACHMENT 1ALMO 6 Operating Manual4.9.5. Error DisplayThe device recognizes the following error states:* ,,No probe": if no probe has been detected at a probe input* ,,Probe error": if a probe is connected to a probe input, but the probe type isnot identified correctly, or if one of the probes did not receive any counts fora long time* ,,Measuring range exceeding":
if the measuring range of a probe has beenexceeded* ,,Lifetime end": if the total number of counts 5-1010 received by a GM probehas been exceeded" ,,System error": if a hardware error of the device has been detected* ,,Undervoltage":
if the battery voltage has dropped below 1 VOn this menu you can define how individual error states will be indicated.
- Moreover, you can define the priority of the error displays on the ,,Error priorities" menu.Since the submenus for the error states ,,No probe", ,,Probe error", ,,Measuring range exceeding" and ,,Lifetime end" and the submenus
,,System error" and,,Undervoltage" look the same, we will only describe the submenus
,,No probe"and ,,System error" on the following pages.Page 32Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbldthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M r- 1) 1ALMO 6 Operating Manual4.9.5.1.
Error Display ,,No Probe"The device includes the following options to display an error:* Message on the LC display* Acoustic signal through an internal loudspeaker
- Indication through the built-in LED light or the external traffic light 1* Indication through the external traffic light 2* Indication through the external total alarm traffic light A and B* Acoustic signal through an external loudspeaker A and BThe first four display options are configured on the menu ,,no probe":" With the checkbox
,,Message on LCD" you can choose if a message is to bedisplayed on the LC display or not if an error occurs* With the checkbox
,,Int. acoustics" you can enable or disable the signaling of errors through the internal loudspeaker
" With the radio buttons you can select in which color the error is to bedisplayed by the traffic lights of the probe causing the errorIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltthstrasse 14 a, D-01277 DresdenPage 33 ATTACHMENT 1I M r- 1) 1ALMO 6 Operating Manual4.9.5.1.1.Error Display ,,No Probe"--Total Alarm SettingsIn addition to the probe traffic lights, an error message can also be indicated through the total alarm traffic lights A and B. The color of the lights is defined onthis menu. Moreover, with the checkboxes you can define if the error shouldtrigger an acoustic alarm or not.Since several errors may be indicated by the total alarm traffic lights (e.g. probe 1:no probe, probe 2: alarm threshold exceeding, probe 3: lifetime end), the errors atthe total alarm traffic lights are indicated according to the settings on the menuError display--Error priorities.
4.9.5.2.
Error Display System ErrorThe display of a hardware error can be configured on this menu. You can definethe colors of the probe traffic lights 1 and 2 and of both total alarm traffic lights.Moreover, acoustic signaling through the internal and external loudspeakers can beenabled or disabled via the checkboxes.
Page 34Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblflthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M r 1) 1ALMO 6 Operating Manual4.9.5.3.
Error Display Error PriorityThe error priorities are defined on this menu. At the top, you see the error with thelowest priority, at the bottom, the one with the highest priority.
To change thepriority, select an error with the " key and move it up or down in the error listwith the !__ and LA keys.If several errors occur in one probe channel (e.g. lifetime end, alarm threshold 2exceeded and measuring range exceeded),
the probe traffic lights show only theerror with the highest priority.
Push the 0 key once to turn off the alarm tone andpush it once more to display low priority errors. This is true only if the currentmeasured value has dropped below the displayed alarm threshold.
If the currentmeasured value is still higher than the alarm threshold, only the acoustic display ofthe alarm threshold exceeding can be turned off, but not the traffic light indication.
Issue 05/2013 E, Subject to technical modifications without notice Page 35MED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1ALMO 6 Operating Manual4.9.6. Date and Time SettingsYou can set the current date and time on this menu. Moreover, you can turn theautomatic change over to daylight saving time on or off. During daylight savingtime, one hour is added to the current time. The automatic setting of daylightsaving time and standard time takes place on 2 a.m. of the last Sunday in March.The automatic setting back to standard time takes place on 2 a.m. of the lastSunday in October.Page 36Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltithstrasse 14 a, D-01277 Dresden ATTACHMENT 1I MrD IALMO 6 Operating Manual4.9.7. Illumination SettingsOn this menu you can configure the background illumination of the LC display.
Ifthe checkbox
,,Lllumination off at emergency power" is ticked, the LCDbackground illumination is turned off if the device power is not supplied by thepower supply system, but by the built-in battery.The illumination can either be turned on or off permanently (radio buttons,,Illumination always on" and ,,Illumination always off") or it can be configured such that it will be turned on or off only if a certain brightness level has beenexceeded.
This threshold can be set in the range from 0 to 15 in the input field,,Illumination-on-threshold".
Once you have selected the input field with the _.key, you can set the new value with the C: and I[ keys. Push the " key oncemore to accept the new value.The currently set brightness is displayed as "LDR-Value".
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombluithstrasse 14 a, D-01277 DresdenPage 37 ATTACHMENT 1ALMO 6 Operating Manual4.9.8. Reset System Parameters to Factory SettingsWith the menu items ,,Reset system parameters" and ,,Reset probe parameters" youcan reset all parameters to factory-set values, with the exception of the parameters if external traffic lights and loudspeakers are to be operated with 24V or if they arepotential-free.
After selection of one of these two menu items with the Enter key, aconfirmation prompt will be displayed, as shown on the screenshot.
With the leftsoftkey you can close the confirmation prompt dialog again without resetting theparameters.
With the right softkey you can reset the respective parameters andstore them to the EEPROM.Page 38Issue 05/2012 E, Subject to technical modifications without noticeMED Nuldear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 Dresden ATTACHMENT 1I ?A U DALMO 6 Operating Manual4.10. Probe Settings4.10.1.Probe Selection To change the parameters of an individual probe, you have to select this probe onthe ,,Probe settings" menu. Besides the probe type, the remaining lifetime for theGM-probes is displayed on this menu.Since the menus for all probes are identical, we will describe them using probe 1 asan example.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltithstrasse 14 a, D-01277 DresdenPage 39 ATTACHMENT 1I M E 1) 1ALMO 6 Operating Manual4.10.1.1.
Settings for Probe 1xpe mo emenu imp emenumenue menuOn this menu you can set the display options for probe 1. The checkbox
,,Display headline" determines if a probe headline is displayed in the measured valuedisplays (except bar graph). If display headline is enabled, two options can beselected:
- display the probe type as headline or* display freely selectable textThis selection is made with the radio buttons ,,Free text" and ,,Probe type". If youhave selected free text as headline, the contents of the headline is taken from theinput field ,,Free text.With the radio buttons ,,Unit: cps" and ,,Acc. to probe type" you choose in whichunit the value is to be displayed.
You can select the units Sv/h and cps (count persecond) for the Graetz probes 18550CE,
- 18509CE, 18545CE, 18529CE and for theNal probes lx 1 in and 1.5x2in.
For all other probes, this parameter is ignored andthe measured value is displayed in cps.With the checkbox
,,Store alarms" you can enable the storage of the alarms in theEEPROM for this probe. The alarms can later be viewed under the menu item,,Stored alarms" and deleted, if necessary (see chapter 4.11).Select the menu items ,,Alarm thresholds",
,,Alarm assignment",
,,Average determination" and ,,Lifetime" to open submenus in which further probeparameters can be set. The submenu ,,Alarm assignment" is available in the Expertmode only.Page 40Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombliathstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M 1: 1) 1ALMO 6 Operating Manual4.10.2.Alarm Thresholds On this submenu you can set the alarm thresholds in Sv/h and counts/sec.
Depending on the unit you have chosen for the probe on the previous menu, thealarm threshold pair will be used with the respective unit. The other pair will beignored.The first alarm threshold must always be lower than the second alarm threshold.
Ifthis is not the case, both alarm thresholds will be exchanged when you try to storethem (you will be alerted by a corresponding message).
- Moreover, both alarmthresholds must lie within the measuring range of the probe. If you enter an alarmthreshold which lies outside the measuring range of the probe, it will not becorrected.
On the measured value display, this alarm threshold will be displayed as,,Ofl". Nevertheless, exceeding of this alarm threshold will be checked and, ifnecessary, an alarm is triggered (at the same time with the error ,,Measuring rangeexceeding").
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 DresdenPage 41 ATTACHMENT 1ALMO 6 Operating Manual4.10.3. Alarm Assignment On this menu you can set the following parameters:
" Assign the colors of the external probe traffic light 1 and 2 to the individual alarm states (no alarm, alarm threshold 1 exceeded, alarm threshold 2exceeded)
" Specify if the external probe traffic light 1 is supplied with 24V by thedevice (radio button ,,Traff.
light 1: 24V") or if it has its own power supply(radio button ,,Potential free")" Turn the quit mode on and off (checkbox
,,Quit mode"). If quit mode isenabled, the decision whether an alarm threshold has been exceeded is notbased on the current measured value, but on the maximum measured value.If a quit button (external or internal (0), depending on the setting on themenu ,,System parameters--Total alarm settings")
is pushed several times,the maximum measured value is reset to the current measured value" If the checkbox
,,also for traffic.
light" is ticked, the determination of thetraffic light color is also not based on the current, but on the maximummeasured value.1&ýCaution:
Before the 24 Volt are switched to the traffic light or to the additional relay and the acoustics, you have to check if the connected components aredesigned for these voltages.
If the relays are switched potential-free, max. 24 Volt 1 Ampere may be switchedper relay.In case of a 24 Volt supply of the components by the device, the total powerconsumption must not exceed 1500mA.If this is disregarded, the device or the connected consumers may bedestroyed.
Page 42Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M r D IALMO 6 Operating Manual4.10.3.1.
Alarm Assignment Total Alarm SettingsBesides the assignment of the colors of the probe traffic light 1 and 2 to the alarmstates, the colors of the external total alarm traffic lights A and B can be assignedto the alarm states on the menu ,,Total alarm settings probe 1". Instead of the colorgreen, you have the option not to indicate the alarm status (radio buttons ,,noalarm").
Thus, one can switch the alarms of probes 1-3 to total alarm traffic light Aand the alarms of probes 4-6 to total alarm traffic light B.Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltithstrasse 14 a, D-0 1277 DresdenPage 43 ATTACHMENT 1ALMO 6 Operating Manual4.10.4.Averaging 4.10.4.1.
Statistical ErrorNuclear decays, i.e. transformation of nuclei are natural, randomly distributed events. If one examines e.g. a radiation source using a detector and measures thenumber of registered events periodically over a fixed measuring time, then one willsee that an accumulation occurs in a certain area. From the size of the area of thisaverage value one can easily infer the intensity of the source. Its true intensity,
- however, remains unknown, since one cannot choose an infinitely long period ofobservation.
The average value becomes an exact value only if the period ofobservation is infinite.
When interpreting the measured values one only has toindicate the range in which the exact intensity is expected!
The mathematical relationship between random events is described by theprobability
- calculus, where the natural distribution, e.g. in case of nuclear decay, isexpressed by a so-called Gaussian distribution.
This can be presented in a simplified manner:It is more probable to obtain measured values which come close to the exactquantity than measured values that are subject to significant deviations.
It is equally probable that measured values smaller or larger than the exact valuewill be obtained (symmetrical distribution).
Example:A radioactive source of known intensity emits on average 100 particles per secondwhich are registered by a detector in 1-second cycles.The statistical variability for +I- 1 a (Sigma) is:= +1- 10 countsIf a large number of measuring cycles are evaluated, the following relationship becomes apparent:
Number of Measured values Standard deviation cycles in % from to (+I- 1 a) %27 90 110 145 80 120 273 70 130 3997 60 140 4999943 50 150 5Table 1Page 44Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbhlthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M F 1) 1ALMO 6 Operating ManualThis shows that it may be improbable but by no means impossible to find ameasured value smaller than 50 or larger than 150; however, this probability isonly approx. 1 to 1 700 000.The purpose of this short mathematical excursion is to further the understanding ofthe function of the ring buffer.The procedure for averaging is selected on the menu ,,Average determination".
Thefollowing options are available:
dynamic averaging and averaging by means of thering buffers.
The ring buffer size can be set in the range from 1 to 99 values.The ring buffer size can be changed only if a probe is connected and correctly recognized.
Dynamic:
The ring buffer quantity is automatically calculated and set by means ofthe count rates. A dynamic smoothing procedure is applied= Yotd * (Smoothing factor -1) + Count rateSmoothing factorThe smoothing factor is calculated using the formula:Smoothing factor = 100- ZCount rate + 1Limits: For count rates higher than 10000 the smoothing factor is 1; for low countrates (background) approx. 100. The advantage of this is that in case of sufficiently long measuring time the standard deviation is always < 1%.Ring buffer: The counts are collected in a ring buffer. The values are added anddivided by the quantity.
If the ring buffer is full, the oldest values are overwritten (first in first out). The number of memory slots can be defined from 2 -99 memoryIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-01277 DresdenPage 45 ATTACHMENT 1ALMO 6 Operating Manualslots. In case of count rates > 400 cps the system works with a fixed defined ringbuffer of 2.Ring buffer size: For the result display, an average is calculated from the numberof values. The number of memory slots is defimed in this menu item. A smallervalue e.g. < 10 results in a higher variability of the reading but small changes aredetected faster. A larger value causes a very stable reading, but small changesrequire a very long time and may possibly not be detected.
A general recommendation for setting cannot be given, since the setting stronglydepends on your field of application.
Page 46Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombl-ithstrasse 14 a, D-01277 Dresden ATTACHMENT 1I MEDALMO 6 Operating Manual4.10.5. Probe LifetimeTheoretically, the lifetime of the Graetz probes 18550CE, 18509CE and 18529CEis limited to 5-1010 counts. The device stores the number of counts received, so thatthe elapsed and the remaining lifetime can be calculated.
If one of the above mentioned probes is connected to the device and if it is of thesame type as the probe that was last connected to this probe port, then the promptappears on the display to enter the lifetime and the serial number for this probe.If one of the above mentioned probes is connected and it is of another type than theprobe connected last, you will be prompted on the display to enter the serialnumber for this probe. The lifetime is reset to 100%.The menu ,,Probe settings--Probe 1--Lifetime" provides information on thelifetime of the probe that is currently connected to probe port 1.The six-digit serial number of the probe has to be entered by the user. It identifies the probe and does not have any influence on the calculation.
If the probe isseparated from the device, the serial number is again reset to 000000.The elapsed lifetime can be entered in percent of the total lifetime in the,,Consumed:"
text field. The remaining lifetime is calculated from this value, andfrom the average count rate the expected lifetime of the probe in days is calculated and displayed.
Both values cannot by changed by the user.Besides the manual entry of 0% in the ,,Consumed:"
text field, the remaining lifetime can be reset to 100% using the menu item ,,Reset lifetime to 100%". Inthis case, the number of counts received will be deleted, so that any prediction as tothe lifetime is not possible.
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmnbH, Dornbltithstrasse 14 a, D-01277 DresdenPage 47 ATTACHMENT 1I M 1: 1) 1ALMO 6 Operating Manual4.11. Stored AlarmsOn the ,,Stored alarms" menu you can display and delete the stored alarm threshold exceeding of those probes for which storage of the alarms has been enabled (seechapter 4.10.1.1).
To view the alarms, select in the left column either the menuitem ,,all" to view all stored alarms or one of the probes to view only the alarmsthat have been triggered by this probe. Select an entry in the right column to deletestored alarms.If the checkbox
,,Confirm whilst deleting" is ticked, a confirmation prompt will bedisplayed before the alarm is actually deleted from the EEPROM.Page 48Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbllthstrasse 14 a, D-0 1277 Dresden ATTACHMENT 1I III r- D IALMO 6 Operating ManualBoth menus to delete and view stored alarms differ only in a few aspects:
theDelete menu contains as first entry ,,Delete all entries".
- Moreover, on the Deletemenu the J key and the right f1 key of the function
,,Delete entry" are occupied.
Ifyou push these keys, the selected entry will be deleted, after confirming aconfirmation prom t. To rule out that an entry can be deleted inadvertently bypushing the right U key twice, you have to push the left [1 key to confirm thedeletion.
The menu includes the following information:
- Total number of displayed alarms (in Figure 27)* Index of the presently selected alarms (in Figure 2)* Index of the probe which has triggered the alarm (with the selected entry 1)* Start and end time of the alarm, exceeded alarm threshold, max. measuredvalueIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, DornblUthstrasse 14 a, D-0 1277 DresdenPage 49 ATTACHMENT 1I M r- 1) 1ALMO 6 Operating Manual4.12. Security SettingsOn this menu you can configure settings to protect the device against unauthorized access. The following options are available:
" Protect menu access by a four-digit access code (checkbox
,,Access via codenumber" and input field ,,Access code")" Exit the menu after a certain time. If the checkbox
,,Automatic menuescape" is ticked, the menu is closed after a certain time of user inactivity.
The time can be set in the input field ,,Automatic menu escape after". Thisfunction helps to protect the menu if an authorized user has forgotten to quitthis menu manually.
" If changes you have made on the menu have not yet been stored, aconfirmation prompt is displayed when you quit the menu manually, provided the checkbox
,,Confirm menu escape" is ticked." If the checkbox
,,Expert mode" is not ticked, some menu items are hidden.The hidden settings are still valid, but they cannot be changed.* If the checkbox
,,Turn off via menu only" is ticked, the ,,Off" button on thedevice is blocked.
In this case, you can turn off the device only by means ofthe next menu item.Page 50Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltithstrasse 14 a, D-01277 Dresden ATTACHMENT 1I 1A r- D 71ALMO 6 Operating Manual4.13. Traff. Light Relay Check:This menu includes functions for testing internal and external traffic lights. Thetwo last menu entries include submenus which are used to test the other hardwareof the device.All tests can be quit by pushing the 0 key.4.13.1.1.
Traff. Light / Relay Check Total AlarmWith the functions of this submenu you can test the external total alarm trafficlights A and B, both external loudspeakers and both external quit buttons.
Thecheckboxes cannot be selected by the user. They indicate the status of the externalquit button (pushed or not)Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblflthstrasse 14 a, D-0 1277 DresdenPage 51 ATTACHMENT 1I M 1: 1) 1ALMO 6 Operating Manual4.13.1.2.
Test Internal HardwareOn this menu you can test both internal loudspeakers, the LC display and the LDRsensor on the membrane keypad.If you activate the LCD test, the presentation on the display changes in 1-secondintervals from normal to inverted, so that you can check if all pixels on the displayfunction correctly.
,,Current LDR-Value" shows the value currently measured by the LDR sensor. Ifyou cover the LDR sensor by a dark object, this value goes towards 0Page 52Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornbltlthstrasse 14 a, D-01277 Dresden ATTACHMENT 11 1`4 r- 1) 1ALMO 6 Operating Manual4.14. InfoIf you select ,,Info" on the main menu, the same screen appears as at the start of thedevice. If shows the following information:
- Hardware version* Software version* Date of first use* Date of last software update (last service)* Logo and contact information of the manufacturer Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 DresdenPage 53 I M 1` 1) 1ATTACHMENT 1ALMO 6 Operating Manual5. Transmission ProtocolInterface:
RS232Protocol:
ASCII format; 9600 baud, 8 data bit, I stop bit, no parityIn the menu 'System parametersIData transmissionlData transmission setting' (see 4.9.4.3) youcan define if the long or short (only measuring value) data record has to be transmitted.
The data record is compatible to the ALMO-6. The data record consists of 6 parts. Each partcontains the data for one probe. Each sub record is terminated by a semicolon Data record (longz)The length of each partial data record is maximal 57 byte (incl. semicolon).
Each sub record consists of the following elements:
- Probe identification e.g.: isi 1: probe channel, S: fixed letter, 1: probe type (l=Graetz 18550)or L3off, if no probe is connected.
In this case, the sub record is finished" Current measuring valuee.g.: 1, 5L.usv/h equals 1,51 gSv/h" Alarm threshold parameter 1e.g.: wSTlO0,0 lSv/h.off.
o wsI: alarm threshold 1,o 10, 0_usv/h alarm threshold value equals 10.OtSv/h, o off: alarm threshold is currently not exceeded.
(on: alarm threshold exceeded)
- Alarm threshold parameter 2e.g.: wsIIl, 00_msv/h.off.
Same meaning as for alarm threshold 1.Each data record is terminated by the ASCII characters Carriage Return (OxOD) and Line Feed(OxOA).Example Data record (long):1SI.1, 51_usv/h wsI 10 00_usv/h-off-wsIIl1,00_msv/hKoff; 2_off; 3_off; 4_.off; 5.off; 6_off; F40D<CR><L F>Data record (short)The length of each partial data record is maximal 16byte (incl. semicolon).
Each sub record consists of the following elements:
- Probe identification e.g.: 1s5 1: probe channel, S: fixed letter, 1: probe type (l=Graetz 18 550)" Current measuring valuee.g.: 1,29_usv/h equals 1,29piSv/h Each data record is terminated by the ASCII characters CR and LF.Example Data record (short):1sl.1, 29_usv/h
- 2_off; 3_off;4_off; Soff; 6_off; 76AO<CR><LF>
If the measuring range is exceeded, the message 'ofl' appears instead of a measuring value.1Sl.ofl ;2_off; 3_.off;4_off; Soff; 6_off; 9D7E<CR><LF>
In case of an extraordinary error, the message 'Err' appears:1SlErr ; 2_off; 3_off;4_off;
_off;6_off; 7EDC<CR><LF>
In these examples, only one probe is connected to channel 1. Channel 2 to 6 are not connected toa probe.Page 54Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dombltlthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I M r_ 1) 1ALMO 6 Operating Manual6. Technical Data6.1. Technical Data ALMO 6Device type:Stationary alarm device for connection of up to 6 detectors Type :ALMO 6Company:MED Nuklear-Medizintechnik Dresden GmbHDornbltithstrasse 14 a01277 Dresden, GermanyDimensions:
Depth:Width:Height:280 mm300 mm120 mmWeight:approx. 2.2 kg (with emergency power supply 2.7 kg)Mains adapter / charger 24V=; Mains voltage 100-230Volt-Operating voltage:Power consumption:
max. 60 VA, depending on alarm triggering Display:LC displayDisplay illumination:
CCFL background illumination Keyboard:
Membrane keypadAlarm thresholds:
Setting range:2 for each probe, freely definable Dependent on probe. Example probe 18550 CE:0.1 -999.9 gtSv/h 0.1 gtSv/h steps0.01 -19.99 mSv/h in 10 ptSv/h stepsAlarm:Visual and acoustic, automatic resetReset of alarm(quit mode)Relays:Switching capacity:
max. 24 V, 1 Ampere per channelCurrent for traffic light, acoustic and additional elementsIf not switched potential-free:
24 V, total current of all6 channels max. 1500 mAA: switchable:
USB, RS-232, RS-422 or RS-485B: switchable:
RS-232, RS-422 or RS-485Serial interfaces:
Issue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 DresdenPage 55 ATTACHMENT 1I M 1* 1) 1ALMO 6 Operating Manual6.2. Technical Data Probes6.2.1. y -Low Dose Probe with Nal-Detector Type of radiation:
Calibration:
Unit of measurement:
Nominal working range of thePhoton energy:Preferred direction:
Detector:
Position of detector:
Nal 25B38for Gamma measurement (DC installations) with Gamma radiation, Cs 137photon equivalent dose rate25 keV-1.3 MeVAxial radiation onto the probe bodyNaI(TI) crystalThe detector is positioned axially in the center of the probe.Nal 38B38 Nal 76B76ActiverangeNominal working range of therelative humidity:
Nominal working range foroutside air pressure:
Nominal working rangeof the temperature:
Housing:Active Activerange range0 -95 %, no influence.
100-1300 hPa, influence negligible.
Operation:
-20 'C to + 50 ICStorage:
-25 'C to + 60 'CAt < 100 C/hAluminum sleeve, black anodized, protection class IP 55Type NaI 25B38 Na1 38B38 Na1 76B76Dimensions of 38 x 25 mm 0 38 x 38 mm 0 76x76mm 0DetectorDimensions
/ length 145 mm, length 190 mm, length 285 mm,Weight 0 32 mm, 0 45 mm, 0 85/59/68 ram,1210g 370 g 1940 gPage 56Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Domblilthstrasse 14 a, D-01277 Dresden ATTACHMENT 1I ?A E D IALMO 6 Operating Manual6.2.2. y-Low Dose Rate ProbesType of radiation:
for Gamma and X-ray measurement of(DC installations)
Calibration:
Unit of measurement:
Preferred direction:
Position of detectorin device:Position of detectorin device:with Gamma radiation, Cs 137photon equivalent dose rateradial radiation onto the probe body; +/- 450The detector is positioned axially in the center of the probe.The detector is positioned axially in the center of the probe.*Nominal working range of therelative humidity:
0 -95 %, no influence, the device is dustproof and watertight according to DIN 40050 (IP 67)*Nominal working range foroutside air pressure:
100-1300 hPa, influence negligible.
- Nominal working rangeof the temperature:
Operation:
-30'C to + 60'CStorage:
-40'C to + 70'CAverage life expectancy of the counter tube: 5 xl 010 hHousing:Aluminum sleeve, bronze anodized, protection class WP 67Type Probe 18509 CE Probe 18529 CE Probe 18545 CE Probe 18550 CEworking range of the 55 keV-1.3 MeV 70 keV-3 MeV 40 keV-1.3 MeV 40 keV-1.3 MeVphoton energyMeasuring range 50 gtSv/h- 0,5 mSv/h- 150 nSv/h- 10 tSv/h -999 mSv/h 9,99 Sv/h 199,9 j+/-Sv/h 19,9 mSv/hdimensions
/ length 110 mm, length 110 mm, length 345 ram, length 110 mm,weight 040mnm, 150g 040rmm, 150g 025/40mm,380g 040mm, 150gdetectordimensions effective length: 17 mm 7 mm 244 mm 40 mmwall thickness:
80-100 mg/cm2 80-100 mg/cm2 525 mg/cm2 250 mg/cm2dimensions:
16x6,2 mm0 16x6,2 mm0 266x24 mm 0 41 x 15 mm0overload capacity
> 50 Sv/h > 50 Sv/h > 20 mSv/h > 1 Sv/h(continuous radiation)
I I _Ilife expectancy atl0 mSv/h atl0 mSv/h at100 gtSv/h atl mSv/h approx.approx. 17500h approx. 55000h approx. 92 000h 17500hIssue 05/2013 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblethstrasse 14 a, D-0 1277 DresdenPage 57 ATTACHMENT 1I M E 1)ALMO 6 Operating Manual6.2.3. Low Dose Probe 18526 DDetector:
ZP 1430, window counter tubeWindow: micaThickness:
1.5 -2 mg/cm2Effective diameter:
27.8 mmEffective area: 6.1 cmn2Covered by protection grid: 20 %
Background:
Counts in case of radialirradiation (Cs 137)approx. 25 counts / minuteapprox. 4 counts/s/tSv/h Radiation axial:Temperature range:with cap:without cap:Operation:
Storage:only y-radiation a-, 03- and y-radiation
-30'C to + 60'C-40'C to + 70'COutside air:Housing:Dimensions:
500-1300 hPa, influence cannot be determined inpractical use. Transport in planes up to a height of3000 m: Changes in air pressure have to be performed slowly.Aluminum sleeve, red anodized40 mm0 x 110mmWeight:approx. 150 gIf Geiger-Mueller probes are connected, the unit can no longer be changed toBq/m3.Page 58Issue 05/2012 E, Subject to technical modifications without noticeMED Nuklear-Medizintechnik Dresden GmbH, Dornblithstrasse 14 a, D-01277 Dresden