ML11189A065

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University of Maryland, Maryland, Response to Request for Additional Information in Regard to Remaining Technical Specifications
ML11189A065
Person / Time
Site: University of Maryland
Issue date: 07/05/2011
From: Al-Sheikhly M
Univ of Maryland - College Park
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11189A065 (17)


Text

NIVERSITY OF Building 090 College Park, Maryland 20742-2115 301.405.5207 TEL 301.314.2029 FAX sARYLANDe.und.edu GLENN L. MARTIN INSTITUTE OF TECHNOLOGY A. JAMES CLARK SCHOOL OF ENGINEERING Departnt/ *of,Aatetna/s Scienc and Entineenne July 5, 2011 Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555-0001

Reference:

University of Maryland, Maryland University Training Reactor ("MUTR"),

DocketNo. 50-166, License No. R-70, Technical Specifications, Response to February 18, 2011, Request for Additional Information ("RAI") Regarding Remaining Technical Specifications The University of Maryland herewith submits the following documents in connection with its application for a renewal of the MUTR license identified above:

1.

Tentative schedule for Ar-41 Measurement and Analysis and

2.

Response to the NRC Request for Further Information Regarding the Dose to Workers, Members of the Public and the Nearest Residence during Normal Operations and during an MHA Incident at the University of Maryland Training Reactor.

If you have questions about these submittals, please write me at 2309F Chemical & Nuclear Engineering Building, University of Maryland, College Park, MD 20742-2115 or email me at mohamad@umd.edu.

Please copy Prof. Robert Briber on any correspondence: 2135 Chemical &

Nuclear Engineering Building, University of Maryland, College Park, MD 20742-2115; rbriber@umd.edu.

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

Sincerely, Mohamad AI-Sheikhly Professor and Director Maryland University Training Reactor Enclosures (2) cc: Robert Briber

Tentative Schedule for Ar-41 Measurement and Analysis Fission chamber delivery - week of 4 July Ex-reactor operational testing, final assembly, installation into reactor - completed by 22 July In-core testing and calibration - completed by 29 July Reactor operation (various power levels/run times), sample collection and analysis - completed by 19 August Final dose calculations and assessment, final report - completed by 31 August

I Response to the NRC request for further information regarding the dose to workers, members of the public and the nearest residence during normal operations and during an MHA incident at the UMTR, University of Maryland Training Reactor.

Sources of radiation during normal and MHA conditions:

During normal operations in the reactor facilities, Ar-41 is produced primarily from irradiation of dissolved argon gas in the reactor pool, a fraction of which eventually evolves into the air of the reactor bay. This evolution results from the reduced solubility of argon gas in water as the water temperature increases. Additionally, Ar-41 can be generated from activated argon in air filled cavities such as the thermal column, beam-ports, and through-tube. These auxiliary systems are utilized in approximately 1% of experiments and therefore contribute a negligible amount of Ar-41 to the reactor bay in comparison to the pool generation and diffusion from the pool to the air volume in the reactor.

The UMTR is capable of exhausting the air in the reactor bay via two exhausf fans mounted on the side of the reactor building. The fans exhaust at a rate of 2.83 m3/s. During normal operations the fans are not in operation. Two conditions exist for the normal operation and MHA event: Ventilation ON (fans running), and Ventilation OFF (fans turned off). In the case of Ventilation OFF, a conservative assumption is made that there will be leakage at a rate of 5%

per hour out of the reactor bay through several cavities such as the entrance/exit doors on the ground floor and upper balcony level as well as the roll up door on the ground floor of the reactor bay.

The Maximum Hypothetical Accident, MHA that could occur as stated in the SAR is a fuel element manipulation incident that results in the failure of one fuel element in air with subsequent release of isotopes into the reactor bay volume. Values of the release of isotopes are listed in tables 13.1-13.3 of the SAR. There are 6 conditions that are considered in regards to doses to the operator, nearby member of the public and nearest residence for both an MHA and for normal operations.

During an MHA and during Normal Operations:

1. Occupational dose to workers ventilation ON
2. Occupational dose to workers ventilation OFF
3. Maximum dose to the public at the nearest residence ventilation ON
4. Maximum dose to the public at the nearest residence ventilation OFF
5. Maximum dose to a member of the public adjacent to MUTR ventilation ON
6. Maximum dose to a member of the public adjacent to MUTR ventilation OFF

2 Action taken, assumptions, formulas, and reference data are as follows:

" The production rate as stated in the SAR for Ar-41 in the reactor pool during normal operations is 0.1 Ci / 30 MWhrs operation. This rate is utilized to determine the steady state equilibrium rate of Ar-41 generation in the pool for 250 kw, 365 days, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day for a whole year

" Total Effective Dose Equivalents (TEDE) is the sum of external dose as well, (DDE) and the internal Committed Effective Dose Equivalent (CEDE);

" Building Leakage was assessed at 12 different locations in the Reactor building utilizing Drager smoke emitting air current tubes to observe the flow and direction of smoke in the reactor bay;

" A leakage rate of.05/hr was assumed out of the reactor bay with ventilation OFF;

  • Uniform mixing and instantaneous release of the nuclides during an MHA was assumed;
  • Dose Conversion Factors (DCFs) reflect those contained in IAEA Safety Series No. 115, Federal Guidance Report 11 and ICRP 68 for the isotopes in question;

" The Occupational Dose to workers is taken over 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br />;..

  • The Gaussian Plume model and Pasquill Categories of Atmospheric Stability were utilized to determine maximum concentration downwind of the reactor for doses to the nearest residence; DOSE CALCULATIONS

" The Occupational internal dose to workers:

D = C - (Br) - t. (DCF)

Where:

D

- Dose to the worker inside the reactor [rem]

C

- concentration Cv, CL ventilation and leakage [Ci/m 3]

Br

- breathing rate [m3/s]

DCF

= Dose Conversion Factor [rem/Ci]

t

= time to evacuate the building [s]

" The Occupational external dose to workers:

Dy [rads/s] = (0.057) EY, avg (MeV) X [Ci/m 3]

Where:

Dy = Gamma dose rate from the cloud in [rads/s]

3 EV, avg = Gamma ray energy in MeV X = the concentration in the cloud in [Ci/m 3]

D3 = 0. 2 3 EavgX [rads/s]

Where:

D= Beta dose rate from the cloud in [rads/s]

E avg = Average Beta ray in MeV X = the concentration in the cloud in [Ci/m3]

The maximum dose to the nearest residence:

Using the Gaussian Plume model for the ground level centerline concentration:

Q y2

- (z-h)2

_(z+h)2 X

EXP (..

)

[EXP (-- ----- ) +

EXP 7-- )]

27E(Ty0zt 20y2 2oi2.

20z2 For an elevated release, ventilation ON (fans running), and a center line concentration:

Q H2 e -----

27m:y~zýL, 2yz 2" For a ground release, ventilation OFF (leakage), and a center line concentration:

Q 271:oyy~zg The maximum ground level concentration occurs for az= H//2 Where H is defined as the effective height:

H = h + d. (v/g) 4(I+AT)/T Where h = effective release height in meters d = diameter of the outlet in meters

4 v = exit velocity of the gas m/s

[ = average wind speed m/s AT = difference in the ambient and effluent gas temperature T = temperature of the effluent gas D =frei A* (x/Q) * (Br) * (DCF)

Where:

D

= Dose to the public outside the reactor [rem]

frel

- fraction of activity released,f fL ventilation and leakage A

= total activity that could be released [Ci]

X/Q atmospheric diffusion factor [s/m 3]

Br breathing rate [m3/s]

DCF = Dose Conversion Factor [rem/Ci]

The maximum dose to person in areas adjacent -to MUTR:

Condition: a member of the public located on the lower level outside the reception room on the south side of the reactor, figure 3.4 of the SAR: in the case of ventilation ON, the only source of exposure to the individual would be from shine inside the reactor bay. In the case of ventilation OFF the individual could receive an exposure from leakage out of the reactor and shine from source terms in the reactor.

Summary of doses:

5 MHA Summary Occupational dose to workers ventilation ON = 219 mrem Occupational dose to workers ventilation OFF = 278 mrem Data MHA CEDE (worker)

MHA 1.2.Extemal Occupational Dose to Worker Shallow Dose Equivalent SDE at 7 mg/cm 2 ON OFF Beta Dose rate from the Cloud (SDE = DN) Dp = 2.45 x E-7 C E.,g e" 1o.o7 mGy/hr SDE rem SDE rem release Xo Avg Xi/v Avg Xt.A Dose X0 Dose Xv Dose XA Isotope E avn (keV) mCi x [Ci/m 3]

IMt e" 't°0'00 M[mGy/hr] Vent factor Leak factor 300s [rads] 300s[rads] 300s[rads]

Kr-85m 230 1.0760 6.3593E-07 3.3279E+01 7.9219E-01 1.0504E-03 7.870E-01 9.960E-01 8.7530E-06 6.889E-06 8.718E-06 Kr-85 228 0.0180 1.0638E-08 3.3702E+01 7.8985E-01 1.7367E-05 7.870E-01 9.960E-01 1.4472E-07 1.139E-07 1.441E-07 Kr-87 1329 2.0700 1.2234E-06 2.8316E+0)0 9.8037E-01 1.4450E-02 7.870E-01 9.960E-01 1.2041E-04 9.477E-05 1.199E-04 Kr-88 366 2.9590 1.7488E-06 1.7129E+01 8.8701E-01 5.1466E-03 7.870E-01 9.960E-01 4.2888E-05 3.375E-05 4.272E-05 Kr-89 1650 3.6380 2.1501E-06 2.1001E+00 9.8541E-01 3.1691E-02 7.870E-01 9.960E-01 2.6409E-04 2.078E-04 2.630E-04 Kr-90 800 4.1330 2.4427E-06 5.7229E+00 9.6073E-01 1.7019E-02 7.870E-01 9.960E-01 1.4182E-04 1.116E-04 1.413E-04 Xe-133 416 8.5160 5.0331E-06 1.4293E+01 9.0479E-01 1.7173E-02 7.870E-01 9.960E-01 1.4311E-04 1.126E-04 1.425E-04 Ke-135n 100 2.2430 1.3257E-06 1.1532E+02 4.4608E-01 5.3605E-04 7.870E-01 9.960E-01 4.4671E-06 3.516E-06 4.449E-06 Xe-135 302 3.8440 2.2719E-06 2.2510E+01 8.5422E-01 5.3128E-03 7.870E-01 9.960E-01 4.4274E-05 3.484E-05 4.410E-05 Sr-89 584 0.2500 1.4775E-07 8.8761E+00 9.3976E-01 7.3508E-04 7.870E-01 9.960E-01 6.1257E-06 4.821E-06 6.101E-06 Sr-91 1354 323.0000 1.9090E-04 2.7595E+00 9.8087E-01 2.2983E+00 7.870E-01 9.960E-01 1.9152E-02 1.507E-02 1.908E-02 Sr-92 1521 365.5000 2.1602E-04 2.3499E+00 9.8369E-01 2.9298E+00 7.870E-01 9.960E-01 2.4415E-02 1.921E-02 2.432E-02 Sr-93 1000 414.5000 2.4498E-04 4.1980E+00 9.7104E-01 2.1564E+00 7.870E-01 9.960E-01 1.7970E-02 1.414E-02 1.790E-02 Cs-134 156 0.8000 4.7281E-07 5.8735E+01 6.6289E-01 4.4322E-04 7.870E-01 9.960E-01 3.6935E-06 2.907E-06 3.679E-06 Cs-136 116 6.5000 3.8416E-06 9.1732E+01 5.2617E-01 2.1255E-03 7.870E-01 9.960E-01 1.7713E-05 1.394E-05 1.764E-05 Cs-137 170 124.0000 7.3286E-05 5.1725E+01 6.9623E-01 7.8631E-02 7.870E-01 9.960E-01 6.5526E-04 5.157E-04 6.526E-04 Cs-138 1239 515.0000 3.0437E-04 3.1199E+00 9.7840E-01 3.3447E+00 7.870E-01 9.960E-01 2.7873E-02 2.194E-02 2.776E-02 1-131 190.00 0.0041 2.3936E-09 4.3932E+01 7.3526E-01 3.0312E-06 7.870E-01 9.960E-01 2.5260E-08 1.988E-08 2.516E-08 1-132 270.00 0.0062 3.6820E-09 2.6420E+01 8.3115E-01 7.4903E-06 7.870E-01 9.960E-01 6.2419E-08 4.912E-08 6.217E-08 1-133 440.00 0.0725 4.2849E-08 1.3206E+01 9.1170E-01 1.5582E-04 7.870E-01 9.960E-01 1.2985E-06 1.022E-06 1.293E-06 1-134 460.00 0.0095 5.6383E-09 1.2405E+01 9.1683E-01 2.1556E-05 7.870E-01 9.960E-01 1.7963E-07 1.414E-07 1.789E-07 1-135 530.00 0.0083 4.9054E-09 1.0168E+01 9.3130E-01 2.1949E-05 7.870E-01 9.960E-01 1.8291E-07 1.439E-07 1.822E-07 I_

I Total SDE 7.151E-02 9.05OE-02

6 MHA DDE worker Gamma Contribution MHA-I 1.2.External Occupational Dose to Worker ON OFF Gamma Dose rate from the Cloud (DDE = Dy)

DDE [rem] DDE [rem]

Xo Avg Xt, Avg x Dose Xo Dose Xv Dose xL.

Isotope Eyavg(MeV)1elease mC X [Ci/m 3 I] Dy [rads/s]

Vent factor Leak factor 300s [rads] 300s: [rads]

300s [rias]

Kr-83m 0.00939 0.465 2.748E-07 1.308E-09 7.870E-01 9.960E-01 3.925E-07 3.089E-07 3.909E-07 Kr-85m 0.15118 1.076 6.359E-07 4.874E-08 7.870E-01 9.960E-01 1.462E-05 1.151E-05 1.456E-05 Kr-85 0.51400 0.018 1.064E-08 2.772E-09 7.870E-01 9.960E-01 8.317E-07 6.545E-07 8.284E-07 Kr-87 0.40256 2.070 1.223E-06 2.497E-07 7.870E-01 9.960E-01 7.491E-05 5.895E-05 7.461E-05 Kr-88 2.39210 2.959 1.749E-06 2.121E-06 7.870E-01' 9.960E-01 6.363E-04 5.008E-04 6.337E-04 Kr-89 0.22090 3.638 2.150E-06 2.408E-07 7.870E-01 9.960E-01 7.224E-05 5.685E-05 7.195E-05 Kr-90 1.11870 4.133 2.443E-06 1.385E-06 7.870E-01 9.960E-01 4.156E-04 3.271E-04 4.140E-04 Xe-133r 0.03304 0.146 8.629E-08 1.446E-09 7.870E-01 9.960E-01 4.337E-07 3.413E-07 4.319E-07 Xe-133 0.02330 8.516 5.033E-06 5.946E-08 7.870E-01 9.960E-01 1.784E-O5

'1.404E-05 1.777E-05 Xe-135r 0.42128 2.243 1.326E-06 2.831E-07 7.870E-01 9.960E-01 8.494E-05 6.685E-05 8.460E-05 Xe-135 0.25466 3.844 2.272E-06 2.933E-07 7.870E-01 9.960E-01 8.800E-05 6.925E-05 8.765E-05 Sr-89 0.00010 0.2500 1.478E-07 7.491E-12 7.870E-01 9.960E-01 2.247E-09 1.769E-09 2.238E-09 Sr-91 0.62900 323.00 1.909E-04 6.088E-05 7.870E-01 9.960E-01 1.826E-02 1.437E-02 1.819E-02 Sr-92 1.29200 365.50 2.160E-04 1.415E-04 7.870E-01 9.960E-01 4.245E-02 3.341E-02 4.228E-02 Sr-93 1.66000 414.50 2.450E-04 2.062E-04 7.870E-01 9.960E-01 6.185E-02 4.868E-02 6.161E-02 Cs-134rr 0.01792 0.5000 2.955E-07 2.685E-09 7.870E-01 9.960E-01 8.054E-07 6.339E-07 8.022E-07 Cs-134 1.39800 0.8000 4.728E-07 3.351E-07 7.870E-01 9.960E-01 1.005E-04 7.912E-05 1.O1E-04 Cs-136 1.79500 6.5000 3.842E-06 3.496E-06 7.870E-01 9.960E-01 1.049E-03 8.254E-04 1.045E-03 Cs-137 0.59510 124.00 7.329E-05 2.211E-05 7.870E-01 9.960E-01 6.633E-03 5.221E-03 6.607E-03 Cs-138 1.04100 515.00 3.044E-04 1.606E-04 7.870E-01 9.960E-01 4.819E-02 3.793E-02 4.800E-02 DDE =

I 1.799E-01 1.4i6E-01 1.792E-01

7 MHA SDE worker Beta contribution MHA 1.2.External Occupational Dose to Worker Shallow Dose Equivalent SDE at 7 mg/cm 2 ON OFF Beta Dose rate from the Cloud (SDE = Dm)

Dp = 2.45 x E-7 C E.,0 eP X 00 7 mGy/hr SDE rem SDE rem release Xo Avg XtwiV Avg Xtw/L Dose Xo Dose Xv Dose XL Isotope E.avg(keV) mCi x [Ci/m 3 ]

kt e-Ptx° 0.07 DM [mGy/hr] Vent factor Leak factor 300s [rads]

300s [rads] 300s [rads]

Kr-85m 230 1.0760 6.3593E-07 3.3279E+01 7.9219E-01 1.0504E-03 7.870E-01, 9.960E-01 8.7530E-06 6.889E-06 8.718E-06 Kr-85 228 0.0180 1.0638E-08 3.3702E+01 7.8985E-01 1.7367E-05 7.870E-01. 9.960E-01 1.4472E-07 1.139E-07 1.441E-07 Kr-87 1329 2.0700 1.2234E-06 2.8316E+00 9.8037E-01 1.4450E-02 7.870E-01 9.960E-01 1.2041E-04 9.477E-05 1.199E-04 Kr-88 366 2.9590 1.7488E-06 1.7129E+01 8.8701E-01 5.1466E-03 7.870E-01 9.960E-01 4.2888E-05 3.375E-05 4.272E-05 Kr-89 1650 3.6380 2.1501E-06 2.1001E+00 9.8541E-01 3.1691E-02' 7.870E-01 9.960E-01 2.6409E-04 2.078E-04 2.630E-04 Kr-90 800 4.1330 2.4427E-06 5.7229E+00 9.6073E-01 1.7019E-02 7.870E-0i 9.960E-01 1.4182E-04 1.116E-04 1.413E-04 Xe-133 416 8.5160 5.0331E-06 1.4293E+01 9.0479E-01 1.7173E-02 7.870E-01 9§960E-01 1.4311E-04 1.126E-04 1.425E-04 (e-135rr 100 2.2430 1.3257E-06 1.1532E+02 4.4608E-01 5.3605E-04 7.870E-01 9.960E-01,4.4671E-06 3.516E-06 4.449E-06 Xe-135 302 3.8440 2.2719E-06 2.2510E+01 8.5422E-01 5.3128E-03 7.870E-01 9.960E-01 4.4274E-05 3.484E-05 4.410E-05 Sr-89 584 0.2500 1.4775E-07 8.8761E+00 9.3976E-01 7.3508E-04 7.870E-01 9.960E-01 6.1257E-061 4.821E-06 6.101E-06 Sr-91 1354 323.0000 1.9090E-04 2.7595E+00 9.8087E-01 2.2983E+00 7.870E-01 9.960E-01 1.9152E-02 1.507E-02 1.908E-02 Sr-92 1521 365.5000 2.1602E-04 2.3499E+00 9.8369E-01 2.9298E+00 7.870E-01 9.960E-01 2.4415E-02 1.921E-02 2.432E-02 Sr-93 1000 414.5000 2.4498E-04 4.1980E+00 9.7104E-01 2.1564E+00 7.870E-01 9.960E-01 1.7970E-02 1.414E-02 1.790E-02 Cs-134 156 0.8000 4.7281E-07 5.8735E+01 6.6289E-01 4.4322E-04 7.870E-01 9.960E-01 3.6935E-06 2.907E-06 3.679E-06 Cs-136 116 6.5000 3.8416E-06 9.1732E+01 5.2617E-01 2.1255E-03 7.870E-01 9.960E-01 1.7713E-05 1.394E-05 1.764E-05 Cs-137 170 124.0000 7.3286E-05 5.1725E+01 6.9623E-01 7.8631E-02' 7.870E-01 9.960E-01 6.5526E-04 5.157E-04 6.526E-04 Cs-138 1239 515.0000 3.0437E-04 3.1199E+00 9.7840E-01 3.3447E+00 7.870E-01 9.960E-01 2.7873E-02 2.194E-02 2.776E-02 1-131 190.00 0.0041 2.3936E-09 4.3932E+01 7.3526E-01 3.0312E-06 7.870E-01 9.960E-01 2.5260E-08 1.988E-08 2.516E-08 1-132 270.00 0.0062 3.6820E-09 2.6420E+01 8.3115E-01 7.4903E-06 7.870E-01 9.960E-01 6.2419E-08 4.912E-08 6.217E-08 1-133 440.00 0.0725 4.2849E-08 1.3206E+01 9.1170E-01 1.5582E-04 7.870E-01 9.960E-01 1.2985E-06 1.022E-06 1.293E-06 1-134 460.00 0.0095 5.6383E-09 1.2405E+01 9.1683E-01 2.1556E-05 7.870E-01 9.960E-01 1.7963E-07 1.414E-07 1.789E-07 1-135 530.00 0.0083 4.9054E-09 1.0168E+01 9.3130E-01 2.1949E-05 7.870E-01 9.960E-01 1.8291E-07 1.439E-07 1.822E-07 I

I_

I I

Total SDE 7.151E-02 9.050E-02

8 Max dose to public (nearest residence) ventilation ON = 28.6 prem Max dose to public (nearest residence) ventilation OFF = 39.4 prem Data Pasquill Atmospheric Stability classes and associated values Stability Clss factors for 175,200, and 300 meters downwind on the center line I

I I

I

] oy [m]

I_[ pi

[

wlndspeed effheight (x,0) [mI A

B C

f E F

A B

r E

E IaI u

mL 1:11331 175 40 27.5 20 10 7

28 18 4

5 2.5 1314 21 7

S32551 200 45 30 22.5 12.5 8

30 20 15 5.5 3

3.14 2

7.3255 300 70 46.35 8

13 55 30 22.5 8.5 4.7 3.14 2

7.3255

[_/__ _]

Ie

-[1/2 (H/M Z1 1)40)Ira]

A B

C f

E A

II C [

175 1.4217E-04 3.2169E-041 1.9904E-03 6.3694E-031 9.0992E-03 9.6636E-01 9.2052E-01 1.8694E-011 3.4189E-01 1.3663E-02 200 1.1795E-04 2.6539E-041 4.7181E-04 4.2463E-031 6.6348E-03 9.7063E-01 9.3512E-01 8.8758E-01[ 4.1189E-01 5.0728E-02 300 4.1360E-05 1.1415E-041 2.0220E-041 18822E-031 26061E-0319,9117E-01 9.70363-01 9.4838E-01 I 8.89796-O1 2.9882E-01

_JQ [s/m'1 = [I1/uoolx x e-[1/2 (H/o)^2_

(x,0) 1m]

A a

C E.

J1 175 1.3739E-04 2,9612E-04 3.7209E-04 2.1777E-03 1.2433E-04 200 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 300 4.0995E-05 1.1079E-04 1.9177E-04 1.2983E-03 7.7355E-04 Data Max Concentration Plume Data Ventilation ON nearest Residence Part 1 Ventilation ON Max Concentration distance 200 m MHA data Plume IV 200 m Nearest Residence A 200 B 200 C 200 E 200 F 200 Nudides fv [m 3/s] fLs(t) [M 3/s]

A [Ci]

Co [Ci/m3 Q% [CisI]

QzLs%) [Cl/si X/JQ [s/m 3] X/Q [s/m 3] X/Q [s/M 3] X/Q [s/M 3] X/Q [s/.

3]

Kr-83m 2.83 0.0235 4.6500E-04 2.7482E-07 7.7775E-07 6.4583E-09 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Kr-85m 2.83 0.0235 1.0760E-03 6.3593E-07 1.7997E-06 1.4944E-08 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Kr-85 2.83 0.0235 1.8000E-05 1.0638E-08 3.0106E-08 2.5000E-10 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Kr-87 2.83 0.0235 2.0700E-03 1.2234E-06 3.4622E-06 2.8750E-08 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3,3657E-04 Kr-88 2.83 0.0235 2.9590E-03 1.7488E-06 4.9492E-06 4.1097E-08 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Xe-133m 2.83 0.0235 1.4600E-04 8.6288E-08 2.4420E-07 2,0278E-09 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Xe-133 2.83 0.0235 8.5160E-03 5.0331E-06 1.4244E-05 1.1828E-07 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Xe-135m 2.83 0.0235 2.2430E-03 1.3257E-06 3.7516E-06 3.1153E-08 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Xe-135 2.83 0.0235 3.8440E-03 2.2719E-06 6.4294E-06 5.3389E-08 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 A 200 B 200 C 200 E 200 F 200 Nudides fv[m 3/s] f Is',)[mS/s]

A [Ci]

C. [CI/mr3]

QC [Ci/s]

O4s5)

[Cl/s] X/Q[s/rm3]s]

X/ [S/

3] X/Q [s/M 3] X/Q[s/M 3

1] X/Q [s/m 31 1-131 2.83 0.0235 4.0500E-03 2.3936E-06 6,7739E-06 1.5919E-07 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 1-132 2.83 0.0235 6.2300E-03 3.6820E-06 1.0420E-05 2.4487E-07 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 1-133 2.83 0.0235 7.2500E-02 4.2849E-05 1.2126E-04 2.8497E-06 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 1-134 2.83 0.0235 9.5400E-03 5.6383E-06 1.5956E-05 3.7498E-07 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 1-135 2.83 0.0235 8.3000E-03 4.9054E-06 1.3882E-05 3.2624E-07 1.1449E-04 2.4817E-04 4.1877E-04 1.7490E-03 3.3657E-04 Data

9 Max Concentration Plume Data Ventilation ON nearest Residence Part 2

A 200 B 200 C 200 E 200 F 200 A 200 B200 C 200 E 200 F 200 X& [C

[Cml/]

& [C

[/ml/n X. [Cl/rn 3]

X [Ci/m31 X. [Cl/r 3]

[rem/hr/Ci DDE [rem]

DDE [rem]

DDE [rem]

DDE [rem]

DDE [rem]

8.9043E-11 1.9302E-10 3.2570E-10 1.3603E-09 2.6177E-10 3.2375E-02 2.8828E-12 6.2489E-12 1.0544E-11 4.4040E-11 8,4747E-12 2.0604E-10 4.4664E-10 7.5366E-10 3.1477E-09 6.0573E-10 9.0958E+01 1.8741E-08 4.0625E-08 6.8552E-08 2.8631E-07 5.5096E-08 3.4468E-12 7.4716E-12 1.2608E-11 5.2657E-11 1.0133E-11 3.3917E+00 1.1690E-11 2.5341E-11 4.2761E-11 1.7859E-10 3.4368E-11 3.9638E-10 8.5924E-10 1.4499E-09 6.0555E-09 1.1653E-09 5.2417E+02 2.0777E-07 4.5038E-07 7.5998E-07 3.1741E-06 6.1081E-07 5.6662E-10 1.2283E-09 2.0726E-09 8.6562E-09 1.6657E-09 1.2950E+03 7.3377E-07 1.5906E-06 2.6840E-06 1.1210E-05 2.1571E-06 2.7957E-11 6.0603E-11 1.0226E-10 4.2710E-10 8.2190E-11 1.6958E+01 4.7411E-10 1.0277E-09 1.7342E-09 7.2430E-09 1.3938E-09 1.6307E-09 3.5349E-09 5.9648E-09 2.4912E-08 4.7940E-09 1.8500E+01 3.0168E-08 6.5396E-08 1.1035E-07 4.6088E-07 8.8689E-08 4.2951E-10 9.3105E-10 1.5711E-09 6.5616E-09 1.2627E-09 2.4667E+02 1.0595E-07 2.2966E-07 3.8753E-07 1.6185E-06 3.1146E-07 7.3609E-10 1.5956E-09 2.6924E-09 1.1245E-08 2,1640E-09 1.4800E+02 1.0894E-07 2.3615E-07 3.9848E-07 1.6643E-06 3.2026E-07 Total DDE 1.2058E-06 2.6139E-06 4A106E-06 1.8421E-05 3.5449E-06 CED A 200 B 200 C 200 E 200 F 200 Br[m3/s]

DCF [rem/Ci]

CEDE [rem]

CEDE [rem]

CEDE [rem]

CEDE [rem]

CEDE [rem]

3.33E-04 7.4000E+02 3.4278E-09 7.4304E-09 1.2538E-08 5.2366E-08 1.0077E-08 3.33E-04 4.0700E+02 2.9001E-09 6.2864E-09 1.0608E-08 4.4304E-08 8.5256E-09 3.33E-04 7.7700E+03 6.4429E-07 1.3966E-06 2.3567E-06 9.8428E-06 1.8941E-06 3.33E-04 2.9230E+02 3.1893E-09 6.9135E-09 1.1666E-08 4.8723E-08 9.3761E-09 3.33E-04 1.7020E+03 1.6157E-08 3.5024E-08 5.9099E-08 2.4683E-07 4.7499E-08 Total CEDE 6.6997E-07 1A523E-06 2A506E-06 1.0235E-OS 1.9696E-06 TEDE 1.87S8E-061 4.0661E-061 6.8612E-06 2.8656E-05 S.514SE-06 Data Max Concentration Plume Data Ventilation OFF nearest Residence Part 1 MHA Plume Model 200 m Nearest Residence Ground Release Ventilation OFF (lea ke)

MHA data Plume IV 200 m Nearest Residence A 200 B 200 C 200 E 200 Nuclides (5%) [m 3/

A [Ci]

Co [Ci/m3]

OLl)

[Ci/s] X/Q [s/rn 3 Q [s/r 3 XQ [s/s n3 XQ [s/mr3]

X/Q [s/mr3]

Kr-83m 0.0235 4.6500E-04 2.7482E-07 6.4583E-09 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Kr-85m 0.0235 1.0760E-03 6.3593E-07 1.4944E-08 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Kr-85 0.0235 1.8000E-05 1.0638E-08 2.50OOE-10 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Kr-87 0.0235 2.0700E-03 1.2234E-06 2.8750E-08 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Kr-88 0.0235 2.9590E-03 1.7488E-06 4.1097E-08 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Xe-133m 0.0235 1.4600E-04 8.6288E-08 2.0278E-09 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Xe-133 0.0235 8.5160E-03 5.0331E-06 1.1828E-07 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Xe-135m 0.0235 2.2430E-03 1.3257E-06 3.1153E-08 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 Xe-135 0.0235 3.8440E-03 2.2719E-06 5.3389E-08 0.000118 0.0002654 0.0004718 0.0042463 0.0066348 A 200 B 200 C 200 E 200 F 200 Nudides (s%) [m 3/

A [Ci]

Co [Ci/m3]

QL(s%) [Ci/sl X/Q [s/m 3] X/Q [s/m 3] x/Q [s/r 3

m] X/Q [s/m 3]

X/JQ [s/m 3 ]

1-131 0.0235 4.0500E-03 2.3936E-06 5.6250E-08 1.1795E-04 2.6539E-04 4.7181E-04 4.2463E-03 6.6348E-03 1-132 0.0235 6.2300E-03 3.6820E-06 8.6528E-08 1.1795E-04 2.6539E-04 4.7181E-04 4.2463E-03 6.6348E-03 1-133 0.0235 7.2500E-02 4.2849E-05 1.0069E-06 1.1795E-04 2.6539E-04 4.7181E-04 4.2463E-03 6.6348E-03 1-134 0.0235 9.5400E-03 5.6383E-06 1.3250E-07 1.1795E-04 2.6539E-04 4.7181E-04 4.2463E-03 6.6348E-03 1-135 0.0235 8.3000E-03 4.9054E-06 1.1528E-07 1.1795E-04 2.6539E-04 4.7181E-04 4.2463E-03 6.6348E-03

10 Data Max Concentration Plume Data Ventilation OFF nearest Residence Part 2 F 200 A 200 B 200 C 200 E 200 F 200 A 200 B 200 C 200 E 200 F 200 XL [Ci/mr]

XL [Cl/m 3]

XL [C/rm3]

XL [Ci/m 3]

XL [Cl/m 3]

[rem/hr/Ci/I DDE [rem]

DDE [rem]

DDE [rem]

DDE [rem)

DDE [rem]

7.6178E-13 1.7140E-12 3.0471E-12 2.7424E-11 4.2850E-11 3.2375E-02 2.4662E-14 5.5491E-14 9.8650E-14 8.8785E-13 1.3873E-12 1.7627E-12 3.9661E-12 7.0509E-12 6.3458E-11 9.9154E-11 9.0958E+01 1.6034E-10 3.6075E-10 6.4134E-10 5.7721E-09 9.0189E-09 2.9488E-14 6.6348E-14 1.1795E-13 1.0616E-12 1.6587E-12 3.3917E+00 1.0001E-13 2.2503E-13 4,0006E-13 3.6005E-12 5.6258E-12 3.3911E-12 7.6300E-12 1.3565E-11 1.2208E-10 1.9075E-10 5.2417E+02 1.7775E-09 3.9994E-09 7.1101E-09 6.3991E-08 9.9985E-08 4.8475E-12 1.0907E-11 1.9390E-11 1.7451E-10 2.7267E-10 1.2950E+03 6.2775E-09 1.4124E-08 2.5110E-08 2.2599E-07 3.5311E-07 2.3918E-13 5.3816E-13 9.5672E-13 8.6105E-12 1.3454E-11 1.6958E+01 4.0561E-12 9.1263E-12 1.6224E-11 1.4602E-10 2.2816E-10 1.3951E-11 3.1390E-11 5.5805E-11 5.0224E-10 7.8475E-10 1.8500E+01 2.5810E-10 5.8072E-10 1.0324E-09 9.2915E-09 1,4518E-08 3.6745E-12 8.2677E-12 1.4698E-11 1.3228E-10 2.0669E-10 2.4667E+02 9.0639E-10 2.0394E-09 3.6255E-09 3.2630E-08 5.0984E-08 6.2973E-12 1.4169E-11 2.5189E-11 2.2670E-10 3.5423E-10 1.4800E+02 9.3201E-10 2.0970E-09 3.7280E-09 3.3552E-08 5.2425E-08 Total DDE 1.0316E-08 2.3211E-08 4.1264E-08 3.7138E-07 58028E-07 CED A 200 8200 C 200 E 200 F 200 Br1[m3/s]

DCF [rem/C]

CEDE [rem]

CEDE [rem]

CEDE [rem]

CEDE [rem]

CEDE [rem]

3.33E-04 7.4000E+02 3.5315E-09 7.9459E-09 1.4126E-08 1.2713E-07 1.9865E-07 3.33E-04 4.0700E+02 2.9878E-09 6.7226E-09 1.1951E-08 1.0756E-07 1.6806E-07 3.33E-04 7.7700E+03 6.6379E-07 1.4935E-06 2.6552E-06 2.3896E-05 3.7338E-05 3.33E-04 I 2.9230E+02 3.2859E-09 7.3932E-09 1.3143E-08 1.1829E-07 1.8483E-07 3.33E-04 I 1.7020E+03 I 1.6646E-08 3.7453E-08 6.6584E-08 5.9926E-07 9.3634E-07 Total CEDE 639024E-07 I.S530E-06 2.7610E-06 2AS49E-OS 3.8826E-O5 TEDE [rem] I 7.0056E-07 1.5763E-061 2.8022E-06

-2.-s22o E-o-5T3.9 4 06E-0 5

11 Max dose rate to public at door to reactor ventilation ON = 1.22 mremihr Max dose rate to public at door to reactor ventilation OFF = 25.86 mrem/hr Data MHA Public at the Door Gamma Contribution Ventilation ON and OFF Ventilation ON/OFF Gamma Dose rate from the volume cloud inside the reactor at door Gamma half-life Avg, [Ci/m3]

linear energ Avg, [Ci/m3]

Dosev ON DoseL OFF Nuclides Constant A [Ci]

Time [hr]

absorption

[rem/hr/Ci/m2]

coefficient 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-91 Sr-92 Sr-93 Cs-134m Cs-134 Cs-136 Cs-137 Cs-138 0.11873 0.00047 0.16013 0.00108 0.00156 1.8E-05 0.43253 0.00207 1.02453 0.00296 0.11225 0.00015 0.10297 0.00852 0.32008 0.00224 0.18947 0.00384 0.28293 0.00405 1.4274 0.00623 0.4088 0.0725 1.5728 0.00954 0.8609 0.0083 0.00008158 0.00025 0.41366 0.323 0.72002 0.3655 1.35605 0.4145 0.070448 0.0005 0.99937 0.0008 1.34384 0.0065 0.38184 0.124 1.26614 0.515 1.83 2.28598E-07 3.01502E-05 2.28776E-07 5.90721E-08 1.08185E-07 4.48 5.8871E-07 3I24794E-05 5.89185E-07 2.05174E-07 9.19869E-07 93907.2 1.06294E-08 3.84318E-05 1.06382E-08 3.60893E-11 9.14396E-07 1.271666667 9.42465E-07 3.83024E-05 9.43176E-07 8.87213E-07 1.12909E-06 0.047333333 1.19434E-07 3.02796E-05 1.19448E-07 2.66319E-07 1.26074E-08 52.512 8.565E-08 3.01502E-05 8.57209E-08 2.09249E-08 1.09886E-06 125.88 5.01508E-06 3.01502E-05 5.01923E-06 1.12392E-06 0.000141331 0.254833333 4.55118E-07 3.83024E-05 4.55342E-07 3.17051E-07 8.08361E-08 9.09 2.18562E-06 3.59732E-05 2.18741E-06 9.01286E-07 8.19821E-06 192 2.38731E-06 3.83024E-05 2.38929E-06 1.47006E-06 0.000281454 2.3 3.17656E-06 3.79142E-05 3.17906E-06 9.86846E-06 2.27148E-05 20.8 4.21077E-05 3.83024E-05 4.21425E-05 3.74645E-05 0.000779608 0.876666667 3.89429E-06 3.79142E-05 3.8971E-06 1.33306E-05 1.16949E-05 6.61 4.65322E-06 3.73966E-05 4.65702E-06 8.71874E-06 5.76718E-05 1212 1.47712E-07 3.01502E-05 1.47712E-07 2.62269E-11 1.4767E-07 9.5 0.000184102 3.83024E-05 0.000184102 0.000165748 0.000177547 2.71 0.000190608 3.46792E-05 0.000190608 0.000298698 0.000168188 0.13 4.57327E-05 0.00003235 4.57327E-05 0.000134974 8.53748E-06 2.9 2.62852E-07 3.01502E-05 2.62852E-07 4.03022E-08 2.33805E-07 18063 4.72804E-07 0.000033644 4.72804E-07 1.02838E-06 4.72795E-07 314.4 3.83738E-06 0.000031056 3.83738E-06 1.12236E-05 3.83315E-06 262800 7.3286E-05 3.83024E-05 7.3286E-05 6.09044E-05 7.32859E-05 0.54 0.00017145 0.000036232 0.00017145 0.000472463 9.65762E-05 Sub Total 0.001219713 0.001835758

12 Data MHA Public at the door Beta Contribution ON and OFF Ventilation ON/OFF Beta Dose rate from the volume cloud inside the reactor at door D13 = 1.1 x E+3 C Eavg [mrad/hr]

r i

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> exp VI,t air e"PMt Dsurf [mrad/hr] Dsurf [mrad]

2.8994E+01 0.QOOOE+00 0.OOOOE+00 O.OOOOE+00 2.9371E+01 O.OOOE+O0 O.OOOOE+00 O.OOOOE+0O 2.3374E+00 3.6114E-48 4.9925E-45 4.9925E-45 1.4708E+01 2.9816E-299 1.6226E-296 1.6226E-296 1.7223E+00 1.1015E-35 3.3227E-32 3.3227E-32 4.7975E+00 4.2128E-98 6.9996E-95 6.9996E-95 1.2224E+01 7.6822E-249 1.3676E-245 1.3676E-245 1.0325E+02 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+O0 1.9444E+01 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 7.5127E+00 3.2615E-153 2.3928E-151 2.3928E-151 2.2767E+00 6.1711E-47 1.3562E-41 1.3562E-41 1.9319E+00 6.1349E-40 1.7138E-34 1.7138E-34 3.4953E+00 1.1331E-71 2.3601E-66 2.3601E-66 5.1813E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 8.1715E+01 O.OOOE+O0 O.OOOOE+00 O.OOOOE+00 4.5502E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.5809E+00 4.1247E-53 1.3226E-47 1.3226E-47 Subtotal 3.3398E-32 3.3398E-32 Data MHA Public at the door Beta Submersion Contribution Ventilation OFF Ventilation OFF Beta submersion Dose at door 5% of Cavg DCF Isotope CO[Ci/m3]

Cavg [Ci/m3]

fCi/3

/Cm Eavg [Mev]

rem/hr

[Ci/m3]

[rem/hr/Ci/m3]

Kr-85m 6.35934E-07 5.29386E-07 2.6469E-08 0.032375 0.227 1.38196E-09 Kr-85 1.06383E-08 9.85633E-09 4.9282E-10 90.95833333 0.251 2.84503E-11 Kr-87 1.2234E-06 1.2234E-06 6.117E-08 3.391666667 1.27 1.78678E-08 Kr-88 1.74882E-06 1.34825E-06 6.7412E-08 524.1666667 0.28 4.34136E-09 Kr-89 2.15012E-06 1.46857E-07 7.3429E-09 1295 1.4 2.36441E-09 Kr-90 2.44267E-06 2.42662E-06 1.2133E-07 16.95833333 0.8 2.23249E-08 Xe-133 5.0331E-06 5.01927E-06 2.5096E-07 18.5 0.1 5.77216E-09 Xe-135m 1.32565E-06 4.55344E-07 2.2767E-08 246.6666667 0.1 5.23645E-10 Xe-135 2.27187E-06 2.18743E-06 1.0937E-07 148 0.28 7.04351E-09 I

I Subtotal 6.16482E-08

13 Data MHA Public at Door Vent OFF Ventilation OFF Gamma submersion dose at door what Gamma leaks out submersion 5% of dose lhr OFF OFF C rads Ey, avg (MeV) 1.14E-08 1.96045E-07 0.00939 2.95E-08 8.12881E-06 0.15118 5.32E-10 4.99012E-07 0.514 4.72E-08 3.465E-05 0.40256 5.97E-09 2.60758E-05 2.3921 4.29E-09 1.72808E-06 0.2209 2.51E-07 0.000512426 1.1187 2.28E-08 1.37304E-06 0.033042 1.09E-07 4.65122E-06 0.0233 1.19E-07 8.28576E-05 0.38 1.59E-07 0.000193511 0.667 2.11E-06 0.002192175 0.57 1.95E-07 0.000257134 0.723 2.33E-07 0.000359549 0.846 Subtotal 0.003674956 Data MHA Public at Door Ventilation OFF Ventilation OFF Internal dose public at the door Br [m 3/s]

tevac [s]

DCF [rem/Ci]

DpL 3600s [rem]

0.000333 3600 740 0.000105978 0.000333 3600 407 7.75551E-05 0.000333 3600 7770 0.019627172 0.000333 3600 292.3 6.82789E-05 0.000333 3600 1702 0.000475099 Subtotal 0.020354083

14 Normal Operations Summary The occupational dose to the worker with ventilation OFF assumes that 100% of the Ar-41 readily diffuses out of the water and into the reactor volume. Air and Water sampling during operation at full power has shown that the majority of the Ar-41 remains in the pool and is not diffused to the atmosphere, therefore a factor of at least 1/4 can be applied to the activity in the reactor bay due to Ar-41 production in the pool. For 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> of operation the dose to workers is:

Occupational dose to workers ventilation ON = 19.6 mrem Occupational dose to workers ventilation OFF = 289 mrem Calculation:

The Argon-41 production rate is stated as 0.1 Ci/30 MWhrs For a member of the public located on the lower level outside the double doors on the south side of the reactor in the case of ventilation ON,the only source of exposure to the individual would be from shine inside the reactor bay. In the case of ventilation OFF the individual could receive an exposure from leakage out of the reactor and from any shine from Ar-41 production inside the reactor.

Annual dose to the public at the door to the reactor, ventilation ON = 3.71 mrem Annual dose to the public at the door to the reactor, ventilation OFF will be determined by air sampling and quantification of Ar-41 over the pool and in the reactor bay volume, with subsequent dose calculation. The reactor is currently not operating in order to install new fission chamber elements. Upon start up Ar-41 will be collected by grab sample and measured through HpGe and Nal gamma spectroscopy.

Doses to the public located at the nearest residence from elevated releases (ventilation ON) and from a ground release (ventilation OFF) is calculated using the Gaussian Plume model.

Max dose to public (nearest residence) ventilation ON = 6.33 mrem Max dose to public (nearest residence) ventilation OFF = 0.200 mrem

15