Text

& Big Rock Point, Submittal of 2011 Annual Radioactive Effluent Release and Waste Disposal Report
	ML12121A010
Person / Time
Site:	Palisades, Big Rock Point File:Consumers Energy icon.png
Issue date:	04/26/2012
From:	Gustafson O; Entergy Nuclear Operations
To:	; NRC/FSME, Office of Nuclear Reactor Regulation, Document Control Desk
References
	PNP 2012-032
	Download: ML12121A010 (261)
	v • d • e

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant Entei 27780 Blue Star Memorial Highway Covert, Ml 49043 Tel 269 764 2000 Otto W. Gustafson Licensing Manager PNP 2012-032 April 26, 2012 10 CFR 50.36a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

2011 Annual Radioactive Effluent Release and Waste Disposal Report Palisades Nuclear Plant Big Rock Point Docket 50-255 Dockets 50-1 55 and 72-043 License No. DPR-20 License No. DPR-6

Dear Sir or Madam:

Attached are the Entergy Nuclear Operations, Inc. 2011 Annual Radioactive Effluent Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are submitted in accordance with 10 CFR 50.36a(a)(2). contains the report for PNP. Attachment 2 contains the report for the BRP ISFSI.

These reports provide a summary of the quantities of radioactive liquid and gaseous effluent releases and solid radioactive waste processed during the period of January 1, 2011, through December 31, 2011.

Document Control Desk Page 2 This letter contains no new commitments and no revision to existing commitments.

Sincerely, OWG/bed : Palisades Nuclear Plant 2011 Radioactive Effluent Release Report : Big Rock Point Independent Spent Fuel Storage Installation 2011 Radioactive Effluent Release Report CC Administrator, Region Ill, USNRC Project Manager, Palisades, USNRC Resident Inspector, Palisades, USN RC NRC NMSS Project Manager American Nuclear Insurers (ANI)

ATTACHMENT 1 PALISADES NUCLEAR PLANT 2011 RADIOACTIVE EFFLUENT RELEASE REPORT 2011 Plant Oneratina History Palisades Nuclear Plant (PNP) entered the reporting period on line on January 1, 2011, at nominal full power (NFP). PNP reduced power to approximately 54% on January 8, 2011, due to failure of breaker 252-302, that resulted in loss of cooling tower pump P-39A. On January 16, 2011, the plant returned to NFP. PNP tripped on January 22, 2011, due to a ground fault from one of the main generator cables. The unit returned to NFP on January 25, 2011. PNP reduced power to 52% on March 16, 2011, to perform electrical cable testing for startup transformers. The unit returned to NFP on March 18, 2011. PNP began reducing power and subsequently manually tripped the unit on September 16, 2011, due to exceeding 10 gallons per minute unidentified leakage from the primary coolant system. The unit returned to NFP on September 21, 2011. An automatic reactor trip occurred on September 25, 2011, due to a loss of two of the four preferred AC buses. The unit returned to NFP on October 3, 2011. The unit was manually tripped on December 14, 2011, due to main feed pumps tripping on low suction pressure. The unit returned to NFP on December 17, 2011. PNP was on line for the remainder of 2011. The unit generated 6,641,013 MWHrs of net electrical energy during 2011.

A. Gaseous Effluents Tables A-i, Gaseous Effluents Summation of All Discharges, A-iA, Gaseous Effluents Ground-Level Release Batch Mode, and A-i B, Gaseous Effluents Ground-Level Release Continuous Mode, list and summarize gaseous effluents released during this reporting period.

B. Liquid Effluents Tables A-2, Liquid Effluents Summation of All Discharges, A-2A, Liquid Effluents Batch Mode, and A-2B, Liquid Effluents Continuous Mode, list and summarize liquid effluents released during this reporting period.

C. Solid Waste Storage and Shipments Table A-3, Low-Level Waste for Waste Classification A, B and C, summarizes solid radioactive waste shipped for processing or burial in 2011 for the following waste streams: resins, filters and evaporator bottoms, dry active waste, irradiated components, other waste, and sum of all waste.

Page 1 of 6

D. Dose Assessments Tables A-4, Dose Assessments, 10 CFR Part 50, Appendix li and A-5, EPA 40 CFR Part 190, Individual in the Unrestricted Area, lists annual dose to the members of the public.

E. Sulemental Information Abnormal Discharges In December 2007, tritium was detected in a groundwater monitoring well at a level of 22,000 pCi/L. The source of the activity is leakage associated with T-91, the utility water storage tank, and associated piping. T-91 is used to store processed liquid waste prior to discharge. No radionuclides other than tritium have been detected in the groundwater.

Additional repair of underground piping was performed during the spring of 2011. The overflow line to T-91 was sleeved to ensure piping integrity. This line was assumed to be dry, based on all indication, but contained highly tritiated water of which a small amount was expelled during the sleeving operation. This resulted in an additional release of tritiated water to the groundwater which caused spiking in monitoring well 3. This event is further discussed under section 9 of this report.

Monitoring of the groundwater tritium plume continues in order to determine repair effectiveness and to ensure the accuracy of the site hydrology.

Depth to Local Water Table The depth is approximately eight to nine feet.

Classification of Subsurface Aquifers Not used for drinking water.

Expected Movement/Mobility of Groundwater Plume Westerly direction down-gradient toward Lake Michigan at approximately two feet per day.

Land Use Characteristics PNP site property, water not used for drinking or irrigation.

NRC Notification, Date and Contact Organization The NRC was notified on December 10, 2007, by PNP.

2. Non-Routine Planned Discharges None.

Page 2 of 6

3. Radioactive Waste Treatment System Changes None.

4. Annual Land Use Census Changes The garden critical receptor is now located in the southeast sector at 1.47 miles. The residence critical receptor is unchanged. Also unchanged is that there are no beef cattle, dairy cows or goats located within five miles of the plant.

5. Effluent Monitoring System Inoperability There were no effluent monitors that were out of service for greater than 30 days.

6. Offsite Dose Calculation Manual (00CM) Changes The Offsite Dose Calculation Manual was revised during the report period.

The Offsite Dose Calculation Manual, Appendix A, was revised twice during the report period. The General Manager Plant Operations approval is documented on the procedure cover page.

These revisions did not reduce the accuracy or reliability of dose calculations or setpoint determinations. Enclosure 1 contains a copy of the ODCM revision, as well as copies of ODCM, Appendix A revisions 16 and 17, with changes indicated by marginal markings.

7. Process Control Program Changes None.

8. Errata/Corrections to Previous Reports Attachment 1, Table A-i B, Gaseous Effluents Ground Level Release, Continuous Mode Revised for 2010 data is supplied here in its entirety and is associated with CR-PLP-201 1-05094. The 2010 data for Table A-i, Gaseous Effluents Sum of all releases remains correct.

Page 3 of 6

Section E. Supplemental Information, 1. Abnormal Discharges to the 2010 report was updated per the guidance of CR-PLP-201 1-5094 and is provided here as follows:

In December 2007, tritium was detected in a groundwater monitoring well at a level of 22,000 pCiIL. The source of the activity is leakage associated with T-91, the utility water storage tank, and associated piping. T-91 is used to store processed liquid waste prior to discharge. No radionuclides other than tritium have been detected in the groundwater. Tritium is still being released to the environment (Lake Michigan) via an unmonitored pathway, as demonstrated by the continued detection of monitoring well sample activityPiping leaks associated with T-91 have been repaired and monitoring of the groundwater tritium plume continues in order to determine repair effectiveness and to ensure site hydrology accuracy. However, repairs h-ave been made and tlritium concentrations have dropped to approximately 90%

of values detected in previous years. A definitive release rate or total activity released cannot be determined.

Section D. Dose Assessments, of the 2010 report was updated per the guidance of CR-PLP-2011-5094 and is provided here as follows:

Tables A-4, Dose Assessments, 10 CFR Part 50, Appendix I, and A-5, EPA 40 CFR Part 190, Individual in the Unrestricted Area, lists annual dose to the members of the public. A methodology change was made in determining the radionuclides released through the Main Stack. The Stack radionuclides were linked directly to PrimaR Coolant System gas sample results instead of being considered all Xe-133. This change led to approximately seven additional radionuclides being considered as released.

These additional radionuclides have different dose conversion factors which had a direct impact on the calculated beta and gamma doses.

Conceriatively, 0.5% of the total tritium activity roleacod via batch releases, or half of the percentage that was used in 2007, 2008, and 2009, was used for 2010 effluent calculations.

9. Other Groundwater Monitoring PNP installed five groundwater monitoring wells in 2007, and added an additional nine wells in 2008. These wells were strategically placed within the owner controlled area, both inside and outside the protected area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems. Monitoring well (MW) 3 is most indicative of the leak described in the Abnormal Discharges section. Tritium levels for 2011 Page 4 of 6

in MW3 ranged from less than minimum detectable activity (MDA) to 19,854 pCi/L. Monitoring wells MW2 and MW1 1 tritium levels ranged from <MDA to 1,888 and 3,850 pCi/L respectively. The remaining wells showed no activity throughout the year. The spike in MW3 was associated with additional work done on T-91 piping during 2011. Well locations are depicted in Figure 1.

Carbon-14 In 2010, PNP and other facilities participated in an EPRI task force to build a model to accurately estimate gaseous C-14 releases, given some key site-specific plant parameters (mass of the primary coolant, average thermal neutron cross section, rated MW, etc). This work was completed in November 2010. The estimates for C-i 4 were constructed using the aforementioned EPRI methodology contained with EPRI 1021106, Estimation of Carbon-i4 in Nuclear Power Plant Gaseous Effluents. Using the C-14 curie estimates, the annual dose to man was derived from guidance contained within Regulatory Guide 1.109. Because the dose contribution of C-14 from liquid radioactive waste is much less than that contributed by gaseous radioactive waste, evaluation of C-14 in liquid radioactive waste is not required. (Reg Guide 1.21, Rev 2)

Annual C-14 release PNP and subsequent doses for 2011:

Total Gaseous C-14 Released Curies = 8.13 Gaseous C-14 as C02 Curies = 2.44 Effective Child TB Dose, C-14 mrem 0.0219 Effective Child Bone Dose, C-14 mrem = 0.110 The quarterly curies released are provided in Tables A-iA and A-lB.

Airborne doses due to C-14 are grouped under the category of Particulate, Iodine, and Tritium, which are contained in Table A-4.

Page 5 of 6

C) 0 C

z 0

-D m

9)

(0 (p

0,i 0) 0

-h -Ic

0) Or C) m r

r r

0 C,

0 z

Cl)

ATTACHMENT 1 Palisades Table A-i 2011 Gaseous Effluents Sum of All Releases Summation of All Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Uncertainty Total

(%)

Fission and Activation Gases Ci 4.97E-01 9.47E-01 5.30E+00 3.65E+00 1.04E+O1 Average Release Rate pCi/s 6.40E-02 1 .20E-O1 6.66E-01 4.60E-01 3.30E-O1

% of Limit 7.46E-04 8.57E-04 1 .60E-03 6.81 E-03 2.52E-03 Total 1-131 Ci 7.47E-05 2.66E-05 6.27E-05 8.29E-05 2.47E-04 Average Release Rate pCi/s 9.61 E-06 3.38E-06 7.88E-06 1.04E-05 7.83E-06

% of Limit 1.16E-05 408E-06 9.50E-06 1.26E-05 9.43E-06 Particulates Ci 8.1 1 E-07 1 .01 E-07 4.91 E-05 0.OOE+00 5.OOE-05 Average Release Rate pCi/s 1.04E-07 1.28E-08 6.17E-06 0.OOE÷00 1.58E-06

% of Limit % 1 .24E-07 3.80E-08 5.93E-05 0.OOE+00 1 .50E-05 Tritium Ci 5.37E÷00 4.84E÷00 4.48E+00 3.96E-i-00 1 .87E÷01 4.08 Average Release Rate pCi/s 6.91E-01 6.16E-01 5.64E-01 4.98E-01 5.91E-01

% of Limit 1 .66E-03 1 .48E-03 1 .36E-03 1 .20E-03 1 .43E-03 GrossAlpha Ci ND 1.89E-06 1.19E-07 1.70E-07 2.18E-06 C-14 Ci 1.96E+00 2.15E+00 1.92E+00 2.1OE+00 8.13E+00 Average Release Rate pCi/s 2.52E-01 2.73E-01 2.42E-01 2.64E-01 2.58E-01

% of Limit 2.02E-06 2.20E-06 1.94E-06 2.12E-06 2.07E-06 Page 1 of 1

ATTACHMENT 1 Palisades Table A-i A 2011 Gaseous Effluents Ground Level Release, Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Gases Ar-41 Ci ND ND ND ND Kr-85 Ci ND ND ND ND Kr-85m Ci ND ND ND ND Kr-87 Ci ND ND ND ND Kr-88 Ci ND ND ND ND Xe-131m Ci 4.29E-04 1.23E-02 3.08E-02 2.79E-03 Xe-133 Ci 1.96E-02 3.11E-01 3.70E+00 2.39E-01 Xe-133m Ci ND ND 3.13E-02 2.95E-03 Xe-135 Ci ND ND 1.39E-01 ND Xe-135m Ci ND ND ND ND Xe-i 38 Ci ND ND ND ND Total Ci 2.01 E-02 3.23E-01 6.85E+00 2.45E-01 lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci ND ND 9 .54E-07 1 .68E-06 1-132 Ci ND ND ND ND 1-133 Ci ND ND 9.21 E-07 ND 1-134 Ci ND ND ND ND 1-135 Ci ND ND ND ND Total Ci 0.OOE+00 0.OOE+00 1 .88E-06 1 .68E-06 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Co-58 Ci ND ND 2.1 9E-05 ND Co-60 Ci ND ND 3.39E-06 ND Cr-Si Ci ND ND 1.08E-05 ND Nb-95 Ci ND ND 5. 64E-06 ND Zr-95 Ci ND ND 9.34E-06 ND Cs-i 37 Ci ND ND ND ND Total Ci 0.00 E+00 0.OOE+00 4.91 E-05 0.000E+00 Tritium Ci NA NA 2.21 E-01 NA I Gross Alpha Ci NA NA NA I NA C-14 J Ci NA NA NA NA ND Measurements performed but no activity detected.

NA = Analysis not required and not performed.

Page 1 of 1

ATTACHMENT 1 Palisades Table A-i B 2011 Gaseous Effluents Ground Level Release, Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Gases Ar-41 Ci 8.03E-02 3.27E-02 4.66E-02 i.38E+OO Kr-85 Ci ND ND ND ND Kr-85m Ci 3.86E-03 i.03E-02 4.73E-03 2.27E-02 Kr-87 Ci i.61E-02 3.50E-02 2.18E-02 3.92E-02 Kr-88 Ci 4.59E-02 6.76E-02 i.03E-O1 2.81E-O1 Xe-131m Ci ND ND ND ND Xe-133 Ci 7.45E-03 i.35E-02 ND 6.28E-02 Xe-133m Ci ND ND ND ND Xe-135 Ci l.29E-Oi 1.80E-O1 8.08E-O1 6.33E-O1 Xe-135m Ci 6.13E-02 8.58E-02 2.35E-O1 2.44E-Oi Xe-138 Ci 1.33E-O1 i.99E-Oi 1.75E-O1 7.42E-Ol Total Ci 4.77E-O1 6.24E-Oi 1.39E+OO 3.41 E+OO dines/Halogens U n its Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-13 1 Ci 7.47E-05 2.66E-05 6.1 7E-05 8.12E-05 1-132 Ci ND ND ND ND 1-133 Ci 9.23E-05 5.23E-05 1 .76E-04 1 .98E-04 1-134 Ci ND ND ND ND 1-135 Ci ND ND ND ND Total Ci 7.47E-05 7.89E-05 2.38E-04 2.80E-04 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Co-58 Ci 1.51 E-08 ND ND ND Co-60 Ci ND 4.90E-08 ND ND Sr-89 Ci ND ND ND ND Ag-hOrn Ci ND 5.20E-08 ND ND Cs-i 34 Ci ND ND ND ND Cs-i37 Ci 7.96E-07 ND ND ND Total Ci 8.iiE-07 1.01 E-07 0.OOE+OO O.OOE+0O Tritium jCi j 5.37E+OO 4.84E+OO 4.26E+OO 3.96E+OO GrossAlpha Ci ND 1.89E-06 1.19E-07 i.70E-07 C-14 Ci 1.96E÷OO 2.i5E+OO 1.92E+OO 2.iOE+OO ND = Measurements performed but no activity detected.

Page 1 of 1

ATTACHMENT 1 Palisades Table A-i B I 2011 2010 Revised Gaseous Effluents Ground Level Release, Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Gases Ar-41 1560E-Oi 2.785E-Oi 5.591E+OO 1.800E÷OO Kr-85 ND ND ND ND Kr-85m 6.227E-02 5.112E-02 2.851E-O1 i.149E-03 Kr-87 Ci 1 .638E-Oi 1 .397E-Oi 9.585E-Oi 3.328E-03 Kr-88 2.030E-Oi 1.343E-Oi i.126E+OO 5.918E-O1 Xe-i 31 m ci ND ND ND Xe-i33 9.i62E-Oi 5.23iE+OO 1,497E+OO 1.O3iE÷Oi Xe-i33m Gi ND ND ND ND Xe-i35 Ci 7048E-Oi i.816E+OO 3.8i3E÷OO 3.728E÷OO Xe-i35m 2.594E-Oi 9.343E-Oi i.529E+OO 2.423E-02 Xe-i 38 6697E-Oi 4.755E-Oi 4.066E÷OO 7499E-02 Total Ci 3.135E+OO 9.O6iE+OO 1.887E+Oi i.653E+O1 lodines/Haloaens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 1-131 Ci 7.439E-05 6.465E-04 6.027E-04 3.872E-03 1-132 Ci ND ND ND 3.975E-03 1-133 Ci 2.007E-04 2.990E-04 2.389E-04 2.300E-04 1-134 Ci ND ND ND ND 1-135 Ci ND ND ND ND Total Ci 2.75 1 E-04 9.455E-04 8.41 6E-04 8.077E-03 Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Co-58 Ci ND ND ND 1 .510E-06 Co-60 Ci ND ND 8.61 OE-08 ND Sr-89 Ci ND ND ND ND Sr-90 Ci ND ND ND ND Cs-i 34 Ci ND ND ND ND Cs-i 37 Ci 1 .094E-08 ND ND ND Total Ci 1 .094E-08 O.000E+OO 8.61 OE-08 1 .510E-06 I Tritium I 5.144E+OO 4.693E+OO 4.873E+OO 7.726E+OO Gross Alpha Ci 5.125E-O7jND ND 5511 E-07 C-14 I C 2.117E+OO 1.980E+OO 2.099E+OO i.495E+OO ND = Measurements performed but no activity detected.

Page 1 of 1

ATTACHMENT 1 Palisades Table A-2 2011 Liquid Effluents Sum of All Releases Summation of All Liquid Releases Uncertainty Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)

Fission and Activation Products (excluding tritium, gases, and gross alpha) Ci 4.55E-03 1.65E-03 1.56E-03 1.29E-02 2.06E-02 Average Concentration pCi/mi 1.17E-10 4.28E-11 4.1OE-11 5.73E-10 1.50E-10

% of Limit % 1 .26E-03 7.09E-04 6.34E-04 4.04E-03 1 .39E-03 Tritium Ci 6.98E÷01 5.47E+01 1.63E÷02 3.12E+02 6.OOE+02 Average Concentration pCi/mi 1 .79E-06 1 .42E-06 4.30E-06 1 .39E-05 4.34E-06

% of Limit % 1 .79E-01 1 .42E-01 4.30E-01 1 .39E÷00 4.34E-01 Dissolved and Entrained Gases Ci 0.OOE+00 0.OOE+00 0.OOE÷00 6.08E-04 6.08E-04 Average Concentration pCi/mi 0.OOE÷00 0.OOE÷00 0.OOE÷00 2.71E-11 4.41E-12

% Of Limit 0.OOE+00 0.OOE÷00 0.OOE+00 1 .35E-05 2.20E-06 Gross Alpha Ci 7.85E-06 0.OOE+00 2.OOE-05 1 .69E-05 4A8E-05 Average Concentration pCi/mi 2.O1E-13 0.OOE+00 5.27E-13 7.54E-13 3.24E-13 Volume of Primary System Liquid Effluent (Before Dilution) Liters 3.49E+05 2.34E+05 8.22E+05 1 .07E+06 2.48E+06 Dilution Water Used for Above Liters 3.90E÷1 0 3.86E÷1 0 3.79E+1 0 2.25E+1 0 1 .38E+1 1 Volume of Secondary or Balance-of-Plant Liquid Effluent (e.g., low-activity or unprocessed)

(Before Dilution) Liters 7.84E+09 7.93E+09 1 .01 E+1 0 8.01 E+09 3.39E+1 0 Average Stream Flow m

/

3 s 5.02E+00 4.91 E+00 4.77E+00 2.83E÷00 4.38E+00 Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x mm/day Page 1 of 1

ATTACHMENT 1 Palisades Table A-2A 2011 Liquid Effluents Batch Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Products Cr-51 Ci ND ND ND ND Mn-54 Ci ND ND ND 2.35E-04 Fe-55 Ci 7.82E-04 i.80E-04 2.86E-04 4.80E-04 Fe-59 Ci ND ND ND ND Co-57 Ci ND ND ND ND Co-58 Ci i.67E-03 1.56E-04 9.77E-05 4.19E-03 Co-60 Ci 9.68E-04 5.29E-04 4.11E-04 1.40E-03 Sr-89 Ci ND 1.24E-05 4.08E-06 2.50E-05 Sr-90 Ci ND ND ND 4.90E-05 Nb-95 Ci i.31E-04 ND ND ND Ag-il Om Ci 2.45E-04 4.99E-04 3.30E-04 2.09E-04 Sn-1i3 Ci ND ND ND ND Sb-124 Ci ND ND ND ND Sb-125 Ci ND ND ND ND 1-131 Ci ND ND ND ND 1-133 Ci ND ND ND ND 1-135 Ci ND ND ND ND Cs-134 Ci ND ND ND ND Cs-137 Ci ND ND 2.43E-05 1.89E-05 Ni-63 Ci 6.25E-04 1.12E-04 3.90E-04 6.27E-03 Zn-65 Ci ND ND ND ND Zr-95 Ci 2.49E-04 ND ND ND La-140 Ci ND ND ND ND Totals Ci 4.53E-03 i.49E-03 i.54E-03 1.29E-02 Dissolved and Un its Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-85 Ci ND ND ND ND Xe-i 31rn Ci ND ND ND ND Xe-i 33 Ci ND ND ND 6.08E-04 Xe-i 33m Ci ND ND ND ND Xe-i35 Ci ND ND ND ND Totals 0.00 E+00 0.OOE+00 0.00E÷00 6.08E-04 Tritium j Ci 6.98E÷Oi 5.47E÷01 1.63E+02 3.12E+02

, Gross Alpha Ci 7.85E-06 ND 2.OOE-05 1 .69E-05 ND = None Detected Page 1 of 1

ATTACHMENT 1 Palisades Table A-2B 2011 Liquid Effluents Continuous Mode Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Products Cr-51 Ci ND ND ND ND Mn-54 Ci ND ND ND ND Fe-55 Ci ND ND ND ND Co-58 Ci ND ND ND ND Co-60 Ci 8.78E-07 ND ND ND Sr-89 Ci ND ND ND ND Sr-90 Ci ND ND ND ND Nb-95 Ci ND ND ND ND Ag-ibm Ci ND ND ND ND Sn-113 Ci ND ND ND ND Sb-124 Ci ND ND ND ND Sb-125 Ci ND ND ND ND 1-131 Ci ND ND ND ND 1-133 Ci ND ND ND ND 1-135 Ci ND ND ND ND Cs-i 34 Ci ND ND ND ND Cs-137 Ci 2.iOE-05 ND i.20E-05 ND Ni-63 Ci ND i.63E-4 ND ND Totals Ci 2.19E-05 i.63E-4 120E-05 O.OOE-i-OO Dissolved and Un its Quarter 1 Quarter 2 Quarter 3 Quarter 4 Entrained Gases Kr-85 Ci ND ND ND ND Xe-i 33 Ci ND ND ND ND Xe-i 33m Ci ND ND ND ND Xe-i 35 Ci ND ND ND ND Xe-i 35m Ci ND ND ND ND Totals O.000E+OO O.000E+OO 0. 000 E+00 0.000E+00 Tritium Ci 2.59E-02 4.07E-02 I 4.41 E-02 8.i2E-03 Gross Alpha Ci ND ND ND ND ND = None Detected Page 1 of 1

ATTACHMENT 1 Palisades Table A-3 2011 Low Level Waste Resins, Filters, and Volume Curies Shipped Evaporator Bottoms Waste Class 3 ft 3 m Curies A 3.41 E÷02 9.66E+00 8.80E-04 B 1 .60E÷02 4.53E÷00 2.74E+02 C 0.OOE+00 0.OOE+00 0.OOE+00 ALL 5.01 E+02 i.42E+0i 2.74E+02 Major Nuclides for the Above Table: Mn-54 (2%), Fe-55 (2%), Co-58 (16%), Co-60 (45%),

Ni-63 (14%), Ag-ibm (2%), Sb-125 (3%), Cs-134 (9%), & Cs-i 37(7%)

Dry Active Waste Volume Curies Shipped Waste Class 3 ft 3 m Curies A 8.95E+03 2.54E+02 7.43E-01 B 1.47E+01 4.16E-Oi 1.03E+00 C 9.32E+00 2.64E-0i 3.20E+00 ALL 8.97E÷03 2.55E÷02 4.97E+00 Major Nuclides for the Above Table: H-3 (13%), C-i 4 (2%), Fe-55 (14%), Co-58 (1 %),

Co-60 (7%), Ni-63 (59%), Sr-gO (1%), Ag-ibm (1%), & Cs-i 37 (2%)

Irradiated Components Volume Curies Shipped Waste Class 3 ft 3 m Curies A 0.OOE+00 0.OOE÷00 0.OOE+00 B 0.OOE+00 0.OOE+0O 0.OOE+00 C 0.OOE÷00 0.OOE+00 0.OOE+00 ALL 0.OOE+00 0.OOE+00 0.OOE+00 Major Nuclides for the Above Table:

Other Waste: Used oil & soil Volume Curies Shipped Waste Class 3 ft 3 m Curies A 1 .73E+03 4.90E+01 3.23E+00 B 0.OOE÷00 0.OOE+00 0.OOE+00 C 0.OOE+00 0.OOE+00 0.OOE+00 ALL 1.73E÷03 4.90E÷01 3.23E÷00 Major Nuclides for the Above Table: H-3 (47%), Fe-55 (7%), Co-58 (ii %), Co-60 (7%),

Ni-63 (11%), Sr-90 (2%), Nb-95 (1%), Sb-125 (5%), Cs-i37 (7%) & Ce-144 (2%)

Page 1 of 2

ATTACHMENT 1 Palisades Table A-3 2011 Low Level Waste Sum of All Low-Level Volume Curies Shipped Waste Shipped from Site Waste Class 3 ft 3 m Curies A 1.1OE+04 3.13E+02 3.97E+OO B 1 .75E+02 4.95E--OO 2.75E+02 C 9.32E+OO 2.64E-O1 3.20E+OO ALL 1.12E+04 3.18E÷02 2.82E+02 Major Nuclides for the Above Table: H-3 (1%), Mn-54 (3%), Fe-55 (2%), Co-58 (16%),

Co-60 (44%), Ni-63 (14%), Ag-hOrn (2%), Sb-125 (3%), Cs-134 (9%), & Cs-137 (6%)

Page 2 of 2

ATIACHMENT 1 Palisades Table A-4 2011 Dose Assessments, 10 CFR Part 50, Appendix I Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly Liquid Effluent Dose Limit, Total 1 .5 mrem 1.5 mrem 1.5 mrem 1 .5 mrem 3 mrem Body Total Body Dose 4.66E-04 2.74E-04 3.05E-04 1 .45E-03 2.50E-03

% Of Limit 0.03% 0.02% 0.02% 0.10% 0.08%

Liquid Effluent Dose Limit, Any 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem Organ Organ Dose 9.74E-04 2.80E-04 3.53E-04 2.62E-03 4.23E-03

% of Limit 0.02% 0.01% 0.01% 0.05% 0.04%

Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad Gamma Air Gamma Air Dose 2.48E-04 3.17E-04 5.87E-04 2.01 E-03 3.16E-03

% of Limit 0.00% 0.01% 0.01% 0.04% 0.03%

Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Beta Air Beta Air Dose 1 .22E-04 1 .90E-04 6.1 OE-04 8.70E-04 1 .79E-03

% of Limit 0.001% 0.002% 0.006% 0.009% 0.009%

Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem Organ (Iodine, Tritium, Particulates with >8 day half-life)

Gaseous Effluent Organ Dose 2.64E-02 2.89E-02 2.60E-02 2.84E-02 1 .1 OE-01 (Iodine, Tritium, Particulates with

>8-Day half-life)

% of Limit 0.35% 0.39% 0.35% 0.38% 0.73%

Palisades Table A-5 2011 EPA 40 CFR Part 190, Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Dose 6.29E-02 6.82E-03 4.23E-03

% of Limit 0.25% 0.01% 0.02%

Page 1 of 1

ENCLOSURE 1 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL, REVISION 25 OFFSITE DOSE CALCULATION MANUAL, APPENDIX A, REVISION 16 OFFSITE DOSE CALCULATION MANUAL, APPENDIX A, REVISION 17 202 Pages Follow

ODCM Revision 25 Issued Date 12129111 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: OFFSITE DOSE CALCULATION MANUAL Process Applicability Exclusion Li DWFoster I 12128/11 Procedure Sponsor Date JJMiller I 12115111 Technical Reviewer Date JHager I 12I1 5111 User Reviewer Date DHamilton I 12/19111 General Manager Plant Operations Date

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Table of Contents GASEOUS EFFLUENTS I A. ALARMITRIP SETPOINT METHOD I

1. Allowable Concentration 2

2. Monitor Response 3 B. DOSE RATE CALCULATION 4 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION 19

1. System Description 19

2. Determination of Satisfactory Operation 19 D. RELEASE RATE FOR OFFSITE EC 20 E. PARTICULATE AND IODINE SAMPLING 20 F. NOBLE GAS SAMPLING 21 G. TRITIUM SAMPLING 21 H. FIGURE GASEOUS EFFLUENTS FLOW PATHS 22 LIQUID EFFLUENTS 23 A. CONCENTRATION 23

1. Requirements 23

2. Prerelease Analysis 23

3. Effluent Concentration (EC) Sum of the Ratios 24 B. INSTRUMENT SETPOINTS 25

1. Setpoint Determination 25

2. Composite Samplers 25

3. Post-Release Analysis 26 C. DOSE 26

1. RETS Requirement 26

2. Release Analysis 26 D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT 30 E. RELEASE RATE FOR OFFSITE EC (50 MREMIYR) 30 F. FIGURES 31

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Table of Contents III. URANIUM FUEL CYCLE DOSE 33 A. SPECIFICATION 33 B. ASSUMPTIONS 33 C. DOSE CALCULATION 34 IV. SOURCE REFERENCE DOCUMENTS 34 , Palisades Gaseous And Liquid Source Terms, Curies/Year , Basic Radionuclide Data , Dose Factors for Submersion in Noble Gases , Stable Element Transfer Data , Inhalation Dose Commitment Factors , External Dose Factors for Standing on Contaminated Ground (DFG)

(mrem/hr per pCi/m

)

2 , Bioaccumulation Factors (pCi/gm per pCi/mI) , Ingestion Dose Commitment Factors

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 GASEOUS EFFLUENTS A. ALARMITRIP SETPOINT METHOD Appendix A, Section lII.B.1 requires that the dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:

- For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

- For iodine-I 31, for iodine-I 33, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

Appendix A, Section lll.A.I requires gaseous effluent monitors to have alarm/trip setpoints to ensure that offsite concentrations, when averaged over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , will not be greater than Appendix A, Section lll.B.1. This section of the ODCM describes the methodology that will be used to determine these setpoints.

The methodology for determining alarm/trip setpoints is divided into two major parts.

The first consists of calculating an allowable concentration for the nuclide mixture to be released. The second consists of determining monitor response to this mixture in order to establish the physical settings on the monitors.

I

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Allowable Concentration NOTE: If a batch release is made while a continuous release or another batch release is in progress, the sum of all values of Rk must be less than 10.0.

The total EC-fraction (Rk) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

Rk=XIQXFXZCj/EC10.0 (1.1) where:

C = Actual or measured concentration, at ambient temperature and pressure of nuclide i (j.tCilcc)

EC = The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 R(k) = The total EC-fraction for release point k XIQ = Most conservative sector site boundary dispersion (sec/rn

)

3 (listed in site procedure CH 6.41, Land Use Census)

F = Release flow rate (83,000 cfm = 39.2 m /sec) for stack monitor 3

considerations; variable for other monitors 2

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

2. Monitor Response Normal radioactivity releases consist mainly of well-decayed fission gases.

Therefore, monitor response calibrations are performed to fission gas typical of normal releases (mainly Xe-133). Response of monitors used to define fission product release rates under accident conditions may vary from that of Xe-I 33, however. Monitor response for the two categories of monitor is determined as follows:

a. Normal Release (aged fission gasses)

Total gas concentration (pCi/cc) at the monitor is calculated. The detector response to isotopic activities (cpm/iCi/cc) is applied to determine cpm expected. The setting for monitor alarms is established at some factor (b) greater than 1 but less than 1/Rk (Equation 1.1) times the measured concentration (c):

sbxc (1.2)

b. Accident Releases Monitors are preset to alarm at or before precalculated offsite dose rates would be achieved under hypothetical accident conditions.

These setpoints are established in accordance with Emergency Plan requirements for defining Emergency Action Levels and associated actions. Emergency Implementing Procedures contain monitor-specific curves or calibration constants for conversion between cpm and iCi/cc (or RIhr and 1 iCilcc), depending on monitor type, for fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions, either an appropriately decayed accident conversion curve may be used, or a decayed fission gas calibration factor may be applied. In these cases, setpoints are established as in 1 .A above.

Setpoints of accident monitors (if set to monitor normal releases) are reset to the accident alarm settings at the end of normal release.

Setpoints of other release monitors are maintained at the level used at the latest release (well below the level which would allow 10 times EC to be exceeded at the site boundary), or are reset to approximately three times background in order to detect leakage or inadvertent releases of low level gases.

3

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 B. DOSE RATE CALCULATION Dose rates are calculated for (1) noble gases and (2) iodines and particulates.

Dose rates as defined in this section are based on 10 CFR 50 Appendix I limits of mrem per quarter and millirem per year. All dose pathways of major importance in the Palisades environs are considered. NRCDose is the Effluent Dose Calculation software that supports LADTAP, GASPAR, and XOQDOQ which perform the actual dose calculations using the equations supplied here.

a. Equations and assumptions for calculating doses from noble gases are as follows:

1) Assumptions a) Doses to be calculated are the maximum offsite point in air, total body and skin.

b) Exposure pathway is submersion within a cloud of noble gases.

c) Noble gas radionuclide mix is based on the historically observed source term given in Attachment 2, plus additional nuclides.

d) Basic radionuclide data are given in Attachment 2.

e) All releases are treated as ground-level.

f) Meteorological data expressed as joint-frequency distribution of wind speed, wind direction, and atmospheric stability for the period resulting in X)Qs and DIQs shown in site procedure CH 6.41, Land Use Census.

g) Raw meteorological data consists of wind speed and direction measurements at 1Dm and temperature measurements at lOm and 60m.

h) Dose is to be evaluated at the offsite exposure points where maximum concentrations are expected to exist (overland sector site boundaries), and nearest residents.

4

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 i) Potential maximum population (resident) exposure points are identified in site procedure CH 6.41, Land Use Census.

j) A semi-infinite cloud model is used.

k) Radioactive decay is considered for the plume.

I) Building wake effects on effluent dispersion are considered.

m) A sector-average dispersion equation is used.

n) The wind speed classes that are used are as follows:

Wind Speed Class Number Rancie (mis) Midpoint (mis)

I 0.0-0.4 0.2 2 0.4-1.5 0.95 3 1.5-3.0 2.25 4 3.0-5.0 4.0 5 5.0-7.5 6.25 6 7.5-10.0 8.75 7 > 10.0 o) The stability classes that will be used are the standard A through G classifications. The stability classes 1-7 will correspond to A1, B=2, ..., G7.

p) Terrain effects are not considered.

5

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

2) Equations To calculate the dose for any one of the exposure points, the following equations are used.

For determining the air concentration of any radionuclide:

Jk 1 P Q (1.3) x jr) exp 2i zkUJ (2zx/n) U) j=1 k1 where:

XI = Air concentration of radionuclide i, jiCilm 3

fjk = Joint relative frequency of occurrence of winds in wind speed class j, stability class k, blowing toward this exposure point, expressed as a fraction.

QI = Average release rate of radionuclide i, jiCils.

p = Fraction of radionuclide remaining in plume.

zk = Vertical dispersion coefficient for stability class k (m).

1 U = Midpoint value of wind speed class interval j, rn/s.

x = Downwind distance, m.

n = Number of sectors, 16.

= Radioactive decay coefficient of radionuclide i, sc.

2irx/n = Sector width at point of interest, m.

6

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 For determining the total body dose rate:

Dm Xj DFB (1.4) where:

DTB = Total body dose rate, mrem/y.

XI = Air concentration of radionuclide I, iCi/m 3

DFB = Total body dose factor due to gamma radiation, mrem/y per iiCilm 3 (Attachment 3).

For determining the skin dose rate:

(1.5) where:

D = Skin dose rate, mrem/y.

XI = Air concentration of radionuclide i, DFSI = Skin dose factor due to beta radiation, mrem/y per iCi/m (Attachment 3).

1 3

1.11 = The average ratio of tissue to air energy absorption coefficients, mrem/mrad.

DFY = Gamma-to-air dose factor for radionuclide i, mrad/y per jiCilm 3 (Attachment 3).

For determining dose rate to a point in air:

Daj (DFYIOrDFBI) (1.6) where:

Da = Air dose rate, mrad/yr.

DFBI = Air dose factor for beta radiation (Attachment 3).

7

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

b. Equations and assumptions for calculating doses from radioiodines and particulates are as follows:

1) Assumptions a) Dose is to be calculated for the critical organ, thyroid, and the critical age groups (adult, teen, child, infant), infant (milk) and child (green, leafy vegetables).

b) Exposure pathways from iodines and particulates are milk ingestion, ground contamination, green leafy vegetables from home gardens, and inhalation.

c) The radioiodine and particulate mix is based on the historically observed source term given in Attachment 2.

d) Basic radionuclide data are given in Attachment 3.

e) All releases are treated as ground-level.

f) Mean annual average XIQs are given in site procedure CH 6.41, Land Use Census.

g) Raw meteorological data for ground-level releases consist of wind speed and direction measurements at 1Gm and temperature measurements at 1Gm and 6Gm.

h) Dose is to be evaluated at the potential offsite exposure points where maximum doses to man are expected to exist.

i) Real cow, goat and garden locations are considered.

j) Potential maximum exposure points (site procedure CH 6.41, Land Use Census) considered are the nearest cow, goat, and home garden locations in each sector.

k) Terrain effects and open terrain recirculation factors are not considered.

I) Building wake effects on effluent dispersion are considered.

m) Plume depletion and radioactive decay are considered for air-concentration calculations.

8

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 n) Radioactive decay is considered for ground-concentration calculations.

o) Deposition is calculated based on the curves given in Figure 1.2.

p) Milk cows and goats obtain 100% of their food from pasture grass May through October of each year. Use default values of 0.58 for cows and 0.67 for goats for fraction of year on pasture.

2) Eciuations To calculate the dose for any one of the potential maximum-exposure points, the following equations in Section 1.2.2 are used.

a) Inhalation Equation for calculating air concentration, X is the same as in the Noble Gas Section (Equation 1.3).

For determining the organ dose rate:

DFI 1

X 6

D1X1O B R (1.7) where:

= Organ dose rate due to inhalation, mrem/y.

XI = Air concentration of radionuclide i, j.iCiIm 3

DElI = Inhalation dose factor, mrem/pCi (Attachment 5).

BR = Breathing rate 1400 m/y infant; 3

3700 m /y child; or 8000 m 3 /y teen and 3

adult.

lxi 06 = pCi/iCi conversion factor.

9

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 b) Ground Contamination For determining the ground concentration of any nuclide; 7

fQDR 7

G=3.15x1O [1-exp(,Itb)] (1.8) 1 (22rx!n)2 k=1 where:

= Ground concentration of radionuclide i, 2

jiCi/m k = Stability class.

fk = Joint relative frequency of occurrence of winds in stability class k blowing toward this exposure point, expressed as a fraction.

Q* = Average release rate of radionuclide pCi/s.

DR = Relative deposition rate, m1 (Fig 1.2).

x = Downwind distance, m.

n = Number of sectors, 16.

2rx/n = Sector width at point of interest, m.

= Radioactive decay coefficient of radionuclide i, y.

1 tb = Time for buildup of radionuclides on the ground, 15y.

7 3.15x10 s/y conversion factor.

10

RELATIVE DEPOSITION RATE (PER METER) 0 0 I

-n C -

0

.1 if ii I

1 Cl)

I-. -a

-I C m I in 0 Cl)

I I 0

tiI V Ci) V in m m CD C) Cl) z 3,, z I C in 0 C) C) 0 C I 0 I m 0I

-I 0

z -uI z

z -I C

I I-C-)

0 0

n 0

0 a

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 For determining the total body or organ dose rate from ground contamination:

DG = (8,760)(1 X i0)(0.7) 1 G DFG (1.9) where:

0 D = Dose rate due to ground contamination, mrem/y.

= Ground concentration of radionuclide i, 2

iCiIm DFG = Dose factor for standing on contaminated ground, mrem/h per pCi/rn 2 (Attachment 6).

8,760 = Occupation time, h/y.

lxi 06 pCi/jiCi conversion factor.

0.7 = Shielding factor accounting for a distance of 1.0 meter above ordinary ground, dimensionless.

C) Milk and Vegetation Ingestion For determining the concentration of any nuclide (except C-14 and H-3) in and on vegetation:

1 CV 3,600 fk Qi DR r[1 exp (2E1 t)1

+ B

[1 1 exp(2Itb)}

1 th)))

((exp(2 (1.10)

(2x/n) Yv2EI P2, k=1 where:

CV Concentration of radionuclide i in and on vegetation, j.tCi/kg.

k = Stability class.

fk = Frequency of this stability class and wind direction combination, expressed as a fraction.

12

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 QI = Average release rate of radionuclide i, jiCi/s.

DR = Relative deposition rate, m 1 (Figure 1.2).

x = Downwind distance, m.

n = Number of sectors, 16.

2ix/n = Sector width at point of interest, m.

r = Fraction of deposited activity retained on vegetation (1.0 for iodines, 0.2 for particulates).

Ei = Effective removal rate constant, 2Ei = + , where A is the radioactive decay coefficient, h, and 2 is a measure 1

of physical loss by weathering (2 = 0.0021 h).

te = Period over which deposition occurs, 720 h.

Y, = Agricultural yield, 0.7 kg/rn 2

B = Transfer factor from soil to vegetation of radionuclide i (Attachment 4).

= Radioactive decay coefficient of radionuclide i, h 1

tb = Time for buildup of radionuclides on the ground, 1.31x10 h (15Y).

5 p = Effective surface density of soil, 240 kg/rn 2

3,600 = s/h conversion factor.

th = Holdup time between harvest and consumption of food (2,160 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months for stored food).

13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 For determining the concentration of C-14 in vegetation:

14 =lx io cv 14 (0.11/0.16) x 3 (1.11) where:

14 CV = Concentration of C-14 in vegetation, pCi/kg.

14 X = Air concentration of C-14, iCiIm 3

0.11 = Fraction of total Plant mass that is natural carbon.

0.16 = Concentration of natural carbon in the atmosphere, g/m 3

3 1x10 = g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

75 X

1 CV

)(O.5/H) 1OXT(O. (1.12) where:

CVT = Concentration of H-3 in vegetation, jiCilm 3

XT = Air concentration of H-3, j.tCi/m 3

0.75 = Fraction of total Plant mass that is water.

0.5 = Ratio of tritium concentration in Plant water to tritium concentration in atmospheric water.

H = Absolute humidity of the atmosphere, g/m .

3 lxi = g/kg conversion factor.

14

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 For determining the concentration of any nuclide in cows or goats milk:

CM = 1 FM CV 1 Qf exp (-2. tf) (1.13) where:

CM Concentration of radionuclide i (including C-14 and H-3) in milk, jiCi/I.

CV = Concentration of radionuclide i in and on vegetation, j.iCilkg.

FM = Transfer factor from feed to milk for radionuclide i, d/l (Attachment 4).

Q = Amount of feed consumed by the milk animal per day, kg/d (cow, 50 kg/d or goat 6 kg/d).

A, = Radioactive decay coefficient of radionuclide i, d 1

tf = Transport time of activity from feed to milk to receptor, 2 days.

15

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 For determining the organ dose rate from ingestion of green leafy vegetables and milk:

1 C

6 D=1x1o D FUM M (1.14) where:

D = Organ dose rate due to ingestion, mrem/y.

1 CM Concentration of radionuclide i in vegetables or milk, pCi/kg (or liters).

DF Ingestion dose factor, mrem/pCi (Attachment 8).

UM Ingestion rate for milk, 330 IIy; for vegetables 26 kg/yr (child), no ingestion by infant.

lxi 06 = pCi/pCi conversion factor.

d) Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal flesh:

Cf = Ff CV Qj exp 1 (-2 t ) (1.15) where:

Cfi = Concentration of nuclide i in the animal flesh, pCi/kg.

Ffl = Fraction of animals daily intake which appears in each kg of flesh, days/kg (Attachment 4).

CV = Concentration of radionuclide i in the animals feed (Equation 1.10).

16

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Q = Amount of feed consumed by the cow per day, 50 kg/d.

t = Average time from slaughter to consumption, 20 days.

To determine the organ dose from ingestion of beef:

DCflDfiUf (1.16) where:

Dfj = Ingestion dose factor for age group, mrem/pCi (Attachment 8) for nuclide i.

Uf = Ingestion rate of meat for age group, kg/y (child-41, teen-65, adult-hO).

e) Organ Dose Rates For determining the total body and organ dose rate from iodines and particulates:

D=DI+DG+DM+DV+DF (1.17) where:

D = Total organ dose rate, mrem/y.

1 D = Dose rate due to inhalation, mrem/y.

DG = Dose rate due to ground contamination, mrem/y.

DM = Dose rate due to milk ingestion, mrem/y.

Dv = Dose rate due to vegetable ingestion, mrem/y.

DF = Dose rate due to beef ingestion, mrem/y.

17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

3) The maximum organ dose rate, maximum total body dose rate, and maximum skin dose rate calculated in the previous section (Sec l.B) are used to calculate design basis quantities as described in Section l.B.1.3.

c. Land Use Census Appendix A, Sections J.3.b and J.3.c describe the requirements for an annual land use census. Changes will be effective on January 1 of the year following the year of the survey.

d. Gaseous Releases From the Steam Generator Blowdown Vent and Atmosphere Release Valves Releases from the steam generator blowdown vent and atmospheric relief valves are difficult to quantify as there are no sampling capabilities on these steam release systems. However, neither system is a normal release path. The steam generator blowdown vent is normally routed to the main condenser and recirculated. Radioactive releases will be calculated by analyzing steam generator blowdown liquid and assuming that 100 percent of Noble Gases, 10 percent of the lodines and 1 percent of the Particulates will be released to the environment in the steam phase. Volumes will be released to the environment in the steam phase. Volumes will be calculated using water balances or alternate means as available.

18

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION The gaseous radwaste treatment system (GRTS) described below shall be maintained and operated to keep releases ALARA.

1. System Description A flow diagram for the GRTS is given in Figure 1-1. The system consists of three waste-gas compressor packages, six gas decay tanks, and the associated piping, valves, and instrumentation. Gaseous wastes are received from the following: degassing of the reactor coolant and purging of the volume control tank prior to a cold shutdown and displacing of cover gases caused by liquid accumulation in the tanks connected to the vent header.

Design of the system precludes hydrogen explosion by means of ignition source elimination (diaphragm valves, low flow diaphragm compressors and system electrical grounding), and minimization of leakage outside the system.

Explosive mixtures of hydrogen and oxygen have been demonstrated compatible with the system by operational experience.

2. Determination of Satisfactory Operation Doses will be calculated for batch and continuous releases as described in Section lB. These calculations will be used to ensure that the GRTS is operating as designed. Because the Plant was designed to collect and hold for decay a vast majority of the high level gases generated within the primary system, and because the operating history of the Plant has demonstrated the systems consistent performance well below Appendix I limits, no additional operability requirements are specified.

19

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 D. RELEASE RATE FOR OFFSITE EC 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in concentrations less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. (Note: there are no unrestricted areas anywhere within the site boundary as defined by Figure 1-1.) Concentrations at this level if inhaled or ingested continuously for one year will result in a dose of 50 mrem whole body except for submersion dose isotopes (gaseous tritium and noble gasses) which will results in a dose of 100 mrem whole body. 10 CFR 50.36a requires that the release of radioactive materials be kept as low as reasonably achievable.

However, the section further states that the licensee is permitted the flexibility of operation, to assure a dependable source of power even under unusual operating conditions, to release quantities of material higher than a small percentage of 10 CFR 20.1302 limits but still within those limits. Appendix Ito 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as reasonably achievable requirement.

The GASPAR code has been run to determine the dose due to external radiation and inhalation. The source term used is listed in Attachment 2. The meteorology data is given in site procedure CH 6.41, Land Use Census. Dose using annual average meteorology, to the most limiting organ of the person assume to be residing at the site boundary with highest XIQ, is 2.15E-02 mrem (for one year). The release rate which would result in a dose rate equivalent to 50 mrem/year (using the more conservative total body limit) is the curies/year given in Attachment 2 multiplied by 50/2.15E-02 or 0.11 Ci/sec.

E. PARTICULATE AND IODINE SAMPLING Particulate and iodine samples are obtained from the continuous sample stream pulled from the Plant stack. Samples typically are obtained to represent an integrated release from a gas batch (waste gas decay tank or Containment purge, for example), or a series of samples are obtained to follow the course of a release.

In any event, sample intervals are weekly, at a minimum.

Because HEPA filters are present between most source inputs to the stack and the sample point, releases of particulates normally are significantly less than pre-release calculations indicate. This provides for conservatism in establishing setpoints and in estimation of pre-release dose calculations. However, for the sake of maintaining accurate release totals, monitor results (for gases) and sample results (for particulates and iodines) utilized rather than the pre-release estimates, for cumulative records.

20

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Gamma analytical results for particulate and halogen filters are combined for determination of total activity of particulates and halogens released. Sampling and analysis will be performed per Appendix A, Table B-I requirements.

F. NOBLE GAS SAMPLING Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the Containment prior to purging. Analysis of these samples will be used for accountability of noble gases. Off gas will be sampled at least weekly and used to calculate monthly noble gas releases. Non-routine releases will be quantified from the stack noble gas monitor (RE 2326) which has a LLD of 1 E-06 tCi/cc. Sampling and analysis will be performed per Appendix A, Table B-I requirements.

G. TRITIUM SAMPLING Tritium has a low dose consequence to the public because of low energy decay.

The major contributors to tritium effluents are evaporation from the fuel pool and reactor cavity (when flooded). Because of the low dose impact, gaseous tritium sampling will not be required. Tritium effluents will be estimated using conservative evaporation rate calculations from the fuel pool and reactor cavity.

21

I PALISADES GASEOUS EFFLUENTS 1

C)

C m

C)

Cl) m 0

C 0 Cl) .1 1

m Cl),

-n -I, p m

-n I Cl)

-fi C 0 p OFF GAS m m rn z 0 Cl)

-l Cl) >

(ft I C 1 0 C, 0 I C I 0 I m UI

-I p

-U 0

> z -ur

-I p

> -4z Cl) z C

I-11E U.57iI AND 57?? TIP DIPPLY Aim ONE OF t.O EXWMISTEAS.

F1.ON S NOT lteNAflO PAIJSADES EFFLUENT FLOW PATHS GASEOUS

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 LIQUID EFFLUENTS A. CONCENTRATION Requirements Appendix A, Section IlI.G requires that the concentration of radioactive material released at any time from the site to unrestricted areas shall be limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20, Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-04 jiCi/mi total activity. To ensure compliance, the following approach will be used for each release.

2. Prerelease Analysis Most tanks will be recirculated through two volume changes prior to sampling for release to the environment to ensure that a representative sample is obtained. The appropriate recirculation time for those tanks too large to provide two volume changes will be the time that the suspended particulate concentration reaches steady state. Either a one-time test, or prior sampling data, may be used to determine appropriate recirculation time.

Prior to release, a grab sample will be analyzed for each release, and the concentration of each radionuclide determined.

n C = ZCI (2.1) i=1 where:

C = Total concentration in the liquid effluent at the release point, iCi/mI.

C = Concentration of a single radionuclide i, jiCi/mI.

23

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

3. Effluent Concentration (EC) Sum of the Ratios The EC-Fraction (Ri) for each release point will be calculated by the relationship defined by Note 4 of Appendix B, 10 CFR 20:

=

--10.O (2.2)

EC where:

C = Effluent concentration of radionuclide i, jiCi/mi.

EC = The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, Column 2 .tCi/ml.

R = The Total EC-Fraction for the release point.

The sum of the ratios at the discharge to the lake must be 10 due to the releases from any or all concurrent releases. The following relationship will assure this criterion is met:

fi (Ri 1) +

f2 (R2 -1) + f (R3 -1) F (2.3) where:

3 2

fi,ff = The effluent flow rate (gallons/minute) for the respective releases, determined by Plant personnel.

3 1

R 2 R = The Total EC-Fractions for the respective releases as determined by Equation 2.2.

F = Minimum required dilution flow rate. Normally, a conservatively high dilution flow rate is used, that is, flow rate used = (b)(F) where b is a conservative factor greater than 1.0.

24

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 B. INSTRUMENT SETPOINTS Setpoint Determination Appendix A, Section lIl.F requires alarm setpoints for each liquid effluent monitor will be established using Plant instructions to ensure the requirements of Appendix A, Section llI.G are not exceeded. Concentration, flow rate, dilution, principal gamma emitter, geometry, and detector efficiency are combined to give an equivalent setpoint in counts per minute (cpm). The identification number for each liquid effluent radiation detector is contained in Figure 2-2.

The respective alarm/trip setpoints at each release point will be set such that the sum of the ratios at each point, as calculated by Equation 2.2, will not be exceeded. The value of R is directly related to the total concentration calculated by Equation 2.1. An increase in the concentration would indicate an increase in the value of R. A large increase would cause the limits specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint value is equal to the release concentration, but for ease of operation it may be desired that the setpoint (S) be set above the effluent concentration (C) by the same factor (b) utilized in setting dilution flow. That is:

S = bxC (2.4)

Liquid effluent flow paths and release points are indicated in Figure 2.1.

2. Composite Samplers Effluent pathways, Turbine Sump and Service Water, are equipped with continuous compositors to meet the requirements of Appendix A, Table D-1.

These compositors are adjustable and normally set in a time mode and collect three to six samples hourly, 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly, and quarterly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per Appendix A, Table C-i, Action 3.

25

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

3. Post-Release Analysis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 1 were not exceeded.

A composite list on concentrations (C), by isotope, will be used with the actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the release. The data will be substituted into Equation 2.3 to demonstrate compliance with the limits in Section 1. This data and setpoints will be recorded in auditable records by Plant personnel.

C. DOSE RETS Requirement Appendix A, Section Ill.H.1 requires that the quantity of radionuclides released by limited such that the dose or dose commitment to an individual from radioactive materials in liquid effluents release to unrestricted areas from the reactor (see Figure 2-1) will not exceed:

a. During any calendar quarter, 1.5 mrem to the total body and 5 mrem to any organ, and

b. During any calendar year, 3 mrem to the total body and 10 mrem to any organ.

To ensure compliance, quantities of activity of each radionuclide released will be summed for each release and accumulated for each quarter as follows in Section 2.

2. Release Analysis Dose calculations shall be performed for each batch release, and weekly for continuous releases unless documentation exists to demonstrate an activity below which dose limits of Section ll.C.1 will not be exceeded.

a. Water Ingestion The dose to an individual from ingestion of radioactivity from any source as described by the following equation:

(DCFxI (2.5) 26

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 where:

D = Dose for the Jth organ from radionuclides releases, mrem.

= The organ of interest.

(DCF)IJ = Ingestion dose commitment factor for the jth organ from the jth radionuclide mrem/pCi, see Attachment 8.

I. = Activity ingested of the radionuclide, pCi.

I is described by:

(A)(V)(365)

(1E06) (2.6)

(1 000)(d) where:

365 = Days per year.

A = Annual activity released of radionuclide, 1 iCi.

V = Average rate of water consumption (2000 mI/d adult,-

1400 mI/d teen and child, 900 mI/d infant, ICRP 23, p 358).

d = Dilution water flow for year, ml.

1000 = Dispersion factor from discharge to nearest drinking water supply.

I E06 = Conversion jiCi to pCi.

The dose equation then becomes:

(3.6505)

D (DCF)xAmrem (2.7) 27

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

b. Fish Ingestion The dose to an individual from the consumption of fish is described by Equation 2.10. In this case, the activity ingested of the ith radionuclide (I,) is described by:

AB F

1 (1EO9)

=pCi (2.8) where:

A = Annual released of i radionuclide, pCi.

th B = Fish concentration factor of radionuclide pCi/gm pCi/mi (see Attachment 7).

F = Amount of fish eaten per year (21 kg adult, 16 kg teen, 6.9 kg child, none infant).

15 = Dispersion factor from discharge to fish exposure point.

d = Dilution water flow for year, ml.

1E09 = Conversion of pCi, gm, and Kg to pCi.

Substitution of Equation 2.8 into Equation 2.5 gives:

(6.7E07)F D AxB x

1 DCFmrem (2.9) i=1 28

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25

c. Annual Analysis A complete analysis utilizing the NRC computer code LADTAP with the total source release will be done annually in conjunction with the annual environmental report. This analysis will provide estimates of dose to the total body and various organs in addition to the dose limiting organs considered in the method of Section 2. The following approach is utilized on LADTAP. The dose to the Jth organ from m radionuclides, Dj, is described by:

m D= mrem 1

D 1 (2.10) 1=1 m

= (DCFxImrem (2.11) 1=1 where:

1 D = Dose to the Jth organ from the i radionuclide, mrem.

= The organ of interest (bone, GI tract, thyroid, liver, kidney, lung, or total body).

1 (DCF) = Adult ingestion dose commitment factor for the th organ from the ith radionuclide, mrem/pCi (see Attachment 8).

Ii = Activity ingested of the radionuclide, jiCi.

I for water ingestion is described by:

.1 AiVr pCi (2.12) vd and for fish ingestion Ii is described by:

AiBiFrj (2.13) vd 29

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 where:

0 t

1 f h 1

A = Activity release radionuclide during the year, Ci.

V = Average rate of water consumption (2000 mIld).

F = Number of days during the year (365 d).

v = Dispersion factor from point of discharge to point of exposure.

d = Dilution water volume (ml).

B Fish concentration factor of the radionuclide, p CIgm Attachment 7, p Cl/mI F = Amount of fish eaten per day (57.5 gmld).

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT The Palisades liquid radwaste system is designed to reduce the radioactive materials in liquid wastes prior to their discharge (through deep bed filtration and ion exchange) so that radioactivity in liquid effluent releases to unrestricted areas (see Figure 2-1)will not exceed the limits of Appendix A, III.H.1.

E. RELEASE RATE FOR OFFSITE EC (50 MREMIYR) 10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less than the limits specified in Appendix B, Table 2 when averaged over a period not to exceed one year. Concentrations at this Effluent Concentration (EC) level, if ingested for one year, will result in a dose of 50 millirem to the total body. In addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as low as is reasonably achievable. Appendix Ito 10 CFR 50 provides the numerical guidelines on limiting conditions for operations to meet the as low as is reasonably achievable requirement.

The LADTAP code has been run to determine the dose due to drinking water at Plant discharge concentration (1,000 x nearest drinking water intake concentration).

The nominal average source term used is given in Attachment 2. Dose to the most limiting organ of the person hypothetically drinking this water is 3.88E-03 mrem.

This is only 0.13% of the more conservative 50 mremlyr total body value.

30

B r

-J () I I

D a I z NW I 14 z ww

/ NI 15, S

-J

0. 0 z S..

wNW U) ft LU -J c..1

-J D C C., 0

-J U) z >

Cl) C-, w WW Lii Lii LLI a U) 16 0

Cl, a S

-I UJ I /

$W S 0.

Cn S LI. N U .5 417 C

I 21S M1TIEIS i 9\

U) SITE ENVIRONMENT w TLO STATIONS PALISADES NIJCLEAR PLANT D SITE BOUNDARY 0 FIGuRE 2-I U-

PALISADES RADWASTE EFFLUENTS - LIQUID CT rAN WASrE SYS I IM STEAM GEN

-J BLOWOOWN PRIMARY TANK z SYSTEM 1799 STORAGE TANK RE 0707 Z TITTATFI) -

WASTE T o_ o TANKS (7) TRIP & FLOW CONTROL iz UJj CI c.Ii RETO4g RE0933 II O 0 0 SERVICE D

MISCFI LANTOIJS WASTE SYSTEM WATER Z <

coo a,

- (DIRTY WASE)

I LAKE w LL. AIJNT)RY UTILITY RE (323 0 SYSTEM WATER

< o STORAGE TANK 61 1-91 MIXING FILILNr() TURBINE BLDG BASIN

0. WASTE DRAINS IJ_ TANK SUMP RE 5211 DILUTION FLOW S 1

SERVICE WATER LAKE INLET

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 Ill. URANIUM FUEL CYCLE DOSE A. SPECIFICATION In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly releases exceed the quantity which would cause offsite doses more than twice the limit of Appendix A, Sections lII.C.1, IIl.D.1, or llI.H.1, then the cumulative dose contributions from combined release plus direct radiation sources (from the reactor unit and radwaste storage tanks) shall be calculated. The dose is to be determined for the member of the public protected to be the most highly exposed to these combined sources.

B. ASSUMPTIONS

1. The full time resident determined to be maximally exposed individual (excluding infant) is assumed also to be a fisherman. This individual is assumed to drink water and ingest local fish at the rates specified in Sections II.C.2.1 and II.C.2.2.

2. Amount of shore line fishing (at accessible shoreline adjacent to site security fence) is conservatively assumed as 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months for the fourth quarter and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for the first quarter.

33

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 25 C. DOSE CALCULATION Maximum doses to the total body and internal organs of an individual shall be determined by use of LADTAP and GAS PAR computer codes, and doses to like organs and total body summed. Added to this sum will be a mean dose rate, calculated or measured for the shoreline due to Plant present curing the quarter in question, times the assumed fishing time.

D 4 0 = DG + DL + (RT)(T) (2.15) where:

D 40 40 CFR 190 dose (mrem).

DG = Limiting dose to an individual from gaseous source term (mrem).

DL = Limiting dose to an individual from liquid source term (mrem).

RT = Mean dose rate calculated to be applicable to Lake Michigan shoreline adjacent to Plant site (mrem/hr).

T Assumed shoreline fishing time for the quarter in questions (hours).

IV. SOURCE REFERENCE DOCUMENTS

1. Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioacitve Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants, Ri.

2. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, RI.

3. NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors, April 91.

4. NUREG-0472, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, R3.

5. NUREG/CR-4013, LADTAP II Technical Reference and User Guide, April 86.

6. NUREG/CR-4653, GASPAR II Technical Reference and User Guide, March 87.

7. CH 6.61, Revising the ODCM and ODCM Appendix A.

34

Proc No ODCM Attachment I Revision 25 Page 1 of I PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESIYEAR (1)

Nuclide Gaseous(2) Liciuid(2)

H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1E-01 NA Ar-41 3.IE-02 NA Xe-131m 2.2 NA Xe-133 1493 NA Xe-i 33m 0.43 NA Xe-135 1.11 NA Xe-135m 0.3 NA 1-131 0.025 3.21E-03 1-132 2.91E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 l.84E-02 NA Na-24 1.5E-06 NA Cr-51 2.5E-04 3.9E-03 Mn-54 4.IE-04 7.8E-03 Co-57 2.IE-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.1E-04 Co-60 1.1 E-03 1 .24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 I .79E-04 Mo-99 I .5E-07 NA Ru-103 0.3E-07 0.1E-05 Sb-127 NA 3.5E-05 Cs-i 34 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 i.36E-02 Ba-140 2.8E-07 NA La-140 7.5E-07 1.1E-04 Unidentified beta 3.9E-04 3.3E-03 (1) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4.

(2) Nuclide values listed as NA have not been observed at detectable levels in these waste streams.

Proc No ODCM Attachment 2 Revision 25 Page 1 of 2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA 1 BETA 1 GAMMA (days) (MEV/DIS) (MEV/DIS) 1 Tritium 4.49E 03 1 .79E-09 5.68E-03 0.0 2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0 3 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E00 4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00 5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E00 6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00 7 P-32 1.43E 01 5.61E-07 6.95E-01 0.0 8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00 9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02 10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01 11 MN-56 I .07E-01 7.50E-05 8.29E-01 I .69E 00 12 FE-59 4.50E01 1.78E-07 1.18E-01 1.19E00 13 C0-58 7.13E 01 1.12E-07 3.41 E-02 9.78E-01 14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00 15 ZN-69m 5.75E-01 1.39E-05 2.21E-02 4.16E-01 16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0 17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00 18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02 19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01 20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21E-03 21 KR-87 5.28E-02 1 .52E-04 1 .32E 00 7.93E-01 22 KR-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00 23 KR-89 2.21 E-03 3.63E-03 1.36E 00 1.83E 00 24 RB-88 1.24E-02 6.47E-04 2.06E00 6.26E-01 25 RB-89 1.07E-02 7.50E-04 1.O1E 00 2.05E-00 26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05 27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0 28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01 29 SR-92 1.13E-01 7.1OE-05 1.95E-01 1.34E 00 30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00 31 Y-90 2.67E 00 3.OOE-06 9.36E-01 0.0 32 Y-91m 3.47E-02 2.31E-04 2.73E-02 5.30E-01 33 Y-91 5.88E01 1.36E-07 6.06E-01 3.61E-03 34 Y-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01 35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02 36 ZR-95 6.50E01 1.23E-07 1.16E-01 7.35E-01 37 NB-95m 3.75E00 2.14E-06 1.81E-01 6.06E-02 38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 39 MO-99 2.79E 00 2.87E-06 3.96E-01 I .50E-01 40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01

Proc No ODCM Attachment 2 Revision 25 Page 2 of 2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA 1 BETA 1 GAMMA (days) (us) (MEV/DIS) (MEV/DIS) 41 TC-99 7.74E 07 i.04E-13 8.46E-02 0.0 42 TC-104 i.25E-02 6.42E-04 i.60E 00 1 .95E 00 43 RU-106 3.67E02 2.19E-08 1.O1E-02 0.0 44 TE-132 3.24E00 2.48E-06 1.OOE-01 2.33E-01 45 1-129 6.21E09 1.29E-15 5.43E-02 2.46E-02 46 1-131 8.05E00 9.96E-07 1.94E-01 3.81E-01 47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 49 1-134 3.61 E-02 2.22E-04 6.16E-01 2.59E 00 50 1-135 2.79E-01 2.87E-05 3.68E-0i 1.55E 00 51 XE-i 3im 1.i8E 01 6.80E-07 1.43E-01 2.O1E-02 52 XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 53 XE-133 5.27E00 1.52E-06 1.35E-01 4.60E-02 54 XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 55 XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 56 XE-137 2.71E03 2.96E-03 1.77E00 1.88E-01 57 XE-i 38 9.84E-03 8.15E-04 6.65E-01 1.1OE 00 58 CS-134 7.48E 02 1.07E-08 i.63E-Oi 1.55E 00 59 CS-135 1.1OE 09 7.29E-15 5.63E-02 0.0 60 CS-i 36 1.30E 01 6.17E-07 1.37E-01 2.15E 00 61 CS-137 1.10E04 7.29E-iO 1.71E-01 5.97E-Oi 62 CS-138 2.24E-02 3.58E-04 i.20E00 2.30E00 63 BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 64 BA-140 1.28E01 6.27E-07 3.i5E-Oi i.71E-Oi 65 LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E 00 66 CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 67 PR-143 1.36E 01 5.90E-07 3.14E-Oi 0.0 68 PR-144 1.20E-02 6.68E-04 1.2iE 00 3.18E 00 1

Average energy per disintegration values were obtained from ICRP Publication No 38, Radionuclide Transformations: Enemy and Intensity of Emissions 1983 and NUREG/CR-1413 (ORNL/NUREG-70), a Radionuclide Decay Data Base Index and-Summary Table, DC Kocher, May 1980.

Proc No ODCM Attachment 3 Revision 25 Page 1 of I DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

Gamma body Gamma air Beta skin Beta air 1

dose 2 dose 1 dose 2 dose Kr-85m 1.17E3 1.23E3 1.46E3 1.97E3 Kr-85 1.61E1 1.72E1 1.34E3 1.95E3 Kr-87 5.92E3 6.17E3 9.73E3 1.03E4 Kr-88 1.47E4 1.52E4 2.37E3 2.93E3 Kr-89 1.66E4 1.73E4 1.01E4 1.06E4 Xe-131m 9.15E1 1.56E2 4.76E2 1.11E3 Xe-133m 2.51E2 3.27E2 9.94E2 1.48E3 Xe-133 2.94E2 3.53E2 3.06E2 1.05E3 Xe-135m 3.12E3 3.36E3 7.11E2 7.39E3 Xe-135 1.81E3 1.92E3 1.86E3 2.46E3 Xe-137 1.42E3 1.51E3 1.22E4 1.27E4 Xe-138 8.83E3 9.21E3 4.13E3 4.75E3 Ar-41 8.84E3 9.30E3 2.69E3 3.28E3 I. mrem/y per jiCi/m 3

2. mrad/y per pCi/rn 3

Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from USNRC Regulatory Guide 1.109, Revision 1 (October 1977).

Proc No ODCM Attachment 4 Revision 25 Page 1 of I STABLE ELEMENT TRANSFER DATA Fm MILK (COW)

- Fm MILK (GOAT)

- Ff MEAT

- 1 B

ELEMENT (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOIL)

H 1.OE-02 1.7E-O1 1.2E-02 4.8E-OO C t2E-02 1.OE-O1 3.1E-02 5.5E-OO Na 4.OE-02 4.OE-02 3.OE-02 5.2E-02 P 2.5E-02 2.5E-O1 4.6E-02 1.1E-OO Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.OE-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.OE-02 6.6E-04 Co 1.OE-03 1.OE-03 1.3E-02 9.4E-03 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Cu 1.4E-02 1.3E-02 8.OE-03 1.2E-O1 Zn 3.9E-02 3.9E-02 3.OE-02 4.OE-O1 Rb 3.OE-02 3.OE-02 3.IE-02 1.3E-O1 Sr 8.OE-04 1.4E-02 6.OE-04 1.7E-02 Y 1.OE-05 1.OE-05 4.6E-03 2.6E-03 Zr 5.OE-06 5.OE-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.8E-O1 9.4E-03 Mo 7.5E-03 7.5E-03 8.OE-03 1.2E-O1 Tc 2.5E-02 2.5E-02 4.OE-O1 2.5E-O1 Ru 1.OE-06 1.OE-06 4.OE-O1 5.OE-02 Rh 1.OE-02 1.OE-02 1.5E-03 1.3E+O1 Ag 5.OE-02 5.OE-02 1.7E-02 1.5E-O1 Te 1.OE-03 1.OE-03 7.7E-02 1.3E-OO I 6.OE-03 6.OE-02 2.9E-03 2.OE-02 Cs 1.2E-02 3.OE-O1 4.OE-03 1.OE-02 Ba 4.OE-04 4OE-O4 3.2E-03 5.OE-03 La 5.OE-06 5.OE-06 2.OE-04 2.5E-03 Ce 1.OE-04 1.OE-04 1.2E-03 Z5E-03 Pr 5.OE-06 5.OE-06 4.7E-03 2.5E-03 Nd 5.OE-06 5.OE-06 3.3E-03 2.4E-03 W 5.OE-04 5.OE-04 1.3E-03 1.8E-02 Np 5.OE-06 5.OE-06 2.OE-04 2.5E-03

Proc No ODCM Attachment 5 Revision 25 Page 1 ofl6 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 BEIO 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05 C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.1OE-07 NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 P32 1.45E-03 8.03E-05 5.53E-05 0. 0. 0. 1.15E-05 AR39 0. 0. 0. 0. 0. 1.OOE-08 0.

AR4I 0. 0. 0. 0. 0. 3.14E-08 0.

CA4I 7.48E-05 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 SC46 3.75E-04 5.41E-04 1.69E-04 0. 3.56E-04 0. 2.19E-05 CR51 0. 0. 6.39E-08 4.1IE-08 9.45E-09 9.17E-06 2.55E-07 MN54 0. 1.81E-05 3.56E-06 0. 3.56E-06 7.14E-04 5.04E-06 MN56 0. 1.IOE-09 1.58E-1O 0. 7.86E-10 8.95E-06 5.12E-05 FE55 1.41E-05 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E-07 FE59 9.69E-06 1.68E-05 6.77E-06 0. 0. 7.25E-04 1.77E-05 C057 0. 4.65E-07 4.58E-07 0. 0. 2.71 E-04 3.47E-06 C058 0. 8.71E-07 1.30E-06 0. 0. 5.55E-04 7.95E-06 C060 0. 5.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-05 N159 1.81E-05 5.44E-06 3.1OE-06 0. 0. 5.48E-05 6.34E-07 N163 2.42E-04 1.46E-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 N165 1.71E-09 2.03E-10 8.79E-11 0. 0. 5.80E-06 3.58E-05 CU64 0. 1.34E-09 5.53E-1O 0. 2.84E-09 6.64E-06 1.07E-05 ZN65 1.38E-05 4.47E-05 2.22E-05 0. 2.32E-05 4.62E-04 3.67E-05 ZN69M 8.98E-09 1.84E-08 1.67E-09 0. 7.45E-09 1.91 E-05 2.92E-05 ZN69 3.85E-11 6.91E-11 5.13E-12 0. 2.87E-11 1.05E-06 9.44E-06 SE79 0. 2.25E-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06 BR82 0. 0. 9.49E-06 0. 0. 0. 0.

BR83 0. 0. 2.72E-07 0. 0. 0. 0.

BR84 0. 0. 2.86E-07 0. 0. 0. 0.

BR85 0. 0. 1.46E-08 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 2.50E-09 0.

KR85M 0. 0. 0. 0. 0. 1.31E-08 0.

KR85 0. 0. 0. 0. 0. 1.16E-08 0.

KR87 0. 0. 0. 0. 0. 6.59E-08 0.

KR8S 0. 0. 0. 0. 0. 1.38E-07 0.

KR89 0. 0. 0. 0. 0. 8.67E-08 0.

RB86 0. 1.36E-04 6.30E-05 0. 0. 0. 2.17E-06 RB87 0. 7.11E-05 2.64E-05 0. 0. 0. 2.99E-07 RB88 0. 3.98E-07 2.05E-07 0. 0. 0. 2.42E-07 RB89 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08 SR89 2.84E-04 0. 8.15E-06 0. 0. 1.45E-03 4.57E-05 SR9O 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05 SR9I 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05 SR92 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 1.OOE-04

lncludes a 50% increase to account for percutaneous transpiration.

Proc No ODCM Attachment 5 Revision 25 Page 2 of 16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y9IM 2.91E-1O 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05 Y93 1.07E-07 0. 2.91E-09 0. 0. 5.46E-05 1.19E-04 ZR93 2.24E-04 9.51E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05 ZR97 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.OOE-04 NB93M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 NB95 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 NB97 2.44E-10 5.21E-11 1.88E-11 0. 4.07E-11 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099 0. 1.18E-07 2.31E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC1OI 4.65E-14 5.88E-14 5.80E-13 0. 6.99E-13 4.17E-07 6.03E-07 RUIO3 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 RU1O5 8.74E-1O 0. 2.93E-1O 0. 6.42E-1O 1.12E-05 3.46E-05 RUIO6 6.20E-05 0. 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41E-09 3.63E-09 0. 1.50E-08 2.08E-05 1.37E-05 PDIO7 0. 4.92E-07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07 PDIO9 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 AG11OM 7.13E-06 5.16E-06 3.57E-06 0. 7.80E-06 2.62E-03 2.36E-05 AG1I1 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 1.40E-03 1.65E-05 CDII5M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05 SN123 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.08E-05 SN125 1.O1E-05 2.51E-07 6.OOE-07 2.47E-07 0. 6.43E-04 7.26E-05 SN126 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 SB124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 SB125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 SB126 3.08E-06 6.OIE-08 1.11E-06 2.35E-08 0. 6.88E-04 5.33E-05 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 TEI25M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06 TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TEI29M 1.OIE-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE13IM 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 TEI3I 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TEI33M 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 1.59E-05 TE134 3.18E-11 2.04E-11 1.68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 0. 2.12E-07 1130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0. 7.56E07

Proc No ODCM Attachment 5 Revision 25 Page 3 of 16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 1132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0. 1.36E-06 1133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21E-07 1135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31E-06 XEI31M 0. 0. 0. 0. 0. 6.77E-09 0.

XEI33M 0. 0. 0. 0. 0. 8.89E-09 0.

XE133 0. 0. 0. 0. 0. 7.41E-09 0.

XEI35M 0. 0. 0. 0. 0. 8.05E-09 0.

XE135 0. 0. 0. 0. 0. 1.80E-08 0.

XE137 0. 0. 0. 0. 0. 8.30E-08 0.

XE138 0. 0. 0. 0. 0. 9.78E-08 0.

CS134M 1.32E-07 2.1OE07 1.IIE-07 0. 8.50E-08 2.OOE-08 1.16E-07 CS134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.00E-04 8.66E-05 4.73E-06 0. 2.58E-05 1.O1E-05 2.18E-07 CS136 3.45E-05 9.61E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS137 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61 E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS139 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08 BA139 1.06E-09 7.03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05 BAI4O 4.OOE-05 4.OOE-08 2.07E-06 0. 9.59E-09 1.14E-03 2.74E-05 BAI4I 1.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06 BA142 2.84E-11 2.36E-14 1.40E-12 0. 1.36E-14 1.IIE-06 4.95E-07 LA14O 3.61E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-1O 0. 0. 1.22E-05 5.96E-05 LA142 7.36E-10 2.69E-1O 6.46E-11 0. 0. 5.87E-06 4.25E-05 CEI4I 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05 CE143 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE144 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04 PR143 1.OOE-05 3.74E-06 4.99E-07 0. 1.41E-06 3.09E-04 2.66E-05 PR144 3.42E-11 1.32E-11 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06 ND147 5.67E-06 5.81 E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM147 3.91 E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PMI48M 5.OOE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.1OE-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.OIE-05 PMI5I 7.52E-08 1.IOE-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05 EU152 7.83E-04 1.77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06 EU154 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05 EU156 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05 TBI6O 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.IIE-03 2.14E-05 H0166M 1.45E-03 3.07E-04 2.51E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07 W185 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05

Proc No ODCM Attachment 5 Revision 25 Page 4 of 16 INHALATION DOSE COMMITMENT FACTORS INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB2IO 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 BI21O 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05 P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05 RN222 0. 0. 0. 0. 0. 9.88E-06 0.

RA223 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04 RA224 1.77E-04 4.OOE-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04 RA225 2.57E-03 2.88E-06 5.13E-04 0. 5.31E-05 2.57E-O1 2.87E-04 RA226 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04 RA228 1.60E-01 7.61E-06 1.80E-01 0. 1.53E-04 1.09E-00 5.19E-05 AC225 3.69E-03 4.72E-03 2.48E-04 0. 3.49E-04 1.96E-01 2.71E-04 AC227 5.29E+00 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+00 5.27E-05 TH227 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E-01 3.53E-04 TH228 8.46E-01 1.1OE-02 2.86E-02 0. 5.61E-02 4.65Ei-00 3.62E-04 TH229 1.34E+01 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+01 3.29E-04 TH230 3.46E+00 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+00 3.87E-05 TH232 3.86E+00 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+00 3.29E-05 TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 1.62E-03 7.40E-05 PA231 9.1OE+00 3.OOE-01 3.62E-01 0. 1.62E+00 3.85E-01 4.61E-05 PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06 U232 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+00 4.36E-05 U233 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03E-05 U234 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 U235 5.O1E-02 0. 3.52E-03 0. 1.OIE-02 3.28E-01 5.02E-05 U236 5.O1E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05 U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31E-05 U238 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 NP237 3.03E+00 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.1OE-05 NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05 NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1.78E-05 PU238 5.02E+00 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 PU239 5.50E+00 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 PU240 6.49E+00 6.71 E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 PU241 1.55E-01 6.69E-03 3.IIE-03 0. 1.15E-02 7.62E-04 8.97E-07 PU242 5.09E+00 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 PU244 5.95E+00 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 AM241 1.84E+00 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 AM242M 1.90E+00 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01 E-05 AM243 1.82E+00 8.1OE-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05 CM242 8.58E-02 744E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.IOE-05 CM243 1.73E+00 7.94E-01 1.06E-01 0. 3.91E-01 4.24E-01 5.02E-05 CM244 1.43E+00 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05 CM245 2.26E+00 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 CM246 2.24E+00 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 CM247 2.18E+00 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 CM248 1.82E+01 7.12E+00 1.1OE+00 0. 4.24E+00 3.23E+00 9.43E-04 CF252 4.26E+00 0. 1.OIE-01 0. 0. 1.37E+00 1.85E-04

Proc No ODCM Attachment 5 Revision 25 Page 5 of 16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 BEIO 8.43E-04 9.83E-05 2.12E-05 0. 0. 7.41E-04 1.72E-05 C14 970E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 F18 1.88E-06 0. 1.85E-07 0. 0. 0. 3.37E-07 NA22 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 NA24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 P32 7.04E-04 3.09E-05 2.67E-05 0. 0. 0. 1.14E-05 AR39 0. 0. 0. 0. 0. 4.89E-09 0.

AR4I 0. 0. 0. 0. 0. 1.68E-08 0.

CA4I 7.06E-05 0. 7.70E-06 0. 0. 7.21 E-02 2.94E-07 SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.45E-05 CR51 0. 0. 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07 MN54 0. 1.16E-05 2.57E-06 0. 2.71E-06 4.26E-04 6.19E-06 MN56 0. 4.48E-1O 8.43E-11 0. 4.52E-1O 3.55E-06 3.33E-05 FE55 1.28E-05 6.80E-06 2.1OE-06 0. 0. 3.OOE-05 7.75E-07 FE59 5.59E-06 9.04E-06 4.51 E-06 0. 0. 3.43E-04 1.91 E-05 C057 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.58E-06 C058 0. 4.79E-07 8.55E-07 0. 0. 2.99E-04 9.29E-06 C060 0. 3.55E-06 6.12E-06 0. 0. 1.91E-03 2.60E-05 NI59 1.66E-05 4.67E-06 2.83E-06 0. 0. 2.73E-05 6.29E-07 N163 2.22E-04 1.25E-05 7.56E-06 0. 0. 7.43E-05 1.71E-06 NI65 8.08E-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-05 CU64 0. 5.39E-10 2.90E-1O 0. 1.63E-09 2.59E-06 9.92E-06 ZN65 1.15E-05 3.06E-05 1.90E-05 0. 1.93E-05 2.69E-04 4.41E-06 ZN69M 4.26E-09 7.28E-09 8.59E-1O 0. 4.22E-09 7.36E-06 2.71E-05 ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.58E-11 3.84E-07 2.75E-06 SE79 0. 1.23E-06 2.60E-07 0. 1.71E-06 1.49E-04 3.43E-06 BR82 0. 0. 5.66E-06 0. 0. 0. 0.

BR83 0. 0. 1.28E-07 0. 0. 0. 0.

BR84 0. 0. 1.48E-07 0. 0. 0. 0.

BR85 0. 0. 6.84E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 1.22E-09 0.

KR85M 0. 0. 0. 0. 0. 6.58E-09 0.

KR85 0. 0. 0. 0. 0. 5.66E-09 0.

KR87 0. 0. 0. 0. 0. 3.38E-08 0.

KR88 0. 0. 0. 0. 0. 6.99E-08 0.

KR89 0. 0. 0. 0. 0. 4.55E-08 0.

RB86 0. 5.36E-05 3.09E-05 0. 0. 0. 2.16E-06 RB87 0. 3.16E-05 1.37E-05 0. 0. 0. 2.96E-07 RB88 0. 1.52E-07 9.90E-08 0. 0. 0. 4.66E-09 RB89 0. 9.33E-08 7.83E-08 0. 0. 0. 5.IIE-10 SR89 1.62E-04 0. 4.66E-06 0. 0. 5.83E-04 4.52E-05 SR9O 2.73E-02 0. 1.74E-03 0. 0. 3.99E-03 9.28E-05 SR9I 3.28E-08 0. 1.24E-09 0. 0. 1.44E-05 4.70E-05 SR92 3.54E-09 0. 1.42E-10 0. 0. 6.49E-06 6.55E-05

Includes a 50% increase to account for percutaneous transpiration.

Proc No ODCM Attachment 5 Revision 25 Page 6 of 16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREM!50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.11E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M 1.37E-1O 0. 4.98E-12 0. 0. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.1OE-04 4.97E-05 Y92 5.50E-09 0. 1.57E-1O 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.OIE-05 1.05E-04 ZR93 2.07E-04 7.80E-05 5.55E-05 0. 3.OOE-04 7.1OE-04 1.47E-05 ZR95 5.13E-05 1.13E-05 1.OOE-05 0. 1.61E-05 6.03E-04 1.65E-05 ZR97 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 N895 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.OOE-05 NB97 1.16E-1O 2.08E-11 9.74E-12 0. 2.31E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06 M099 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TCIOI 2.19E-14 2.30E-14 2.91E-13 0. 3.92E-13 1.58E-07 4.41E-09 RUIO3 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21E-05 RUIO5 4.13E-1O 0. 1.50E-10 0. 3.63E-1O 4.30E-06 2.69E-05 RU1O6 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 RHIO5 3.91E-09 2.1OE-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 PDIO7 0. 2.65E-07 2.51E-08 0. 1.97E-06 3.16E-05 7.26E-07 PDIO9 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AGIIOM 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 AGIII 1.81E-07 5.68E-08 3.75E-08 0. 1.71E-07 7.73E-05 2.98E-05 CDII3M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 CDI15M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN126 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 SB124 1.55E-05 2.OOE-07 5.41 E-06 3.41 E-08 0. 8.76E-04 4.43E-05 SB125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 SB126 1.72E-06 2.62E-08 6.16E-07 1.OOE-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51E-09 0. 6.17E-05 3.82E-05 TEI25M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TEI27M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91E-09 2.71E-06 1.52E-05 TE129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05 TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06 TE13IM 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07 TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133M 2.93E-11 1.51E-11 1.50E-11 2.32E-11 1.OIE-10 1.60E-06 4.77E-06 TE134 1.53E-11 8.81E12 9.40E-12 1.24E-11 5.71E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 0. 2.15E-07 1130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. 1.38E-06 1131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07

Proc No ODCM Attachment 5 Revision 25 Page 7 of 16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0. 1.48E-06 1134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XEI31M 0. 0. 0. 0. 0. 3.30E-09 0.

XEI33M 0. 0. 0. 0. 0. 4.36E-09 0.

XE133 0. 0. 0. 0. 0. 3.66E-09 0.

XEI35M 0. 0. 0. 0. 0. 4.48E-09 0.

XE135 0. 0. 0. 0. 0. 9.09E-09 0.

XE137 0. 0. 0. 0. 0. 4.07E-08 0.

XE138 0. 0. 0. 0. 0. 5.17E-08 0.

CS134M 6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS134 1.76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06 CS137 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81E-05 9.78E-07 CS138 1.71E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS139 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12 BA139 4.98E-1O 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05 BAI4O 2.OOE-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05 BAI4I 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 BA142 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10 LA14O 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.IOE-05 LAI41 2.28E-09 5.31E-1O 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-1O 1.IIE-1O 3.49E-11 0. 0. 2.35E-06 2.05E-05 CEI4I 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-06 1.47E-04 1.53E-05 CE143 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144 t83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11E-07 1.17E-04 2.63E-05 PR144 1.61E-11 4.99E-12 8.IOE-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05 PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PMI48M 3.31 E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.O1E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PMI5I 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.73E-04 9.OOE-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51E-04 2.79E-04 5.39E-05 EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TBI6O 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 H0166M 1.34E-03 2.81E-04 2.37E-04 0. 4.O1E-04 1.13E-03 1.63E-05 W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61E-07 W185 8.31E-07 2.08E-07 2.91E-08 0. 0. 1.86E-04 1.1IE-05 W187 4.41E-09 2.61E-09 1.17E-09 0. 0. 1.11E-05 2.46E-05

Proc No ODCM Attachment 5 Revision 25 Page 8 of 16 INHALATION DOSE COMMITMENT FACTORS CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB21O 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05 B1210 0. 5.11E-06 5.65E-07 0. 5.76E-05 3.70E-03 3.21E-05 P0210 1.70E-03 2.76E-03 4.09E-04 0. 8.85E-03 1.05E-01 4.32E-05 RN222 0. 0. 0. 0. 0. 4.82E-06 0.

RA223 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.OOE-04 RA224 8.44E-05 1.53E-07 1.69E-05 0. 4.06E-06 2.92E-02 3.34E-04 RA225 1.28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9.74E-02 2.84E-04 RA226 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04 RA228 1.49E-01 3.94E-06 1.68E-01 0. 1.04E-04 5.37E-01 5.14E-05 AC225 1.81E-03 1.87E-03 1.21E-04 0. 1.99E-04 7.37E-02 2.67E-04 AC227 4.96E+00 8.05E-01 3.07E-O1 0. 1.77E-01 8.04E-01 5.22E-05 TH227 9.24E-04 1.26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04 TH228 8.06E-01 1.04E-02 2.72E-02 0. 5.41E-02 3.34E+00 3.59E-04 TH229 1.28E+01 1.76E-01 6.31E-01 0. 8.68E-01 1.04E+01 3.27E-04 TH230 3.30E+00 1.73E-01 9.20E-02 0. 8.52E-01 1.85E+00 3.84E-05 TH232 3.68E+00 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+00 3.27E-05 TH234 6.94E-06 3.07E-07 2.OOE-07 0. 1.62E-06 6.31 E-04 7.32E-05 PA231 8.62E+00 2.86E-01 3.43E-01 0. 1.56E+00 1.92E-01 4.57E-05 PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9.77E-05 8.95E-06 U232 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05 U233 4.64E-02 0. 2.82E-03 0. 7.62E-03 1.77E-01 4.OOE-05 U234 4.46E-02 0. 2.76E-03 0. 7.47E-03 1.74E-01 3.92E-05 U235 4.27E-02 0. 2.59E-03 0. 7.01 E-03 1.63E-01 4.98E-05 U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05 U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1.29E-05 U238 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51E-05 NP237 2.88E+00 2.21E-01 1.19E-01 0. 7.41E-01 1.74E-01 5.06E-05 NP238 1.26E-06 2.56E-08 1.97E-08 0. 8.16E-08 3.39E-05 2.50E-05 NP239 1.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1.73E-05 PU238 4.77E+00 6.05E-01 1.21E-01 0. 4.47E-01 6.08E-01 4.65E-05 PU239 5.24E+00 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05 PU240 5.23E+00 6.43E-01 1.27E-01 0. 4.77E-01 5.71E-01 4.33E-05 PU241 1.46E-01 6.33E-03 2.93E-03 0. 1.1OE-02 5.06E-04 8.90E-07 PU242 4.85E+00 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05 PU244 5.67E+00 7.1OE-01 1.41E-01 0. 5.27E-01 6.30E-01 6.20E05 AM241 1.74E+00 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 AM242M 1.79E+00 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 AM243 1.72E+00 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05 CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05 CM243 1.61E+00 7.33E-01 9.95E-02 0. 3.74E-01 2.IOE-01 4.98E-05 CM244 1.33E+00 6.48E-01 8.31 E-02 0. 3.06E-01 2.02E-01 4.82E-05 CM245 2.14E+00 8.16E-01 1.28E-01 0. 5.03E-01 1.95E-01 4.49E-05 CM246 2.13E+00 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05 CM247 2.07E+00 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.80E-05 CM248 1.72E+01 6.61E÷00 1.04E+00 0. 4.08E+00 1.61E+00 9.35E-04 CF252 3.92E+00 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04

Proc No ODCM Attachment 5 Revision 25 Page 9 of 16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 BEIO 2.78E-04 4.33E-05 7.09E-06 0. 0. 3.84E-04 1.77E-05 C14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 N13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 F18 6.52E-07 0. 7.10E-08 0. 0. 0. 3.89E-08 NA22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 NA24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 P32 2.36E-04 1.37E-05 8.95E-06 0. 0. 0. 1.16E-05 AR39 0. 0. 0. 0. 0. 4.OOE-09 0.

AR41 0. 0. 0. 0. 0. 1.44E-08 0.

CA4I 4.05E-05 0. 4.38E-06 0. 0. 1.01 E-01 3.03E-07 SC46 7.24E-05 1.41E-04 4.18E-05 0. 1.35E-04 0. 2.98E-05 CR51 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07 MN54 0. 6.39E-06 1.05E-06 0. 1.59E-06 2.48E-04 8.35E-06 MN56 0. 2.12E-1O 3.15E-11 0. 2.24F-1O 1.90E-06 7.18E-06 FE55 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.55E-05 7.99E-07 FE59 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91E-04 2.23E-05 C057 0. 1.18E-07 1.15E-07 0. 0. 7.33E-05 3.93E-06 C058 0. 2.59E-07 3.47E-07 0. 0. 1.68E-04 1.19E-05 C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-05 N159 5.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-05 6.48E-07 N163 7.25E-05 5.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 N165 2.73E-1O 3.66E-11 1.59E-11 0. 0. 1.17E-06 4.59E-06 CU64 0. 2.54E-10 1.06E-10 0. 8.O1E-1O 1.39E-06 7.68E-06 ZN65 4.82E-06 1.67E-05 7.80E-06 0. 1.08E-05 1.55E-04 5.83E-06 ZN69M 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-05 ZN69 6.04E-12 1.15E-11 8.07E-13 0. 7.53E-12 1.98E-07 3.56E-08 SE79 0. 5.43E-07 8.71E-08 0. 8.13E-07 7.71E-05 3.53E-06 BR82 0. 0. 2.28E-06 0. 0. 0. 0.

BR83 0. 0. 4.30E-08 0. 0. 0. 0.

BR84 0. 0. 5.41 E-08 0. 0. 0. 0.

BR85 0. 0. 2.29E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 9.97E-10 0.

KR85M 0. 0. 0. 0. 0. 5.46E-09 0.

KR85 0. 0. 0. 0. 0. 4.63E-09 0.

KR87 0. 0. 0. 0. 0. 2.82E-08 0.

KR88 0. 0. 0. 0. 0. 5.81E-08 0.

KR89 0. 0. 0. 0. 0. 3.85E-08 0.

RB86 0. 2.38E-05 1.05E-05 0. 0. 0. 2.21E-06 RB87 0. 1.40E-05 4.58E-06 0. 0. 0. 3.05E-07 RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.65E-15 RB89 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17 SR89 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05 SR9O 1.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05 SR91 1.1OE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05 SR92 1.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05

Includes a 50% increase to account for percutaneous transpiration.

Proc No ODCM Attachment 5 Revision 25 Page 10 of 16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREM!50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 373E-07 0. 1.OOE-08 0. 0. 3.66E-05 6.99E-05 Y91M 4.63E-11 0. 1.77E-12 0. 0. 4.OOE-07 3.77E-09 Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.11E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05 ZR97 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 NB93M 4.14E-05 1.36E05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 N695 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91E-07 2.71E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81E-05 3.99E-06 M099 0. 2.IIE-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TCIOI 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RUIO3 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 RUIO5 1.40E-1O 0. 5.42E-11 0. 1.76E-1O 2.27E-06 1.13E-05 RU1O6 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.O1E-03 1.20E-04 RHIO5 1.32E-09 9.48E-1O 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD1O7 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 PDIO9 0. 6.56E-1O 1.66E-10 0. 3.36E-09 3.19E-06 1.96E-05 AGIIOM 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41E-05 AG11I 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.OOE-05 3.OOE-05 CDII3M 0. 2.17E-04 7.1OE-06 0. 2.43E-04 3.59E-04 1.68E-05 CD115M 0. 3.48E-05 1.14E-06 0. 2.82E-05 3.03E-04 5.IOE-05 SN123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 SN125 1.66E-06 4.42E.-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 SN126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05 SB124 5.38E-06 9.92E-08 2.1OE-06 1.22E-08 0. 4.81E-04 4.98E-05 SB125 9.23E-06 1.OIE-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.OIE-05 SB127 4.64E-08 9.92E-10 1.75E-08 5.21E-10 0. 3.31E-05 3.94E-05 TEI25M 6.IOE-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TEI27M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.IOE-10 1.40E-06 1.OIE-05 TE129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TEI31M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 TE133M 1.O1E-11 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07 TE134 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 1131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 8.1IE-07

Proc No ODCM Attachment 5 Revision 25 Page 11 ofl6 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. t59E-07 1133 t52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0. 1.29E-06 1134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XEI3IM 0. 0. 0. 0. 0. 2.70E-09 0.

XE133M 0. 0. 0. 0. 0. 3.59E-09 0.

XE133 0. 0. 0. 0. 0. 2.99E-09 0.

XE135M 0. 0. 0. 0. 0. 3.88E-09 0.

XE135 0. 0. 0. 0. 0. 7.55E-09 0.

XE137 0. 0. 0. 0. 0. 3.33E-08 0.

XE138 0. 0. 0. 0. 0. 4.38E-08 0.

CSI34M 2.20E-08 4.35E-08 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08 CS134 6.28E-05 1.41E-04 6.86E-05 0. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS136 6.44E-06 2.42E-05 1.71E-05 0. 1.38E-05 2.22E-06 1.36E-06 CS137 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51E-05 1.06E-06 CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11 CS139 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. 1.1IE-13 8.08E-07 8.06E-07 BA14O 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05 BAI4I 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.IIE-07 9.33E-14 BA142 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA14O 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 LAI4I 7.63E-10 2.35E-1O 3.87E-11 0. 0. 2.31E-06 1.54E-05 LA142 1.20E-10 5.31E-11 1.32E-11 0. 0. 1.27E-06 1.50E-06 CEI4I 3.55E-06 2.37E-06 2.71E-07 0. 1.11E-06 7.67E-05 1.58E-05 CE143 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE144 6.11E-04 2.53E-04 3.28E-05 0. 1.51E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 0. 1.26E-12 2.19E-07 2.94E-14 ND147 9.83E-07 1.07E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM147 1.15E-04 1.IOE-05 4.50E-06 0. 2.1OE-05 1.14E-04 5.87E-06 PM148M 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.IOE-05 PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM149 4.91 E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 PMI5I 1.20E-08 1.99E-09 1.O1E-09 0. 3.57E-09 6.56E-06 2.27E-05 SM15I 1.07E-04 2.1OE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.O1E-08 1.47E-09 0. 6.56E-09 7.1IE-06 1.77E-05 EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.O1E-04 1.35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU155 2.OOE-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51E-03 5.97E-05 EU156 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 TB16O 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05 H0166M 4.40E-04 1.36E-04 9.87E-05 0. 2.OOE-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.O1E-10 0. 0. 2.95E-06 2.69E-07 W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 W187 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05

Proc No 00CM Attachment 5 Revision 25 Page 12 of 16 INHALATION DOSE COMMITMENT FACTORS TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB2IO 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05 B1210 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05 P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21E-03 5.41E-02 4.45E-05 RN222 0. 0. 0. 0. 0. 3.94E-06 0.

RA223 2.57E-04 3.93E-07 5.14E-05 0. 1.12E-05 4.39E-02 3.04E-04 RA224 2.83E-05 6.77E-08 5.65E-06 0. 1.93E-06 1.51 E-02 3.29E-04 RA225 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04 RA226 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-O1 3.I1E-04 RA228 5.34E-02 1.74E-06 5.88E-02 0. 4.97E05 2.78E-01 5.30E-05 AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81 E-02 2.70E-04 AC227 2.49E+00 3.69E-01 1.48E-01 0. 1.07E-01 4.16E-01 5.38E-05 TH227 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04 TH228 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1.69E+00 3.70E-04 TH229 9.06E+00 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+00 3.36E-04 TI-1230 2.34E+00 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 TH232 2.61E+00 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05 TH234 2.32E-06 1.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E-05 PA231 5.32E+00 2.OOE-01 2.07E-01 0. 1.12E+00 9.91E-02 4.71E-05 PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.OOE-05 U232 7.31 E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05 U233 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4.12E-05 U234 1.48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05 U235 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05 U236 1.42E-02 0. 8.86E-04 0. 3.41 E-03 8.62E-02 3.79E-05 U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05 U238 1.36E-02 0. 8.1OE-04 0. 3.12E-03 7.89E-02 3.62E-05 NP237 1.77E+00 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05 NP238 4.23E-07 1.13E-08 6.59E-09 0. 3.88E-08 1.75E-05 2.38E-05 NP239 4.23E-08 3.99E-09 2.21E-09 0. 1.25E-08 8.11E-06 1.65E-05 PU238 2.86E+00 4.06E-01 7.22E-02 0. 3.1OE-01 3.12E-01 4.79E-05 PU239 3.31E+00 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 PU240 3.31E+00 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05 PU241 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07 PU242 3.07E+00 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 PU244 3.59E+00 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05 AM241 1.06E+00 4.07E-01 7.1OE-02 0. 5.32E-01 1.05E-01 4.88E-05 AM242M 1.07E+00 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 AM243 1.06E+00 3.92E-01 6.95E-02 0. 5.21E-01 9.91 E-02 5.72E-05 CM242 2.12E-02 2.14E-02 1.41E-03 0. 6.40E-03 6.76E-02 5.21E-05 CM243 8.45E-01 3.50E-01 5.OOE-02 0. 2.34E-01 1.09E-01 5.13E-05 CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81 E-01 1.05E-01 4.96E-05 CM245 1.32E+00 4.IIE-01 7.53E-02 0. 3.52E-01 1.O1E-01 4.63E-05 CM246 1.31E+00 4.11E-01 7.52E-02 0. 3.51E-01 1.03E-01 4.54E-05 CM247 1.28E+00 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 CM248 1.06E+01 3.33E+00 6.11E-01 0. 2.85E+00 8.32E-01 9.63E-04 CF252 1.29E+00 0. 3.07E-02 0. 0. 3.43E-01 1.89E-04

Proc No ODCM Attachment 5 Revision 25 Page 13 of 16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 BEIO 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05 C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 F18 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09 NA22 I .30E-05 1 .30E-05 1 .30E-05 I .30E-05 1 .30E-05 I .30E-05 1 .30E-05 NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 I.28E-06 1.28E-06 P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05 AR39 0. 0. 0. 0. 0. 2.08E-09 0.

AR41 0. 0. 0. 0. 0. 8.06E-09 0.

CA4I 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 SC46 5.51E-05 1.07E-04 3.I1E-05 0. 9.99E-05 0. 3.23E-05 CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07 MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06 MN56 0. 1.55E-10 2.29E-1I 0. 1.63E-10 1.18E-06 2.53E-06 FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.OIE-06 7.54E-07 FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05 C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06 C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05 C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05 N159 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.1IE-07 N163 5.40E-05 3.93E-06 1.81E-06 0. 0. 2.23E-05 1.67E-06 N165 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.OOE-07 1.54E-06 CU64 0. 1.83E-10 7.69E-11 0. 5.78E-10 8.48E-07 6.12E-06 ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06 ZN69M 1.02E-09 2.45E-09 2.24E-10 0. 1.48E-09 2.38E-06 1.71E-05 ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 1.15E-07 2.04E-09 SE79 0. 3.83E-07 6.09E-08 0. 5.69E-07 4.47E-05 3.33E-06 BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 BR83 0. 0. 3.01 E-08 0. 0. 0. 2.90E-08 BR84 0. 0. 3.91E-08 0. 0. 0. 2.05E-13 BR85 0. 0. 1.60E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 5.19E-10 0.

KR85M 0. 0. 0. 0. 0. 2.91 E-09 0.

KR85 0. 0. 0. 0. 0. 2.41 E-09 0.

KR87 0. 0. 0. 0. 0. 1.53E-08 0.

KR88 0. 0. 0. 0. 0. 3.13E-08 0.

KR89 0. 0. 0. 0. 0. 2.13E-08 0.

RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.08E-06 RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07 RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19 RB89 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21 SR89 3.80E-05 0. 1.09E-06 0. 0. I.75E-04 4.37E-05 SR9O 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05 SR91 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05 SR92 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06

Includes a 50% increase to account for percutaneous transpiration.

Proc No ODCM Attachment 5 Revision 25 Page 14 of 16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.61E-07 0. 7.O1E-09 0. 0. 2.12E-05 6.32E-05 Y9IM 326E-11 0. 1.27E-12 0. 0. 2.40E-07 166E-1O Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81E-05 Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06 Y93 1.18E-08 0. 3.26E-1O 0. 0. 6.06E-06 5.27E-05 ZR93 5.22E-05 2.92E-06 1.37E-06 0. 1.11E-05 2.13E-05 1.51E-06 ZR95 1.34E-05 4.30E-06 2.91E-06 0. 6.77E-06 2.21E-04 1.88E-05 ZR97 1.21E-08 2.45E-09 1.13E-09 0. 3.71E-09 9.84E-06 6.54E-05 NB93M 3.IOE-05 1.O1E-05 2.49E-06 0. 1.16E-05 3.11E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31E-05 1.30E-05 NB97 2.78E-11 7.03E-12 2.56E-12 0. 8.18E-12 3.OOE-07 3.02E-08 M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.IIE-05 3.79E-06 M099 0. 1.51E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.1OE-05 TC99M 1.29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01E-04 7.54E-06 TCIOI 5.22E-15 7.52E-15 7.38E-14 0. 1.35E-13 4.99E-08 1.36E-21 RUIO3 1.91E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 1.38E-05 RUIO5 9.88E-11 0. 3.89E-11 0. 1.27E-10 1.37E-06 6.02E-06 RUIO6 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 RHIO5 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05 PDIO7 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 PD1O9 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 AGIIOM 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AGI11 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 CDII3M 0. 1.54E-04 4.97E-06 0. 1.71E-04 2.08E-04 1.59E-05 CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.80E-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05 SN126 1.58E-04 4.18E-06 6.OOE-06 1.23E-06 0. 1.17E-03 1.59E-05 SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.IOE-04 5.08E-05 SB125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05 SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.O1E-05 SB127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E05 TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06 TE129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08 TE131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TEI31 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE133M 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08 TE134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.1IE-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0. 9.61E-07 1131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.85E-07

Proc No ODCM Attachment 5 Revision 25 Page 15 of 16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10 1135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0. 6.56E-07 XEI3IM 0. 0. 0. 0. 0. 1.40E-09 0.

XE133M 0. 0. 0. 0. 0. 1.89E-09 0.

XE133 0. 0. 0. 0. 0. 1.57E-09 0.

XE135M 0. 0. 0. 0. 0. 2.22E-09 0.

XE135 0. 0. 0. 0. 0. 4.05E-09 0.

XE137 0. 0. 0. 0. 0. 1.74E-08 0.

XE138 0. 0. 0. 0. 0. 2.44E-08 0.

CSI34M 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.1OE-05 0. 3.59E-05 1.22E-05 1.30E-06 CS135 1.46E-05 1.29E-05 5.99E-06 0. 5.11E-06 1.57E-06 2.11E-07 CS136 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-06 1.46E-06 CS137 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.OOE-08 6.07E-09 2.33E-13 CS139 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA139 1.17E-1O 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 BA14O 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E-05 BAI4I 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17 BA142 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1.49E-07 1.96E-26 LA14O 4.30E-08 2.17E-08 5.73E-09 0. 0. 1.70E-05 5.73E-05 LAI41 5.34E-10 1.66E-10 2.71E-11 0. 0. 1.35E-06 7.31E-06 LA142 8.54E-11 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07 CEI41 2.49E-06 1.69E-06 1.91E-07 0. 7.83E-07 4.52E-05 1.50E-05 CE143 2.33E-08 1.72E-08 1.91E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04 PR143 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91E-13 0. 8.81E-13 1.27E-07 2.69E-18 ND147 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06 PMI48M 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21E-06 2.50E-05 PMI51 8.50E-09 1.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.OOE-05 SMI5I 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU152 2.38E-04 5.41E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.1OE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.O1E-04 1.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05 TB16O 2.21E-05 0. 2.75E-06 0. 9.1OE-06 1.92E-04 2.68E-05 H0166M 3.37E-04 1.05E-04 8.OOE-05 0. 1.57E-04 3.94E-04 1.59E-05 W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71E-06 2.53E-07 W185 1.95E-07 6.47E-08 6.81E-09 0. 0. 5.57E-05 1.07E-05 W187 1.06E-09 8.85E-10 3.1OE-10 0. 0. 3.63E-06 1.94E-05

Proc No ODCM Attachment 5 Revision 25 Page 16 of 16 INHALATION DOSE COMMITMENT FACTORS ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB21O 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 B1210 0. 1.59E-06 1.32E-07 0. 1.92E-05 1.11E-03 2.95E-05 P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05 RN222 0. 0. 0. 0. 0. 2.05E-06 0.

RA223 1.80E-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04 RA224 1.98E-05 4.78E-08 3.96E-06 0. 1.35E-06 8.77E-03 3.O1E-04 RA225 3.OOE-04 3.56E-07 5.99E-05 0. 1.OIE-05 2.92E-02 2.71E-04 RA226 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04 RA228 4.41 E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61 E-01 5.OOE-05 AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21E-02 2.52E-04 AC227 2.30E+00 3.05E-01 1.36E-01 0. 9.82E-02 2.41 E-01 5.08E-05 TH227 2.17E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04 TH226 2.OOE-O1 3.39E-03 6.77E-03 0. 1.89E-02 1.O1E+O0 3.49E-04 TH229 8.88E+00 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+00 3.17E-04 TH230 2.29E+00 1.31E-01 6.36E-02 0. 6.40E-01 6.21E-01 3.73E-05 TH232 2.56E+00 1.12E-01 9.04E-02 0. 5.47E-01 5.96E-01 3.17E-05 TH234 1.63E-06 9.56E-08 4.70E-08 0. 5.41E-07 1.89E-04 7.03E-05 PA231 5.08E+00 1.91E-01 1.98E-01 0. 1.07E+00 5.75E-02 4.44E-05 PA233 1.21E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 1.02E-05 U232 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21E-05 U233 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05 U234 1.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81E-05 U235 1.OOE-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 U236 1.OOE-02 0. 6.20E-04 0. 2.39E-03 5.OOE-02 3.57E-05 U237 3.67E-08 0. 9.77E-09 0. 1.51E-07 1.02E-05 1.20E-05 U238 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41E-05 NP237 1.69E+00 1.47E-01 6.87E-02 0. 5.IOE-01 5.22E-02 4.92E-05 NP238 2.96E-07 8.OOE-09 4.61E-09 0. 2.72E-08 1.02E-05 2.13E-05 NP239 2.87E-08 2.82E-09 1.55E-09 0. 8.75E-09 4.70E-06 1.49E-05 PU238 2.74E+00 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 PU239 3.19E+00 4.31E-01 7.75E-02 0. 3.30E-01 1.72E-01 4.13E-05 PU240 3.18E+00 4.30E-01 7.73E-02 0. 3.29E-01 1.72E-01 4.21E-05 PU241 6.41E-02 3.28E-03 1.29E-03 0. 5.93E-03 1.52E-04 8.65E-07 PU242 2.95E+00 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05 PU244 3.45E+00 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05 AM241 1.O1E+00 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05 AM242M 1.02E+00 3.46E-01 6.73E-02 0. 5.01 E-01 244E-02 5.79E-05 AM243 1.O1E+00 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05 CM242 1.48E-02 1.51 E-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91 E-05 CM243 7.86E-01 2.97E-01 4.61E-02 0. 2.15E-01 6.31E-02 4.84E-05 CM244 5.90E-01 2.54E-01 3.51 E-02 0. 1.64E-01 6.06E-02 4.68E-05 CM245 1.26E+00 3.59E-01 7.14E-02 0. 3.33E-01 5.85E-02 4.36E-05 CM246 1.25E+00 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05 CM247 1.22E+00 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 CM248 1.OIE+01 2.91E+00 5.79E-01 0. 2.70E+00 4.82E-01 9.09E-04 CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04

Proc No ODCM Attachment 6 Revision 25 Page 1 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1 (mrem/hr per pCi/rn

)

2 ELEMENT TOTAL BODY SKIN H-3 0.0 0.0 C-14 0.0 0.0 Na-24 2.50E-08 2.90E-08 P-32 0.0 0.0 Cr-51 2.20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-56 1.IOE-08 1.30E-08 Fe-55 0.0 0.0 Fe-59 8.OOE-09 9.40E-09 Co-58 7.OOE-09 8.20E-09 Co-60 1 .70E-08 2.OOE-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.30E-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.OOE-09 4.60E-09 Zn-69 0.0 0.0 Br-83 6.40E-11 9.30E-11 Br-84 I .20E-08 I .40E-08 Br-85 0.0 0.0 Rb-86 6.30E-10 7.20E-10 Rb-88 3.50E-09 4.OOE-09 Rb-89 I .50E-08 I .80E-08 Sr-89 5.60E-13 6.50E-13 Sr-91 7.IOE-09 8.30E-09 Sr-92 9.OOE-09 I .OOE-08 Y-90 2.20E-12 2.60E-12 Y-91m 3.80E-09 4.40E-09 Y-91 2.40E-11 2.70E-11 Y-92 I .60E-09 I .90E-09 Y-93 5.70E-10 7.80E-l0 Zr-95 5.00 E-09 5.80 E-09 Zr-97 5.50E-09 6.40E-09 Nb-95 5.1OE-09 6.OOE-09 Mo-99 1 .90E-09 2.20 E-09 Tc-99m 9.60E-10 1.1OE-09 Tc-101 2.70E-09 3.OOE-09

Proc No ODCM Attachment 6 Revision 25 Page 2 of 2 EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND CDFG1 (mremlhr per pCi/rn

)

2 ELEMENT TOTAL BODY SKIN Ru-I 03 3.60E-09 4.20E-09 Ru-105 4.50E-09 5.IOE-09 Ru-106 I.50E-09 1.80E-09 Ag-Ibm l.80E-08 2.1OE-08 Te-125m 3.50E-I1 4.80E-11 Te-127m 1.IOE-12 I.30E-12 Te-127 I.OOE-1I 1.1OE-l1 Te-129m 7.70E-I0 9.OOE-10 Te-129 7.IOE-I0 8.40E-b0 Te-131m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-I32 1.70E-09 2.OOE-09 1-130 I.40E-08 I.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.OOE-08 1-133 3.70E-09 4.50E-09 1-134 I.60E-08 I.90E-08 1-135 1.20E-08 I.40E-08 Cs-134 l.20E-08 I.40E-08 Cs-136 I.50E-08 1.70E-08 Cs-I 37 4.20E-09 4.90E-09 Cs-138 2.1OE-08 2.40E-08 Ba-I 39 2.40E-09 2.70E-09 Ba-I40 2.IOE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-I 42 7.90E-09 9.OOE-09 La-I40 1.50E-08 1.70E-08 La-142 l.50E-08 1.80E-08 Ce-14I 5.50E-I0 6.20E-l0 Ce-I43 2.20E-09 2.50E-09 Ce-144 3.20E-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.OOE-10 2.30E-bO Nd-I47 1.OOE-09 1.20E-09 W-187 3.IOE-09 3.60E-09 Np-239 9.50E-b0 I.IOE-09

Proc No ODCM Attachment 7 Revision 25 Page 1 of I BIOACCUMULATION FACTORS i.Cilpm per nCiImI FRES HWATER ELEMENT FISH H 9.OE-O1 C 46E 03 NA 1.0E02 P 1.0E05 CR 2.OE 02 MN 4.OE 02 FE 1.0E02 CO 5.OE 01 NI 1.0E02 CU 5.OE 01 ZN 2.0E03 BR 4.2E 02 RB 2.OE 03 SR 3.OE 01 Y 2.5E 01 ZR 3.3E 00 NB 3.OE 04 MO 1.OEOI TC 1.5E01 RU 1.OEO1 RH 1.OEOI TE 4.0E02 I 1.5E01 CS 2.0E03 BA 4.OEOO LA 2.5E01 CE 1.OEOO PR 2.5E 01 ND 2.5E 01 W 1.2E03 NP 1.OEOI

Proc No ODCM Attachment 8 Revision 25 Page 1 of 16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07 BEIO 1.71E-05 2.49E-06 5.16E-07 0. 1.64E-06 0. 2.78E-05 C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 N13 5.85E-08 5.85E-08 5.85E-08 5.835E-08 5.85E-08 5.85E-08 5.85E-08 F18 5.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06 NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 NA24 1.O1E-05 1.QIE-05 1.OIE-05 1.OIE-05 1.OIE-05 1.O1E-05 1.OIE-05 P32 1.70E-03 1.OOE-04 6.59E-05 0. 0. 0. 2.30E-05 AR39 0. 0. 0. 0. 0. 0. 0.

AR4I 0. 0. 0. 0. 0. 0. 0.

CA41 3.74E-04 0. 4.08E-05 0. 0. 0. 1.91 E-07 SC46 3.75E-08 5.41 E-08 1.69E-08 0. 3.56E-08 0. 3.53E-05 CR51 0. 0. 1.41E-08 9.20E-09 2.O1E-09 1.79E-08 4.I1E-07 MN54 0. 1.99E-05 4.51E-06 0. 4.41E-06 0. 7.31E-06 MN56 0. 8.18E-07 1.41E-07 0. 7.03E-07 0. 7.43E-05 FE55 1.39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 FE59 3.08E-05 5.38E-05 2.12E-05 0. 0. 1.59E-05 2.57E-05 C057 0. 1.15E-06 1.87E-06 0. 0. 0. 3.92E-06 C058 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 C060 0. 1.08E-05 2.55E-05 0. 0. 0. 2.57E-05 N159 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16E-07 NI63 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. 1.95E-06 N165 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05 CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.25E-05 ZN65 1.84E-05 6.31E-05 2.91E-05 0. 3.06E-05 0. 5.33E-05 ZN69M 1.50E-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-05 ZN69 9.33E-08 1.68E-07 1.25E-08 0. 6.98E-08 0. 1.37E-05 SE79 0. 2.1OE-05 3.90E-06 0. 2.43E-05 0. 5.58E-07 BR82 0. 0. 1.27E-05 0. 0. 0. 0.

BR83 0. 0. 3.63E-07 0. 0. 0. 0.

BR84 0. 0. 3.82E-07 0. 0. 0. 0.

BR85 0. 0. 1.94E-08 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. 0. 0. 0. 0. 0. 0.

KR87 0. 0. 0. 0. 0. 0. 0.

KR88 0. 0. 0. 0. 0. 0. 0.

KR89 0. 0. 0. 0. 0. 0. 0.

RB86 0. 1.70E-04 8.40E-05 0. 0. 0. 4.35E-06 RB87 0. 8.88E-05 3.52E-05 0. 0. 0. 5.98E-07 RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.85E-07 RB89 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 SR89 2.51E-03 0. 7.20E-05 0. 0. 0. 5.16E-05 SR9O 1.85E-02 0. 4.71 E-03 0. 0. 0. 2.31 E-04 SR91 5.OOE-05 0. 1.81E-06 0. 0. 0. 5.92E-05 SR92 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04

Proc No ODCM Attachment 8 Revision 25 Page 2 of 16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91M 8.1OE-1O 0. 2.76E-11 0. 0. 0. 2.70E-06 Y91 1.13E-06 0. 3.OIE-08 0. 0. 0. 8.1OE-05 Y92 7.65E-09 0. 2.15E-1O 0. 0. 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93 1.93E-07 9.18E-08 5.54E-08 0. 2.71E-07 0. 2.39E-05 ZR95 2.06E-07 5.02E-08 3.56E-08 0. 5.41 E-08 0. 2.50E-05 ZR97 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 NB95 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05 NB97 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21E-06 M099 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99M 1.92E-09 3.96E-09 5.10E-08 0. 4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31E-06 TCIOI 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RUIO3 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RUIO5 1.36E-07 0. 4.58E-08 0. 1.OOE-06 0. 5.41E-05 RU106 2.41E-05 0. 3.OIE-06 0. 2.85E-05 0. 1.83E-04 RH1O5 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 PDIO7 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07 PD109 0. 1.50E-06 3.62E-07 0. 5.51E-06 0. 3.68E-05 AGIIOM 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05 AGIII 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E-05 CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CDII5M 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E-05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 0. 0. 6.58E-05 SN125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.IIE-04 SN126 5.53E-04 7.26E-06 1.80E-05 1.91E-06 0. 0. 2.52E-05 SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05 SB125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91E-05 TEI25M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.IIE-05 TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.1OE-05 TE129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05 TEI31M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0. 1.03E-04 TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.1IE-06 TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.81E-05 TEI33M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 0. 1.93E-05 TE134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.06E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E..02 2.51E-05 0. 4.24E-07 1130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 1.51E-06

Proc No ODCM Attachment 8 Revision 25 Page 3 of 16 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06 1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0. 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06 1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XEI3IM 0. 0. 0. 0. 0. 0. 0.

XE133M 0. 0. 0. 0. 0. 0. 0.

XE133 0. 0. 0. 0. 0. 0. 0.

XE135M 0. 0. 0. 0. 0. 0. 0.

XE135 0. 0. 0. 0. 0. 0. 0.

XE137 0. 0. 0. 0. 0. 0. 0.

XE138 0. 0. 0. 0. 0. 0. 0.

CSI34M 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.77E-04 7.03E-04 7.1OE-05 0. 1.81E-04 7.42E-05 1.91E-06 CS135 1.33E-04 1.21E-04 6.30E-06 0. 3.44E-05 1.31E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.IOE-05 2.05E-06 CS137 5.22E-04 6.IIE-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91E-06 CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 CS139 3.IOE-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05 BAI4O 1.71E-04 1.71E-07 8.81E-06 0. 4.06E-08 1.05E-07 4.20E-05 BA141 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E-10 5.19E-06 BA142 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-11 9.26E-11 7.59E-07 LA14O 2.I1E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 LAI4I 2.89E-09 8.38E-10 1.46E-1O 0. 0. 0. 9.61E-05 LA142 1.1OE-09 4.04E-1O 9.67E-11 0. 0. 0. 6.86E-05 CE14I 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.71E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-11 0. 4.93E-06 ND147 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.88E-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06 PMI48M 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1.38E-08 1.81E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 PM15I 6.18E-09 9.O1E-10 4.56E-1O 0. 1.07E-09 0. 4.17E-05 SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05 EU152 6.74E-07 1.79E-07 1.51E-07 0. 5.02E-07 0. 1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TBI6O 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05 H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0.

W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05

Proc No ODCM Attachment 8 Revision 25 Page4ofl6 INGESTION DOSE COMMITMENT FACTORS INFANT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB21O 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 BI2IO 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.276-05 P0210 3.IOE-03 5.93E-03 7.41E-04 0. 1.26E-02 0. 6.61E-05 RN222 0. 0. 0. 0. 0. 0. 0.

RA223 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04 RA224 1.46E-02 3.296-05 2.91E-03 0. 6.OOE-04 0. 3.866-04 RA225 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04 RA226 6.20E-01 4.76E-05 5.14E-01 0. 8.71 E-04 0. 3.446-04 RA228 4.32E-01 2.58E-05 4.866-01 0. 4.73E-04 0. 5.866-05 AC225 3.92E-05 5.036-05 2.63E-06 0. 3.69E-06 0. 4.36E-04 AC227 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05 TH227 1.20E-04 2.OIE-06 3.45E-06 0. 7.41E-06 0. 5.70E-04 TH228 2.476-03 3.38E-05 8.366-05 0. 1.58E-04 0. 5.84E-04 Th229 1.486-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31 E-04 TH230 3.80E-03 1.90E-04 1.066-04 0. 9.12E-04 0. 6.246-05 TH232 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31E-05 TH234 6.92E-07 3.77E-08 2.006-08 0. 1.39E-07 0. 1.19E-04 PA231 7.576-03 2.50E-04 3.02E-04 0. 1.346-03 0. 7.446-05 PA233 3.116-08 6.09E-09 5.436-09 0. 1.676-08 0. 1.466-05 U232 2.42E-02 0. 2.166-03 0. 2.37E-03 0. 7.04E-05 U233 5.086-03 0. 3.876-04 0. 1.08E-03 0. 6.51E-05 U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.376-05 U235 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.IOE-05 U236 4.67E-03 0. 3.64E-04 0. 1.OIE-03 0. 5.98E-05 U237 4.956-07 0. 1.326-07 0. 1.23E-06 0. 2.I1E-05 U238 4.476-03 0. 3.33E-04 0. 9.286-04 0. 5.716-05 NP237 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.236-05 NP238 1.246-07 3.126-09 1.92E-09 0. 6.81E-09 0. 4.17E-05 NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.986-09 0. 2.876-05 PU238 1.346-03 1.696-04 3.40E-05 0. 1.216-04 0. 7.576-05 PU239 1.456-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.916-05 PU240 1.45E-03 1.776-04 3.546-05 0. 1.28E-04 0. 7.04E-05 PU241 4.38E-05 1.906-06 8.826-07 0. 3.176-06 0. 1.456-06 PU242 1.356-03 1.706-04 3.41E-05 0. 1.236-04 0. 6.77E-05 PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41E-04 0. 1.O1E-04 AM241 1.53E-03 7.186-04 1.09E-04 0. 6.556-04 0. 7.70E-05 AM242M 1.586-03 7.026-04 1.13E-04 0. 6.64E-04 0. 9.696-05 AM243 1.51E-03 6.886-04 1.06E-04 0. 6.366-04 0. 9.03E-05 CM242 1.376-04 1.24E-04 9.1OE-06 0. 2.626-05 0. 8.236-05 CM243 1.45E-03 6.886-04 8.986-05 0. 3.276-04 0. 8.1OE-05 CM244 1.226-03 6.166-04 7.596-05 0. 2.71E-04 0. 7.84E-05 CM245 1.886-03 7.496-04 1.13E-04 0. 4.326-04 0. 7.306-05 CM246 1.876-03 7.49E-04 1.13E-04 0. 4.316-04 0. 7.17E-05 CM247 1.82E-03 7.36E-04 1.116-04 0. 4.246-04 0. 9.43E-05 CM248 1.51E-02 6.076-03 9.166-04 0. 3.506-03 0. 1.526-03 CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04

Proc No ODCM Attachment 8 Revision 25 Page 5 of 16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 113 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 BEIO 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05 C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 N13 3.1OE-08 3.1OE-08 3.1OE-08 3.1OE-08 3.IOE-08 3.1OE-08 3.1OE-08 F18 2.49E-06 0. 2.47E-07 0. 0. 0. 6.74E-07 NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 P32 8.25E-04 3.86E-05 3.18E-05 0. 0. 0. 2.28E-05 AR39 0. 0. 0. 0. 0. 0. 0.

AR41 0. 0. 0. 0. 0. 0. 0.

CA4I 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07 SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05 CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07 MN54 0. 1.07E-05 2.85E-06 0. 3.OOE-06 0. 8.98E-06 MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 0. 4.84E-05 FE55 1.15E-05 6.IOE-06 1.89E-06 0. 0. 3.45E-06 1.13E-06 FE59 1.65E-05 2.67E-05 1.33E-05 0. 0. 7.74E-06 2.78E-05 C057 0. 4.93E-07 9.98E-07 0. 0. 0. 4.04E-06 C058 0. 1.80E-06 5.51E-06 0. 0. 0. 1.05E-05 C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05 N159 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.1OE-07 N163 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 N165 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.56E-05 CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05 ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41 E-06 ZN69M 7.IOE-07 1.21E-06 1.43E-07 0. 7.03E-07 0. 3.94E-05 ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84E-08 0. 3.99E-06 SE79 0. 8.43E-06 1.87E-06 0. 1.37E-05 0. 5.53E-07 BR82 0. 0. 7.55E-06 0. 0. 0. 0.

BR83 0. 0. 1.71E-07 0. 0. 0. 0.

BR84 0. 0. 1.98E-07 0. 0. 0. 0.

BR85 0 0. 9.12E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. 0. 0. 0. 0. 0. 0.

KR87 0. 0. 0. 0. 0. 0. 0.

KR88 0. 0. 0. 0. 0. 0. 0.

KR89 0. 0. 0. 0. 0. 0. 0.

RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31E-06 RB87 0. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07 RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09 RB89 0. 1.17E-07 1.04E-07 0. 0. 0. 1.02E-09 SR89 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11E-05 SR9O 1.70E-02 0. 4.31E-03 0. 0. 0. 2.29E-04 SR91 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05 SR92 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71E-04

Proc No ODCM Attachment 8 Revision 25 Page 6 of 16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 4.1IE-08 0. 1.1OE-09 0. 0. 0. 1.17E-04 Y9IM 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1.04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04 ZR93 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97 6.99E-09 1.O1E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 NB93M 1.05E-07 2.62E-08 8.61 E-09 0. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05 NB97 2.17E-10 3.92E-11 1.83E-11 0. 4.35E-11 0. 1.21E-05 M093 0. 2.41E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.1OE-05 TC99M 9.23E-1O 1.81E-09 3.OOE-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC1OI 1.07E-09 1.12E-09 1.42E-08 0. 1.91E-08 5.92E-10 3.56E-09 RUIO3 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E-05 RU1O5 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 RUIO6 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 RHIO5 5.14E-07 2.76E-07 2.36E-07 0. 1.1OE-06 0. 1.71E-05 PD1O7 0. 4.72E-07 4.OIE-08 0. 3.95E-06 0. 9.37E-07 PDIO9 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AG1IOM 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05 AGIII 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 CD1I3M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 CD1I5M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.O1E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05 SN125 3.55E-05 5.35E-07 t59E-06 5.55E-07 0. 0. 1.1OE-04 SN126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05 SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.1OE-06 8.87E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.1OE-05 TE127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 2.34E-05 TE127 4.71E-07 1.27E-07 1.OIE-07 3.26E-07 1.34E-06 0. 1.84E-05 TE129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0. 1.O1E-04 TEI3I 8.30E08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 TE132 1.O1E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05 TE133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.77E-06 TE134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.376-07 0. 5.89E-07 1129 1.396-05 8.53E-06 7.62E-06 5.586-03 1.44E-05 0. 4.29E-07 1130 2.926-06 5.906-06 3.04E-06 6.506-04 8.82E-06 0. 2.766-06 1131 1.726-05 1.73E-05 9.83E-06 5.726-03 2.84E-05 0. 1.54E-06

Proc No ODCM Attachment 8 Revision 25 Page 7 of 16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06 1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06 1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

XEI33M 0. 0. 0. 0. 0. 0. 0.

XE133 0. 0. 0. 0. 0. 0. 0.

XEI35M 0. 0. 0. 0. 0. 0. 0.

XE135 0. 0. 0. 0. 0. 0. 0.

XE137 0. 0. 0. 0. 0. 0. 0.

XE138 0. 0. 0. 0. 0. 0. 0.

CS134M 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS134 2.34E-04 3.84E-04 8.IOE-05 0. 1.19E-04 4.27E-05 2.07E-06 CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33E-07 CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06 CS137 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.17E-07 2.O1E-07 0. 2.23E-07 2.40E-08 1.46E-07 CS139 1.45E-07 1.61E-07 7.74E-08 0. 1.21E-07 1.22E-08 1.45E-11 BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-1O 2.39E-05 BA14O 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05 BAI4I 2.OOE-07 1.12E-1O 6.51E-09 0. 9.69E-11 6.58E-1O 1.14E-07 BA142 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09 LAI4O 1.O1E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05 CEI4I 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143 6.99E-09 3.79E-06 5.49E-1O 0. 1.59E-09 0. 5.55E-05 CE144 2.08E-06 6.52E-07 1.11E-07 0. 3.61E-07 0. 1.70E-04 PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39EO9 0. 4.24E-05 PR144 1.29E-1O 3.99E-11 6.49E-12 0. 2.I1E-11 0. 8.59E-08 ND147 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05 PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.O1E-08 0. 9.19E-06 PM148M 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05 PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05 PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05 PMI51 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05 SMI5I 2.56E-07 3.81E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05 EU156 5.62E08 3.O1E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05 TB16O 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05 H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0.

W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07 W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61E-05 W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05

Proc No ODCM Attachment 8 Revision 25 Page 8 of 16 INGESTION DOSE COMMITMENT FACTORS CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB2IO 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05 81210 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.17E-05 P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05 RN222 0. 0. 0. 0. 0. 0. 0.

RA223 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04 RA224 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.78E-04 RA225 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21 E-04 RA226 5.75E-01 1.84E-05 4.72E-01 0. 4.88E-04 0. 3.41E-04 RA228 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.81 E-05 AC225 1.88E-05 1.94E-05 1.26E-06 0. 2.07E-06 0. 4.31E-04 AC227 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05 TH227 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04 TH228 2.07E-03 2.65E-05 7.OOE-05 0. 1.38E-04 0. 5.79E-04 TH229 1.38E-02 1.81E-04 6.80E-04 0. 8.84E-04 0. 5.27E-04 TH230 3.55E-03 1.78E-04 9.91E-05 0. 8.67E-04 0. 6.19E-05 TH232 3.96E-03 1.52E-04 3.O1E-04 0. 7.41E-04 0. 5.27E-05 TH234 3.42E-07 1.51E-08 9.88E-09 0. 8.OIE-08 0. 1.18E-04 PA231 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05 PA233 1.81E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05 U232 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05 U233 3.72E-03 0. 2.25E-04 0. 6.1OE-04 0. 6.45E-05 U234 3.57E-03 0. 2.21 E-04 0. 5.98E-04 0. 6.32E-05 U235 3.42E-03 0. 2.07E-04 0. 5.61 E-04 0. 8.03E-05 U236 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05 U237 2.36E-07 0. 6.27E-08 0. 6.81 E-07 0. 2.08E-05 U238 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05 NP237 2.36E-03 1.81E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05 NP238 5.83E-08 1.18E-09 9.08E-10 0. 3.76E-09 0. 4.04E-05 NP239 5.25E-09 3.77E-10 2.65E-10 0. 1.09E-09 0. 2.79E-05 PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05 PU239 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.85E-05 PU240 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.98E-05 PU241 4.OOE-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06 PU242 1.26E-03 1.59E-04 3.19E-05 0. 1.17E-04 0. 6.71E-05 PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 0. 1.OOE-04 AM241 1.43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05 AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 0. 9.61E-05 AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05 CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05 CM243 1.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05 CM244 1.11E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05 CM245 1.76E-03 6.64E-04 1.05E-04 0. 4.11E-04 0. 7.24E-05 CM246 1.74E-03 6.64E-04 1.05E-04 0. 4.10E04 0. 7.1IE-05 CM247 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05 CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51E-03 CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04

Proc No ODCM Attachment 8 Revision 25 Page 9 of 16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 BE1O 4.48E-06 6.94E-07 1.13E-07 0. 5.30E-07 0. 2.84E-05 C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 N13 1.15E-08 1.15E-08 l.15E-08 l.15E-08 1.15E-08 l.15E-08 l.15E-08 F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08 NA22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 P32 2.76E-04 1.71E-05 1.07E-05 0. 0. 0. 2.32E-05 AR39 0. 0. 0. 0. 0. 0. 0.

AR4I 0. 0. 0. 0. 0. 0. 0.

CA4I 1.97E-04 0. 2.13E-05 0. 0. 0. 1.95E-07 SC46 7.24E-09 1.41E-08 4.18E-09 0. 1.35E-08 0. 4.80E-05 CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07 MN54 0. 5.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-05 MN56 0. 1.58E-07 2.81E-08 0. 2.OOE-07 0. 1.04E-05 FE55 3.78E-06 2.68E-06 6.25E-07 0. 0. 1.70E-06 1.16E-06 FE59 5.87E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E-05 C057 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 C058 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05 C060 0 2.81 E-06 6.33E-06 0. 0. 0. 3.66E-05 N159 1.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07 N163 1.77E-04 1.25E-05 6.OOE-06 0. 0. 0. 1.99E-06 N165 7.49E-07 9.57E-08 4.36E-08 0. 0. 0. 5.193-06 CU64 0. 1.15E-07 5.41E-08 0. 2.91E-07 0. 8.92E-06 ZN65 5.76E-06 2.OOE-05 9.33E-06 0. 1.28E-05 0. 8.47E-06 ZN69M 2.40E-07 5.66E-07 5.19E-08 0. 3.44E-07 0. 3.11E-05 ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. 5.16E-08 SE79 0. 3.73E-06 6.27E-07 0. 6.50E-06 0. 5.70E-07 BR82 0. 0. 3.04E-06 0. 0. 0. 0.

BR83 0. 0. 5.74E-08 0. 0. 0. 0.

BR84 0. 0. 7.22E-08 0. 0. 0. 0.

BR85 0. 0. 3.05E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. 0. 0. 0. 0. 0. 0.

KR87 0. 0. 0. 0. 0. 0. 0.

KR88 0. 0. 0. 0. 0. 0. 0.

KR89 0. 0. 0. 0. 0. 0. 0.

RB86 0. 2.98E-05 1.40E-05 0. 0. 0. 4.41E-06 RB87 0. 1.75E-05 6.IIE-06 0. 0. 0. 6.IIE-07 RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15 RB89 0. 5.50E-08 3.89E-08 0. 0. 0. 8.43E-17 SR89 4.40E-04 0. 1.26E-05 0. 0. 0. 5.24E-05 SR9O 8.30E-03 0. 2.05E-03 0. 0. 0. 2.33E-04 SR9I 8.07E-06 0. 3.21 E-07 0. 0. 0. 3.66E-05 SR92 3.05E-06 0. 1.30E-07 0. 0. 0. 7.77E-05

Proc No ODCM Attachment 8 Revision 25 Page 10 of 16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREM!50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.376-08 0. 3.696-10 0. 0. 0. 1.13E-04 Y9IM 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 Y91 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y92 1.21 E-09 0. 3.506-11 0. 0. 0. 3.326-05 Y93 3.836-09 0. 1.05E-10 0. 0. 0. 1.17E-04 ZR93 5.53E-08 2.736-08 1.49E-08 0. 9.656-08 0. 2.58E-05 ZR95 4.12E-08 1.30E-08 8.94E-09 0. 1.916-08 0. 3.OOE-05 ZR97 2.376-09 4.696-10 2.16E-10 0. 7.11E-10 0. 1.276-04 NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06 NB95 8.22E-09 4.56E-09 2.51E-09 0. 4.42E-09 0. 1.95E-05 NB97 7.37E-11 1.83E-11 6.686-12 0. 2.14E-11 0. 4.376-07 M093 0. 1.06E-05 2.90E-07 0. 3.046-06 0. 1.29E-06 M099 0. 6.036-06 1.156-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.146-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.726-08 6.44E-06 TCIOI 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.756-17 RUIO3 2.55E-07 0. 1.096-07 0. 8.996-07 0. 2.136-05 RUIO5 2.18E-08 0. 8.466-09 0. 2.75E-07 0. 1.76E-05 RUIO6 3.926-06 0. 4.94E-07 0. 7.56E-06 0. 1.886-04 RHIO5 1.736-07 1.256-07 8.20E-08 0. 5.31E-07 0. 1.596-05 PDIO7 0. 2.08E-07 1.346-08 0. 1.88E-06 0. 9.66E-07 PDIO9 0. 2.51E-07 5.70E-08 0. 1.45E-06 0. 2.53E-05 AGIIOM 2.05E-07 1.946-07 1.186-07 0. 3.706-07 0. 5.45E-05 AGIII 8.29E-08 3.44E-08 1.73E-08 0. 1.126-07 0. 4.80E-05 CDI13M 0. 4.516-06 1.456-07 0. 4.99E-06 0. 2.71E-05 CDII5M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.08E-06 5.846-07 0. 0. 6.71E-05 SN125 1.196-05 2.376-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 SN126 1.166-04 2.16E-06 3.306-06 5.69E-07 0. 0. 2.586-05 SB124 3.87E-06 7.13E-08 1.51E-06 8.786-09 0. 3.38E-06 7.80E-05 SB125 2.486-06 2.71E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.716-07 8.996-09 0. 1.14E-06 9.416-05 SB127 3.636-07 7.766-09 1.376-07 4.086-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.386-06 5.126-07 1.076-06 0. 0. 1.13E-05 TE127M 9.676-06 3.436-06 1.156-06 2.30E-06 3.92E-05 0. 2.41E-05 TE127 1.58E-07 5.606-08 3.406-08 1.096-07 6.406-07 0. 1.226-05 TE129M 1.636-05 6.05E-06 2.586-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE13IM 2.44E-06 1.176-06 9.76E-07 1.766-06 1.22E-05 0. 9.39E-05 TE13I 2.796-08 1.15E-08 8.726-09 2.15E-08 1.22E-07 0. 2.296-09 TE132 3.49E-06 2.216-06 2.086-06 2.336-06 2.126-05 0. 7.006-05 TE133M 6.44E-08 3.666-08 3.566-08 5.116-08 3.62E-07 0. 1.48E-07 TE134 4.47E-08 2.876-08 3.006-08 3.67E-08 2.746-07 0. 1.66E-09 1129 4.666-06 3.92E-06 6.54E-06 4.776-03 7.016-06 0. 4.576-07 1130 1.03E-06 2.986-06 1.196-06 2.43E-04 4.596-06 0. 2.296-06 1131 5.85E-06 8.196-06 4.40E-06 2.396-03 1.416-05 0. 1.626-06

Proc No ODCM Attachment 8 Revision 25 Page 11 oflG INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07 1133 2.O1E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.58E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.1OE-07 0. 5.1OE-09 1135 6.IOE-07 1.57E-06 5.82E-07 1.OIE-04 2.48E-06 0. 1.74E-06 XEI3IM 0. 0. 0. 0. 0. 0. 0.

XE133M 0. 0. 0. 0. 0. 0. 0.

XE133 0. 0. 0. 0. 0. 0. 0.

XE135M 0. 0. 0. 0. 0. 0. 0.

XE135 0. 0. 0. 0. 0. 0. 0.

XE137 0. 0. 0. 0. 0. 0. 0.

XE138 0. 0. 0. 0. 0. 0. 0.

CSI34M 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.72E-06 CS137 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.1OE-07 1.28E-08 6.76E-11 CS139 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23 BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06 BA14O 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 BAI41 6.71E-08 5.OIE-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13 BA142 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20 LA14O 3.48E-09 1.71E-09 4.55E-10 0. 0. 0. 9.82E-05 LAI4I 4.55E-1O 1.40E-1O 2.31E-11 0. 0. 0. 2.48E-05 LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06 CEI41 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05 CE143 2.35E-09 1.71E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05 CE144 6.96E-07 2.88E-07 3.74E-08 0. 1.72E-07 0. 1.75E-04 PR143 1.31E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.31E-05 PR144 4.30E-11 1.76E-11 2.18E-12 0. 1.O1E-11 0. 4.74E-14 ND147 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06 PMI48M 4.14E-08 1.05E-08 8.21 E-09 0. 1.59E-08 0. 6.61 E-05 PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.OOE-09 0. 9.90E-05 PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05 PMI5I 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05 SM15I 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.O1E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05 EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05 TB16O 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05 H0166M 3.57E-07 1.1OE-07 7.96E-08 0. 1.61E-07 0. 0.

W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07 W185 5.79E-07 1.91E-07 2.02E-08 0. 0. 0. 1.65E-05 W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 3.22E-05

Proc No ODCM Attachment 8 Revision 25 Page 12 of 16 INGESTION DOSE COMMITMENT FACTORS TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB21O 1.81E-02 5.44E-03 7.OIE-04 0. 1.72E-02 0. 5.74E-05 B1210 6.59E-07 4.51E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05 P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05 RN222 0. 0. 0. 0. 0. 0. 0.

RA223 7.1IE-03 1.08E-05 1.42E-03 0. 3.1OE-04 0. 3.43E-04 RA224 2.31E-03 5.52E-06 4.61E-04 0. 1.58E-04 0. 3.71E-04 RA225 9.37E-03 1.1OE-05 1.87E-03 0. 3.15E-04 0. 3.27E-04 RA226 3.22E-O1 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51E-04 RA228 1.37E-01 4.41E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04 AC227 2.05E-03 3.03E-04 1.22E-04 0. 8.81 E-05 0. 8.68E-05 TH227 1.96E-05 3.52E-07 5.65E-07 0. 2.OIE-06 0. 5.75E-04 TH228 6.80E-04 1.14E-05 2.30E-05 0. 6.41E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.I1E-04 0. 6.1OE-04 0. 5.43E-04 TH230 2.16E-03 1.23E-04 6.OOE-05 0. 5.99E-04 0. 6.38E-05 TH232 2.42E-03 1.05E-04 1.63E-04 0. 5.I1E-04 0. 5.43E-05 TH234 1.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21E-04 PA231 4.31E-03 1.62E-04 1.68E-04 0. 9.1OE-04 0. 7.60E-05 PA233 7.33E-09 1.41E-09 1.26E-09 0. 5.32E-09 0. 1.61E-05 U232 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05 U233 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51E-05 U235 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.11E-05 U237 7.89E-08 0. 2.1OE-08 0. 3.24E-07 0. 2.09E-05 U238 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-11 0. 5.21E-10 0. 2.67E-05 PU238 7.21E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.73E-05 PU239 8.27E-04 1.12E-04 2.OIE-05 0. 8.57E-05 0. 7.06E-05 PU240 8.26E-04 1.12E-04 2.OIE-05 0. 8.56E-05 0. 7.19E-05 PU241 1.84E-05 9.42E-07 3.69E-07 0. 1.71E-06 0. 1.48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.25E-05 0. 6.92E-05 PU244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 1.03E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31 E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05 AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05 CM242 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05 CM243 6.91E-04 2.86E-04 4.09E-05 0. 1.91E-04 0. 8.28E-05 CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.OOE-05 CM245 1.07E-03 3.33E-04 6.IOE-05 0. 2.85E-04 0. 7.46E-05 CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05 CM247 1.03E-03 3.27E-04 6.OOE-05 0. 2.80E-04 0. 9.63E-05 CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31E-03 0. 1.55E-03 CR252 3.51 E-04 0. 8.37E-06 0. 0. 0. 3.05E-04

Proc No ODCM Attachment 8 Revision 25 Page 13 of 16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1-13 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 BE1O 3.18E-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05 C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08 NA22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06. 1.70E-06 1.70E-06 1.70E-06 P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05 AR39 0. 0. 0. 0. 0. 0. 0.

AR41 0. 0. 0. 0. 0. 0. 0.

CA4I 1.83E-05 0. 2.OOE-05 0. 0. 0. 1.84E-07 SC46 5.51E-09 1.07E-08 3.IIE-09 0. 9.99E-09 0. 5.21E-05 CR51 0. 0. 2.66E-09 1.59E-09 5.86E-1O 3.53E-09 6.69E-07 MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05 MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06 FE55 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06 FE59 4.34E-06 1.02E-05 3.91E-06 0. 0. 2.85E-06 3.40E-05 C057 0. 1.75E-07 2.91 E-07 0. 0. 0. 4.44E-06 C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51E-05 C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 NI59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 NI63 1.30E-04 9.O1E-06 4.36E-06 0. 0. 0. 1.88E-06 N165 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 CU64 0. 8.33E-08 3.91E-08 0. 2.1OE-07 0. 7.1OE-06 ZN65 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06 ZN69M 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05 ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09 SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07 BR82 0. 0. 2.26E-06 0. 0. 0. 2.59E-06 BR83 0. 0. 4.02E-08 0. 0. 0. 5.79E-08 BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13 BR85 0. 0. 2.14E-09 0. 0. 0. 0.

KR83M 0. 0. 0. 0. 0. 0. 0.

KR85M 0. 0. 0. 0. 0. 0. 0.

KR85 0. 0. 0. 0. 0. 0. 0.

KR87 0. 0. 0. 0. 0. 0. 0.

KR88 0. 0. 0. 0. 0. 0. 0.

KR89 0. 0. 0. 0. 0. 0. 0.

RB86 0. 2.11E-05 9.83E-06 0. 0. 0. 4.16E-06 RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07 RB88 0. 6.05E-08 3.21E-08 0. 0. 0. 8.36E-19 RB89 0. 4.01 E-08 2.82E-08 0. 0. 0. 2.33E-21 SR89 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 SR9O 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04 SR91 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05 SR92 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05

Proc No ODCM Attachment 8 Revision 25 Page 14 of 16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y9IM 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41E-07 0. 3.77E-09 0. 0. 0. 7.76E-05 Y92 8.45E-1O 0. 2.47E-11 0. 0. 0. 1.48E-05 Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05 ZR93 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.09E-05 ZR97 1.68E-09 3.39E-10 1.55E-1O 0. 5.12E-1O 0. 1.05E-04 NB93M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 NB95 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.1OE-05 NB97 5.22E-11 1.32E-11 4.82E-12 0. 1.54E-11 0. 4.87E-08 M093 0. 7.51E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06 M099 0. 4.31 E-06 8.20E-07 0. 9.76E-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.13E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.08E-06 TCIOI 2.54E-10 3.66E-1O 3.59E-09 0. 6.59E-09 1.87E-1O 1.1OE-21 RU1O3 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05 RUIO5 1.54E-08 0. 6.08E-09 0. 1.99E-07 0. 9.42E-06 RUIO6 2.75E-06 0. 3.48E-07 0. 5.31E-06 0. 1.78E-04 RHIO5 1.21E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41E-05 PDIO7 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.IIE-07 P0109 0. 1.77E-07 3.99E-08 0. 1.OIE-06 0. 1.96E-05 AGIIOM 1.60E-07 1.48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05 AG11I 5.81E-08 2.43E-08 1.21E-08 0. 7.84E-08 0. 4.46E-05 CDII3M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 CDII5M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E-05 SN123 3.IIE-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 SN125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 SN126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E05 SB125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 SB127 2.58E-07 5.65E-09 9.90E-08 3.IOE-09 0. 1.53E-07 5.90E-05 TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE125M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05 TE127 1.IOE-07 3.95E-08 2.38E-08 8.ISE-08 4.48E07 0. 8.68E-06 TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0. 2.37E-08 TE13IM 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05 TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09 TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71E-05 TE133M 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.67E-07 0. 6.64E-08 TE134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-11 1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0. 1.92E-06 1131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0. 1.57E-06

Proc No ODCM Attachment 8 Revision 25 Page 15 of 16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-1O 1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

XEI33M 0. 0. 0. 0. 0. 0. 0.

XE133 0. 0. 0. 0. 0. 0. 0.

XEI35M 0. 0. 0. 0. 0. 0. 0.

XE135 0. 0. 0. 0. 0. 0. 0.

XE137 0. 0. 0. 0. 0. 0. 0.

XE138 0. 0. 0. 0. 0. 0. 0.

CS134M 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08 CS134 6.22E-05 1.48E-04 1.21E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS135 1.95E-05 1.80E-05 7.99E-06 0. 6.81E-06 2.04E-06 4.21E-07 CS136 6.51E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.1IE-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.O1E-08 7.91E-09 4.65E-13 CS139 3.41E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.IOE-30 BA139 9.70E-08 6.91E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07 BAI4O 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 BAI4I 4.71E-08 3.56E-11 1.59E-09 0. 3.31E-11 2.02E-11 2.22E-17 BA142 2.13E-08 2.19E-11 1.34E-09 0. 1.85E-11 1.24E-11 3.OOE-26 LAI4O 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05 LA142 1.28E-10 5.82E-11 1.45E-11 0. 0. 0. 4.25E-07 CEI4I 9.36E-09 6.33E-09 7.18E-1O 0. 2.94E-09 0. 2.42E-05 CE143 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05 CE144 4.88E-07 2.04E-07 2.62E-08 0. 1.21E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 PR144 3.O1E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM148M 3.07E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.74E-05 PM148 7.17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05 PMI51 6.97E-10 1.17E-10 5.91E-11 0. 2.09E-10 0. 3.22E-05 SMI5I 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06 SM153 8.57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05 EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05 EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06 EU156 1.37E-08 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05 TB16O 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05 H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.

W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07 W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05 W187 1.03E-07 8.61E-08 3.OIE-08 0. 0. 0. 2.82E-05

Proc No ODCM Attachment 8 Revision 25 Page 16 of 16 INGESTION DOSE COMMITMENT FACTORS ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB2IO 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 BI21O 4.61E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05 P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05 RN222 0. 0. 0. 0. 0. 0. 0.

RA223 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04 RA224 1.61E-03 3.90E-06 3.23E-04 0. 1.1OE-04 0. 3.40E-04 RA225 6.56E-03 7.78E-06 1.31E-03 0. 2.21E-04 0. 3.06E-04 RA226 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04 RA228 1.12E-01 3.12E-06 1.21E-01 0. 8.83E-05 0. 5.64E-05 AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04 AC227 1.87E-03 2.48E-04 1.I1E-04 0. 8.OOE-05 0. 8.19E-05 TH227 1.37E-05 2.48E-07 3.95E-07 0. 1.41E-06 0. 5.40E-04 TH228 4.96E-04 8.40E-06 1.68E-05 0. 4.67E-05 0. 5.63E-04 TH229 7.98E-03 1.19E-04 3.91E-04 0. 5.75E-04 0. 5.12E-04 TH230 2.06E-03 1.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05 TH232 2.30E-03 1.OOE-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 TH234 8.OIE-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04 PA231 4.1OE-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05 PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05 U232 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05 U233 8.71 E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05 U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05 U235 8.O1E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05 U236 8.O1E-04 0. 4.96E-05 0. 1.91E-04 0. 5.76E-05 U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05 U238 7.67E-04 0. 4.54E-05 0. 1.75E-04 0. 5.50E-05 NP237 1.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05 NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05 NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05 PU238 6.80E-04 9.58E-05 1.71E-05 0. 7.32E-05 0. 7.30E-05 PU239 7.87E-04 1.06E-04 1.91E-05 0. 8.1IE-05 0. 6.66E-05 PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.IOE-05 0. 6.78E-05 PU241 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06 PU242 7.29E-04 1.02E-04 1.84E-05 0. 7.81E-05 0. 6.53E-05 PU244 8.52E-04 1.17E-04 2.IIE-05 0. 8.95E-05 0. 9.73E-05 AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.07E-04 0. 7.42E-05 AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05 AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05 CM242 2.06E-05 2.IOE-05 1.37E-06 0. 6.22E-06 0. 7.92E-05 CM243 6.39E-04 2.41E-04 3.75E-05 0. 1.75E-04 0. 7.81E-05 CM244 4.83E-04 2.07E-04 2.87E-05 0. 1.34E-04 0. 7.55E-05 CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05 CM246 1.O1E-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05 CM247 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05 CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03 CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04

ODCM Appendix A Revision 16 Issued Date 5117111 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Process Applicability Exclusion 0 Joe Hager I 5117111 Procedure Sponsor Date JJMiller I 5113/11 Technical Reviewer Date JBBurnett I 6/3/10 User Reviewer Date DHamilton I 5/13/11 General Manager Plant Operations Date

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page i TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents INTRODUCTION I DEFINITIONS I A. CHANNEL CALIBRATION I B. CHANNEL CHECK I C. CHANNEL FUNCTIONAL TEST 2 D. SOURCE CHECK 2 E. OFFSITE DOSE CALCULATION MANUAL 2 F. GASEOUS RADWASTE TREATMENT SYSTEM 2 G. MEMBERS OF THE PUBLIC 2 H. PROCESS CONTROL PROGRAM (PCP) 3 I. SITE BOUNDARY 3 J. UNRESTRICTED AREA 3 K. VENTILATION EXHAUST TREATMENT SYSTEM 3 III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 4 A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4

1. Requirement 4

2. Action 4

3. Surveillance Requirements 4

4. Bases 5 B. GASEOUS EFFLUENTS DOSE RATE 10

1. Requirement 10

2. Action 10

3. Surveillance Requirements 10

4. Bases 11 C. NOBLE GASES DOSE 12

1. Requirement 12

2. Action 12

3. Surveillance Requirements 12

4. Bases 13

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page ii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents D. 1-131, 1-133, TRITIUM, AND PARTICULATES 14

1. Requirement 14

2. Action 14

3. Surveillance Requirements 14

4. Bases 15 E. GASEOUS WASTE TREATMENT SYSTEM 18

1. Requirement 18

2. Action 18

3. Surveillance Requirements 18

4. Bases 19 F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 19

1. Requirement 19

2. Action 20

3. Surveillance Requirements 20

4. Bases 20 G. LIQUID EFFLUENTS CONCENTRATION 25

1. Requirement 25

2. Action 25

3. Surveillance Requirements 25

4. Bases 26 H. LIQUID EFFLUENT DOSE 29

1. Requirement 29

2. Action 29

3. Surveillance Requirements 29

4. Bases 30 TOTAL DOSE 31

1. Requirement 31

2. Action 31

3. Surveillance Requirements 32

4. Bases 33

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page iii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents J. RADIOLOGICAL ENVIRONMENTAL MONITORING 34

1. Requirement 34

2. Action 34

3. Surveillance Requirements 35

4. Bases 36 K. SIRW OR TEMPORARY LIQUID STORAGE TANK 46

1. Requirement 46

2. Action 46

3. Surveillance Requirement 46

4. Bases 47 L. SURVEILLANCE REQUIREMENT TIME INTERVALS 47

1. Requirement 47

2. Action 47

3. Surveillance Requirements 48

4. Bases 48 M. SEALED SOURCE CONTAMINATION 48

1. Requirement 48

2. Action 48

3. Surveillance Requirements 49

4. Bases 49 IV. REPORTING REQUIREMENTS 50 A. RADIOLOGICAL EFFLUENT RELEASE REPORT 50 B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 50 C. NONROUTINE REPORTS 51 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS 53 A. LICENSEE MODIFICATIONS 53 B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 54 VI. ONSITE GROUND WATER MONITORING 55

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page iv TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents TABLES A-I Radioactive Gaseous Effluent Monitoring Instrumentation A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements B-I Radioactive Gaseous Waste Sampling and Analysis Program C-I Radioactive Liquid Effluent Monitoring Instrumentation C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program E-1 Radiological Environmental Monitoring Program E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples E-3 Detection Capabilities for Environmental Sample Analysis F-i Environmental Radiological Monitoring Program Summary

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 1 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

INTRODUCTION The NRC, through 10CFR5O.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procedural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of I OCFR5O.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements.

DEFINITIONS A. CHANNEL CALIBRATION

- a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test.

The Channel Calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

B. CHANNEL CHECK

- a Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 2 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. CHANNEL FUNCTIONAL TEST

- a Channel Functional Test shall be:

1. Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

2. Bistable channels the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.

D. SOURCE CHECK

- a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

E. OFFSITE DOSE CALCULATION MANUAL

- (per Plant Technical Specifications) the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications, and 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Specifications.

F. GASEOUS RADWASTE TREATMENT SYSTEM

- any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

G. MEMBERS OF THE PUBLIC

- all persons who are not occupationally associated with the Plant. This category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 3 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. PROCESS CONTROL PROGRAM (PCP)

- shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Part 20, IOCFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.

SITE BOUNDARY

- that line beyond which the land is neither owned nor otherwise controlled by the licensee.

J. UNRESTRICTED AREA

- any area at or beyond the Site Boundary access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or, any area within the Site Boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

K. VENTILATION EXHAUST TREATMENT SYSTEM

- any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 4 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-I shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement lll.B.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

2. Action

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-I. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table A-2.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 5 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 6 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) Providing Alarm and Automatic Termination of Release (1) At All Times 1

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1) Above 210°F 3 Modes 1,2,3,4 Above 210°F

b. Evacuation Flow Indicator (Fl-0631 or Fl-0632) (1 )*** Modes 1, 2, 3, 4

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2326)* (1) At All Times 3

b. Iodine/Particulate/Sampler/Monitor (RIA 2325) (1) At All Times 3

c. Sampler Flow Rate Monitor (FE-2346) (1) At All Times 2

d. Hi Range Noble Gas (RIA 2327)* (1) Above 210°F 4 Modes 1,2,3,4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 3 Modes 1,2,3,4

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor* I per Main Above 325°F 4 (RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** I per Room Above 210°F 5 (RlAl8lOandI8ll) Modesl,2,3,4 Setpoints for these instruments are exempted from III.B.1 limfts, but are governed by Emergency Implementing Procedures or Operating procedures.

Setpoints for these instruments are exempted from III.B.1 limits, but are governed by Technical Specifications SR 3.3.10.3.

Documentation of operability not required.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 7 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I (Contd)

TABLE NOTATION ACTION STATEMENTS ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels requirements, the contents of the tank(s) may be released to the environment provided that prior to initiating the release:

a. At least two independent samples of the tanks contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve line up; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 4 - With the number of operable channels less than required by the Minimum Operable Channels requirements, initiate the preplanned alternate method of monitoring the appropriate parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

a. Either restore the inoperable channel(s) to operable status within 7 days of the event, or

b. Prepare and submit a Special Report to the NRC within 30 days following the event outlining the actions taken, the cause of the inoperability, and the plans and schedule for restoring the system to operable status.

ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with that channel shall be closed immediately and action shall be taken to have the affected channel repaired. The dampers associated with the channel shall not be opened until the affected channel has been declared operable.

(Reference Technical Specifications LCO 3.3.10.)

PALISADES NUCLEAR PLANT 00CM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 8 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements anne.*

fL.

ource , Channel Modes in Which Instrument Functional Surveillance

....ecn v.,iiecn 4.aIIIJraLlon Test Required WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and D(4) i R(3) Q(1 )(2)

Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2) Above 210°F

b. Evacuation Flow Indicator (FI-0632) or *** *** *** ***

c. Evacuation Flow Indicator (Fl-0631) Modes 1 2 3 4

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2) *

b. Iodine Particulate Sampler/Monitor w M** R(3)**

c. NA

Sampler Flow Rate Monitor D NA R NA *

d. Hi Range Noble Gas D M R(3) Q(2) Above 210°F Modes 1, 2, 3, 4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM Above 210°F

a. Noble Gas Activity Monitor D M R(3) Q(2) Modes 1, 2, 3, 4

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE Above 325°F D M R(3) Q(2) Modes 1, 2, 3

a. Gross_Gamma_Activity_Monitor

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months (3) 31 days(1)(2) Above 210°F (Technical Specifications SR 3.3.10 and Modes 1, 2, 3, 4 SR_3.7.13.1)

At all times other than when the line is valved out and locked.

Sampler not applicable This type of Flowmeter doesnt have any surveillance requirements.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 9 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-2 (Contd)

Table Notation (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists.

a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Range Noble Gas).

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

b. For subsequent Channel Calibration, sources that have been related to the (1) calibration may be used.

(4) Channel Check shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months M At least once per 31 days P Prior to radioactive batch release Q At least once per 92 days R At least once per 18 months W At least once per week

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 10 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. GASEOUS EFFLUENTS DOSE RATE Requirement The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and

b. For Iodine-i 31, for Iodine-I 33, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.

2. Action With the dose rate(s) averaged over a period of one hour exceeding the above limits, without delay, restore the release rate to within the above limit(s).

3. Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the limits of B.1 .a in accordance with the methodology and parameters in the ODCM.

b. The dose rate due to lodine-131, Iodine-I 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents shall be determined to be within the limits of B.1 .b in accordance with the methodology and parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table B-i.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 11 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This is provided to ensure that the dose at any time at and beyond the Site Boundary from gaseous effluents from all units on the site will be within 10 times the annual dose limits of IOCFR Part 20 to Unrestricted Areas. The annual dose limits are the doses associated with the concentrations of 10 times 10CFR Part 20, Appendix B, Table 2, Column 1. These restrictions provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public in an Unrestricted Area, either within or outside the Site Boundary, to annual exposure greater than design objectives of 10CFR 50, Appendix I, Section ll.B.1. For Members of the Public who may at times be within the Site Boundary, the occupancy of the Member of the Public will usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the Site Boundary. Examples of calculations for such Members of the Public, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding dose rate above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrems/yr to the total body.

The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLD5). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, L A, Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry, Anal Chem 40, 586-93 (1968), and Hartwell, JK, Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 12 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. NOBLE GASES DOSE Requirement The air dose due to noble gases released in gaseous effluents to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

2. Action With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 13 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement is provided to implement the requirements of Sections ll.B, lll.A, and IV.A of Appendix I, IOCFR Part 50. The limiting Condition for Operation implements the guides set forth in Section II.B of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents to Unrestricted Areas will be kept as low as is reasonably achievable. The Surveillance Requirements implement the requirements in Section lll.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The dose calculation methodology and parameters established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors, Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and beyond the Site Boundary are based upon the historical average atmospheric conditions.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 14 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

D. 1-131, 1-133, TRITIUM, AND PARTICULATES Requirement The dose to a Member of the Public from Iodine-i 31, Iodine-i 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the Site Boundary (see Figure 2-1) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ, and

b. During any calendar year: Less than or equal to 15 mrems to any organ.

2. Action With the calculated dose from the release of lodine-131, Iodine-i 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit and define(s) the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.

3. Surveillance Requirements Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-i 31, Iodine-i 33, tritium, and radionuclides in particulate form with half-lives greater than 8 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 15 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement is provided to implement the requirements of Sections ll.C, lll.A, and IV.A of Appendix I, IOCFR Part 50. The requirements are the guides set forth in Section ll.C of Appendix I.

The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to Unrestricted Areas will be kept as low as is reasonably achievable. The ODCM calculational methods specified in the Surveillance Requirements implement the requirements in Section ll.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methodology and parameters for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with IOCFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.111, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases From Light-Water-Cooled Reactors, Revision 1, July 1977.

These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate requirements for lodine-131, lodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man, in areas at and beyond the Site Boundary. The pathways that were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 16 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table B-I Radioactive Gaseous Waste Sampling and Analysis Program Gaseous Release Type Sampling Minimum Type of Lower Limit Frequency Analysis Activity Analysis Detection (LLD)a Frequency (pCi!ml)

A. Waste Gas Storage Tank P Each Tank P Grab Sample Each Tank Principal Gamma Emitters 1 x io B. Containment PURGE P Each PURGE P Grab Sample Each PURGE Principal Gamma Emittersb I x C. Stack Gas Effluent ContinuousC Charcoal 1-131, 1-133 1 x 1O Sample W

Continuousc Particulate Principal Gamma Emittersb I x iü Sample (1-131, Others)

Q Continuousc Composite Sr-89, Sr-90, and i x i0 Particulate Gross Alpha Sample Noble Gas Noble Gases I E-06 ContinuousC Monitor Gross Beta or Gamma

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 17 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table B-I (Contd)

Table Notation a The LLD is defined, in Table E-3, note C.

b The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-i 35, and Xe-i 38 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo99*, Cs-i 34, Cs-i 37, Ce-141, and Cei44* for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

Ten times the LLD because of low gamma yields.

c The ratio of the sample flow rate to the sample stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with requirements lll.B.i, lll.C.1, and lll.D.i.

d Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

e With channels operable on iodine monitor RIA 2325 less than required per lll.A.i, sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 18 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

E. GASEOUS WASTE TREATMENT SYSTEM Requirement When gaseous waste exceeds a Xe-I 33 concentration of I E-05 pCi/cc, the Waste Gas Decay Tank System shall be used to reduce radioactive gaseous effluents by holding gaseous waste collected by the system for a minimum of 15 days.

2. Action

a. If a waste gas decay tank is required to be released with less than 15 days holdup time, the system waste gas tank contents shall be evaluated and the waste gas decay tank with the lowest Xe-i 33 content shall be released.

b. Gaseous waste may be discharged directly from the waste gas surge tank through a high-efficiency filter or from a waste gas decay tank with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet requirements lll.B, C, and D.

3. Surveillance Requirements Not Applicable.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 19 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept as low as is reasonably achievable by meeting the design objectives given in Section Il.D of Appendix Ito IOCFR5O.

It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.1302 of 10CFR2O.

At the same time the licensee is permitted the flexibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in lll.B, C, and D.

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Requirement The radioactive liquid effluent monitoring instrumentation channels shown in Table C-I shall be operable with their alarm/trip setpoints set to ensure that the limits of lll.G are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the Offsite Dose Calculation Manual (ODCM).

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 20 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

2. Action

a. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above specification, without delay suspend the release of radioactive liquid effluents monitored by the affected channel or declare the channel inoperable, or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels Operable, take the Action shown in Table C-i. Exert best efforts to return the instruments to Operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. Surveillance Requirements Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated Operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table C-2.

4. Bases The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding 10 times the limits of I OCFR Part 20. The Operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to I OCFR Part 50.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 21 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-I Radioactive Liquid Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RIA 1049) (1) For Effluent Releases 1

b. Steam Generator Blowdown Effluent Line (1) For Effluent Releases 2 (RIA_0707)

2. GROSS BETA OR GAMMA RADIOACTIVE MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (RIA 0833) (1) For Effluent Releases 3

b. Turbine Building (Floor Drains) Sumps Effluent (1) For Effluent Releases 3 Line_(RIA_5211)

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (FIC 1051 or (1) For Effluent Releases 4 1050)

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip Setpoints are not applicable)

a. Turbine Building Sumps Effluent Line (1) For Effluent Releases 3

b. Service Water System Effluent (1) For Effluent Releases 3

c. Steam Generator Blowdown Effluent (1) For Effluent Releases 3

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 22 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-I (Contd)

TABLE NOTATION ACTION I - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases may continue provided that prior to initiating a release:

a. At least two independent samples are analyzed in accordance with requirements and

b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided grab samples are analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NOTES The Steam Generator blowdown monitor is normally used in a clean up closed loop system instead of as an effluent monitor. The action statement only applies when the monitor is used as an effluent monitor.

ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided that, at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , grab samples are collected and analyzed for radioactivity at a lower limit of detection as specified in Table D-1 for principle gamma emitters and 1-131.

ACTION 4 - With the number of channels operable less than required by the Minimum Operable Channels requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases. Pump performance curves or tank levels may be used to estimate flow.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 23 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements Channel Source Channel Instrument Channel Check Check

. Functional Calibration Test

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RIA 1049) P P R(3) Q(1)(2)

b. Steam Generator Blowdown Effluent Line (RIA 0707) D M R(3) Q(l )(2)

2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Service Water System Effluent Line (RIA 0833) D M R(3) Q(2)

b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211) D M R(3) Q(2)

3. FLOW RATE MEASUREMENT DEVICES (5)

a. Liquid Radwaste Effluent Line (FtC 1051 or 1050) D(4) NA R NA

4. TURBINE SUMP EFFLUENT COMPOSITER D(4) NA NA NA

5. SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER D(4) NA NA NA

6. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER D(4) NA NA NA

PALISADES NUCLEAR PLANT 00CM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 24 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-2 (Contd)

TABLE NOTATION (1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if either of the following conditions exists:

a. Instrument indicates measured levels above the alarm setpoint.

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in measurement assurance activities with N 1ST. These standards shall permit calibrating the system over its intended range of energy and measurement range.

b. For subsequent Channel Calibration, sources that have been related to the (a) calibration may be used.

(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

(5) Turbine Sump Discharge Flow Meter FQI-5210 was calibrated at factory and doesnt require recafibration.

TABLE FREQUENCY NOTATION D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Q At least once per 92 days M At least once per 31 days R At least once per 18 months P Prior to radioactive batch release W At least once per week

PALISADES NUCLEAR PLANT 00CM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 25 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

G. LIQUID EFFLUENTS CONCENTRATION Requirement The concentration of radioactive material released in liquid effluents to Unrestricted Areas shall be limited to 10 times the concentrations specified in IOCFR Part 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x i0 microcuries/mI total activity.

2. Action With the concentration of radioactive material released in liquid effluents to Unrestricted Areas exceeding the above limits, without delay, restore the concentration to within the above limits.

3. Surveillance Requirements

a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table D-1.

b. The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits of G.1 above.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 26 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to Unrestricted Areas will be less than 10 times the concentration levels specified in 10CFR Part 20, Appendix B, Table 2, Column 2. This limitation provides additional assurance that the levels of radioactive materials in bodies of water in Unrestricted Areas will result in exposures within the Section ll.A design objectives of Appendix I, IOCFR Part 50, to a Member of the Public. The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-i 35 is the controlling radioisotope and 10 times the effluent concentration in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and other detection limits can be found in HASL Procedures Manual, HASL-300, Currie, LA, Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry, Anal Chem 40, 586-93 (1968), and Hartwell, JK, Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 27 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table D-1 Radioactive Liciuid Waste SamDlinq and Analysis Proqram Liquid Release Type Sampling Minimum Analysis Type of Activity Analysis Lower Limit Frequency Frequency Detection (LLD)a (pCi/mI)

A. Batch Waste Release Tanksb P P Principal Gamma Emittersc 5 x iO Each Batch Each Batch 1-131 1 x 1O P M Dissolved and Entrained Gases 1 x iO One Batch/M (Gamma Emitters)

P M H-3 1x10 5

Each Batch Composited Gross Alpha I x 1O P Q Sr-89, Sr-90 5 x IO Each Batch Compositec B. Continuous Releasese t Continuous W Principal Gamma Emittersc 5 x iO (Turbine Sump, Steam Generator t Composite 1-131 1 X 1O Blowdown, and Service Water)

M M Dissolved and Entrained Gases Grab Sample (Gamma Emitters) 1 x 1O t

Continuous M H-3 I x iO t

Composite Gross Alpha 1 x 1O Continuous Q Sr-89, Sr-90 5 x 1O Composite Frequency Notation P Prior to batch release M Calendar month Q Calendar quarter W Calendar week

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 28 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table D-1 (Contd)

TABLE NOTATION a The LLD is defined, in Table E-3, Note C.

b A batch release is the discharge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated and then thoroughly mixed to assure representative sampling.

c The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo99*, Cs-i 34, Cs-i 37, Ce-i41, and Ce144*. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

LLD 5E-06 because of low gamma yields.

d A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.

e A continuous release is the discharge of liquid wastes of a nondiscrete volume; eg, from a volume of a system that has an input flow during the continuous release.

f To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected in a series of aliquots of constant volume collected at regular time intervals and combined to form a single sample. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representative of the effluent release.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 29 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. LIQUID EFFLUENT DOSE Requirement The dose or dose commitment to a Member of the Public from radioactive materials in liquid effluents released from each reactor unit to Unrestricted Areas shall be limited:

a. During any calendar quarter to less than or equal to 1 .5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

2. Action With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include the results of radiological analyses of the drinking water source.

3. Surveillance Requirements Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once every 31 days.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 30 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement is provided to implement the requirements of Sections ll.A, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section ll.A of Appendix I. The Action statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to Unrestricted Areas will be kept as low as is reasonably achievable. Also, for freshwater sites with drinking water supplies that can be potentially affected by Plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 4OCFR Part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section lll.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a Member of the Public through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 OCFR Part 50, Appendix I, Revision 1, October 1977 and Regulatory Guide 1.113, Estimating Aquatic Dispersion of Effluents From Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 31 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

TOTAL DOSE Requirement The annual (calendar year) dose or dose commitment to any Member of the Public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

2. Action With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of lll.C.1 .a, lll.C.1.b, lll.D.1.a, lll.D.1.b, lll.H.1.a, or III.H.1.b, calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of 111.1.1 have been exceeded. If such is the case, prepare and submit to the NRC within 30 days a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 400FR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 4OCFR Part 190. Submittal of the report is considered a timely request and a variance is granted until staff action on the request is complete.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 32 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

3. Surveillance Requirements

a. Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Ill.C.1, lIl.D.1, and lll.H.1 and in accordance with the methodology and parameters in the ODCM.

b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions set forth in Action 1.2 above.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 33 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement is provided to meet the dose limitations of 4OCFR Part 190 that have been incorporated into 10CFR Part 20 by 46 FR 18525. It also requires the preparation and submittal of a Special Report whenever the calculated doses from Plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except for thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to 4 reactors, it is highly unlikely that the resultant dose to a Member of the Public will exceed the dose limits of 4OCFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix I and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a Member of the Public to within the 4OCFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the Member of the Public from other uranium fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any Member of the Public is estimated to exceed the requirements of 4OCFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 4OCFR Part 190 have not already been corrected), in accordance with the provisions of 4OCFR Part 190.11 and IOCFR Part 20.2203, is considered to be a timely request and fulfills the requirements of 4OCFR Part 190 until NRC staff action is completed. The variance only relates to the limits of 4OCFR Part 190 and does not apply in any way to the other requirements for dose limitation of IOCFR Part 20. An individual is not considered a Member of the Public during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 34 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

J. RADIOLOGICAL ENVIRONMENTAL MONITORING Requirement The radiological environmental monitoring program shall be conducted as specified in Table E-1.

2. Action

a. With the radiological environmental monitoring program not being conducted as specified in Table E-1, prepare and submit to the NRC, in the Annual Radiological Environmental Operating Report a description of the reasons for not conducting the program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of Plant effluents in an environmental sampling medium at a specified location exceeding the reporting levels of Table E-2 when averaged over any calendar quarter, prepare and submit to the NRC within 30 days a Special Report that identifies the cause(s) for exceeding the limit(s) and defines the corrective actions to be taken to reduce radioactive effluents. When more than one of the radionuclides in Table E-2 are detected in the sampling medium, this report shall be submitted if:

Concentration (1) + Concentration (2) + ....> 1.0 Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table E-2 are detected and are the result of Plant effluents, this report shall be submitted if the potential annual dose to a Member of the Public is equal to or greater than the calendar year limits of Ill.C.1, lll.D.1, and lll.H.1. This report is not required if the measured level of radioactivity was not the result of Plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 35 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

c. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Identify the cause of the unavailability of samples and identify the new location(s) for obtaining replacement samples in the next Annual Radiological Environmental Report.

3. Surveillance Requirements

a. The radiological environmental monitoring samples shall be collected pursuant to Table E-1 and shall be analyzed pursuant to the requirements of Table E-1 and the detection capabilities required by Table E-3.

b. A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 9 overland meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50 m 2 (500 ft) 2 producing broad leaf vegetation.

c. The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report and shall be included in a revision of the ODCM for use in the following calendar year.

d. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the NRC.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 36 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

e. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report.

f. The environmental air samplers shall be operationally checked monthly and airflow verified annually.

4. Bases

a. Monitoring Program The radiological environmental monitoring program provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of Members of the Public resulting from the station operation. This monitoring program implements Section lV.B.2 of Appendix Ito 10CFR Part 50 and thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the modeling of the environmental exposure pathways. Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring. The initially specified monitoring program will be effective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience.

The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table E-3 are considered optimum for routine environmental measurements in industrial laboratories.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300, Currie, LA, Limits for Qualitative Detection and Quantitative Determination Application to Radiochemistry, Anal Chem 40, 586-92 (1968), and Hartwell, JK, Detection Limits for Radioanalytical Counting Techniques, Atlantic Richfield Hanford Company Report ARH-SA-15 (June 1975).

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 37 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

b. Land Use Census:

This requirement is provided to ensure that changes in the use of areas at and beyond the site boundary are identified and that modifications to the radiological environmental monitoring program are made if required by results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix Ito IOCFR Part 50. Restricting the census to gardens of greater than 50 m 2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (16 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child.

To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (ie, similar to lettuce and cabbage), and (2) a vegetation yield of 2 kglm 2

c. Interlaboratory Comparison Program:

The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix I to IOCFR Part 50.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 38 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-1 Radiological Environmental Monitoring Program Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis

1. DIRECT RADIATIONb 21 routine monitoring stations either with two or Quarterly Gamma dose quarterly more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:

An inner ring of stations, one in each overland meteorological sector (9) in the general area of the Site Boundary.

An outer ring of stations, one in each overland meteorological sector (9) within the 12 km range from the site.

The balance of the stations (3) to be placed to serve as control stations.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 39 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAG NO 75060)

Exposure Pathway Number of Representative Sampling and Type and Frequency and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis

2. AIRBORNE Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:

Particulates operation with sample 1-131 analysis weekly for 3 samples from within 6 km of the Site Boundary collection weekly or more each filter change.

in different sectors (2.4 km-SSW, 5.6 km-ESE, frequently if required by and 1.6 km-N). dust loading. Particulate Samrler:

Gross beta radioactivity 1 sample from the vicinity of a community having analysis following filter the highest calculated annual average ground changed. Gamma isotopic level DIQ (Covert-5.6 km-SE). analysise if gross beta

>1.0 pCi/m 3

I sample from a control location in the least prevalent wind directionc (Grand Rapids 89 km-NNE).

3. WATERBORNE

a. Lake (surface) Plant lake water inlet. Composite sample over Gross beta (>10 pCi/I 1-month period t requires gamma) and tritium monthly.

b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gross beta (>10 pCi/I 1-month period t requires gamma) and tritium monthly.

1 sample from a control location (Ludington Composite sample over Gross beta (>10 pCi/I Pumped Storage 201 km N) 1-month period t requires gamma) and tritium monthly.

c. Well (drinking) 1 grab sample per month when Palisades Park 1 grab sample per month Gross beta (>10 pCi/I community drinking water well is in operation (Park when operational requires gamma) and tritium is seasonal in operations and is only open for the per month when Park is summer months) operational

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 40 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Exposure Pathway Number of Representative Sampling and Type and Frequency andlor Sample Samples and Sample Locationsa Collection Frequency of Analysis

d. Sediment from shoreline I sample from between north boundary and Van Semiannually Gamma isotopic analysise Buren State Park beach, approximately % mile semiannually.

north of the Plant discharge.

4. INGESTION

a. Milk Samples from milking animals in 3 locations Monthly Gamma isotopice and 1-131 between 5-8 km distance. analysis monthly.

1 sample from milking animals at a control location, Monthly Gamma isotopice and 1-131 15-30 km distance. analysis monthly.

b. Broad leaf Samples of 3 different kinds of broad leaf vegetation Monthly during growing Gamma isotopice and 1-131 vegetation grown nearest each of two different offsite locations season analysis of highest predicted annual average ground level D/Q if milk sample is not performed. (SE or SSE sectors near site.)

I sample of each of the similar broad leaf vegetation Monthly during growing Gamma isotopice and 1-131 grown 1 5-30 km distance in the least prevalent wind season analysis direction if milk sampling is not performed. (NNE or NE sectors.)

c. Fish Sample 2 species of commercially and/or Sample in season or Gamma iSotOpjce and 1-131 recreationally important species in vicinity of Plant semiannually if they are analysis.

discharge area. 1 sample of same species in areas not seasonal.

not influenced by Plant discharge.

d. Food Products I sample each of two principal fruit crops At time of harvest 9 Gamma Isotopice and 1-131 (blueberries and apples). analysis.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 41 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-1 (Contd)

Table Notation a

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

b One or more instwments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors or phosphor readout zones in a packet are considered as two or more dosimeters.

C The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet this criteria are acceptable).

g If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.

PALISADES NUCLEAR PLANT 00CM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 42 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples Reporting Levels

. Water Airborne Particulates Fish Milk Food Products Analysis (pCill) or Gases (pCi/rn

)

3 (pCi/kg, Wet) (pCiII) (pCilkg, Wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 1-131 2 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-I 37 50 20 2,000 70 2,000 Ba-La-140 200 300 For drinking water samples. This is 4OCFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 43 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-3 Detection Capabilities for Environmental Sample Analysisa Lower Limit of Detection (LLD)

Water Airborne Particulates Fish Milk Food Products Sediment Analysis (pCill) or Gases (pCi/rn 3)

(pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) (pCi/kg, Dry)

Gross Beta 4 0.01 H-3 2,000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 1-131 d 1

0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-I 37 18 0.06 150 18 80 180 Ba-La-140 15 15 If no drinking water pathway exists, a value of 3,000 pCi/I may be used.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 44 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-3 (Contd)

TABLE NOTATION a

This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

C The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a real signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66 b

E V 2.22 Y Exp (-l..At)

Where:

LLD is the a priori lower limit of detection as defined above, as picocuries per unit mass or volume.

Sb iS the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute.

E is the counting efficiency, as counts per disintegration.

V is the sample size in units of mass or volume.

2.22 is the number of disintegrations per minute per picocurie.

Y is the fractional radiochemical yield, when applicable.

A is the radioactive decay constant for the particular radionuclide.

t for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting.

Typical values of E, V, Y, and t should be used in the calculation.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 45 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-3 (Contd)

Table Notation It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.

PALISADES NUCLEAR PLANT 00CM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 46 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

K. SIRW OR TEMPORARY LIQUID STORAGE TANK Requirement The concentration of radioactive material contained in the SIRW tank or any unprotected outside temporary tank* shall be limited such that the mixture radionuclides do not exceed 1,000 times the effluent concentration (EC) as listed in 10CFR Part 20, Appendix B, Table 2, Column 2.

+ k*.*Qi = <1000 ECa ECb EC 1

2. Action With the quantity of radioactive material in any of the above listed tanks exceeding the above concentration, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.

3. Surveillance Requirement The concentration of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the tanks contents at least once per 7 days when radioactive materials are being added to the tank.

or A calculational methodology performed prior to the material being transferred may be used to show compliance with the requirement of this section if a representative sample cannot be obtained at least once per seven days. A representative sample of the radioactive material to be added to the SIRW or Temporary Liquid Storage Tank shall be analyzed and a calculation performed to show compliance with the 1000 EC limit.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 47 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases This requirement will provide reasonable assurance that in the event of an uncontrolled release of the tanks contents, the resulting concentrations would be less than the limits of 10CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area.

(The dilution between Palisades and the South Haven drinking water supply has been established as 1000.)

Tanks included in this specification are those outdoor tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system.

NOTES The limit for the SIRW Tank may be exceeded for operational flexibility if the conditions of this section are met.

L. SURVEILLANCE REQUIREMENT TIME INTERVALS Requirement Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.

2. Action Failure to perform a Surveillance Requirement within the allowed surveillance interval shall constitute noncompliance with the operability requirements. The time limits of the action requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The action requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the action requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 48 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

3. Surveillance Requirements The applicable surveillance interval frequencies are specified in Tables A-2 and C-2. The applicable sampling and/or analysis frequencies are specified in Tables A-i, B-I, C-I, D-1, and E-1.

Extendable surveillance requirements are limited to Channel Checks, Source Checks, Channel Calibrations, Channel Functional Checks, sampling frequencies and/or analysis frequencies.

4. Bases The maximum allowable extension for a surveillance interval is consistent with the surveillance requirements specified in the Technical Specifications, Section 4.0. Until relocated in the ODCM, all of the effluent surveillances were subject to these same requirements.

M. SEALED SOURCE CONTAMINATION

1. Requirement Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 microcuries of removable contamination.

2. Action

a. With a sealed source having removable contamination in excess of 0.005 microcuries, immediately withdraw the sealed source from use and either:

(1) Decontaminate and repair the sealed source, or (2) Dispose of the sealed source in accordance with applicable regulations.

b. A report shall be prepared and submitted to the Commission on an annual basis if sealed source leakage tests reveal the presence of greater than or equal to 0.005 microcuries of removable contamination.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 49 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

3. Surveillance Requirements

a. Each category of sealed sources as described in the requirement with a half-life greater than 30 days (excluding Hydrogen-3), and in any other form than gas, shall be tested for leakage and/or contamination at intervals not to exceed 6 months.

b. The test shall be performed by the licensee or by other persons specifically authorized by the Commission or an Agreement State. The test method shall have a detection sensitivity of at least 0.005 microcuries per test sample.

c. The test sample shall be taken from the sealed source or, in the case of permanently mounted sources, from the surfaces of the mounting device on which contamination would be expected to accumulate.

d. The periodic leak test does not apply to sealed sources that are stored and not being used. These sources shall be tested prior to use or transfer to another licensee, unless tested within the previous 6 months. Sealed sources which are continuously enclosed within a shielded mechanism (ie, sealed sources within radiation monitoring or boron measuring devices) are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

e. Sealed sources transferred without a certificate indicating the last test date shall be tested prior to being placed in use.

4. Bases The requirement, actions, and surveillance requirements are the same as contained in the Technical Specifications 6.21 prior to relocation to the ODCM and will provide assurance that sealed sources are tested to demonstrate that source integrity is being maintained.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 50 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

IV. REPORTING REQUIREMENTS A. RADIOLOGICAL EFFLUENT RELEASE REPORT The Radioactive Effluent Release Report shall be submitted in accordance with IOCFR 50.36a prior to May 1 of each year. The report shall follow the guidance contained in Regulatory Guide 1.21 Revision 2, Section 8, Format and Content of the Annual Radioactive Effluent release Report.

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT The Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 15 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, lV.B.3, and IV.C of Appendix Ito IOCFR5O.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretation and statistical evaluation of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the Plant operation on the environment. The reports shall also include the results of land use census pursuant to Ill.J.3.c.

The Annual Radiological Environmental Operating Reports shall include summarized and tabulated results in the format of Table F-I of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

The reports shall also include the following; a summary description of the radiological environmental monitoring program, including sampling methods for each sample type, a map of all sampling locations keyed to a table giving distances and directions from the reactor and the results of land use census required by IlI.J.3.c and results of the Interlaboratory Comparison Program required by III.J.3.e.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 51 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. NONROUTINE REPORTS A report shall be submitted to the NRC in the event that: 1) the Radiological Environmental Monitoring Programs are not substantially conducted as described in Section Ill.J, or 2) an unusual or important event occurs from Plant operation that causes a significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 52 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table F-I Environmental Radiological Monitoring Program Summary Name of Facility Docket No Location of Facility Reporting Period________________

(County, Stat&)4 Medium or Pathway Type/Total Lower Limit All Indicator Number of of Locations Name (f)b Control Locations Number of Sampled (f)b Mean Mean(f)b REPORTABLE Analyses Detectiona Mean Distance & Direction Rangeb (Unit of Measure)

Performed (LLD) Ranges Rang&> OCCURRENCES Air Particulates Gross R 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1

)

3 (pCi/rn (200/312) 5 miles 3400 (0.08-2.0) (0.05-1.40) v-Spec 32 (0.05-2.0)

Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4 (0.03-0.13) 2.5 miles 160° (0.03-0.13)

Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1 (0.01 -0.08) 4 miles 270° (0.01-0.08)

Sr-89 40 0.002 <LLD -- -- <LLD 0 Sr-90 40 0.0003 <LLD -- -- <LLD 0 Fish v-Spec 8 pCi/kg (dry weight) <LLD Cs-137 80 -- <LLD 90(1/4) 0

<LLD Cs-134 80 <LLD <LLD 0 120 (3/4)

Co-60 80 (90-200) River Mile 35 See <LLD 0 Podunk River Column 4 a

Nominal Lower Limit of Detection (LLD) as defined in table notation c of Table E-3.

b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (f).

NOTE: The example data are provided for illustrative purposes only.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 53 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. LICENSEE MODIFICATIONS Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.

1. Shall be reported to the NRC pursuant to IOCFR 50.59. The discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that the modification could be made in accordance with IOCFR Part 50.59.

b. A description of the equipment, components and processes involved, and the interfaces with other Plant systems.

c. Documentation of the fact that the modification was reviewed and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the General Manager Plant Operations.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 54 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 1.

Purpose:

The purpose of this definition is to assure that this requirement will be satisfied under clearly identifiable circumstances, and with the objective that current radwaste system capabilities are not jeopardized.

2. Definition:

A major radwaste system modification is a modification which would remove (either by bypassing for greater than 7 days or physical removal) or replace with less efficient equipment, any components of the radwaste system:

a. Letdown filters or demineralizers.

b. Vacuum degassifier (not applicable when the reactor is in cold shutdown and depressurized).

c. Miscellaneous or clean waste evaporators.

d. The present waste gas compressor/decay tank system.

e. Fuel Pool filters/demineralizers.

f. Radwaste polishing demineralizers.

g. Radwaste Solidification system.

Improvements or additions to improve efficiency will not be considered major modifications unless a complete substitution of equipment or systems is made with equipment of unrelated design. Examples would be: 1) replacement of mechanical degassifier with steam, jet degassifier, 2) replacement of waste gas system with cryogenic system, 3) replacement of asphalt solidification with cement system, and 4) change from deep bead resins to Powdex, etc.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 16 Page 55 of 55 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

VI. ONSITE GROUND WATER MONITORING Palisades installed 5 ground water monitoring wells in 2007 and added an additional 9 wells in 2008. These wells were installed in response to NEI 07-07, Industry Ground Water Protection Initiative Final Guidance Document. These wells are strategically placed within the Owner Controlled Area, both inside and outside the Protected Area to allow detection of radioactive contamination of ground water due to leaks or spills from plant systems.

ODCM Appendix A Revision 17 Issued Date 12129111 PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Process Applicability Exclusion DWFoster for JHager I 12I28/11 Procedure Sponsor Date JJMiller / 12/15111 Technical Reviewer Date JHager I 12/15/11 User Reviewer Date DHamilton I 12l19I11 General Manager Plant Operations Date

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page i TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents INTRODUCTION I DEFINITIONS I A. CHANNEL CALIBRATION I B. CHANNEL CHECK I C. CHANNEL FUNCTIONAL TEST 2

0. SOURCE CHECK 2 E. OFFSITE DOSE CALCULATION MANUAL 2 F. GASEOUS RADWASTE TREATMENT SYSTEM 2 G. MEMBERS OF THE PUBLIC 2 H. PROCESS CONTROL PROGRAM (PCP) 3 I. SITE BOUNDARY 3 J. UNRESTRICTED AREA 3 K. VENTILATION EXHAUST TREATMENT SYSTEM 3 III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 4 A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4

1. Requirement 4

2. Action 4

3. Surveillance Requirements 4

4. Bases 5 B. GASEOUS EFFLUENTS DOSE RATE 10

1. Requirement 10

2. Action 10

3. Surveillance Requirements 10

4. Bases 11 C. NOBLE GASES DOSE 12

1. Requirement 12

2. Action 12

3. Surveillance Requirements 12

4. Bases 13

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page ii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents D. 1-131, 1-133, TRITIUM, AND PARTICULATES 14

1. Requirement 14

2. Action 14

3. Surveillance Requirements 14

4. Bases 15 E. GASEOUS WASTE TREATMENT SYSTEM 19

1. Requirement 19

2. Action 19

3. Surveillance Requirements 19

4. Bases 20 F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 20

1. Requirement 20

2. Action 21

3. Surveillance Requirements 21

4. Bases 21 G. LIQUID EFFLUENTS CONCENTRATION 26

1. Requirement 26

2. Action 26

3. Surveillance Requirements 26

4. Bases 27 H. LIQUID EFFLUENT DOSE 30

1. Requirement 30

2. Action 30

3. Surveillance Requirements 30

4. Bases 31 TOTAL DOSE 32

1. Requirement 32

2. Action 32

3. Surveillance Requirements 33

4. Bases 34

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page iii TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents J. RADIOLOGICAL ENVIRONMENTAL MONITORING 35

1. Requirement 35

2. Action 35

3. Surveillance Requirements 36

4. Bases 37 K. SIRW OR TEMPORARY LIQUID STORAGE TANK 51

1. Requirement 51

2. Action 51

3. Surveillance Requirement 51

4. Bases 52 L. SURVEILLANCE REQUIREMENT TIME INTERVALS 52

1. Requirement 52

2. Action 52

3. Surveillance Requirements 53

4. Bases 53 M. SEALED SOURCE CONTAMINATION 53

1. Requirement 53

2. Action 53

3. Surveillance Requirements 54

4. Bases 54 IV. REPORTING REQUIREMENTS 55 A. RADIOLOGICAL EFFLUENT RELEASE REPORT 55 B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 56 C. NONROUTINE REPORTS 56 V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS 58 A. LICENSEE MODIFICATIONS 58 B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 59 VI. ONSITE GROUND WATER MONITORING 60

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page iv TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents TABLES A-I Radioactive Gaseous Effluent Monitoring Instrumentation A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements B-I Radioactive Gaseous Waste Sampling and Analysis Program C-i Radioactive Liquid Effluent Monitoring Instrumentation C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements D-1 Radioactive Liquid Waste Sampling and Analysis Program E-I Radiological Environmental Monitoring Program E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples E-3 Detection Capabilities for Environmental Sample Analysis E-4 Radiological Environmental Monitoring Program Locations F-I Environmental Radiological Monitoring Program Summary

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 1 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

INTRODUCTION The NRC, through 10CFR5O.36a, requires implementation of Technical Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01, dated January 31, 1989, allowed relocation of the existing procedural requirements from the Technical Specifications (implemented in Amendment 85, November 9, 1984). The relocated procedural requirements related to gaseous and liquid effluents, total dose, environmental monitoring program, and associated procedural reporting requirements follow below. Programmatic controls are retained in the Administrative Controls section of the Technical Specification to satisfy the regulatory requirements of 10CFR5O.36a. The Technical Specifications programmatic controls include requirements for the establishment, implementation, maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well as record retention and reporting requirements.

DEFINITIONS A. CHANNEL CALIBRATION

- a Channel Calibration shall be the adjustment, as necessary, of the channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors. The Channel Calibration shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the Channel Function Test.

The Channel Calibration may be performed by any series of sequential, overlapping, or total channel steps such that the entire channel is calibrated.

B. CHANNEL CHECK

- a Channel Check shall be the qualitative assessment of channel behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrumentation channels measuring the same parameter.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 2 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. CHANNEL FUNCTIONAL TEST

- a Channel Functional Test shall be:

1. Analog channels the injection of a simulated signal into the channel as close to the sensor as practicable to verify operability including alarm and/or trip functions.

2. Bistable channels the injection of a simulated signal into the sensor to verify operability including alarm and/or trip functions.

D. SOURCE CHECK

- a source check shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

E. OFFSITE DOSE CALCULATION MANUAL

- (per Plant Technical Specifications) the Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain: 1)the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by the Technical Specifications, and 2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release Reports required by the Technical Specifications.

F. GASEOUS RADWASTE TREATMENT SYSTEM

- any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

G. MEMBERS OF THE PUBLIC

- all persons who are not occupationally associated with the Plant. This category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service equipment or to make deliveries.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 3 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. PROCESS CONTROL PROGRAM (PCP)

- shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with IOCFR Part 20, IOCFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.

SITE BOUNDARY

- that line beyond which the land is neither owned nor otherwise controlled by the licensee.

J. UNRESTRICTED AREA

- any area at or beyond the Site Boundary access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or, any area within the Site Boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.

K. VENTILATION EXHAUST TREATMENT SYSTEM

- any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal absorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment. Such a system is not considered to have any effect on noble gas effluents. Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be ventilation exhaust treatment system components.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 4 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION Requirement The radioactive gaseous effluent monitoring instrumentation channels shown in Table A-i shall be operable with their alarm/trip setpoints set to ensure that the limits of requirement lll.B.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

2. Action

a. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above requirement, without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable or change the setpoint so it is acceptably conservative.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels operable, take the action shown in Table A-i. Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

3. Surveillance Requirements Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated operable by performance of the Channel Check, Source Check, Channel Calibration, and Channel Functional Test operations at the frequencies shown in Table A-2.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 5 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents. The alarm/trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of 10CFR Part 20.

The operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to IOCFR Part 50.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 6 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I Radioactive Gaseous Effluent Monitoring Instrumentation Minimum Instrument Operable Applicability Action Channels WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) Providing Alarm and Automatic Termination of Release (1) At All Times I

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1) Above 210°F 3 Modes 1, 2, 3, 4 Above 21 0°F

b. Evacuation Flow Indicator (Fl-0631 or Fl-0632) (1 )*** Modes 1, 2, 3, 4

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2326)* (1) At All Times 3

b. Iodine/Particulate/Sampler/Monitor (RIA 2325) (1) At All Times 6

c. Sampler Flow Rate Monitor (FE-2346) (1) At All Times 2

d. Hi Range Noble Gas (RIA 2327)* (1) Above 210°F 4 Modes 1, 2, 3, 4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 3 Modes 1,2,3,4

5. MAIN STEAM SAFETY AND DUMP VALVE DISCHARGE LINE

a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 4 (RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** I per Room Above 210°F 5 (RIA 1810 and 1811) Modes 1,2,3,4 Setpoints for these instruments are exempted from llI.B.1 limits, bit are governed by Emergency Implementing Procedures or Operating procedures.

Setpoints for these instruments are exempted from lII.B.1 limits, but are governed by Technical Specifications SR 3.3.10.3.

Documentation of operability not required.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 17 Page 7 of 60 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)