nrc: home page - u n iversity of marylandenergy (kcv) l0 activity was determined by first decay...

U N IVERSITY OF Building 090College Park, Maryland 20742-2115301.405.5207 TEL 301.314.2029 FAXMARYLAND vwww.nmse.umd.edu

GLENN L. MARTIN INSTITUTE OF TECHNOLOGYA. JAMES CLARK SCHOOL OF ENGINEERING

Department of Materials Science and Engineering

March 21, 2013

Document Control DeskUnited States Nuclear Regulatory CommissionWashington, D.C. 20555-0001

Reference: UNIVERSITY OF MARYLAND, LICENSE RENEWAL FOR THE MARYLANDUNIVERSITY TRAINING REACTOR ("MUTR") (TAC NO. ME1592), Docket No. 50-166, License No. R-70

The University of Maryland hereby submits the following documents for the MarylandUniversity Training Reactor in connection with the renexval application identified above:

1. Ar-41 Occupational and Public Dose Assessment Report at the MUTR; and2. Accident Analysis MHA Report (updated).

If there are questions about the information submitted, please write to me at: Department ofMaterials Science and Engineering, University of Maryland, College Park, MD 20742-2115 or emailme at [email protected]. Please copy Prof. Robert Briber on any such correspondence:Department of Materials Science and Engineering, University of Maryland, College Park, MD 20742-2115; [email protected].

I declare under penalty of perjury that the foregoing and the enclosed documents are true andcorrect.

Sincerely,

Mohamad Al-SheikhlyProfessor and DirectorMaryland University Training Reactor

Enclosures (2)cc: Robert Briber (By E-mail).

Ar-41 Occupational and Public Dose Assessment at the MUTR

This section deals with the assessment of radiation dose contributions due to Argon-41 gas generated

from operation of the Maryland University Training Reactor (MUTR). The MUTR is housed at the

Chemical and Nuclear Engineering Building on the University of Maryland College Park Campus. TheMUTR is used for the training of Nuclear Engineering students and for research purposes.

Radiation Protection

Federal guidelines demand that "A sustained effort should be made to ensure that collective doses, as well

as annual, committed, and cumulative lifetime individual doses, are maintained ALARA (As Low As

Reasonably Achievable)." In working toward this goal, several conditions needed to be taken intoaccount. Firstly, the dose levels of Argon-41 achievable in areas immediately adjacent to the MUTR

accessible by the general public were to be kept below limits as outlined in Federal regulation 10 CFR 20.

Secondly, total dose contribution of Argon-41 for radiation workers in the MUTR facility must not only

be kept below the limits specified in 10 CFR 20, but also ALARA. Thirdly, actions taken to comply with

the first two tenets must not cause excess wear or damage to operation controls or components of theMUTR or induce excessively adverse working conditions for radiation workers at the MUTR.

To ensure safe and productive use of the MUTR, all activities taken there are conducted in strict

accordance with federal and state safety regulations. Operation at the MUTR shall be carried out in ways

designed to minimize unnecessary radiation dose to radiation workers and to members of the general

public. These doses shall be maintained ALARA.

Sources of Argon-41

Argon-41 is generated during use of the MUTR. Most stems from the activation of dissolved air in the

reactor water, though some trace contributions may come from neutron beam activation of air trapped inthe thermal column or beam ports. As the reactor water warms, it loses its ability to hold air and it

percolates through the reactor pool surface. Assays of Argon-41 levels within the MUTR have been

performed to determine concentration and public dose due to normal reactor operations.

Occupational Dose to Argon-41 from Normal Reactor Operations

The dose risk for those occupationally exposed to Argon-41 is determined by calculating its concentration

in air in terms of activity per unit volume. This is compared to the Derived Air Concentration (DAC),which is the threshold whereupon a radiation worker over the course of a standard "work-year" would

receive a dose equivalent to their annual limit of 5 rem per year for whole body dose. The DAC for

Argon-41 is 3.0 x 10-6 uCi/ml.

An accurate measure of Argon-41 levels at the MUTR was necessary to evaluate actions to mitigate

potential doses. Two techniques were chosen to obtain this data. The first involved using an unshielded

radiation measuring probe, a High Purity Germanium (HPGe) detector, to directly measure gamma

emissions from Argon-41 and track its increase in concentration until equilibrium was obtained. This

data provided the time required to reach maximum Argon-41 concentration, as shown in Figure 1.

2

Figure 1 Argon-41 levels at maximum power from time zero to 300 minutes

MUTR Control Room Spectra

60000

50000Post Shutdown. + 2 Minutes

M)S kW . 799 Minutes

. 250kW. 276 Minutes

40000 -- )S0 kW + IS) Minutes

--- 25OkW 4228 Minutes

-4-250 kW s 204 Minutes

AO kW 1$D Minutel,

IXX) i---2501kW 15SMinutes

-250 kW 1 136 Minutes

-- 250 kW * 114 Wutes

-250 kW + 92 MInutes(XXX) -250kW + G9 Minutes

--*-250kW 1 47 Minutes

-4-250kW + 25 Minutes

-.-- 250 kW + 0 Minutes10"0

01WS0 1160 WOll IMt 1.,W) 13W0 1311) 13A11 1:130 1:40 3IW)

Channe

The results indicated a time of between 3 V2 and 4 hours to reach equilibrium of Argon-41 within theMUTR facility. These results were projected in a graph versus time, as shown in Figure 2. The samplecounts taken from 180 minutes to shutdown were averaged to determine an equilibrium value. From thisprojection, Argon-41 increased approximately 0.56% of the averaged equilibrium rate per minute fromTime Zero.

Figure 2 Argon-41 levels versus time

45000

40000

35000

30000

25000

20000

15000

10000

5000

0

R' = 09876 -

7-

0 50 100 150 200 250 300 350

3

The second technique took air samples from various locations within the MUTR facility and measuredactivities of Argon-41. Concentrations in various zones within the MUTR and in areas adjacent to itcould then be determined. All measurements in these assays were taken with the MUTR at its maximumpower (250 kW) and air samples were taken with Argon-41 levels at equilibrium. In actuality, the MUTRcould not be operated at maximum power for the duration of one "work-year" (2000 hours) in the courseof a calendar year. These conditions were chosen for the evaluation, however, to provide a safety marginas it represented "worst-case" conditions.

Air samples were taken from four zones within the MUTR facility as indicated in Figure 3. All thesamples were taken at breathing level, defined as I meter above the floor for sitting position, and 1.5meters for standing positions. Position A took samples at the reactor pool edge at a height of 1.5 meters.Position B took samples 1 meter back from the reactor control console at a height of I meter. Position Ctook samples at 2 meters back from thermal column at a height of 1.5 meters. Position D took samples at1 meter from balcony edge at a height of 1.5 meters.

I liter Marinelli beakers evacuated under vacuum were used to take the air samples. Measurements of theMarinelli beakers after evacuation indicated a pressure of approximately 150 Torr, a level comparable tothe rating of the vacuum pump used (Little Giant model 13154). This translates to approximately 20% ofthe original volume of air held within the beaker. To account for the difference from ideal vacuum, theMarinelli beakers were evacuated in the sample zone within the MUTR. Each Marinelli beaker was thenevacuated three times (opening on-site in between each evacuation) to reduce the amount of originalambient air within the beaker to less than 1% of the sample volume. Three samples were taken at eachlocation and the sample closest to the median was used for activity calculations. This would eliminate theeffect of outliers possibly caused by loss of vacuum of the Marinelli beakers or anomalous plumes ofArgon-41.

Figure 3 Argon-41 sampling locations

22308EB

A

1308A

D

2308D

4

To account for deviations from Normal Temperature and Pressure (NTP - 200 C and 760 Torr),measurements of ambient temperatures and pressures were taken with each sample. With this data, an

Effective Volume of air contained within the Marinelli beaker was calculated. Effective volume was

determined from the Ideal Gas Law. With PV=nRT as our sample of gas and P'V'=nRT' as a sample of

gas at NTP, we can calculate the following:

nRTV =P

nRT

V p

V' nRT'p/

nRT'P/

nRT

nR P T'v n--R-rPf

As V' = 1 liter

nRTV- P

nRT'P

1

T

VT

TP'PT'

Efficiency calibration carried out using an air equivalent standard (Eckhart and Ziegler Standard 81144A-

577), as shown in Figure 4. The efficiency for Argon-41(which has a gamma emission energy of 1293keV) was determined by calculating the slope between Co-60 energies (1173 keV and 1332 keV). For the

measurements taken in this assay, the fractional efficiency for Argon-41 was calculated to be 6.61 x 10'.

Figure 4 - Efficiencies of radionuclides contained in Eckhart and Ziegler Standard 81144A-577

i.OOE-o2

Lioo_0E-o 3

t " "

0 500 1000 1500

Energy (kcV)

l0

Activity was determined by first decay correcting the total counts back to the time of sampling. Thedecay-corrected counts were then divided by the detector efficiency to get the total counts over the

counting period.

5

The counts were divided by the total time in seconds to determine decays per second (Bq) and then

converted to jtCi. The equation is as follows:

Activity = (Counts/1200 )/(37000dps/(j±CO)

The final concentration is a ratio of the Activity to the Effective Volume in milliliters.

The results of the assays of the MUTR at maximum power and Argon-41 levels at equilibrium are shown

in Tables 1 and 2.

Table 1 Argon-41 count levels with relevant sample data at time of acquisition with calculation

values highlighted.

Location # Time of Transit Time of Air Humidity Pressure Water CountsSample time (s) Acquisition Temp (%) (in) Temp

Console I MR- Room2 12:51 159 12: 75 24 30.16 39.1 13303 13:13 152 13:15 75 25 30.15 38 1150

Bridge I -4- -2 13:59 138 14:02 78 25 30.11 36.3 11323 14:21 158 14:24 78 25 30.10 35.6 1205

Experiment 1 14:45 120 14:47 69 28 30.09 35.1 2643Floor

2 •5 --U-•03 15:31 125 15:33 65 33 30.08 34.3 3794

BalconyT 1 15:52 129 15:54 75 30 30.07 33.8 9612 16:14 250 16:18 75 30 30.07 33.8 964

1 As only two samples could be obtained prior to reactor shutdown, their results were averaged for the sake ofcalculation.

6

Table 2 Argon-41 concentrations at equilibrium expressed as activity/volume and in percentage ofDAC in the occupationally exposed area of the MUTR at maximum power

Sample Location Air Temp (C) Air Press (TORR) Effective Volume (I)

Console 23.3 766.1 1.16

Bridge 25.6 765.3 1.27

Exp. Floor 18.9 764 0.94

Balcony2 23.9 763.8 1.19

Sample Time Acquisition Time Counts Decay Corrected

12:30 12:32 1296 1312.5

13:36 13:38 1134 1148.4

15:08 15:10 2848 2884.2

15:52 15:54 963 975.3

Activity (gCi) Concentration (ftCi/ml) % of DAC

0.0045 3.87E-06 129.0

0.0039 3.08E-06 102.6

0.0098 1.05E-05 348.5

0.0033 2.79E-06 93.2

Since the MUTR takes between 3 /2 and 4 hours for Argon-41 to reach equilibrium values, the calculatedconcentrations of Argon41 do not represent a proper way to compare to the DAC. To account for lowerconcentration of Argon-41 over the time interval between Time Zero and equilibrium, an EffectiveConcentration was determined by 1) assuming a linear increase in concentration until equilibrium; 2)obtaining the equilibrium level from an average of counts taken between 180 to 299 minutes; and 3) using4 hours as the time to reach average equilibrium. With a linear concentration increase inArgon-41concentration, the effective concentration would be 0.75 of the average equilibrium, assuming 8 houroperation of the MUTR. The results are shown in Table 3.

Table 3 Effective Concentration of Argon-41 levels over 8-hour operation of the MUTR at

maximum power

Sample Location Activity (jtCi) Concentration Effective % of DAC_(Ci/ml) Concentration • _"_"__:__.'____

Console 0.0045 3.87E-06 2.90E-06 96.7Bridge 0.0039 3.08E-06 2.31E-06 77.0

Exp. Floor 0.0098 1.05E-05 7.84E-06 261.4Balcony 0.0033 2.79E-06 2.10E-06 69.9

7

Even adjusted as Effective Concentration, the assays of Argon-41 still yield two zones near or above theDAC. One possible action to minimize levels of Argon-41 would be to run the ventilation fans within theMUTR during all hours of operation. While this would definitely minimize public and radiation workerdose contributions from Argon-41, it would have several negative effects on the MUTR facility and itsoperation. During the winter months, outside air would cause a severe drop in temperature, as the air isnot conditioned, and this would likely affect safe operator and worker performance. High humidity,especially in the summer months, would eventually corrode and degrade control components such asrelays. For this reason, constant operation of the fans was not considered a viable action. Instead,intermittent use of the fans during MUTR operation was chosen as the technique best suited to meet therequired conditions. At 50% of the maximum concentration of Argon-41, the fans were operated for tenand fifteen minutes intervals (allowing for a complete change of the volume of air in the MUTR). In thisway Argon-4 l's dose contributions would be mitigated, as dictated by the ALARA principle, while notaffecting the safe operation of the MUTR through excess wear. This was tested in the experiment shownbelow.

The first trials tested 10 minute runs of the ventilation fans approximately every two hours. Assays wereconducted using both an open HPGe probe at the Console and evacuated Marinelli beaker samples at theExperiment Floor. The HPGe probe logged data every 20 minutes and the Marinelli samples were takenat points prior to and after fan operation. These tests indicated the technique would result in an effectiveconcentration of 50 to 55% of the average equilibrium, assuming an 8 hour operation of the MUTR at fullpower (See Figure 5).

Figure 5 Chart of effects of 10 minute ventilation fan operation on Argon 41 concentration,expressed as percentage of the DAC

120%

Fan Effects on Argon 41 Concentration in Control Room. Normalized to U 0:00

E 0:23100% N 0:43

0 1:07

0 1:3080% 0 1:52

a 2:24

60% 2:46

% 3:10

%~IN 3:32

40% 3:57

0 4:28

E 4:5020%

065:11

N 5:44

0% Aq,6:06

Time (HH:MM)

8

Considering the concentration of Argon-41 found on the Experiment Floor, the next trial increased thelength of fan operation to 15 minutes. Evacuated Marinelli beakers were used to assay Argon-41concentration at the Console. Two samples were taken for each fan run, one prior and one after, tocalculate the drop in Argon-41 concentration. For these tests, movement to and from the MUTR wasrestricted as much as possible and the door from the Console to the Bridge was shut. This resulted inhigher concentrations of Argon-41 than would be found under normal conditions, but would give theclearest indication of the ventilation fan performance. The results of the tests are shown in Table 4.

Table 4 Argon-41 reductions in concentration with ventilation fan operation expressed asactivity/volume and in percentage of DAC in the occupationally exposed area of the MUTRat maximum power

Sample Location Air Temp (C) Air Press (TORR) Adjusted Volume (I)

Console pre 1 22.2 771.9 1.09

Console post 1 18.8 771.9 0.93

Console pre 2 20 771.9 0.98

Console post 2 20 771.4 0.99

Console pre 3 21.7 769.9 1.07

Console post 3 20 769.9 0.99

Sample Time Acquisition Time Counts Decay Correced

10:45 10:48 1093 1106.91

11:16 11:17 339 343.31

1:04 1:06 1575 1595.04

1:34 1:36 395 400.03

3:22 3:23 1793 1815.81

3:49 3:51 315 319.01

Decay Corrected Concentration -Activity (pCi) (RCi/mi) %of DAC % rebd i ticr

1106.91 0.0035 3.16E-06 105.32

343.31 0.0011 1.16E-06 38.57 0.69

1595.04 0.005 5.05E-06 168.45

400.03 0.0012 1.27E-06 42.22 0.75

1815.81 0.0057 5.29E-06 176.29

319.01 0.0001 1.01E-06 33.6 0.82

Argon-41 concentrations averaged drops of 75% after ventilation fan runs of 15 minutes. We can projectthis pattern of reduction onto the equilibrium levels of Argon-41 obtained under normal conditions atmaximum power. Conducting 15 minute fan runs every two hours results in the reductions in Argon-41concentrations in the following tables and graphs.

9

Table 6 Reduction in Argon-41 concentration at MUTR Bridge expressed as percentage of DACwith reactor power at 250kW

0 02 52.5

2.42 16.3

4.42 68.8

4.84 17.2

6.84 69.7

7.26 12.3

%of DAC

80o

60

40 - U %of DAC

20

040 2 2.42 4.42 4.84 6.84 7.26

Average % of DAC 33.8

Table 7 Reduction in Argon-41 concentration at MUTR Console expressed as percentage of DACwith reactor power at 250kW

U U

2 65

2.42 20.2

4.42 85.2

4.84 21.3

6.84 86.3

7.26 15.2

%of DAC10090 .. . . .. . ..

70

50 -m %of DAC40

30

2010

0 2 2.42 4.42 4.84 6.84 7.26

Average % of DAC 41.9

Table 8 Reduction in Argon-41 concentration at MUTR Balcony expressed as percentage of DAC

with reactor power at 250kW

%of DAC

0 0

2 46.6

2.42 14.4

4.42 61.0

4.84 15.3

6.84 61.9

7.26 10.9

70

60

50

40

30 m %of DAC

20

10

0Average % of DAC 30.0

0 2 2.42 4.42 4.84 6.84 7.26

10

Table 9 Reduction in Argon-41 concentration at MUTR Experiment Floor expressed as percentageof DAC with reactor power at 250kW

%of DAC

0 02 175

2.42 54.3

4.42 229.3

4.84 57.3

6.84 232.3

7.26 40.9

250

200

150 -

100 -U %of DAC

50 -

0 -I A) Ah A)~ AQA rQA 71r

Average % of DAC 112.7 1..

Using ventilation fan runs at two hour intervals result in overall Argon-41 concentrations well below theDAC except in the case of the Experiment Floor, which remains at an estimated 112.7% of the DAC.

Estimated Annual Dose to Uncontrolled Areas due to Argon-41 Production from the MUTRThe dose risk for members of the general public in uncontrolled areas due to Argon-41 is conducted usingtwo modeling software packages: the Environmental Protection Agency program COMPLY, and HotSpot(Version 2.07.1). To model the dose to the general public outside the Chemical and Nuclear EngineeringBuilding, which houses the MUTR, both programs are used.

Both models take into consideration factors such as release height and wind speed. HotSpot uses a moredetailed model to calculate the Total Effective Dose Equivalent (TEDE) to a receptor. For the totalactivity, the average concentration of Argon-41 generated by the MUTR at maximum power atequilibrium, 5.82 xl0-6 ý.Ci/ml, was multiplied by the total volume of the facility. This figure wasdetermined by averaging the three highest concentrations of Argon-41 in the MUTR as listed on Table 2.The balcony was excluded due to insufficient data, and, since the balcony measurements were the lowestof the four locations, discounting it results in a more conservative value. With ventilation fans runningevery 2 hours during operation, 4 "flushes" of 75% of the total Argon-41 activity would occur eachoperating day. Projected over 250 operating days per year, this calculates to 1.7 Curies per Yearreleased.

The HotSpot program projection can be found in Attachment A. According to HotSpot, the maximumpossible dose received by a member of the general public would be 1.81 mrem.

The factors were then entered into the COMPLY program as a confirmation model. The report can befound in Attachment B. The maximum potential dose according to the COMPLY model projects to 5.1mrem per year.

To account for seepage of Argon-41 at ground level, HotSpot was used to model leakage. A leakage rateof 5% of the previously calculated total activity at the surface was used to calculate potential dose. As apoint of comparison the leakage model was calculated manually. The calculation assumed no ventilationfans run during the operation, the most conservative model. One calculates the Deep Dose Equivalent(DDE) to members of the public at a given distance downwind from the facility by the followingequation:

11

DDE thy or DDEwb = [i [(X/Q) DCFCXt Ai X, [exp{-iti)-exp{-Ait 2}])/()

Where:

Parameters used to calculated Dose

Room Ventilation exhaust rate

Room Leakage rate

Reactor Room Volume

2.83

0.00236

1700

m 3/S

m 3/S

m 3

Variables in the Dose

X/Q

DCFext

Ai

ti

t2

Atmospheric dispersion coefficient in s/m 3

External Dose Conversion Factors mrem M3 uCi' s1

Released Activity per isotope I in uCi

Ventilation Constant (leakage rate/reactor volume) 1/s

time plume arrives at receptor point s 5 s

time plume has passed receptor point s 28800 s

radioactive decay constant in

1/s

Note: only one set of t1 and t 2 values are used as the change in arrival and passage

does not change the TEDE values with any significance between 100 and 300 m.

The results of this calculation are shown in Table 10.

Table 10 Argon-41 Leakage Dose rate per day in mrem/day

DDE Public Ground Level Release (Leakage Case)

Isotope X/Q (10) X/Q X/Q X/Q (300) BR DCFu Ai [uCil .1(100) (200)

Ar-41 6.OOE-02 2.41E-02 6.63E- 2.61E-03 3.30E- 2.41 E- 3.95E+03 1.052E-

1 03 04 04 04ti exp{-

A&tIt2 exp{-

Xt 2)DDE(,Om) DDE DDE

(100m) (200m)DDE

(300m)

0 1.OOE+00 2.88E+04 4.83E-02 1.74E-02 2.86E- 7.86E- 3.09E-0403 04

Total dose to public over 50 weeks/yr at 8hr/d =

Ai is 8 hour activitytI is 0 timet2 is 8hrs

12

Figure 6 Forecasted Exponential Trend Line Analysis of the X/Q Values for 100 to 300 meters

Leakage forecast of 10 meter x/Q [s/m3]

0.08

0.07

0.06

0.05

0.04 - XIQ [s/m3]

0.03 - Expon. (x/Q [s/m3])yy -= 0.069e&o-11x

0.02 = 0.9914

0.01 "

00 50 100 150 200 250 300 350

distance along centerline

Ground Level Release (H =0) Centerline

XIQ [S/M3i = [1/p OEI!I

______ [ ___] A C E_

100 4.02E_04 9.5E0 1.59E-03 1.75E02 2.41E-0 2

200 1.18E-04 2.5E0 4.72E-04 4.25-03 663E-03

300 4.14E-05 1OJ.14E-04 2.02E-04 1.88-03 2.61E-03]

X(xO) [M] XIO. [s/rn3]

300 2.61E-03

200 6.63E-03

100 2.41E-02

10 6.00E-02

These hand calculations were carried out as a verification of the HotSpot and COMPLY models. TheHotSpot leakage model projection, used as the official calculation in this publication, can be found inAttachment C. As such, the maximum potential dose to a member of the general public according to theHotSpot model is 4.39 mrem, which is below 10 CFR Part 20 limits.

ConclusionIn uncontrolled areas, the potential public dose due to Argon-41 is well within the limits specified in 10CFR 20. The potential occupational dose contribution due to Argon-41 is also well within regulatorylimits when the ventilation fans are operated at 2 hour intervals for a minimum of 15 minutes at all

locations within the MUTR except the Experiment Floor. In order to maintain the occupational dose of

all workers around the MUTR, the following additional precautions will be taken.

13

EXPERIMENT FLOOR KILOWATT HOUR RESTRICTION

The DAC of 3.0 x 10-6 ýiCi per ml is based on a work year of 2000 hours. Access to the Experiment Floorof the MUTR shall have an annual cap of the equivalent of 1500 hours at full power. After reaching this

threshold, personnel shall be restricted from accessing the Experiment Floor during reactor operation.Logs of total kilowatt hours of operation are maintained at the MUTR. With such a cap in place, all of

the zones within the MUTR will have effective Argon-41 concentrations below the DAC (projected over

the course of the calendar year).

ALARA PROGRAM

All radiation workers at the MUTR are issued dosimetry sensitive to beta, gamma and neutron radiation

on a bimonthly basis. The ALARA program triggers an investigation whenever a radiation workerreceives a dose of 10% of the bimonthly limit (approximately 80 mrem). The investigation will take into

account worker technique and evaluate possible changes in potential dose. This assures workers at theMUTR that not only will their occupational dose be within regulatory limits, but will be maintained

ALARA.

The MUTR will continue to evaluate performance on an ongoing basis and strive to optimize alltechniques to reduce the level of exposure due to Argon-41. In this way, we can assure that both workers

within the MUTR and the general public that safety is a top concern at the University of Maryland.

14

Attachment A - Annual Release of Ar-41 from MUTREffluent Assessment From HotSpot

15

Annual Release of Ar-41 from MUTR

HotSpot Version 2.07.1 General Plume

Feb 03, 2012 03:33 PM

Source Material Ar-41 1.0961 E+02 m

Material-at-Risk (MAR) :7.4200E+00 Ci

Damage Ratio (DR) :1.000

Airborne Fraction (ARF) :1.000

Respirable Fraction (RF) 1.000

Leakpath Factor (LPF) :1.000

Respirable Source Term : 7.42E+00 Ci

Non-respirable Source Term : 0.OOE+00 Ci

Effective Release Height : 7.25 m

Wind Speed (h=10 m) : 2.00 m/s

Distance Coordinates : All distances are on the Plume Centerline

Wind Speed (h=H-eff) :1.68 m/s

Stability Class : F

Respirable Dep. Vel. : 0.00 cm/s

Non-respirable Dep. Vel. : 8.00 cm/s

Receptor Height :1.5 m

Inversion Layer Height : None

Sample Time :10.000 min

Breathing Rate : 3.33E-04 m3/sec

Maximum Dose Distance : 0.32 km

MAXIMUM TEDE : 1.81E-03 rem

Inner Contour Dose : 1.0 rem

Middle Contour Dose : 0.500 rem

Outer Contour Dose : 0.100 rem

16

Exceeds Inner Dose Out To : Not Exceeded

Exceeds Middle Dose Out To : Not Exceeded

Exceeds Outer Dose Out To : Not Exceeded

FGR-1 I Dose Conversion Data - Total Effective Dose Equivalent (TEDE)

Include Plume Passage Inhalation and Submersion

Include Resuspension (Resuspension Factor : Constant Value) 1.00E-05 1/meter

Exposure Window:(Start: 0.00 years; Duration: 1.00 years) [100% stay time].

Initial Deposition and Dose Rate shown

Ground Roughness Correction Factor: 1.000

RESPIRABLE

DISTANCE T E D E TIME-INTEGRATED ARRIVAL TIME

AIR CONCENTRATION

km (rem) (Ci-sec)/m3 (hour:min)

0.010

0.100

0.200

0.300

0.400

0.500

0.0E+00

2.9E-05

1.2E-03

1.8E-03

1.7E-03

I.4E-03

0.OE+00

1.2E-04

5.2E-03

7.5E-03

7.OE-03

5.9E-03

<00:01

<00:01

00:01

00:02

00:03

00:04

17

Attachment B - Annual Release of Ar-41 from MUTR

Effluent Assessment From COMPLY

'.1

18

40 CFR Part 61

National Emission Standards

for Hazardous Air Pollutants

REPORT ON COMPLIANCE WITH

THE CLEAN AIR ACT LIMITS FOR RADIONUCLIDE EMISSIONS

FROM THE COMPLY CODE, VERSION 1.4

Prepared by:

University of Maryland

MUTR

Building 090

Mary Dorman

301-314-8336

Prepared for:

U.S. Environmental Protection Agency

Office of Radiation Programs

Washington, D.C. 20460

Ar-41 release from MUTR

SCREENING LEVEL 2

DATA ENTERED:

RELEASE RATES FOR STACK 1.

Release RateNuclide (curies/YEAR)

AR-41 3.710E+00

RELEASE RATES FOR STACK 2.

19

Release RateNuclide (curies/YEAR)

AR-41 3.710E+00

SITE DATA FOR STACK 1.

Release height 7 meters.

Building height 11 meters.

The source and receptor are not on the same building.

Distance from the source to the receptor is 10 meters.

Building width 14 meters.

SITE DATA FOR STACK 2.

Release height 7 meters.

Building height 11 meters.

The source and receptor are not on the same building.

Distance from the source to the receptor is 10 meters.

Building width 14 meters.

Default mean wind speed used (2.0 m/sec).

NOTES:

Input parameters outside the "normal" range:

None.

RESULTS:

Effective dose equivalent: 5.1 mrem/yr.

*** Comply at level 2.

This facility is in COMPLIANCE.

It may or may not be EXEMPT from reporting to the EPA.

You may contact your regional EPA office for more information.

*** * END OF COMPLIANCE REPORT *

20

Attachment C - Leakage Dose from MUTR for Argon-41Effluent Assessment From HotSpot

21

Annual Leakage Dose from MUTR for Ar-41HotSpot Version 2.07.1 General PlumeFeb 03, 2012 03:31 PM

Source Material : Ar-41 1.0961E+02 mMaterial-at-Risk (MAR) :3.7100E-01 CiDamage Ratio (DR) :1.000Airborne Fraction (ARF) :1.000Respirable Fraction (RF) : 1.000Leakpath Factor (LPF) :1.000Respirable Source Term : 3.71E-01 CiNon-respirable Source Term : 0.OOE+00 CiEffective Release Height : 0.00 mWind Speed (h=10 m) : 2.00 mrsDistance Coordinates : All distances are on the Plume CenterlineWind Speed (h=H-eff) : 0.83 m/sStability Class : FRespirable Dep. Vel. : 0.00 cm/sNon-respirable Dep. Vel. : 8.00 cm/sReceptor Height :1.5 mInversion Layer Height : NoneSample Time :10.000 minBreathing Rate : 3.33E-04 m3/sec

Maximum Dose Distance : 0.067 kmMAXIMUM TEDE : 4.39E-03 remInner Contour Dose : 1.0 remMiddle Contour Dose : 0.500 remOuter Contour Dose : 0.100 remExceeds Inner Dose Out To : Not ExceededExceeds Middle Dose Out To : Not ExceededExceeds Outer Dose Out To : Not Exceeded

FGR-I I Dose Conversion Data - Total Effective Dose Equivalent (TEDE)

Include Plume Passage Inhalation and SubmersionInclude Resuspension (Resuspension Factor: Constant Value) 1.OOE-05 1/meterExposure Window:(Start: 0.00 years; Duration: 1.00 years) [100% stay time].Initial Deposition and Dose Rate shownGround Roughness Correction Factor: 1.000

RESPIRABLEDISTANCE T E D E TIME-INTEGRATED ARRIVAL TIME

AIR CONCENTRATIONkm (rem) (Ci-sec)/m3 (hour:min)

0.010 0.OE+00 1.4E-19 <00:010.100 3.4E-03 1.4E-02 00:020.200 1.2E-03 5.2E-03 00:040.300 6.OE-04 2.5E-03 00:060.400 3.5E-04 1.5E-03 00:080.500 2.3E-04 9.7E-04 00:10

Accident Analysis MHA

Accident Analysis

Introduction

The NRC licenses research and test reactors consistent with the NRC mission to ensureadequate protection of the public health and safety and to promote and protect the environment.NUREG 1537 Part 1 and 2 guidance describes acceptable format and content of the safety analysisreport (SAR) to be submitted to the U.S. Nuclear Regulatory Commission (NRC) by an applicant orlicensee of a non-power reactor for a license renewal.

Chapter 13 lists the bases, scenarios, and analyses of accidents at the reactor facility, anddescribes a Maximum Hypothetical Accident, MHA, which may include a fission product release,and radiological consequences to the operational staff reactor users and the public. For researchreactors licensed before January 1, 1994, the doses that the NRC has generally found acceptable foraccident analysis result in less than 5 rem whole body and less than 30 rem thyroid for occupationalexposure, and less than 0.5 rem whole body and less than 3 rem thyroid for members of the public.

The, MHA, which assumes an incredible failure that can lead to fuel cladding or to a fueledexperiment containment breach, is used to bound credible accidents in the accident analysis. TheMHA for TRIGA reactors is a cladding failure of a single irradiated fuel element in air with releaseof fission product inventories to the reactor confines and the public. In general, the escape of fissionproducts from fuel 'or fueled 'experiments and their release to the unrestricted environment would bethe most hazardous radiological accident conceivable at a non-power reactor. However, non-powerreactors are designed and operated so that a fission product release is not credible for most.Therefore, this release under accident conditions can reasonably be selected as the MHA, whichbounds all credible accidents and can be used in the analysis of events and consequences during theaccidental release of radioactive material. Instantaneous release of noble gases and halogen fissionproducts follow from the cladding failure of this one element. The gases and fission productsinstantly and uniformly mix with the reactor room air. This concentration may be exhausted out ofthe building through elevated vents 'elevated release', at a rate of 2.83 m3 per s. Leakage out of thebuilding through a window crack or doorway leak 'ground release', is assumed to occur at a rate of5%/hour, at a rate of 2.42 x 10-2 m3 per s.

Fuel element failure can occur at any time during normal operations or when the reactor is atrest and shutdown. In this worst case scenario a single element has been removed from the reactorand dropped to the floor of the reactor building outside of the biological shield. Fission products arereleased in air from the gap and the cladding and instantaneously and uniformly mix in the volume ofthe reactor building.

In NUREG CR-2387 Credible Accident Analysis for TRIGA and TRIGA Fueled Reactors,the only potential for offsite exposures and doses is indicated as a fuel handling accident that basedon highly conservative assumptions would result in dose equivalents of < 1 mrem TEDE from noblegases and < 1.2 rem to the thyroid from radioiodines.

The analysis and accident scenario given in NUREG 2387 gives the following analysis for a1MW TRIGA after 1 year of continuous operation at full power, 365MWd. The Maryland UniversityTraining Reactor, MUTR is a 250 kW TRIGA reactor and therefore not capable of this level of

1


operation. The analysis and subsequent inventories and released activities from the damaged fuelelements are thus highly conservative for this facility.

The analysis assumes 50 elements were present in the core and the central elementexperiences the greater than average burn up. At 1/50 or 2% or the total the element would contain4% of the total activity in the core. The noble gas and radioiodine activities in this element are3828.8 Ci or Krypton, 9431 Ci of Iodine, and 3933 Ci of Xenon. A one year operation of the MUTRat 250 kW for 365 days is 91.25 MWd and the equivalent activities would be 25% of these values or957.2 Ci or Krypton, 2357.8 Ci of Iodine and 983.3 Ci of Xenon.

All the activity would not be released from the element as the fuel matrix acts strongly toretain the fission products. According to NUREG 2387 the gap activity fraction is approximately1.5xl0 5 . GA developed a conservative correlation for fission product release to be:

e = 1.5E-5 + 3.6x10 3 e {-1.34x10/ (T+273)}, at T = 300 for the MUTR this yields 1.5E-5

For the MUTR the total release activity based on this release fraction would be 14.4 mCiKrypton, 35.4 mCi of Iodine and 14.7 mCi of Xenon. Activities and released values are as follows:

Noble Gases Iodine products Cesium and Strontium

Released Released ReleasedActivity Activities Activity Activities Activity Activities

Isotope (Ci) (mCi) Isotope (Ci) (mCi) Isotope (Ci) (mCi)

Kr-83m 30.9 0.463 1-131 270.0 4.05 Sr-89 16.7 0.25Kr-85m 71.7 1.076 1-132 415.3 6.23 Sr-90 0.5 0.008

Kr-85 1.2 0.018 1-133 483.3 7.25 Sr-91 21.5 0.323

Kr-87 138.0 2.07 1-134 636.0 9.54 Sr-92 24.4 0.366

Kr-88 197.3 2.959 1-135 553.3 8.3 Cs-134m 0.1 0.001

Xe-133m 9.7 0.146 Cs-134 0.1 0.001

Xe-133 566.7 8.5 Cs-136 0.5 0.007

Xe-135m 149.5 2.243 Cs-137 8.3 0.124

Xe-135 256.3 3.844 Cs-138 34.3 0.515

Dose determination for these released activities was calculated using Federal Guidance Report 11 and12 Dose Conversion Factors (DCF) for internal and external values. For atmospheric stability aground level release was assumed for the case of leakage out of the reactor building and an elevatedrelease for exhaust through the MUTR ventilation system. Horizontal and vertical diffusioncoefficients were utilized from CEMBER, Introduction to Health Physics third edition as referencedfrom D.H. Slade, Meteorology and Atomic Energy Tech Inform 1968 and are also readily availablethrough other references. A Pasquill category F, moderately stable condition, was chosen for allreleases as a conservative category. Values below 100 m are not available in any reference thereforedose determination at minimum distances to the unrestricted areas such as at I Om were determinedusing HOTSPOT software.

2


Atmospheric Dispersion Values for Pasquill F category:

[l/lY__,__[] e"[1/2 (H/G)A2]

X(x,O)[m] A B C E F A B C E F

100 4.02E-04 9.95E-04 1.59E-03 1.72E-02 2.41E-02 9.21E-01 7.65E-01 6.58E-01 5.07E-02 5.25E-05

200 1.18E-04 2.65E-04 4.72E-04 4.25E-03 6.63E-03 9.71E-01 9.35E-01 8.88E-01 4.12E-01 5.07E-02

300 4.14E-05 1.14E-04 2.02E-04 1.88E-03 2.61E-03 9.91E-01 9.71E-01 9.48E-01 6.90E-01 2.97E-01

Elevated Release ( Effective Height H, centerline)

x/Q [s/m 3]=[ 1/I=[1 y zat] x e-[1/2 (H/G)A2]

x(x,O)[m] A B C E F

100 3.70E-04 7.61E-04 1.05E-03 8.74E-04 1.27E-06

200 1.14E-04 2.48E-04 4.19E-04 1.75E-03 3.37E-04

300 4.10E-05 1.11E-04 1.92E-04 1.30E-03 7.74E-04

Ground Level Release (H = 0) Centerline

x/Q [s/m 3 1 = [1/gwaazir_]

x(x,O)[im] A B C E F

100 4.02E-04 9.95E-04 1.59E-03 1.75E-02 2.41E-02

200 1.18E-04 2.65E-04 4.72E-04 4.25E-03 6.63E-03

300 4.14E-05 1.14E-04 2.02E-04 1.88E-03 2.61E-03

Moderately Stable conditions selected Pasquill Category F

3

Accident Analysis M HA

Ground Level Release Leakage (ventilation OFF) Public Dose

Committed Dose Equivalent (CDE) to the thyroid and CEDE for members of the public at a given distance

downwind from the facility for all isotopes of concern can be calculated by the following equation:

CDE or CEDE = 1i [(X/Q) BR DCFint Aj Xv [exp{Xit 11-exp{Xit 2}] )

Parameters used to calculated DoseRoom Ventilation exhaust 2.83 m3/S

rate

Room Leakage rate 0.00236 m3/s

Reactor Room Volume 1700 m 3

Breathing Rate 3.30E-04 m3/s

Variables in the Dose Equation

X/Q Atmospheric dispersion coefficient in s M3

BR Breathing rate 3.3e-4 m 3 s1

DCF1nt Internal Dose Conversion Factors mrem uCi'

Ai Released Activity per isotope uCi

XV Ventilation Constant (leakage rate/reactor volume) s-

tj time plume arrives at receptor point s 50 s

t2 time plume has passed receptor point s 72050 s

Note - the tj and t2 values were not changed for 200 and 300, there should be little

change in the values based on these changes

4


CEDE Public Ground Level Release (Leakage Case)

Isotope

Kr-83m

Kr-85m

Kr-85

Kr-87

Kr-88

Xe-133m

Xe-133

Xe-135m

Xe-135

1-131

1-132

1-133

1-134

1-135

Sr-89

Sr-90

Sr-91Sr-92

Cs-134m

Cs- 134

Cs-136

Cs-137

Cs-138

X/Q (W0) X/Q (200) /Q (300) BR

2.41E-022.41E-022.41E-022.41E-02

2.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-022.41E-02

2.41E-022.41E-022.41E-022.41E-02

6.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036.63E-036,63E-036.63E-036.63E-036.63E-03

2.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-032.61E-03

3.30E-043.30E-043.30E-043.30E-04

3.30E-043.3E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-04

DCFjr

O.EOOE0

O.OOE40OO.OOE40OO.00E400OX.EOOE0

4.63E+021.08E+031.80E+012,07E+032.96E+031.46E+02

O.OOE+O0 8.50E+03

O.OOE+00

3.29E+013.81E-015.85E+00

2.24E+033.84E+034.05E+036.23E+037.25E+03

1.05E-044.30E-052.05E-091.51E-044.07E-033.67E-061.53E-067.55E-042.12E-051.OOE-068.37E-059.25E-062.20E-042.91E-051.59E-077.58E-102.03E-057.10E-056.64E-051.07E-086.12E-077.32E-103.56E-04

exp{-k.Q

9.95E-019.98E-01

9.92E-018.16E-011.OOE+0O1.00E4009.63E-019.99E-01

9.96E-011.OJE+009.89E-019.99E-011.00E4001A.EOOE09.99E-019.96E-019.97E-01

7.20E+04 5.14E-047.20E+047.20E+047.20E-+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+047.20E+04

7.20E+047.20E+047.20E+047.20E+04

4.53E-02

1.85E-056.78E-128

7.68E-018.96E-012.40E-242.18E-019.30E-012.41E-035.14E-011.36E-071.23E-019.89E-011.OOE+0O2.32E-016.02E-038.40E-03

O.OOE+00O.OOE40O

O.OOE40O

O.O3E+OOO.OOE40O

O.OOE40O1.02E+003.10E-032.45E-016.20E-043.37E-021.28E-021.51E-021.25E-033.53E-047.14E-083.65E-043.97E-043.13E-021.5S-os

O.OOE+00O.OOE40OO.OOE44JO.OOE+00O.00E400O.,EOOE0O.AOE+iJO.OOE40O2.79E-018.51E-046.72E-021.71E-049.26E-033.52E-034.16E-033,44E-049.70E-051.96E-081.01E-041.09E-048.61E-034.35E406

O.OOE+00O.OOE+00O.COE+0OO.OOE40OO.OOE+00O.OOE4OOO.OOE40OO.EOOE01.OE-O13.34E-042.64E-026.70E-053.64E-031.38E-031.64E-031.35E-043.81E-057.71E-093.95E-054.28E-053.38E-03IIiir ti

t2 expf-At 2} CEDE (10m) CEDE (200m) CEDE (30Om)

aMOE+M O.WE4OO O.WE4O

3.30E-04 1.31E-01 9.54E+03

3.30E-043.30E-04

3.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.3E-043.30E-04

1.23E4WJ6.51E+002.39E+029.32E-016.29E-014.37E-024.63E+017.33E+003.19E+011.01E-01

8.30E+032.50E+028.OOE40O3.23E+023.66E+021.OOE+001.OOE+0O7.OOE40O1.24E+025.15E+02

1.OOE40O 7.20E+04 9.99E-011.00E4001.OOE40O9.82E-01

7.20E+047.20E+047.20E+04

9.57E-011.OOE40O7.13F-12

5


Ground Level Release (Leakage Case) ventilation OFF

Deep Dose Equivalent (DDE) to the thyroid and CEDE for members of the public at a given distance


DDE thy or D DEwb = Ii [(X/Q) DCFext Ai X• [exp{-Xjiti-exp{-Xit 2}]) X(i) ]



Room Leakage rate

Reactor Room Volume

2.83

0.00236

1700

m 3/S

m 3/

Variables in the DoseEquation

X/Q

DCFext

Ai

Xv

ti

t 2

Xi

Atmospheric dispersion coefficient in s/m 3

External Dose Conversion Factors mrem m3 uCi- s1

Released Activity per isotope I in uCi

Ventilation Constant (leakage rate/reactor volume) 1/s

time plume arrives at receptor point s 50 s

time plume has passed receptor point s 72050 s

radioactive decay constant in 1/s

Note: only one set of t1 and t 2 values are used as the change in arrival and passage

does not change the TEDE values with any significance between 100 and 300 m

6


DDE Public Ground Level Release (Leakage Case)

Isotope X/Q(100) X/Q(200) X/Q(300)

Kr-83m

Kr-85m

Kr-85

Kr-87

Kr-88

Xe-133m

Xe-133

Xe-135m

Xe-135

1-131

1-132

1-133

1-134

1-135

Sr-89Sr-90

Sr-91

Sr-92

Cs- 134m

Cs- 134

Cs- 136

Cs- 137

Cs-138

2.41E-02

2.41E-022.41E-02

2.41E-022.41E-02-

2.41E-022,41E-02

2.41E-022.41E-022.41E-02

2,41E-02

2.41E-022.41E-022.41E-02

2.41E-022.41E-02

2.41E-022.41E-022.41E-022.41E-02

2,41E-022.41E-02

2.41E-02

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

6.63E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

2.61E-03

BR

3.30E-04

3.30E-04

3.30E-043.30E-04

3.30E-04

3.30E-04

3.30E-043.30E-04

3.30E-043.30E-04

3.30E-043.30E-04

3.30E-043.30E-043.30E-04

.3.30E-043.30E-04

3.30E-043,30E-043.30E-043.30E-04

3.30E-04

3.30E-04

DCFext

5.55E-092,74E-054.40E-07

1,52E-043.77E-04

5.07E-065.77E-067.55E-054.40E-05

6.73E-054.14E-041.09E-04

4.81E-04

2.95E-042.86E-072.79E-081.28E-042.51E-04

3,35E-062,80E-043.92E-042.86E-08

4.48E-04

A, i4.63E+02 1.052E-04

1.08E+03 4.297E-05

1.80E+01 2.050E-09

2.07E+03 1.514E-04

2.96E+03 4.067E-03

1.46E+02 3.666E-06

8.50E+03 1.529E-06

2.24E+03 7.554E-04

3.84E+03 2.118E-05

4.05E+03 1.003E-06

6.23E+03 8.370E-05

7.25E+03 9.255E-06

9.54E+03 2.196E-04

8.30E+03 2.912E-05

2.50E+02 1.588E-07

8.OOE+00 7.580E-10

3.23E+02 2.026E-05

3.66E+02 7.100E-05

1.00E+00 6.638E-05

1.OOE+00 1.066E-08

7.OOE+00 6.123E-07

1.24E+02 7.325E-10

5.15E+02 3.565E-04

exp{--.tj} t2 exp{-?*t4} DDE (100m) DDE (200m) DDE (300m)

9.95E-019.98E-011.00E+009,92E-018.16E-011.00E+001.00E+009.63E-019.99E-011,00E+009.96E-011.OOE+009.89E-019.99E-011.00E+001.00E+009.99E-019.96E-019.97E-011,00E+001.00E+001.00E+009.82E-01

7.20E+04 5.14E-04

7,20E-•04 4,53E-02

7.20E+04 1.OOE+00

7.20E+04 1.85E-05,

7.20E+04 6.78E-128

7.20E+04 7.68E-01

7.20E+04 8.96E-01

7.20E+04 2.40E-24

7.20E+04 2.18E-01

7.20E+04 9.30E-01

7.20E+04 2.41E-03'

7.20E+04 5.14E-01

7.20E+04 1.36E-07

7.20E+04 1.23E-01

7.20E+04 9.89E-01

7.20E+04 1.OOE+007.20E+04 2.32E-01

7.20E+04 6.02E-03

7.20E+04 8.40E-03

7.20E+04 9.99E-01

7.20E+04 9.57E-01

7.20E+04 1.OOE+00

7.20E+04 7.13E-12

Total DDE

mrem

8.09E-092,17E-04

1.90E-076.89E-047,46E-051.56E-051.11E-037.19E-052.08E-036.30E-031.02E-02'1,38E-026.88E-032.45E-021.70E-065.34E-095.19E-044.27E-04,1.66E-086.71E-06,6.43E-058,51E-082.12E-04,

0.067

2.22E-09!5,98E-055.22E-081.89E-04i2.05E-054.28E-063.06E-04,_1.-98E-05.,5.72E-041.73E-03:2.81E-033.79E-011.89E-036.75E-03'4.68E-071.47E-091.43E-04,1.17E-04

4.56E-091.84E-06'1.77E-052.34E-08,5.82E-05:0.018

8.74E-10ý2,35E-052.05E-08

-7.44E-05.8,06E-06'1.68E-061.20E-04"7.76E-062.25E-04

-6.81-E-04,1.10E-031.49E-03,7.43E-04

2.65E-0311.84E-075.77E- 105.61E-05,4.61E-051.79E-09.

-7.25E-07:6.95E-069.19E-092.29E-05!0.007

7


Elevated Release (ventilation ON) Public Dose

Committed Dose Equivalent (CDE) to the thyroid and CEDE for members of the public at a given distance


CDE or CEDE = 1i [(X/Q) BR DCFint Ai Xv [exp{Xitji-exp{Ait 2 }] )/(WAi)]

Parameters used to calculated DoseRoom Ventilation exhaust 2.83 m3/Srate

Room Leakage rate 0.00236 m 3/s

Reactor Room Volume 1700 m3



X/Q Atmospheric dispersion coefficient in s m3

BR Breathing rate 3.3e-4 m 3 S1

DCFint Internal Dose Conversion Factors mrem uCi'


Xv Ventilation Constant (ventilation rate/reactor volume) s'

ti time plume arrives at receptor point s 50 s

t2 time plume has passed receptor point s 650 s

8


CEDE Public Elevated Release (Ventilation Case)

Isotope X/Q (100) X/Q (200) X/Q (300) BR DCFj A1 -A t1 exp{-kt1} t2 exp{-ktz] CEDE (100m) CEDE (200m) CEDE(300m)

Kr-83m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 0.O0E+00 4.63E+02 LOSE-04 SO 9.95E-01 650 9.34E-01 0.00E+001 0.OOE+0 2.94E-06Kr-&Sm 1.27E-06 3.37E-04 7.74E-04 3.30E-04 0.OOE+00 1.08E+03 4.30E-05 50 9.98E-01 650 9.72E-01 0.00E+00 0.00E+00 2.89E-06

Kr-85 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+00 1.80E+01 2.OSE-OS 50 1.OOE+00 650 1.OE00E+ O.OOE+O0 O.OOE+O0 2.37E-12Kr-V 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+00 2.07E+03 1.51E-04 SO 9.92E-01 650 9.06E-01 O.OOE+00 O.OOE+O0 1.84E-05

Kr-88 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+O0 2.96E+03 4.07E-03 50 8.16E-01 650 7.11E-02 O.OOE+00 OOOE+O0 6.74E-05

Xe-133m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+O0 1.46E+02 3.67E-06 50 1.O0E+O0 650 9.98E-01 O.OOE+00 O.OOE+O0 3.43E-08Xe-133 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+O0 8.5OE+03 1.53E-06 50 1.OCE+O0 650 9.99E-01 O.OOE+00 O.OOE+00 8.34E-07

Xe-135m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+00 2.24E+03 7.55E-04 50 9.63E-01 650 6.12E-01 O.OOE+00 O.OOE+OO 6.92E-05Xe-135 1.27E-06 3.37E-04 7.74E-04 3.30E-04 O.OOE+O0 3.84E+03 2.12E-05 50 9.99E-01 650 9.86E-01 O.OOE+O0 O.OOE+OO 5.16E-O6

1-131 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.29E+01 4.05E+03 1.OOE-06 50 1.O0E+O0 650 9.99E-01 5.56E-05 9.71E-07 2.61E-071-132 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.81E-01 6.23E+03 8.37E-05 50 9.96E-01 650 9.47E-01 9.63E-07 1.45E-06 3.19E-05

1-133 1.27E-06 3.37E-04 7.74E-04 3.30E-04 5.85E+00 7.25E+03 9.25E-06 50 1.00E+OO 650 9.94E-01 1.76E-05 2.85E-06 4.29E-06

1-134 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.31E-01 9.54E+03 2.20E-04 SO 9.89E-01 650 8.67E-01 4.5E-07 2.O0E-OE 1.18E-041-135 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.23E+00 8.30E+03 2.91E-05 50 9.99E-01 650 9.81E-01 4.21E-06 2.16E-06 1.53E-05

Sr-89 1.27E-06 3.37E-04 7.74E-04 3.30E-04 6.51E+00 2.5OE+02 1.59E-07 50 i.O0E+O0 650 1.O0E+OG 6.80E-07 1.88E-OS 2.55E-OSSr-90 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.39E+02 8.OOE+0O 7.58E-1O 50 1.O0E+O0 650 1.O0E+(O 7.99E-07 1.06E-11 3.90E-13

Sr-91 1.27E-06 3.37E-04 7.74E-04 3.30E-04 9.32E-01 3.23E+02 2.03E-05 50 9.99E-01 650 9.87E-01 1.25E-07 4.44E-08 4.15E-07Sr-92 1.27E-06 3.37E-04 7.74E-04 3.30E-04 6.29E-01 3.66E+02 7.lIE-05 50 9.96E-01 650 9.5SE-01 9.37E-08 1.19E-07 1.60E-06

Cs-134m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.37E-02 1.OOE+O0 6.64E-05 50 9.97E-01 650 9.S8E-01 1.78E-11 2.11E-11 4.10E-09Cs-134 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.63E+01 1.00E+O0 1.07E-O 50 1.O0E+O0 650 1.00E+O0 1.93E-08 3.58E-12 6.85E-13

Cs-36 1.27E-06 3.37E-04 7.74E-04 3.30E-04 7.33E+0C 7.OOE+00 6.12E-07 50 1.O0E+O0 650 1.OOE+O0 2.14E-08 2.28E-10 2.75E-10Cs-137 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.19E+01 1.24E+02 7.32E-10 SO 1.O0E+O0 650 l.O0E+O0 1.65E-06 2.11E-1 5.84E-12

Cs-138 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.01E-01 5.15E+02 3.56E-04 50 9.82E-01 650 7.93E-0 1.93E-08 1.35E-07 9.52E-06Total CEDE mrem 8.23E-05 9.73E-06 3.48E-04

9


Elevated Release (ventilation ON) Public Dose

Deep Dose Equivalent (DDE) to the thyroid and CEDE for members of the public at a given distance


DDE thy or DDEwb = Ii [ (X/Q) DCFext Ai Av [exp{-Xitj}-exp{-Xit 2}]) W/(hI)]



Room Leakage rate

Reactor Room Volume

2.83

0.00236

1700

m 3/s

m 3/sm 3


X/Q Atmospheric dispersion coefficient in s/m 3

DCFet External Dose Conversion Factors mrem m 3 uCi1 s1

Ai Released Activity per isotope I in uCi

X,, Ventilation Constant (leakage rate/reactor volume) 1/s

tj time plume arrives at receptor point s

t2 time plume has passed receptor point s

Xi radioactive decay constant in 1/s

10


DDE Public Elevated Release (Ventilation Case)

Isotope X/Q (100) X/Q (200) X/Q (300) Ai k~ ti exp{-Akt1 t2 exP{-t 21 DDE (100M1) ýE(00) DBR DCFet

Kr-83m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 5.55E-09 4.63E+02 1.0SE-04 50 9.95E-01 650 9.34E-01 3.13E-12 8.31E-10 1.91E-09

Kr-85m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.74E-05 1.08E+03 4.30E-05 50 9.98E-01 650 9.72E-01 3.67E-08 9.74E-06 2.24E-05

Kr-85 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.40E-07 1.80E+01 2.05E-09 50 1.00E+00 650 1.00E+00 1.OOE-11 2.66E-09 6.11E-09

Kr-87 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.52E-04 2.07E+03 1.51E-04 50 9.92E-01 650 9.06E-01 3.79E-07 1.00E-04 2.31E-04

Kr-88 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.77E-04 2.96E+03 4.07E-03 50 8.16E-01 650 7.11E-02 4.31E-07 1.14E-04 2.63E-04

Xe-133m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 5.07E-06 1.46E+02 3.67E-06 50 1.00E+00 650 9.98E-01 9.35E-10 2.48E-07 5.70E-07

Xe-133 1.27E-06 3.37E-04 7.74E-04 3.30E-04 5.77E-06 8.SOE+03 1.53E-06 50 1.O0E+00 650 9.99E-01 6.20E-08 1.65E-05 3.78E-05

Xe-135m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 7.55E-05 2.24E+03 7.55E-04 50 9.63E-01 650 6.12E-01 1.66E-07 4.40E-05 1.01E-04

Xe-135 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.40E-05 3.84E+03 2.12E-05 50 9.99E-01 650 9.86E-01 2.13E-07 5.64E-05 1.30E-04

1-131 1.27E-06 3.37E-04 7.74E-04 3.30E-04 6.73E-05 4.05E+03 1.00E-06 50 1.00E+00 650 9.99E-01 3.45E-07 9.15E-05 2.10E-04

1-132 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.14E-04 6.23E+03 8.37E-05 50 9.96E-01 650 9.47E-01 3.17E-06 8.42E-04 1.93E-03

1-133 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.09E-04 7.25E+03 9.25E-06 50 1.00E+00 650 9.94E-01 9.94E-07 2.64E-04 6.06E-04

1-134 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.81E-04 9.54E+03 2.20E-04 50 9.89E-01 650 8.67E-01 5.38E-06 1.43E-03 3.28E-03

1-135 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.95E-04 8.30E+03 2.91E-05 50 9.99E-01 650 9.81E-01 3.07E-06 8.14E-04 1.87E-03

Sr-89 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.86E-07 2.50E+02 1.59E-07 50 1.00E+00 650 1.00E+00 9.04E-11 2.40E-08 S.S1E-08

Sr-90 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.79E-08 8.OOE+00 7.58E-10 50 1.OOE+00 650 1.OOE+00 2.82E-13 7.48E-11 1.72E-10

Sr-91 1.27E-06 3.37E-04 7.74E-04 3.30E-04 1.28E-04 3.23E+02 2.03E-05 50 9.99E-01 650 9.87E-01 5.18E-08 1.37E-05 3.16E-05

Sr-92 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.51E-04 3.66E+02 7.10E-05 50 9.96E-01 650 9.55E-01 1.13E-07 3.01E-05 6.92E-05

Cs-134m 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.35E-06 1.OOE+00 6.64E-05 50 9.97E-01 650 9.5SE-01 4.14E-12 1.10E-09 2.52E-09

Cs-134 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.80E-04 1.OOE+00 1.07E-08 50 1.OOE+00 650 1.OOE+00 3.54E-10 9.40E-08 2.16E-07

Cs-136 1.27E-06 3.37E-04 7.74E-04 3.30E-04 3.92E-04 7.OOE+00 6.12E-07 50 1.OOE+00 650 1.00E+00 3.47E-09 9.21E-07 2.12E-06

Cs-137 1.27E-06 3.37E-04 7.74E-04 3.30E-04 2.86E-08 1.24E+02 7.32E-10 50 1.OOE+00 650 1.OOE+00 4.49E-12 1.19E-09 2.74E-09

Cs-138 1.27E-06 3.37E-04 7.74E-04 3.30E-04 4.48E-04 5.15E+02 3.56E-04 50 9.82E-01 650 7.93E-01 2.I8E-07 6.84E-05 1.57E-04

Total DDE 1.47E-05 3.89E-03 8.94E-03mrem

11


Internal Dose to Occupational Reactor Staff Ventilation ON and Ventilation OFF (leakage)

Committed Dose Equivalent (CDE) to the thyroid and CEDE for reactor occupational workers

in the facility for all isotopes of concern can be calculated by the following equation:

CDE or CEDE = X [ BR DCFIt Ai [1-exp{-Xefftst}] )/(XeffV)]


Room Ventilation exhaust rate 2.83 m3/s

Room Leakage rate 0.00236 m3/s

Reactor Room Volume V 1700 m3



BR Breathing rate 3.3e-4 m 3 s-1

DCFint Internal Dose Conversion Factors mrem uCi-1

Ai Released Activity per isotope uCiVentilation Constant (ventilation rate/reactor volume) 1.66E-3 s-

Xv 1

Xl Leakage Constant (leakage rate/reactor volume) 1.388E-5 s'

tst reactor worker stay time of 5 minutes (evac time) 300 s

V room volume m 3

Xj radioactive decay constant

Xeff vent Xi + Xv

Xeff leak X•i + X1,

12


CEDE Occupational Workers in Reactor from MHA Fans ON vent and Fans OFF leak On Off

CEDE (vent) CEDE (leak)Isotope

Kr-83m

Kr-85m

Kr-85

Kr-87

Kr-88

Xe-133m

Xe-133

Xe-135m

Xe-135

1-131

1-132

1-133

1-134

1-135

Sr-89

Sr-90

Sr-91

Sr-92

Cs- 134m

Cs-134

Cs-136

Cs-137

Cs-138

BR

3.30E-043.30E-04

3.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-043.30E-04

DCFint

0.00E+000.00E+0O0.OOE+O00.00E+O00.00E+000.00E+000.00E+0OO.00E+00O.OOE+003.29E+013.81E-015.85E+001.31E-01

.1.23E+006.51E+002.39E+029.32E-016.29E-014.37E-024.63E+017.33E+003. 19E+011.01 E-01

4.63E+021.08E+031.80E+012.07E+032.96E+031.46E+028.50E+032.24E+033.84E+034.05E+036.23E+037.25E+039.54E+038.30E+032.50E+02

N effvent kffleak

1.052E-04 1.765E-03 1.191E-04

4.297E-05 1.703E-03 5.685E-05

2.050E-09 1.660E-03 1.388E-05

1.514E-04 1.811E-03 1.653E-04

4.067E-03 5.727E-03 4.081E-03

3.666E-06 1.664E-03 1.755E-05

1.529E-06 1.662E-03 1.541E-05

7.554E-04 2.415E-03 7.693E-04

2.118E-05 1.681E-03 3.506E-05

1.003E-06 1.661E-03 1.488E-05

8.370E-05 1.744E-03 9.758E-05

9.255E-06 1.669E-03 2.313E-05

2.196E-04 1.880E-03 2.335E-04

2.912E-05 1.689E-03 4.300E-05

1.588E-07 1.660E-03 1.404E-05

tst

300300300300300300300

300300300300

300300300300

300300300

300300300

300300

1-exp{4-ffventtst}

4.11E-01

4.00E-01

3.92E-01

4.19E-01

8.21E-01

3.93E-01

3.93E-01

5.15E-01

3.96E-01

3.92E-01

4.07E-01

3.94E-01

4.31E-01

3.98E-01

3.92E-01

3.92E-01

3.96E-01

4.05E-01

4.04E-01

3.92E-01

3.92E-01

3.92E-01

4.54E-01

1-exp{-Xeffleaktst)

3.51E-02

1.69E-02

4.16E-03

4.84E-02

7.06E-01

5.25E-03

4.61E-03

2.06E-01

1.05E-02

4.45E-03

2.88E-02

6.92E-03

6.76E-02

1.28E-02

4.20E-03

4.16E-03

1.02E-02

2.51E-02

2.38E-02

4.16E-03

4.34E-03

4.16E-03

1.05E-01

Total CEDE mrem

0.00E+000.00E+000.00E+0O0.00E+0O_0.00E+O00.00E+O00.00E+O00.00E+O00.00E+OO6. 11E+001.08E-011.94E+00-'5.58E-024.66E-017.47E-028.78E-02

-1.38E-02-1.05E-021.98E-062.12E-032.35E-031.82E-0 12.28E-03

0.00E+O00.00E+O00.00E+O00.00E+OO0.00E+O00.00E+OO0.00E+O00.00E+O00.00E+O007.74E+001.3611-012.46E+00_7.05E-025.90-E-01.9.46E-021.11iE-011.74E-021.32E-022.51E-062.69E-032.98-E-0.32.30E-012.88E-03

8.00E+O0 7.580E-10 1.660E-03 1.388E-05

3.23E+02 2.026E-05 1.680E-03 3.414E-05

3.66E+02 7.100E-05 1.731E-03 8.488E-05

1.00E+00 6.638E-05 1.726E-03 8.026E-05

1.00E+O0 1.066E-08 1.660E-03 1.389E-05

7.00E+O0 6.123E-07 1.661E-03 1.449E-05

1.24E+02 7.325E-10 1.660E-03 1.388E-05

5.15E+02 3.565E-04 2.016E-03 3.704E-04

9.056 11.472

13


External Dose to Occupational Reactor Staff Ventilation ON and OFF (leakage)

Deep Dose Equivalent (DDE) to reactor occupational workersin the facility for all isotopes of concern can be calculated by the following equation:

DDE thy or DDEvcb= =i [ DCFCt Ai [l-exp{-Xefftst}]/,effV]


Room Ventilation exhaust rate 2.83 m3/s

Room Leakage rate 0.00236 1ml3/s

Reactor Room Volume 1700 m3


DCFext External Dose Conversion Factors mrem m 3 uCi' S-1


Ventilation Constant (ventilation rate/reactor volume) 1.66E-3 s-

Leakage Constant (leakage rate/reactor volume) 1.388E-5 s'

~t• reactor worker stay time of 5 minutes (evac time) 300 s

V room volume m3

kradioactive decay constant

keff vent k + ?1,

14


External Dose DDE to Occupational Reactor Staff Ventilation ON and OFF (leakage)

On Off

Isotope

Kr-83m

Kr-85m

Kr-85

Kr-87

Kr-88

Xe-133m

Xe-133

Xe-135m

Xe-135

1-131

1-132

1-133

1-134

1-135Sr-89

Sr-90

Sr-91

Sr-92

Cs-134m

Cs- 134

Cs-136

Cs-137

Cs-138

5.55E-09

2.74E-05

4.40E-07

1.52E-04

3.77E-04

5.07E-06

5.77E-06

7.55E-05

4.40E-05

6.73E-05

4.14E-04

1.09E-04

4.81E-04

2.95E-04

2.86E-07

2.79E-08

1.28E-04

2.51E-04

3.35E-06

2.80E-04

3.92E-04

2.86E-08

4.48E-04

4.63E+02

1.08E+031.80E+01,2.07E+032.96E+031.46E+028.50E+032.24E+033.84E+034.05E+036.23E+037.25E+039.54E+038.30E+032.50E+028.OOE+I003.23E+023.66E+021.OOE+0O1.00E+007.00E+001. 24E+025. 15E+02

N kffvent

1.05E-04 1.77E-03

4.30E-05

2.05E-09

1.51E-04

4.07E-03

3.67E-06

1.53E-06

7.55E-04

2.12E-05

1.00E-06

8.37E-05

9.25E-06

2.20E-04

2.91E-05

1.59E-07

7.58E-10

2.03E-05

7.10E-05

6.64E-05

1.07E-08

6.12E-07

7.32E-10

3.56E-04

1.70E-03

1.66E-03

1.81E-03

5.73E-03

1.66E-03

1.66E-03

2.42E-03

1.68E-03

1.66E-03

1.74E-03

1.67E-03

1.88E-03

1.69E-03

1.66E-03

1.66E-03

1.68E-03

1.73E-03

1.73E-03

1.66E-03

1.66E-03

1.66E-03

2.02E-03

Xeffleak

1.19E-04

5.68E-05

1.39E-05

1.65E-04

4.08E-03

1.75E-05

1.54E-05

7.69E-04

3.51E-05

1.49E-05

9.76E-05

2.31E-05

2.33E-04

4.30E-05

1.40E-05

1.39E-05

3.41E-05

8.49E-05

8.03E-05

1.39E-05

1.45E-05

1.39E-05

3.70E-04

tst

300

300

300

300

300

300

300

300

300

300

300

300300

300

300

300

300300

300300

300300300

1-exp{-kffventtst}

4.11E-01

4.OOE-01

3.92E-01

4.19E-01

8.21E-01

3.93E-01

3.93E-015.15E-01

3.96E-01

3.92E-01

4.07E-01

3.94E-01

4.31E-01

3.98E-01

3.92E-01

3.92E-01

3.96E-01

4.05E-01

4.04E-01

3.92E-01

3.92E-01

3.92E-01

4.54E-01

1-exp{-kffleaktstl3.51E-02

1.69E-02

4.16E-03

4.84E-02

7.06E-01

5.25E-03

4.61E-03

2.06E-01

1.05E-o02...

4.45E-03

2.88E-02

6.92E-03

6.76E-02

1.28E-02

4.20E-03

4.16E-03

1.02E-02

2.51E-02

2.38E-02

4.16E-03

4.34E-03

4.16E-03

1.05E-01

Total DDE mrem

DDE (vent)

3.52E-07

4.07E-03

1.10E-06

4.30E-029.41E-02

1.03E-04

6.82E-03

2.13E-02

2.35E-02

3.79E-02

3.55E-011.09E-01

6.19E-01

3.39E-019.94E-063.10E-08

5.72E-031.27E-02

4.61E.073.89E-05

3.82E-04

4.94E-073.05E-02

1.702

DDE (leak)

4.45E-07

5.15E-03

1.40E-065.43E-021.14E-01

1.30E-04

8.64E-03

2.67E-022.97E-02 .-4.80E-02 J4.49E-01

1.39E-017.82E-01

4.30E-01

1.26E-05

3.93E-087.24E-03

1.60E-02

5.84E-07

4.93E-05

4.83E-04

6.25E-07

3.85E-02

2.148

15


HOTSPOT Total Effective Dose Results for MHA Elevated Release

Hotspot Version 2.07.2 General Plume Elevated Release Ventilation ON

Jan 25, 2012 09:56 PM

Source Term: MUTR.mix (Mixture Scale Factor = 1.0000E+00) Noble gas

Effective Release Height : 7.25 m

Wind Speed (h=10 m) : 2.32 m/s

Wind Speed (h=H-eff) : 1.94 m/s

Stability Class :F

Receptor Height : 1.5 m

Inversion Layer Height : None

Sample Time : 10.000 min

Breathing Rate : 4.17E-04 m3/sec

Distance Coordinates : All distances are on the Plume Centerline

Maximum Dose Distance : 0.31 km

MAXIMUM TED : 1.86E-04 rem

Inner Contour Dose : 0.500 rem

Middle Contour Dose : 0.100 rem

Outer Contour Dose : 0.010 rem

Exceeds Inner Dose Out To: Not Exceeded

Exceeds Middle Dose Out To: Not Exceeded

Exceeds Outer Dose Out To: Not Exceeded

Include Plume Passage Inhalation and SubmersionInclude Resuspension (Resuspension Factor: Maxwell-Anspaugh)

Exposure Window:( Start: 0.00 hours; Duration: 0.34 hours) [100% stay time].

Initial Deposition and Dose Rate shown

Ground Roughness Correction Factor: 1.000

RespirableTime-Integrated Ground Surface Ground Shine Arrival

Distance TED Air Concentration Deposition Dose Rate Time

(km) (Rem) (Ci-sec)/m3 (uCi/m2) (rem/hr) (hour:min)

0.010 0.OE+00 O.OE+00 O.OE+00 O.OE+00 <00:01

0.025 O.OE+00 O.OE+00 0.OE+00 O.OE+00 <00:010.050 3.1E-14 8.9E-15 4.9E-18 O.OE+00 <00:01

0.100 3.OE-06 8.6E-07 5.5E-05 1.1E-09 <00:01

0.200 1.3E-04 3.7E-05 4.2E-02 8.7E-07 00:01

0.300 1.9E-04 5.3E-05 8.9E-02 1.8E-06 00:020.400 1.7E-04 4.9E-05 8.8E-02 1.8E-06 00:03

0.500 1.4E-04 4.OE-05 7.4E-02 1.5E-06 00:04

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HOTSPOT Total Effective Dose Results for MHA Ground ReleaseHotspot Version 2.07.2 General Plume Ground Release Ventilation OFF'(leakage)Jan 25, 2012 09:54 PM

Source Term: MUTR.mix (Mixture Scale Factor = 1.OOOOE+00)Effective Release Height : 0.00 mWind Speed (h=10 m) : 2.32 m/sWind Speed (h=H-eff) : 0.96 m/sStability Class : FReceptor Height : 1.5 mInversion Layer Height : NoneSample Time : 10.000 minBreathing Rate : 4.17E-04 m3/secDistance Coordinates : All distances are on the Plume Centerline

Maximum Dose Distance, : 0.065 kmMAXIMUM TED : 6.74E-03 remInner Contour Dose : 0.500 remMiddle Contour Dose : 0.100 remOuter Contour Dose : 0.010 remExceeds Inner Dose Out To: Not ExceededExceeds Middle Dose Out To: Not ExceededExceeds Outer Dose Out To: Not Exceeded

Include Plume Passage Inhalation and SubmersionInclude Resuspension (Resuspension Factor: Maxwell-Anspaugh)Exposure Window :( Start: 0.00 hours; Duration: 20.00 hours) [100% stay time].Initial Deposition and Dose Rate shownGround Roughness Correction Factor: 1.000

RespirableTime Integrated - Ground Surface GROUND SHINE ARRIVAL

Distance TED Air concentration Deposition DOSE RATE TIMEkm (rem) (Ci-sec)/m3 (uCi/m2) (rem/hr.) (Hour: min)

0.010 1.8E-03 1.6E-04 5.8E+02 1.2E-02 <00:010.025 3.8E-04 6.OE-05 8.1E+01 1.7E-03 <00:010.050 5.7E-03 1.8E-03 1.8E+01 3.8E-04 <00:010.100 5.OE-03 1.7E-03 4.1E+00 8.6E-05 00:010.200 1.6E-03 5.6E-04 9.5E-01 2.OE-05 00:030.300 7.5E-04 2.6E-04 4.1E-01 8.3E-06 00:050.400 4.2E-04 1.5E-04 2.2E-01 4.5E-06 00:060.500 2.7E-04 9.5E-05 1.4E-01 2.8E-06 00:08

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The results of all calculations for the MHA scenario are given in the Summation and Public DoseSummary Table following. In all cases the doses to the general public and to reactor staffoccupational workers are well below the annual dose limits as specified by 10 CFR 20 as well as anyguidance on doses expected from an MHA type scenario accident.

Summation of Doses for the MHA and Summary Table

MHA Condition Fans Off/Leakage

Public Dose at 100 m 200 m 300 m

CEDE mrem 1.361 0.374 0.147

DDE mrem 0.067 0.019 0.007

TEDE mrem 1.428 0.393 0.154

MHA Condition Fans On/Ventilation

Public Dose at 100 m 200 m 300 m

CEDE mrem 8.23E-05 9.73E-06 3.84E-04

DDE mrem 1.47E-05 3.89E-03 8.94E-03

TEDE mrem 9.70E-05 3.90E-03 9.32E-03

MHA Condition Fans Off Fans On

Occupational Dose 5 min 5 min

CEDE mrem 11.472 9.056

DDE mrem 2.148 1.702

TEDE mrem 13.620 10.758

Summary Table

MHA MHACondition Fans On/Ventilation mrem Condition Fans Off/Leakage mrem

Public Dose at 100 m 200 m 300 m Public Dose at 100 m 200m 300hm

CEDE mrem 8.23E-05 9.73E-06 3.48E-04 CEDE mrem 1.361 0.374 0.147DDE mrem 1.47E-05 3.89E-03 8.94E-03 DDE mrem 0.067 0.019 0.007

TEDE mrem 9.70E-05 3.90E-03 9.29E-03 TEDE mrem 1.428 0.393 0.154

HOTSPOT ANALYSIS RESULTS

MHA MHACondition Fans Off/leakage -Condition Fans ON/Ventilation

HOTSPOT at lom 100m 200m HOTSPOT at 10m 100m 200mTEDE mrem 1.83 5.00 1.00 TEDE mrem < 1.00 < 1.00 < 1.00

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