PNP 2016-024 

April 25, 2016 

U.S. Nuclear Regulatory Commission 

ATTN: Document Control Desk 

Washington, DC 20555-0001 

Entergy Nuclear Operations, Inc. 

Palisades Nuclear Plant 

27780 Blue Star Memorial Highway 

Covert, Ml 49043 

Tel 269 764 2000 

Jeffery A. Hardy 

Regulatory Assurance Manager 

10 CFR 50.36a 

Subject: 2015 Annual Radioactive Effluent Release and Waste Disposal Report 

Palisades Nuclear Plant 

Docket 50-255 

License No. DPR-20 

Dear Sir or Madam: 

Big Rock Point 

Dockets 50-155 and 72-043 

License No. DPR-6 

Attached are the Entergy Nuclear Operations, Inc. 2015 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). 

Attachment 1 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, 2015, through December 31, 2015. 
PNP 2016-024 

Document Control Desk 

Page2 

This letter contains no new commitments and no revision to existing commitments. 

Sincerely, 

JAH/bed 

Attachment 1: Palisades Nuclear Plant 2015 Radioactive Effluent Release Report 

Attachment 2: Big Rock Point Independent Spent Fuel Storage Installation 2015 

Radioactive Effluent Release Report 

CC Administrator, Region Ill, USNRC 

Project Manager, Palisades, USNRC (w/o Attachments) 

Resident Inspector, Palisades, USNRC (w/o Attachmens) 

NRC NMSS Project Manager, USNRC (w/o Attachments) 

American Nuclear Insurers (ANI) 
ATTACHMENT 1 

Palisades Nuclear Plant 2015 Radioactive Effluent Release Report 

2015 Plant Operating History 

Palisades Nuclear Plant (PNP) entered the reporting period online on January 1, 2015, 

at essentially 100% full power. PNP experienced an unexpected scram on 

September 16, 2015, because of a digital electrohydraulic control system malfunction 

on the turbine. Refueling outage 1 R24 commenced shortly thereafter on 

September 18, 2015. The unit attained criticality on October 19, 2015, and returned to 

full power on October 22, 2015. The unit generated 6,318,519 MWHrs of net electrical 

energy during 2015. 

A. Gaseous Effluents 

Tables 1 A, "Gaseous Effluents - Summation of All Releases," 1 B, "Gaseous 

Effluents - Ground-Level Release - Batch Mode," and 1 C, "Gaseous Effluents -

Ground-Level Release - Continuous Mode," list and summarize gaseous effluents 

released during this reporting period. 

B. Liquid Effluents 

Tables 2A, "Liquid Effluents - Summation of All Releases," 2B, "Liquid Effluents -

Batch Mode," and 2C, "Liquid Effluents - Continuous Mode," list and summarize 

liquid effluents released during this reporting period. 

C. Solid Waste Storage and Shipments 

Table 3, "Low-Level Waste for Waste Classification A, Band C, summarizes solid 

radioactive waste shipped for processing or burial in 2015 for the following waste 

streams: resins, filters and evaporator bottoms, dry active waste, irradiated 

components and other waste. 

D. Dose Assessments 

Tables 4, "Dose Assessments, 1 O CFR Part 50, Appendix I," and 5, "EPA 

40 CFR Part 190, Individual in the Unrestricted Area," lists annual dose to the 

members of the public. 

E. Supplemental Information 

1. Regulatory Limits 

a. Noble Gases 

The air dose in unrestricted areas due to noble gas released in gaseous 

effluents shall be limited to the following: 

Page 1 of 10 
•During the calendar quarter, to s 5 mrad for gamma radiation ands 10 mrad 

for beta radiation. 

• During the calendar year, to s 10 mrad gamma radiation and s 20 mrad for 

beta radiation. 

b. Iodines - Particulates 

The dose to a member of the public from radioiodines, radioactive material in 

particulate form with half-lives greater than eight days, and radionuclides 

other than noble gas, e.g., tritium, in gaseous effluents released to 

unrestricted areas shall be limited to the following: 

•During any calendar quarter, to s 7.5 mrem to any organ 

• During any calendar year, to s 15 mrem to any organ 

c. Liquid Effluents 

The dose or dose commitment to an individual from radioactive material in 

liquid effluents released to unrestricted areas shall be limited to the following: 

• During any calendar quarter to s 1.5 mrem to the total body and s 5 mrem 

to any organ. 

• During any calendar quarter to s 3 mrem to the total body and s .1 O mrem to 

any organ. 

d. Total Dose 

The dose or dose commitment to a real individual from all uranium fuel cycle 

sources is limited to s 25 mrem to the total body <?r any organ (except the 

thyroid, which is limited to s 75 mrem) over a period of 12 consecutive 

months. 

2. Maximum Permissible Concentrations (Effluent Concentration Limits) 

a. Gaseous Effluents 

The dose rate due to radioactive material released in gaseous effluents from 

the site shall be limited to the following: 

• For noble gases: s 500 mrem/yr to the total body and s 3000 mrem/yr to the 

skin 

• For all radioiodines and for all radioactive materials in particulate form with 

half-lives greater than eight days and for radionuclides other than noble 

gases: s 1500 mrem/yr to any organ. 

Page 2 of 10 
The above limits are provided to ensure that radioactive material discharged 

in gaseous effluents will not result in the exposure of an individual in an 

unrestricted area to annual average concentrations exceeding the limits of 

1 O CFR 20, Appendix B, Table 2, Column 1. 

b. Liquid Effluents 

The concentration of radioactive material. released at any time from the site to 

unrestricted areas shall be limited to the concentrations specified in 

10 CFR 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 2E-4 μCi/ml total activity. 

3. Average Energy 

The average energy ( E) of the radionuclide mixture in releases of fission and 

activation gases as defined in Regulatory Guide 1.21, Appendix B, Section A.3 is 

not applicable because the limits used for gaseous releases are based on 

calculated dose to members of the public. 

4. Measurements and Approximations of Total Radioactivity 

PNP uses 0.25 KeV per channel with a range of 0-2000 KeV. 

a. Fission and activation gases are sampled and then analyzed on an 8192 

channel analyzer with a high purity germanium (HpGe) detector. 

b. Iodines are sampled and then analyzed on an 8192 channel analyzer with an 

HpGe detector. 

c. Particulates are sampled and then analyzed on an 8192 channel analyzer 

with an HpGe detector. 

d. Liquid effluents are sampled and then analyzed on an 8192 channel analyzer 

with an HpGe detector. Tritium analysis is performed using liquid scintillation. 

Fe-55, Ni-63, Sr-89, and Sr-90 analyses are performed by an offsite vendor. 

Page 3 of 10 
5. Batch Releases - 2015 

For PNP, these totals are not directly proportional to actual release volumes due to 

PNP having two sets of tanks with different volumes in both the gaseous and liquid 

release systems that are utilized for batch releases. The number of batches 

performed in this section will fluctuate from year to year due to the utilization of the 

smaller and larger tanks in different frequencies. This information is better 

quantified in the tables contained later in this report. Reporting average stream flow 

during periods of release of effluent into a flowing stream is not required as PNP's 

releases are made into Lake Michigan, and not a flowing stream of water. 

a. Liquid 

Number of batch releases for each quarter: 1 in the 1st quarter 

1 in the 2nd quarter 

5 in the 3rd quarter 

4 in the 4th quarter 

Total time period for batch releases: 10598 minutes 

Maximum time period for a batch release: 2580 minutes 

Average time period for a batch release: 963 minutes 

Minimum time period for a batch release: 434 minutes 

b. Gaseous 

Number of batch releases for each quarter: 

\ 

2 in the 1st quarter 

0 in the 2nd quarter 

2 in the 3rd quarter 

5 in the 4th quarter 

Total time period for batch releases: 2897 minutes 

Maximum time period for a batch release: 930 minutes 

Average time period for a batch release: 322 minutes 

_ Minimum time period for a batch release: 78 minutes 

Page 4 of 10 
6. Abnormal Discharges 

a. Liquid 

Number of releases for each quarter 

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 

1 0 0 0 

Total activity released in Curies (Ci) 

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 

0.0387 0 0 0 

On February 26, 2015, as a result of routine monitoring well sampling, PNP 

identified tritium in temporary wells 7 and 8, located within the plant protected 

area. PNP completed notifications, in accordance with NEI 07-07 Criterion 2.2.b, 

on March 19, 2015. Tritium concentrations were less than the threshold value 

(20,000 pci/L) for initiating voluntary communications in accordance with NEI 

Ground Water Protection Initiative. The station promptly isolated the pipe that 

runs from the turbine sump oil/water separator to the turbine building drain tank 

as the likely source. Subsequent sample concentrations from samples obtained 

on March 18, 2015, resulted in concentrations of tritium less than the minimum 

detectable activity, thus confirming the source. 

The pipe that runs from the turbine sump oil/water separator to the turbine 

building drain tank is a monitored effluent pathway that discharges waste to Lake 

Michigan. All activity and volume along this pathway is accounted for by routine 

effluent calculations, as shown in Table 2C. However, the activity released to 

the ground through this path is considered abnormal due to the fact that the 

release did not occur at the designed discharge location. The fraction of release 

from the pipe is unknown, so it was conservatively assumed that 100% of the 

liquid discharge traveling through the pipe went to the ground. The most 

conservative range of time during which this could have occurred was calculated 

to be between October 2, 2014, and March 7, 2015, based upon groundwater 

well measurements and groundwater flowrates. Therefore, it is conservatively 

estimated that 0.0387 Ci of tritium in 1st Quarter 2015, and 0.0533 Ci in 4th 

Quarter 2014 was released to the ground from this pipe. 

Voluntary notifications were made to the Michigan Department of Environmental 

Quality, VanBuren County Administrator, Covert, Geneva, and South Haven 

Township Supervisors, as well as the City of South Haven Mayor and City 

Manager. 

The NRC Resident Inspectors were notified, and reporting was completed in 

accordance with 1 O CFR 50.72(b)(2)(xi). 

Page 5 of 10 
b. Gaseous 

None. 

7. Controlled Discharge 

a. Liquid 

None. 

b. Gaseous 

Number of releases for each quarter 

1st Quarter 2nd Quarter 3rd Quarter 4th Quarter 

0 1 8 -----'-'15"------

Total activity released in Curies (Ci) 

1st Quarter 

0 

2nd Quarter 

0.00000626 

3rd Quarter 

1.42 

8. Radioactive Waste Treatment System Changes 

None. 

9. Annual Land Use Census Changes 

4th Quarter 

0.0165 

The garden critical receptor is unchanged and remains located in the SSE sector at 

0.69 miles. The residence critical receptor is unchanged and remains in the SSW 

sector at 0.49 miles. The goat critical receptor is unchanged and remains in the NE 

sector at 2.45 miles and are fed stored feed. Beef cattle remain located in the SE 

sector at 4.27 miles. There are no dairy cows located within five miles of the plant. 

10. Effluent Monitoring System lnoperability 

One effluent monitor was out of service for greater than 30 days during the 

reporting period. 

RIA-2320, steam generator blowdown tank vent monitor, was declared inoperable 

on November 3, 2015, due to the failure of a monthly monitor functional check. 

Compensatory actions were taken in accordance with the ODCM Table A-1. The 

monitor was declared operable on December 8, 2015. The extended delay was a 

result of having to send the spare detector to the vendor upon failing to make the 

spare detector operable. 

Page 6 of 10 
11. Offsite Dose Calculation Manual (ODCM) Changes 

The Offsite Dose Calculation Manual (ODCM), ODCM Appendix A, and ODCM 

Appendix B were not revised in 2015. The General Manager Plant Operations 

approval is required for changes to the ODCM. 

The ODCM, ODCM Appendix A and ODCM Appendix B are being revised in 2016. 

Revision will include the updated meteorological data and turbine sump totalizer 

surveillance frequency. 

A copy of the ODCM, ODCM Appendix A, and ODCM Appendix B are attached in 

Enclosure 1 . 

12. Process Control Program Changes 

None. 

13. Errata/Corrections to Previous Reports 

On page 18 of 108 of the 2014 Annual Radioactive Effluent Release and Waste 

Disposal Report the volume of type 'a' waste, spent resin, filters, evaporator 

bottoms, etc., was reported as 1.38 m3 but should have been reported as 1.83 m3

. 

This means the value reported was less conservative than the actual value by 25%. 

This is considered a large error under the guidance of regulatory guide 1.21. A 

special submittal was not made to the NRC upon discovery of this error because 

the error was discovered within 90 days of the submittal of this report which is 

within guidance of Regulatory guide 1.21. The total curries shipped for this 

category was reported correctly. 

Page 7 of 10 
14. Other 

Groundwater Monitoring 

PNP has 21 ground water monitoring wells (MW) strategically placed within the 

owner controlled area to allow for detection of radioactive contamination of ground 

water due to leaks or spills from plant systems. Four of these MW were installed in 

December, 2014 for monitoring starting in 2015. PNP added 18 temporary wells 

(TW) in 2009 to determine the potential source of tritium in groundwater in the 

vicinity of MW-3. Of the 18 TW installed, 16 are still functional. Tanks T-90, 

primary makeup tank, T-91, utility water storage tank, and associated underground 

piping between these tanks and the auxiliary building addition are located in this 

area. 

TW-15 is most indicative of an historic leak that continues to be monitored. 2015 

tritium levels in TW-15 peaked in January at 31,846 pCi/L. Tritium levels spike in 

TW-15 when the water table rises from a large rainfall or spring melt. The high 

tritium levels in this area are a result of a leak which was reported to the NRC on 

December 10, 2007. None of the wells between TW-15 and Lake Michigan have 

had reportable concentrations of tritium in this reporting period. 

Monitoring of the groundwater tritium plume continues to assess repair 

effectiveness and follow the site hydrology data. Well. locations are depicted in 

Figure t. 

Depth to Local Water Table - The depth range for 2015 was approximately 7 to 8.5 

feet. 

Classification of Subsurface Aquifers - Not used for drinking water. 

Expected Movement/Mobility of Groundwater Plume - Westerly direction downgradient toward Lake Michigan at approximately 2.2 feet per day. 

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

irrigation. 

Page 8 of 10 
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-14 were constructed using the aforementioned EPRI methodology contained 

within EPRI 1021106, Estimation of Carbon-14 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. 

Gaseous C-14 is reported as C02 Curies because the major pathway by which 

C-14 contributes to the dose to man is by entering vegetables in the form of C02 

and then being ingested. 

Annual C-14 release for PNP and subsequent doses for 2015: 

Total Gaseous C-14 Released Curies= 7.74 

Gaseous C-14 as C02 Curies = 2.32 

Effective Child TB Dose, C-14 mrem = 0.0703 

Effective Child Bone Dose, C-14 mrem = 0.352 

The quarterly curies released are provided in Table 1 A, Table 1 B, arid Table 

1C. Airborne doses due to C-14 are contained in Table 1A. 

Meteorological Data 

A meteorological monitoring report is generated semiannually. From January 1, 

2015, to June 30, 2015, the meteorological data recovery was at 96% or greater for 

all variables. The two most frequently occurring directions at the 10-meter level 

were in the SSE and WNW sectors, accounting for over 22% of the observations 

from January through June. The two most frequently occurring directions at 60 

meters were WNW·and S, accounting for over 19% of the observations from 

January through June. The highest average speeds were associated with NNW 

winds at both the 10-meter and 60-meter levels. The mean speed for all directions 

at 10 meters was 3.63 mis (8.12 mph), and at 60 meters was 6.42 mis (14.36 mph). 

Compared to the same period in the previous year, the 10-meter speed was 0.23 

mis (0.51 mph) lower while the 60-meter speed was 0.50 mis (1.12 mph) lower. 

Page 9 of 10 
From July 1, 2015, to December 31, 2015, the meteorological data recovery was at 

99% or greater for all variables. The two most frequently occurring directions at the 

10-meter level were SE and SSE, which accounted for over 24% of all observations 

from July to December. At 60 meters, the two predominant directions were SW 

and NNW, which accounted for over 20% of all observations from July to 

December. The highest average speeds were associated with SE winds at 10 

meters and SW winds at 60 meters. The mean speed for all directions at 10 meters 

was 2.26 mis (5.06 mph), and at 60 meters was 4.91 mis (10.98mph). Compared to 

the same period in the previous year, the 10-meter speed is 0.02 mis (0.04 mph) 

higher while the 60-meter speed is 0.19 mis (0.43 mph) higher. 

Data from this report and the annual meteorological data (Hourly Average Data or 

Joint Frequency Distribution) will be maintained on site and will be made available 

upon NRC request. 

Page 10 of 10 

Summation of 

All Releases 

Fission and 

Activation 

Gases 

Average 

Release Rate 

% of Limit 

1-131 

Average 

Release Rate 

% of Limit 

Particulates 

Average 

Release Rate 

% of Limit 

Tritium 

Average 

Release Rate 

% of Limit 

Gross Alpha 

C-14 

Average 

Release Rate 

% of Limit 

ATTACHMENT 1 

Palisades - Table 1 A 

2015 Gaseous Effluents - Sum of All Releases 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci 2.79E+OO 1.86E+OO 2.99E+OO 3.16E+OO 

Ci/s 3.59E-01 2.36E-01 3.76E-01 3.98E-01 

3.66E-03 2.67E-03 4.69E-03 3.28E-03 

4.27E-05 3.50E-05 5.64E-05 9.45E-05 

Ci/s 5.49E-06 4.45E-06 7.10E-06 1.19E-05 

% 6.29E-08 5.09E-08 8.13E-08 1.36E-07 

Ci O.OOE+OO 1.88E-05 1.89E-05 1.82E-04 

Ci/s O.OOE+OO 2.40E-06 2.38E.:06 2.29E-05 

% O.OOE+OO 1.10E-05 1.0BE-05 9.66E-06 

Ci 1.93E+OO 1.71 E+OO 2.88E+OO 4.37E+OO 

Ci/s 2.48E-01 2.1 BE-01 3.62E-01 5.SOE-01 

% 5.68E-04 4.99E-04 8.30E-04 1,26E-03 

Ci ND ND ND ND 

Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 

Ci/s 2.73E-01 2.73E-01 2.24E-01 2.15E-01 

% 2.09E-06 2.0BE-06 1.71 E-06 1.64E-06 

Page 1 of 1 

Uncertainty Total (%) 

1.08E+01 24.03 

3.43E-01 

3.58E-03 

2.29E-04 

7.25E-06 

a .. 30E-08 

2.20E-04 

6.96E-06 

7.90E-06 

1.09E+01 

3.45E-01 

7.91 E-04 

ND 

7.74E+OO 

2.45E-01 

1.87E-06 
ATTACHMENT 1 

Palisades - Table 1 B 

2015 Gaseous Effluents - Ground Level Release, Batch Mode 

Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ar-41 Ci ND ND ND ND 

Kr-85 Ci ND ND 2.70E-04 2.35E-04 

Kr-85m Ci ND ND ND 2.30E-03 

Kr-87 Ci ND ND ND ND 

Kr-88 Ci ND ND ND ND 

Xe-131m Ci ND ND ND 2.40E-03 

Xe-133 Ci ND ND 8.40E-04 1.03E+OO 

Xe-133m Ci ND ND ND 2.13E-02 

Xe-135 Ci ND ND 2.36E-05 5.48E-02 

Xe-135m Ci ND ND ND ND 

Xe-137 Ci ND ND ND ND 

Xe-138 Ci ND ND ND ND 

(List Others) Ci ND ND ND ND 

Total Ci ND ND 1.13E-03 1.11 E+OO 

Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

1-131 Ci ND ND ND 7.99E-05 

1-132 Ci ND ND ND ND 

1-133 Ci ND ND ND ND 

1-134 Ci ND ND ND ND 

1-135 Ci ND ND ND ND 

Total Ci ND ND ND 7.99E-05 

Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Co-58 Ci ND 3.53E-08 1.02E-07 9.99E-06 

Co-60 Ci ND 1.88E-05 1.88E-05 1.60E-05 

Cr-51 Ci ND ND ND 4.25E-07 

Mn-54 Ci ND ND ND ND 

Mn-56 Ci ND ND ND ND 

Rb-88 Ci ND ND ND 1.47E"04 

Sr-89 Ci NR NR NR NR 

Sr-90 Ci NR NR NR NR 

Sr-92 Ci ND ND ND ND 

Nb-95 Ci ND ND ND 2.63E-06 

Zr-95 Ci ND ND ND 1.4BE-07 

Nb-97 Ci ND ND ND 5.43E-06 

Ag,1 iom Ci ND ND ND 1.47E-07 

Sb-125 Ci ND ND ND ND 

Cs"137 Ci ND ND ND 9.82E-08 

Ce-144 Ci ND ND ND ND 

Total Ci ND 1.88E-05 1.89E-05 1.82E-04 

Page 1 of 2 

Annual 

ND 

5.05E-04 

2.30E-03 

ND 

ND 

2.40E-03 

1.03E+OO 

2.13E-02 

5.48E-02 

ND 

ND 

ND 

ND 

1.11 E+OO 

Annual 

7.99E-05 

ND 

ND 

ND 

ND 

7.99E-05 

Annual 

1.01 E-05 

5.36E-05 

4.25E-07 

ND 

ND 

1.47E-04 

NR 

NR 

ND 

2.63E-06 

1.48E-07 

5.43E-06 

1.47E-07 

ND 

9.82E-08 

ND 

2.20E-04 
ATTACHMENT 1 

Palisades - Table 1 B 

2015 Gaseous Effluents - Ground Level Release, Batch Mode 

Fission and Activation Gases Units Quarter 1 Quarter 2 

Tritium Ci ND ND 

Gross Alpha Ci NR NR 

C-14 Ci NA NA 

ND = Measurements performed but no activity detected. 

NA = Not applicable 

NR = Analysis not required & not performed 

Page 2of2 

Quarter 3 Quarter 4 

ND 3.83E-01 

NR NR 

NA NA 

Annual 

3.83E-01 

NR 

ND 
ATTACHMENT 1 

Palisades - Table 1 C 

2015 Gaseous Effluents - Ground Level Release, Continuous Mode 

Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 

Ar-41 Ci 3.62E-01 3.01 E-01 9.40E-01 6.04E-01 2.21E+OO 

Kr-85 Ci ND ND ND ND ND 

Kr-85m Ci 7.00E-02 3.51 E-02 4.79E-02 9.47E-03 1.62E-01 

Kr-87 Ci 1.60E~01 8.11 E-02 9.45E-02 8.74E-02 4.23E-01 

Kr-88 Ci 1.16E-01 7.22E-02 3.71 E-02 3.08E-02 2.56E-01 

Xe-131m Ci ND ND ND ND ND 

Xe-133 Ci 2.46E-01 1.48E-01 3.82E-01 1.11 E-01 8.88E-01 

Xe-133m Ci ND ND ND ND ND 

Xe-135 Ci 7.04E-01 3.25E-01 4.38E-01 5.02E-01 1.97E+OO 

Xe-135m Ci 3.48E-02 1.62E-02 1.99E-03 ND 5.30E-02 

Xe-137 Ci 2.33E-01 3.54E-01 4.41 E-01 1.52E-01 1.18E+OO 

Xe-138 Ci 8.66E-01 5.26E-01 6.07E-01 5.55E-01 2.55E+OO 

Total Ci 2.79E+OO 1.86E+OO 2.99E+OO 2.05E+OO 9.69E+OO 

Iodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 

1-131 Ci 4.27E-05 3.50E-05 5.64E-05 1.46E-05 1.49E-04 

1-132 Ci ND ND ND ND ND 

1-133 Ci 8.15E"05 1.03E-04 5.76E-05 ND 2.42E-04 

1-134 Ci ND ND ND ND ND 

1-135 Ci ND ND ND ND ND 

Total Ci 1.24E~04 1.38E-04 .1.14E-04 1.46E-05 3.91 E-04 

Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Annual 

Co-58 Ci ND ND ND ND ND 

Co-60 Ci ND ND ND ND ND 

Cr-51 Ci ND ND ND ND ND 

Mn-54 Ci ND ND ND ND ND 

Mn"56 Ci ND ND ND· ND ND 

Rb-88 Ci ND ND ND ND ND 

Sr-89 Ci ND ND ND ND ND 

Sr-90 Ci ND ND ND ND ND 

Sr-92 Ci ND ND ND ND ND 

Nb-95 Ci ND ND ND ND ND 

Zr-95 Ci ND ND ND ND ND 

Nb~97 Ci ND ND ND ND ND 

Ag-110m Ci ND ND ND ND ND 

Sb-125 Ci ND ND ND ND ND 

Cs-137 Ci ND ND ND ND ND 

Ce-144 Ci ND ND ND ND ND 

Total Ci ND ND ND ND ND 

Page 1 of 2 
ATTACHMENT 1 

Palisades - Table 1 C 

2015 Gaseous Effluents - Ground Level Release, Continuous Mode 

Fission and Activation Gases Units Quarter 1 Quarter 2 Quarter3 Quarter 4 Annual 

Tritium Ci 1.93E+OO 1.71 E+OO 2.88E+OO 3.99E+OO 1.05E+01 

Gross Alpha Ci ND ND ND ND ND 

C-14 Ci 2.13E+OO 2.15E+OO 1.78E+OO 1.71 E+OO 7.74E+OO 

ND = Measurements performed but rio activity detected. 

Page 2 of 2 
ATIACHMENT1 

Palisades -Table 2A 

2015 Liquid Effluents - Sum of All Releases 

Summation of All Uncertainty Liquid Releases Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total O/o 

Fission and 

Activation Products 

(excluding tritium, 

gases, and gross 

al ha Ci O.OOE+OO 1.17E-04 4.19E-04 2.58E-03 3.11 E-03 11.50 

Average 

Concentration Ci/ml O.OOE+OO 3.49E-12 1.26E-11 8.03E-11 2.25E-11 

% of Limit % O.OOE+OO 4.97E-05 2.43E-04 1.01 E-03 3.05E-04 

Tritium Ci 8.09E+01 1.71 E+02 2.41 E+02 3.70E+01 5.30E+02 

Average 

Concentration Ci/ml 2.Q6E-06 5.10E-06 7.21 E-06 1.15E-06 3.83E-06 

% of Limit % 2.06E-01 5.1 OE-01 7.21 E-01 1.15E-01 3.83E-01 

Dissolved and 

Entrained Gases Ci O.OOE+OO O.OOE+OO 6.57E-04 O.OOE+OO 6.57E-04 

Average 

Concentration Ci/ml O.OOE+OO 0.00E+OO 1.97E-11 O.OOE+OO 4.75E-12 

% Of Limit % O.OOE+OO O.OOE+OO 9.85E-06 O.OOE+OO 2.38E-06 

Gross Alpha Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 0.00E+OO 

Average 

Concentration Ci/ml O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 

Volume of Batch 

Liquid Effluent 

(Before Dilution) Liters O.OOE+OO 1.79E+05 O.OOE+OO O.OOE+OO 1.79E+05 

Dilution Water Used 

for Above Liters 3.93E+10 3.36E+10 3.34E+10 3.21E+10 1.38E+11 

Volume of 

Continuous or 

Balance-of-Plant 

Liquid Effluent (e.g., 

low-activity or 

unprocessed) 

Before Dilution Liters 7.84E+09 7.93E+09 8.49E+09 7.75E+09 3.20E+10 

Average Stream 

Flow m3/s 5.05E+OO 4.27E+OO 4.20E+OO 4.04E+OO 4.39E+OO 

Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day 

Page 1 of 1 
Fission and Activation Units 

Products 

Cr-51 Ci 

Mn-54 Ci 

Fe-55 Ci 

Fe-59 Ci 

Co-57 Ci 

Co-58 Ci 

Co-60 Ci 

Sr-89 Ci 

Sr-90 Ci 

Nb-95 Ci 

Nb-97 Ci 

Ag-11 Om Ci 

Sn-113 Ci 

Sb-124 Ci 

Sb-125 Ci 

1-131 Ci 

1-133 Ci 

1-135 Ci 

Cs-134 Ci 

Cs-137 Ci 

Ni-63 Ci 

Zn-65 Ci 

Zr-95 Ci 

Mo-99 Ci 

Ru-105 Ci 

La-140 Ci 

Ce-141 Ci 

Ce-144 Ci 

Totals Ci 

Dissolved and Entrained Units 

Gases 

Kr-85 Ci 

Kr-85m Ci 

Kr-88 Ci 

Xe-131m Ci 

Xe-133 Ci 

Xe-133m Ci 

Xe-135 Ci 

Xe-135m Ci 

Totals 

ATTACHMENT 1 

Palisades - Table 28 

2015 Liquid Effluents - Batch Mode 

Quarter 1 Quarter 2 Quarter 3 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND 

ND ND 

ND 2.45E-05 2.42E-05 

ND ND 1.45E-04 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND 6.03E-05 

ND 9.28E-05 1.89E-04 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND 1.17E-04 4.19E-04 

Quarter 1 Quarter 2 Quarter 3 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND 6.57E-04 

ND ND ND 

ND ND ND 

ND ND ND 

ND ND 6.57E-04 

Page 1 of 2 

Quarter 4 Annual 

ND ND 

ND ND 

ND ND 

3.56E-05 3.56E-05 

ND ND 

1.51 E-03 1.56E-03 

2.15E-04 3.60E-04 

ND ND 

ND ND 

5.55E-05 5.55E-05 

ND 6.03E-05 

6.40E-04 9.22E-04 

ND ND 

ND ND 

ND ND 

ND ND 

ND ND 

ND ND 

ND ND 

2.68E-05 2.68E-05 

ND ND 

ND ND 

ND ND 

ND ND 

5.65E-05 5.65E-05 

ND ND 

ND ND 

ND ND 

2.54E-03 3.08E-03 

Quarter 4 Annual 

ND ND 

ND ND 

ND ND 

ND ND 

ND 6.57E-04 

ND ND 

ND ND 

ND ND 

ND 6.57E-04 
Fission and Activation Units 

Products 

Tritium Ci 

Gross Alpha Ci 

ND= None Detected 

ATTACHMENT 1 

Palisades - Table 28 

2015 Liquid Effluents - Batch Mode 

Quarter 1 Quarter 2 Quarter 3 

8.08E+01 1.71 E+02 2.41 E+02 

ND ND ND 

Page 2 of 2 

Quarter 4 Annual 

3.70E+01 5.30E+02 

ND ND 
Fission and Activation Units 

Products 

Cr-51 Ci 

Mn-54 Ci 

Fe-55 Ci 

Fe-59 Ci 

Co-57 Ci 

Co-58 Ci 

Co-60 Ci 

Sr-89 Ci 

Sr-90 Ci 

Nb-95 Ci 

Nb-97 Ci 

Ag-110m Ci 

Sn-113 Ci 

Sb-124 Ci 

Sb-125 Ci 

1-131 Ci 

1-133 Ci 

1-135 Ci 

Cs-134 Ci 

Cs-137 Ci 

Ni-63 Ci 

Zn-65 Ci 

Zr-95 Ci 

Mo-99 Ci 

Ru-105 Ci 

La-140 Ci 

Ce-141 Ci 

Ce-144 Ci 

Totals Ci 

Dissolved and Entrained Units 

Gases 

Kr-85 Ci 

Kr-85m Ci 

Kr-88 Ci 

Xe-131m Ci 

Xe-133 Ci 

Xe-133m Ci 

Xe-135 Ci 

Xe-135m Ci 

Totals 

ATTACHMENT 1 

Palisades -Table 2C 

2015 Liquid Effluents - Continuous Mode 

Quarter 1 Quarter2 Quarter 3 Quarter 4 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND 3.75E-05 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND 3.75E-05 

Quarter 1 Quarter 2 Quarter 3 Quarter 4 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

ND ND ND ND 

Page 1 of 2 

Annual 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

3.75E"05 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

3.75E-05 

Annual 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 

ND 
Fission and Activation Units 

Products 

Tritium Ci 

Gross Alpha Ci 

ND = None Detected 

ATTACHMENT 1 

Palisades - Table 2C 

2015 Liquid Effluents - Continuous Mode 

Quarter 1 Quarter 2 Quarter3 Quarter 4 

5.40E-02 5.34E-02 1.50E-02 1.37E-02 

ND ND ND ND 

Page 2 of 2 

Annual 

1.36E-01 

ND 
ATTACHMENT 1 

Palisades - Table 3 

2015 Low-Level Waste 

1. Solid waste shipped offsite for burial or disposal (not irradiated fuel) 

1. Type of waste Unit Estimated amount 

a. Spent resin, filters, m;:i 9.28E+OO 

evaporator bottoms, etc. Curies 2.65E+01 

b. Dry compressible waste, m;:i 2.22E+02 dry active waste 

contaminated equipment, Curies 3.50E+OO etc. 

c. Irradiated components, m;:i O.OOE+OO 

control rods, etc. Curies O.OOE+OO 

d. Other (metal waste, and m;:i 8.62E+OO 

used oil) Curies 3.67E+OO 

e. sum of all waste m;j 2.40E+02 

Curies 3.37E+01 

Page 1 of 3 

Est Total Error,% 

25 

25 

25 

25 
ATTACHMENT 1 

Palisades - Table 3 

2015 Low-Level Waste 

2. Estimate of Major Nuclide composition (by type of waste), list nuclides as needed 

a. Co-60 52% H-3 1.64% 

Fe-55 18% Sb-125 1.73% 

Ni-63 19% Co-58 5.28% 

b. Co-60 24% Co-58 16.71% 

Fe-55 17% Ni-63 11.79% 

Cs-137 1% Nb-95 5.94% 

Cr-51 5% Cm-243 1.69% 

AG-110m 4.73% H-3 1.27% 

Zr-95 3.44% C-14 2.81% 

c. NA NA NA NA 

d. H-3 3% Co-60 5.39% 

C-14 2% Ni-63 77.79% 

Sr-90 1% Fe-55 9% 

Pu-241 1% 

e. H-3 1.72% Ag-110m 1.06% 

Fe-55 16.71% Sb-125 1.43% 

Co-58 5.90% Ni-63 24.84% 

Co-60 43.70% 

NA - Not Applicable 

Page 2 of 3 
3. Solid waste disposition 

Number of shipments 

2 

1 

11 

1 

1 

ATTACHMENT 1 

Palisades - Table 3 

2015 Low-Level Waste 

Mode of transportation 

Hittman Transport 

Hittman Transport 

Hittman Transport 

Landstar lnway 

Landstar Ranger Inc. 

Destination 

Alaron-Nuclear 2138 State Route 18 

Duratek Gallaher Road Facility 628 

Gallaher Road 

Entergy Solutions Bear Creek Facility 

1560 Bear Creek Road 

Entergy Solutions Bear Creek Facility 

1560 Bear Creek Road 

Entergy Solutions Bear Creek Facility 

1560 Bear Creek Road 

Irradiated fuel shipments (disposition) 

Number of shipments 

0 

Mode of transportation 

N/A 

Page 3 of 3 

Destination 

N/A 
ATTACHMENT 1 

Palisades - Table 4 

2015 Dose Assessments, 10 CFR Part 50, Appendix I 

Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Liquid Effluent Dose Limit, Total 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 

Body 

Total Body Dose (mrem) 6.07E-05 1.52E-04 2.43E-04 2.65E-04 

% Of Limit 0.00% 0.01% 0.02% 0.02% 

Liquid Effluent Dose Limit, Any 5 mrem 5mrem 5 mrem 5 mrem 

Organ 

Liquid Effluent Organ Dose 6.07E-05 1.53E-04 2.45E-04 4.88E-04 

(mrem) 

% of Limit 0.00% 0.00% 0.00% 0.01% 

Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 

GammaAir 

Gamma Air Dose (mrad) 1.16E-03 7.62E-04 1.24E-03 9.72E-04 

% of Limit 0.02% 0.02% 0.02% 0.02% 

Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 

Beta Air 

Beta Air Dose (mrad) 8.97E-04 7.27E-04 1.03E-03 7.35E-04 

% of Limit 0.009% 0.007% 0.010% 0.007% 

Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 

Organ (mrem) (Iodine, Tritium, 

Particulates) 

Gaseous Effluent Organ Dose 4.50E-03 3.94E-03 6.07E-03 7.BBE-03 

(mrem) (Iodine, Tritium, 

Particulates) 

% of Limit 0.06% 0.05% 0.08% 0.11% 

Page 1 of 1 

Annual 

3mrem 

6.44E-04 

0.02% 

10 mrem 

8.72E-04-

0.01% 

10 mrad 

4.14E-03 

0.04% 

20 mrad 

3.39E-03 

0.017% 

15 mrem 

2.24E-02 

0.15% 
ATTACHMENT 1 

Palisades - Table 5 

2015 Dose Assessments, EPA 40 CFR Part 190, Individual in the Unrestricted Area 

Whole Body Thyroid Any Other Organ 

Dose Limit (mrem) 25 75 25 

Dose (mrem) 8.05E-02 8.98E~02 3.75E-01 

% of Limit 0.32% 0.12% 1.50% 

Page 1 of 1 
ENCLOSURE 1 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL, REVISION 26 

OFFSITE DOSE CALCULATION MANUAL APPENDIX A, REVISION 18 

OFFSITE DOSE CALCULATION MANUAL APPENDIX B, REVISION 0 

229 Pages Follow 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

ODCM 

Revision 26 

lss ued Date 7 /30/14 

TITLE: OFF SITE DOSE CALCULATION MANUAL 

J Process Applicability Exclusion D 

AKGennrich I 7/30/14 

Procedure Sponsor Date 

MESoja I 6/22/14 

Technical Reviewer Date 

CLJones I 7/29/14 

User Reviewer Date 

AL Williams I 7/29/14 

General Manager Plant Operations Date 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

Table of Contents 

I. GASEOUS EFFLUENTS ............................................................................................... 1 

A. ALARM/TRIP SETPOINT METHOD .............................................................. 1 

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 RA TE 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 

II. 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 MREMNR) .................................. 30 

F. FIGURES ..................................................................................................... 31 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

Table of Contents 

Ill. URANIUM FUEL CYCLE DOSE .................................................................................. 33 

A. SPECIFICATION .......................................................................................... 33 

8. ASSUMPTIONS ........................................................................................... 33 

C. DOSE CALCULATION ................................................................................ 34 

IV. SOURCE REFERENCE DOCUMENTS ....................................................................... 34 

Attachment 1 , 

Attachment 2, 

Attachment 3, 

Attachment 4, 

Attachment 5, 

Attachment 6, 

Attachment 7, 

Attachment 8, 

Attachment 9, 

"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 (DFGi) 

(mrem/hr per pCi/m2

)" 

"Bioaccumulation Factors (μCi/gm per μCi/ml)" 

"Ingestion Dose Commitment Factors" 

"Palisades 10 Year X/Q - D/Q Data" 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

I. GASEOUS EFFLUENTS 

A. ALARM/TRIP SETPOINT METHOD 

Appendix A, Section 111.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-131, for iodine-133, 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 111.A.1 requires gaseous effluent monitors to have alarm/trip 

setpoints to ensure that offsite concentrations, when averaged over 1 hour, will not 

be greater than Appendix A, Section 111.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. 

1 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

1. 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 = XIQ x F x Li C/ECi :5 10.0 (1.1) 

where: 

X/Q = 

F = 

Actual or measured concentration, at ambient temperature and 

pressure of nuclide i (μCi/cc) 

The EC of nuclide i from 10 CFR 20, Appendix B, Table 2 

The total EC-fraction for release point k 

Most conservative sector site boundary dispersion (sec/m3

) 

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

Release flow rate (83,000 cfm = 39.2 m3/sec) for stack monitor 

considerations; variable for other monitors 

2 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

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-133, however. Monitor response for the two categories of monitor is 

determined as follows: 

a. Normal Release (aged fission gasses) 

Total gas concentration (μCi/cc) at the monitor is calculated. The 

detector response to isotopic activities (cpm/μCi/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): 

s=bxc 

b. Accident Releases 

Monitors are preset to alarm at or before precalculated offsite dose 

rates would be achieved under hypothetical accident conditions. 

(1.2) 

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 μCi/cc (or R/hr and μCi/cc), 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 26 

B. DOSE RA TE CALCULATION 

1. 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) 

b) 

c) 

d) 

e) 

f) 

g) 

h) 

Doses to be calculated are the maximum offsite point in 

air, total body and skin. 

Exposure pathway is submersion within a cloud of noble \. 

gases. 

Noble gas radionuclide mix is based on the historically 

observed source term given in Attachment 2, plus 

additional nuclides. 

Basic radionuclide data are given in Attachment 2. 

All releases are treated as ground-level. 

Meteorological data expressed as joint-frequency 

distribution of wind speed, wind direction, and 

atmospheric stability for the period resulting in X/Q's and 

D/Q's shown in site procedure CH 6.41, "Land Use 

Census." 

Raw meteorological data consists of wind speed and 

direction measurements at 1 Om and temperature 

measurements at 1 Om and 60m. 

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 26 

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 

1 

2 

3 

4 

5 

6 

~1 

Range (m/s) 

0.0-0.4 

0.4-1.5 

1.5-3.0 

3.0-5.0 

5.0-7.5 

7.5-10.0 

> 10.0 

Midpoint (m/s) 

0.2 

0.95 

2.25 

4.0 

6.25 

8.75 

o) The stability classes that will be used are the standard A 

through G classifications. The stability classes 1-7 will 

correspond to A=1, 8=2, ... , G=7. 

p) Terrain effects are not considered. 

5 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

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: 

X = I 9 7 I ( 2) 1/2 f1k Qi P - [ ( ;i. x Jl 

' j=l k=l 7r LzkVJ (27rxln) exp IUi 

(1.3) 

where: 

= 

= 

= 

p = 

Lzk = 

Uj = 

x = 

n = 

Ai = 

2nx/n = 

Air concentration of radionuclide i, μCi/m3

. 

Joint relative frequency of occurrence of winds in 

wind speed class j, stability class k, blowing 

toward this exposure point, expressed as a 

fraction. 

Average release rate of radionuclide i, μCits. 

Fraction of radionuclide remaining in plume. 

Vertical dispersion coefficient for stability 

class k (m). 

Midpoint value of wind speed class interval j, m/s. 

Downwind distance, m. 

Number of sectors, 16. 

Radioactive decay coefficient of radionuclide i, s-1

. 

Sector width at point of interest, m. 

6 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

For determining the total body dose rate: 

where: 

Drs = 

xi = 

DFBi = 

(1.4) 

Total body dose rate, mrem/y. 

Air concentration of radionuclide I, μCi/m3

. 

Total body dose factor due to gamma radiation, 

mrem/y per μCi/m3 (Attachment 3). 

For determining the skin dose rate: 

where: 

= 

= 

1.11 = 

(1.5) 

Skin dose rate, mrem/y. 

Air concentration of radionuclide i, μCi/m3 

Skin dose factor due to beta radiation, mrem/y per 

μGi/m3 (Attachment 3). 

The average ratio of tissue to air energy 

absorption coefficients, mrem/mrad. 

Gamma-to-air dose factor for 

radionuclide i, mrad/y per μCi/m3 (Attachment 3). 

For determining dose rate to a point in air: 

(1.6) 

where: 

= Air dose rate, mrad/yr. 

Air dose factor for beta radiation (Attachment 3). 

7 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

b. Equations and assumptions for calculating doses from radioiodines 

and particulates are as follo'!lfs: 

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 X/Q's 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 

1 Om and temperature measurements at 1 Om and 60m. 

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. 

8 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

m) Plume depletion and radioactive decay are considered 

for air-concentration calculations. 

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) Equations 

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, Xi is the same 

as in the Noble Gas Section (Equation 1.3). 

For determining the organ dose rate: 

Di= 1x106 L X;DFI; BR (1.7) 

where: 

Di = 

xi = 

DFli = 

BR = 

1x106 = 

9 

Organ dose rate due to inhalation, mrem/y. 

Air concentration of radionuclide i, μCi/m3

. 

Inhalation dose factor, mrem/pCi 

(Attachment 5). 

Breathing rate 1400 m3

/y infant; 

3700 m3/y child; or 8000 m3/y teen and 

adult. 

pCi/μCi conversion factor. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

b) Ground Contamination 

For determining the ground concentration of any nuclide; 

where: 

k = 

DR = 

x = 

n = 

2mc/n = 

= 

= 

3.15x107 

= 

10 

Ground concentration of radionuclide i, 

μCi/m2

. 

Stability class. 

Joint relative frequency of occurrence of 

winds in stability class k blowing toward this 

exposure point, expressed as a fraction. 

Average release rate of radionuclide i, 

μCi/s. 

Relative deposition rate, m-1 (Fig 1.2). 

Downwind distance, m. 

Number of sectors, 16. 

Sector width at point of interest, m. 

Radioactive decay coefficient of 

radionuclide i, y-1

. 

Time for buildup of radionuclides on the 

ground, 15 y. 

s/y conversion factor. 
10 -3 

i.o-4 

~ 

-

a: 

II.I 

~ 

II.I 

:I 

cc: 

II.I 

!; 

II.I 

~ 

c( 

a: 

·-co 11J""i' 0 

~ 

~ "' Q 

"' 2

~ 

ct 

.... 

"' IC 

1o-8 

10-7 

0.1 

~ 

-

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

Figure 1.2 

.. 

' ""Iii. "' ~ 

"' '"-lilo 

-.... - .. 

~ 

......... 

'" 

. 1.0 10.0 

PLUME TRAVEL DISTANCE (KILOMETERS) 

" 

Corrected 

January 1977 

' 

I 

I I I I ~ : ' 'l : 

I I ! 

i 

j 

; 

' ... 

'\\. I 

"' ...... 

I I 

; 

i I ! 

I 1 

! 

' I 

I I J 11 

I 

' 

11 I; j 

100.0 200.0 

Figure 7. Relative Deposition for Ground Level R1leam (All Atmospheric 

St1bility Cl1sses) 

n - -- r11 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

For determining the total body or organ dose rate from 

ground contamination: 

Da = (8, 760)(1X106)(0. 7) LG; DFG; (1.9) 

where: 

8,760 = 

1x106 = 

0.7 = 

Dose rate due to ground contamination, 

mrem/y. 

Ground concentration of radionuclide i, 

μCi/m2

. 

Dose factor for standing on contaminated 

ground, mrem/h per pCi/m2 (Attachment 6). 

Occupation time, h/y. 

pCi/μCi conversion factor. 

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: 

7 . 

. = 3 600 L fkQ;DR (r[l-exp(-A,E;te)] + B;Jl-exp(-.4/b)]Jrrex (- . )]] (

1.10) CV, , (2 xi) . PA. u_ P .4,!b k = 1 Jr n Yv AE1 i 

where: 

cvi = 

k = 

fk = 

12 

Concentration of radionuclide i in and on 

vegetation, μCi/kg. 

Stability class. 

Frequency of this stability class and wind 

direction combination, expressed as a 

fraction. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

Qi = Average release rate of radionuclide i, 

μCi/s. 

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

x = Downwind distance, m. 

n = Number of sectors, 16. 

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

r = Fraction of deposited activity retained on 

vegetation (1.0 for iodines, 0.2 for 

particulates). 

AEi = Effective removal rate constant, 

AEi = Ai + "'J..w, where Ai is the radioactive 

decay coefficient, h-1

, and "'J..w is a measure 

of physical loss by weathering 

("'J..w = 0.0021 h} 

te = Period over which deposition occurs, 720 h. 

Yv = Agricultural yield, 0.7 kg/m2

. 

Biv = Transfer factor from soil to vegetation of 

radionuclide i (Attachment 4). 

Ai = Radioactive decay coefficient of 

radionuclide i, h-1. 

tb = Time for buildup of radionuclides on the 

ground, 1.31x105 h (15Y). 

p = Effective surface density of soil, 240 kg/m2

. 

3,600 = s/h conversion factor. 

th = Holdup time between harvest and 

consumption of food (2, 160 hours for stored 

food). 

13 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

For determining the concentration of C-14 in vegetation: 

CV14 =1 X103 X14 (0.11/0.16) (1.11) 

where: 

0.11 = 

0.16 = 

1x103 = 

Concentration of C-14 in vegetation, μCi/kg. 

Air concentration of C-14, μCi/m3

. 

Fraction of total Plant mass that is natural 

carbon. 

Concentration of natural carbon in the 

atmosphere, g/m3

. 

g/kg conversion factor. 

For determining the concentration of H-3 in vegetation: 

CVr=1x1Q3 Xr(0.75)(0.5/H) (1.12) 

where: 

CVr = 

Xr = 

0.75 = 

0.5 = 

H = 

1x103 = 

14 

Concentration of H-3 in vegetation, μCi/m3

. 

Air concentration of H-3, μCi/m3

. 

Fraction of total Plant mass that is water. 

Ratio of tritium concentration in Plant water 

to tritium concentration in atmospheric 

water. · 

Absolute humidity of the atmosphere, g/m3

. 

g/kg conversion factor. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

For determining the concentration of any nuclide in cow's 

or goat's milk: 

where: 

CMi = 

cvi = 

FMi = 

Ot = 

= 

= 

15 

(1.13) 

Concentration of radionuclide i (including 

C-14 and H-3) in milk, μCi/I. 

Concentration of radionuclide i in and on 

vegetation, μCi/kg. 

Transfer factor from feed to milk for 

radionuclide i, d/I (Attachment 4). 

Amount of feed consumed by the milk 

animal per day, kg/d (cow, 50 kg/d or 

goat 6 kg/d). 

Radioactive decay coefficient of 

radionuclide i, d-1

• 

Transport time of activity from feed to milk 

to receptor, 2 days. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

For determining the organ dose rate from ingestion 'Of 

green leafy vegetables and milk: 

D=l xl06 LCM; DE UM (1.14) 

where: 

D = 

CMi = 

DFi = 

UM = 

1x106 = 

Organ dose rate due to ingestion, mrem/y. 

Concentration of radionuclide i in 

vegetables or milk, μCi/kg (or liters). 

Ingestion dose factor, mrem/pCi 

(Attachment 8). 

Ingestion rate for milk, 330 l/y; for 

vegetables 26 kg/yr (child), no ingestion by 

infant. 

pCi/μCi conversion factor. 

d) Meat Ingestion (Beef) 

To calculate the concentration of a nuclide in animal 

flesh: 

where: 

cfi = 

16 

(1.15) 

Concentration-of nuclide i in the animal 

flesh, pCi/kg. 

Fraction of animal's daily intake which 

appears in each kg of flesh, days/kg 

(Attachment 4). 

Concentration of radionuclide i in the 

animal's feed (Equation 1.10). 
,, 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

= 

= 

Amount of feed consumed by the cow per 

day, 50 kg/d. 

Average time from slaughter to 

consumption, 20 days. 

To determine the organ dose from ingestion of beef: 

where: 

= 

= 

Ingestion dose factor for age group, 

mrem/pCi (Attachment 8) for nuclide i. 

Ingestion rate of meat for age group, 

kg/y (child-41, teen-65, adult-110). 

(1.16) 

e) OrganDose Rates 

For determining the total body and organ dose rate from 

iodines and particulates: 

(1.17) 

where: 

D = Total organ dose rate, mrem/y. 

D1 = 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 26 

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 Slowdown 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 Iodines 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 26 

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 l.B. 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 

system's consistent performance well below Appendix I limits, no additional 

operability requirements are specified. 

19 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

D. RELEASE RA TE 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 I to 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 X/Q, 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 26 

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-1 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 μCi/cc. Sampling 

and analysis will be performed per Appendix A, Table B-1 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 
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PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

11. LIQUID EFFLUENTS 

A. CONCENTRATION 

1. Requirements 

Appendix A, Section 111.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 μCi/ml 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. 

c = 

where: 

c = 

= 

Total concentration in the liquid effluent at the release 

point, μCi/ml. 

Concentration of a single radionuclide i, μCi/ml. 

23 

(2.1) 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

3. Effluent Concentration (EC) - Sum of the Ratios 

The EC-Fraction (Rj) for each release point will be calculated by the 

relationship defined by Note 4 of Appendix B, 10 CFR 20: 

Rj 

where: 

Ci = 

ECi = 

Ri = 

I __9_:::;10.0 

EC 

Effluent concentration of radionuclide i, μCi/ml. 

The EC of radionuclide i, 10 CFR 20, Appendix B, Table 2, 

Column 2 - μCi/ml. 

The Total EC-Fraction for the release point. 

(2.2) 

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: 

where: 

= 

= 

F = 

(2.3) 

The effluent flow rate (gallons/minute) for the respective 

releases, determined by Plant personnel. 

The Total EC-Fractions for the respective releases as 

determined by Equation 2.2. 

Minimum required dilution flow rate. Normally, a 

conservatively high dilution flow rate is used, that is, flow 

rate used = (bi)(F) where bi is a conservative factor 

greater than 1.0. 

24 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

B. INSTRUMENT SETPOINTS 

1. Setpoint Determination 

Appendix A, Section 111.F requires alarm setpoints for each liquid effluent 

monitor will be established using Plant instructions to ensure the 

requirements of Appendix A, Section 111.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 hours 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 hours per Appendix A, Table C-1, 

Action 3. 

25 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

3. Post-Release Analysis 

C. DOSE 

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 (Ci), 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. 

1. RETS Requirement 

Appendix A, Section 111.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 11.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: 

Di I (DCF)ii x h 

i= I 

26 

(2.5) 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

where: 

= Dose for the r organ from radionuclides releases, mrem. 

(DCF)ij 

= The organ of interest. 

= Ingestion dose commitment factor for the jth organ from 

the i

1

h radionuclide mrem/pCi, see Attachment 8. 

= Activity ingested of the i

1

h radionuclide, pCi. 

Ii is described by: 

I·= (Ai)(V)(365) (1E06) 

I (1QQQ)(d} (2.6) 

where: 

365 = 

Ai = 

v = 

d = 

1000 = 

1E06 = 

Days per year. 

Annual activity released of i

1

h radionuclide, μCi. 

Average rate of water consumption (2000 ml/d - adult, 

1400 ml/d - teen and child, 900 ml/d - infant, ICRP 23, p 

358). 

Dilution water flow for year, ml. 

Dispersion factor from discharge to nearest drinking 

water supply. 

Conversion μCi to pCi. 

The dose equation then becomes: 

i 

Di= .SS~OS)(V) L: (DCF)iiXAimrem 

i=1 

(2.7) 

27 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

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 

(h) is described by: 

_ AiBiF(1E09) _ c· 

h- 15d -p I 

where: 

= 

= 

Annual released of ith radionuclide, μCi. 

Fish concentration factor of ith radionuclide 

(see Attachment 7). 

μCi/gm 

μCi/ml 

(2.8) 

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 μCi, gm, and Kg to pCi. 

Substitution of Equation 2.8 into Equation 2.5 gives: 

i 

(6.7E07)F Di= d I AiXBiXDCFimrem 

i = 1 

28 

(2.9) 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

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 LADT AP. The dose to the j1h organ from m 

radionuclides, Dj, is described by: 

m 

Di= I oiimrem 

i = 1 

m 

= I (DCF )ii x Ii mrem 

i = 1 

where: 

(2.10) 

(2.11) 

Dose to the j1h organ from the i

1

h radionuclide, mrem. 

= 

(DCF)ij = 

= 

The organ of interest (bone, GI tract, thyroid, liver, 

kidney, lung, or total body). 

Adult ingestion dose commitment factor for the j1h organ 

from the i

1

h radionuclide, mrem/pCi (see Attachment 8). 

Activity ingested of the i

1

h radionuclide, μCi. 

h for water ingestion is described by: 

I _AiVr er· ·---μ 

I Vd 

and for fish ingestion Ii is described by: 

29 

(2.12) 

(2.13) 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

where: 

Ai = 

v = 

r = 

v = 

d = 

Bi = 

F = 

Activity release of j1h radionuclide during the year, μCi. 

Average rate of water consumption (2000 mild). 

Number of days during the year (365 d). 

Dispersion factor from point of discharge to point of 

exposure. 

Dilution water volume (ml). 

Fish concentration factor of the i

1

h radionuclide, 

μCi/gm 

Attachment 7, μCi/ml 

Amount of fish eaten per day (57.5 gm/d). 

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, 111.H.1. 

E. RELEASE RATE FOR OFFSITE EC (50 MREMNR) 

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 I to 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 mrem/yr total body value. 

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U\ (}\ 

{ ! 

1' 215 METERS 

I 

~· rl '11 I L1.; ("Q 

SITE NVIRONMENT 

TLO STATIONS 

PALISADES NUCLEAR PLANT 

SIT£ OUNDARY 

FIGIJ E 2-1 ------------------+----·--·---·-----------'·-----+--------' 
...J 

<C 

::::> 

1-Z 

z<C 

<C :!: 

...J z a. 0 

0::: i= <C :5 co i w N 

...J ::::> c: u u 0 

::::> ...J 'iii 

Z<( ·s; 

enU Cl) 

w w 0::: 

c en <C 0 ~ c 

...J w 

<C Ia.-en 

u. 

u. 

0 

PALISADES RADWASTE EFFLUENTS - uauro I!"'· ,-,, 

I 

~-· .-I 

•H I f:l[l\N 1

y, CJ 

Wl\STE 

SYSllM 

TRE!\IEn 

WASTE 

TANKS(]J 

MISCHI ANEOUS WASTE SYSTEM 

(DIJ!TY WASTE) 

LAUNDRY 

SYSTEM 

flll[Rf.D 

WASTE 

TANK 

UTILITY 

WATF.R 

STORAGE 

TANK 

T-91 

PRIMARY 

SYSTEM 

STORAGE 

TANK 

T·!IO 

TRIP & FLOW CONTROL 

r----, 

I 

RE 1049 t--D::]--, 

TURBINE BLDG 

DRAINS ----. 

RE 08JJ 

. ~A~~1~E ................ _ ... 

LAKE 

SERVICE WATER ___ ,___..._ ________ LA_K_E_IN...;l;:.;,E;..:T __ -Yr 

N 

('(') 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

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 111.C.1, 111.D.1, or 111.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 11.C.2.1 and 11.C.2.2. 

2. Amount of shore line fishing (at accessible shoreline adjacent to site security 

fence) is conservatively assumed as 48 hours 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 hours for the fourth quarter and 16 hours for the 

first quarter. 

33 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

Revision 26 

C. DOSE CALCULATION 

Maximum doses to the total body and internal organs of an individual shall be 

determined by use of LADTAP and GASPAR 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. 

D4o = (2.15) 

where: 

D4o = 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). 

Rr = 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, R 1. 

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, R1. 

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 1 

Revision 26 

Page 1of1 

PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESNEAR (1) 

Nuclide 

H-3 

Kr-85 

Kr-85m 

Kr-87 

Kr-88 

Ar-41 

Xe-131m 

Xe-133 

Xe-133m 

Xe-135 

Xe-135m 

1-131 

1-132 

1-133 

1-134 

1-135 

Na-24 

Cr-51 

Mn-54 

Co~57 

Co-58 

Fe-59 

Co-60 

Se-75 

Nb-95 

Zr-95 

Mo-99 

Ru-103 

Sb-127 

Cs-134 

Cs-136 

Cs-137 

Ba-140 

La-140 

Unidentified beta 

Gaseous(2) 

5.5 

4.1 

0.12 

8.4E-02 

2.1E-01 

3.1E-02 

2.2 

1493 

0.43 

1.11 

0.3 

0.025 

2.91E-03 

6.5E-03 

4.8E-04 

1.84E-02 

1.5E-06 

'2.5E-04 

4.1E-04 

2.1 E-06 

8.6E-04 

6.6E-06 

1.1E-03 

3.7E-06 

2.4E-05 

4.7E-06 

1.5E-07 

0.3E-07 

NA 

4.5E-05 

NA 

2.6E-04 

2.8E-07 

7.5E-07 

3.9E-04 

Liquid(2) 

159 

NA 

NA 

NA 

NA 

NA 

NA 

NA 

NA 

NA 

NA 

3.21E-03 

NA 

4.7E-05 

NA 

NA 

NA 

3.9E-03 

7.8E-03 

3.2E-05 

2.9E-02 

4.1E-04 

1.24E-02 

NA 

4.53E-04 

1.79E-04 

NA 

0.1 E-05 

3.5E-05 

0.7 

1.8E-06 

1.36E-02 

NA 

1.1 E-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 26 

Page 1of2 

BASIC RADIONUCLIDE DATA 

NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1 

(days) (1/s) (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 4.91 E-01 1.02E 00 

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 1.02E 00 

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 1.07E-01 7.50E-05 8.29E-01 1.69E 00 

12 FE-59 4.50E 01 1.78E-07 1.18E-01 1.19E 00 

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 2.21E-03 3.63E-03 1.36E 00 1.83E 00 

24 RB-88 1.24E-02 6.47E-04 2.06E 00 6.26E-01 

25 RB-89 1.07E-02 7.50E-04 1.01E 00 2.05E-OO 

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 7.1 OE-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 3.00E-06 9.36E-01 0.0 

32 Y-91m 3.47E-02 2.31E-04 2.73E-02 5.30E-01 

33 Y-91 5.88E 01 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 6.50E 01 1.23E-07 1.16E-01 7.35E-01 

37 NB-95m 3.75E 00 2.14E-06 1.81 E-01 6.06E-02 

38 NB-95 3.50E 01 2.29E-07 4.44E-02 7.64E-01 

39 M0-99 2.79E 00 2.87E-06 3.96E-01 1.50E-01 

40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01 
41 

42 

43 

44 

45 

46 

47 

48 

49 

50 

51 

52 

53 

54 

55 

56 

57 

58 

59 

60 

61 

62 

63 

64 

65 

66 

67 

68 

Proc No ODCM 

Attachment 2 

Revision 26 

Page 2 of2 

BASIC RADIONUCLIDE DATA 

NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA1 

~ (1/s) (MEV/DIS) (MEV/DIS) 

TC-99 7.74E 07 1.04E-13 8.46E-02 0.0 

TC-104 1.25E-02 6.42E-04 1.60E 00 1 ,95E 00 

RU-106 3.67E 02 2.19E-08 1.01 E-02 0.0 

TE-132 3.24E 00 2.48E-06 1.00E-01 2.33E-01 

1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02 

1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01 

1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00 

1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01 

1-134 3.61E-02 2.22E-04 6.16E-01 2.59E 00 

1-135 2.79E-01 2.87E-05 3.68E-01 1.55E 00 

XE-131m 1.18E 01 6.80E-07 1.43E-01 2.01E-02 

XE-133m 2.26E 00 3.55E-06 1.90E-01 4.15E-02 

XE-133 5.27E 00 1.52E-06 1.35E-01 4.60E-02 

XE-135m 1.08E-02 7.43E-04 9.58E-02 4.32E-01 

XE-135 3.83E-01 2.09E-05 3.17E-01 2.47E-01 

XE-137 2.71E 03 2.96E-03 1.77E 00 1.88E-01 

XE-138 9.84E-03 8.15E-04 6.65E-01 1.10E 00 

CS-134 7.48E 02 1.07E-08 1.63E-01 1.55E 00 

CS-135 1.10E 09 7.29E-15 5.63E-02 0.0 

CS-136 1.30E 01 6.17E-07 1.37E-01 2.15E 00 

CS-137 1.10E 04 7.29E-10 1.71E-01 5.97E-01 

CS-138 2.24E-02 3.58E-04 1.20E 00 2.30E 00 

BA-139 5.76E-02 1.39E-04 8.96E-01 3.53E-02 

BA-140 1.28E 01 6.27E-07 3.15E-01 1.71 E-01 

LA-140 1.68E 00 4.77E-06 5.33E-01 2.31E00 

CE-144 2.84E 02 2.82E-08 9.13E-02 1.93E-02 

PR-143 1.36E 01 5.90E-07 3.14E-01 0.0 

PR-144 1.20E-02 6.68E-04 1.21E 00 3.18E 00 

Average energy per disintegration values were obtained from ICRP Publication No 38, 

Radionuclide Transformations: Energy and Intensity of Emissions 1983 and 

NUREG/CR-1413 (ORNUNUREG-70), a Radionuclide Decay Data Base - Index and 

Summary Table, DC Kocher, May 1980. 
Proc No ODCM 

Attachment 3 

Revision 26 

Page 1of1 

DOSE FACTORS FOR SUBMERSION IN NOBLE GASES* 

Gamma body Gamma air Beta skin Beta air 

dose1 dose2 dose1 dose2 

Kr-85m 1.17E3 1.23E3 1.46E3 1.97E3 

Kr-85 1.61 E1 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 1.01 E4 1.06E4 

Xe-131 m 9.15E1 1.56E2 4.76E2 1.11 E3 

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 1.81 E3 1.92E3 1.86E3 2.46E3 

Xe-137 1.42E3 1.51 E3 1.22E4 1.27E4 

Xe-138 8.83E3 9.21E3 4.13E3 4.75E3 

Ar-41 8.84E3 9.30E3 2.69E3 3.28E3 

1. mrem/y per μCi/m3 

2. mrad/y per μCi/m3 

*Dose factors for exposure to a semi-infinite cloud of noble gases. Values were obtained from 

USN RC Regulatory Guide 1.109, Revision 1 (October 1977). 
ELEMENT 

H 

c 

Na 

p 

Cr 

Mn 

Fe 

Co 

Ni 

Cu 

Zn 

Rb 

Sr 

y 

Zr 

Nb 

Mo 

Tc 

Ru 

Rh 

Ag 

Te 

I 

Cs 

Ba 

La 

Ce 

Pr 

Nd 

w 

Np 

STABLE ELEMENT TRANSFER DATA 

Fm - MILK (COW) Fm - MILK (GOAT) Ft- MEAT 

(DAYS/L) (DAYS/L) (DAYS/KG) 

1.0E-02 1.?E-01 1.2E-02 

1.2E-02 1.0E-01 3.1 E-02 

4.0E-02 4.0E-02 3.0E-02 

2.5E-02 2.5E-01 4.6E-02 

2.2E-03 2.2E-03 2.4E-03 

2.5E-04 2.5E-04 8.0E-04 

1.2E-03 1.3E-04 4.0E-02 

1.0E-03 1.0E-03 1.3E-02 

6.?E-03 6.?E-03 5.3E-02 

1.4E-02 1.3E-02 8.0E-03 

3.9E-02 3.9E-02 3.0E-02 

3.0E-02 3.0E-02 3.1 E-02 

8.0E-04 1.4E-02 6.0E-04 

1.0E-05 1.0E-05 4.6E-03 

5.0E-06 5.0E-06 3.4E-02 

2.5E-03 2.5E-03 2.8E-01 

7.5E-03 7.5E-03 8.0E-03 

2.5E-02 2.5E-02 4.0E-01 

1.0E-06 1.0E-06 4.0E-01 

1.0E-02 1.0E-02 1.5E-03 

5.0E-02 5.0E-02 1.?E-02 

1.0E-03 1.0E-03 7.?E-02 

6.0E-03 6.0E-02 2.9E-03 

1.2E-02 3.0E-01 4.0E-03 

4.0E-04 4.0E-04 3.2E-03 

5.0E-06 5.0E-06 2.0E-04 

1.0E-04 1.0E-04 1.2E-03 

5.0E-06 5.0E-06 4.?E-03 

5.0E-06 5.0E-06 3.3E-03 

5.0E-04 5.0E-04 1.3E-03 

5.0E-06 5.0E-06 2.0E-04 

Proc No ODCM 

Attachment 4 

Revision 26 

Page 1of1 

Biv 

(VEG/SOIL) 

4.8E-OO 

5.5E-OO 

5.2E-02 

1.1 E-00 

2.5E-04 

2.9E-02 

6.6E-04 

9.4E-03 

1.9E-02 

1.2E-01 

4.0E-01 

1.3E-01 

1.?E-02 

2.6E-03 

1.?E-04 

9.4E-03 

1.2E-01 

2.5E-01 

5.0E-02 

1.3E+01 

1.5E-01 

1.3E-OO 

2.0E-02 

1.0E-02 

5.0E-03 

2.5E-03 

2.5E-03 

2.5E-03 

2.4E-03 

1.8E-02 

2.5E-03 
INHALATION DOSE COMMITMENT FACTORS 

Proc NoODCM 

Attachment 5 

Revision 26 

Page 1 of 16 

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 

BE10 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. 6.10E-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.S4E-06 7.S4E-06 7.S4E-06 7.S4E-06 

P32 1.4SE-03 8.03E-OS S.S3E-OS 0. 0. 0. 1.1SE-OS 

AR39 0. 0. 0. 0. 0. 1.00E-08 0. 

AR41 0. 0. 0. 0. 0. 3.14E-08 0. 

CA41 7.48E-OS 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07 

SC46 3.?SE-04 5.41E·04 1.69E-04 0. 3.S6E-04 0. 2.19E-OS 

CRS1 0. 0. 6.39E-08 4.11E-08 9.4SE-09 9.176-06 2.SSE-07 

MNS4 0. 1.81 E-OS 3.S6E-06 0. 3.S6E-06 7.14E-04 S.04E-06 

MNS6 0. 1.10E-09 1.S8E-10 0. 7.86E-10 8.9SE-06 S.12E-OS 

FESS 1.41E-OS 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E-07 

FES9 9.69E-06 1.68E-OS 6.77E-06 0. 0. 7.2SE-04 1.77E-05 

COS? 0. 4.6SE-07 4.S8E-07 0. 0. 2.71E-04 3.47E-06 

C058 0. 8.71E-07 1.306-06 0. 0. S.SSE-04 7.95E-06 

C060 0. S.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-OS 

Nl59 1.81 E-OS 5.44E-06 3.10E-06 0. 0. S.48E-OS 6.34E-07 

Nl63 2.42E-04 1.466-05 8.29E-06 0. 0. 1.49E-04 1.73E-06 

Nl6S 1.71E-09 2.03E-10 8.79E-11 0. 0. S.80E-06 3.58E-OS 

CU64 0. 1.34E-09 5.53E-10 0. 2.84E-09 6.64E-06 1.07E-OS 

ZN65 1.38E-OS 4.47E-OS 2.22E-OS 0. 2.32E-OS 4.62E-04 3.67E-05 

ZN69M 8.98E-09 1.84E-08 1.67E-09 0. 7.4SE-09 1.91 E-OS 2.92E-OS 

ZN69 3.85E-11 6.91E-11 S.13E-12 0. 2.87E-11 1.05E-06 9.44E-06 

SE79 0. 2.2SE-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. 

BR8S 0. 0. 1.46E-08 0. 0. 0. 0. 

KR83M 0. 0. 0. 0. 0. 2.SOE-09 0. 

KR8SM 0. 0. 0. 0. 0. 1.31E-oa 0. 

KR8S 0. 0. 0. 0. 0. 1.16E-08 0. 

KR87 0. 0. 0. 0. 0. 6.S9E-08 0. 

KR88 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-OS 0. 0. 0. 2.17E-06 

RB87 0. 7.11 E-OS 2.64E-0S 0. 0. 0. 2.99E-07 

RB88 0. 3.98E-07 2.0SE-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. 8.1SE-06 0. 0. 1.4SE-03 4.S7E-OS 

SR90 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-OS 

SR91 6.83E-08 0. 2.47E-09 0. 0. 3.76E-OS S.24E-OS 

SR92 7.50E-09 0. 2.79E-10 0. 0. 1.70E-OS 1.00E-04 

*Includes a SO% increase to account for percutaneous transpiration. 
INHALATION DOSE COMMITMENT FACTORS 

Proc NoODCM 

Attachment 5 

Revision 26 

Page 2of16 

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 

Y91M 2.91E-10 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 1.00E-04 

N893M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 

N895 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 

N897 2.44E-10 5.21 E-11 1.BBE-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 

TC101 4.65E-14 5.BBE-14 5.BOE-13 0. 6.99E-13 4.17E-07 6.03E-07 

RU103 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 

RU105 8.74E-10 0. 2.93E-10 0. 6.42E-10 1.12E-05 3.46E-05 

RU106 6.20E-05 0. 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04 

RH105 8.26E-09 5.41 E-09 3.63E-09 0. 1.50E-08 2.0BE-05 1.37E-05 

PD107 0. 4.92E~07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07 

PD109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 

AG110M 7.13E-06 5.16E-06 3.57E-06 0. 7.BOE-06 2.62E-03 2.36E-05 

AG111 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.BOE-04 1.40E-03 1.65E-05 

CD115M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05 

8N123 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.0BE-05 

8N125 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0. 6.43E-04 7.26E-05 

8N126 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 

88124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 

88125 · 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 

88126 3.0BE-06 6.01E-08 1.11E-06 2.35E-08 0. 6.BBE-04 5.33E-05 

88127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 

TE125M 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 

TE129M 1.01 E-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.BBE-05 

TE131M 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05 

TE131 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 

TE133M 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.BBE-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. 7.56E-07 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 3of16 

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

1132 1.21 E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-06 0. 1.36E-06 

1133 9.46E-06 1.37E-05 4.00E-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. 1.31 E-06 

XE131M 0. 0. 0. 0. 0. 6.77E-09 0. 

XE133M 0. 0. 0. 0. 0. 8.89E-09 0. 

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

XE135M 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 2.10E-07 1.11E-07 0. 8.50E-08 2.00E-08 1.16E-07 

CSt34 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 1.01 E-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 3.61E-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 

BA140 4.00E-05 4.00E-08 2.07E-06 0. 9.59E-09 1.141:-03 2.74E-05 

BA141 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 1.11 E~o6 4.95E-07 

LA140 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-10 0. 0. 1.22E-05 5.96E-05 

LA142 7.36E-10 2.69E-10 6.46E-11 0. 0. 5.87E-06 4.25E-05 

CE141 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 1.00E-05 3.74E-06 4.99E-07 0. 1.41 E-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 5.81E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 

PM147 3.91E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 

PM148M 5.0QE-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 3.10E-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.01E-05 

PM151 7.52E-08 1.10E-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 

TB160 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.11 E-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 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page4of16 

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

PB210 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05 

81210 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 4.00E-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-01 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-OO 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+OO 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+OO 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 1.10E-02 2.86E-02 0. 5.61E-02 4.65E+OO 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+OO 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+OO 3.87E-05 

TH232 3.86E+OO 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+OO 3.29E-05 

TH234 1.33E-05 7.17E-07 3.84E-07 0. 2.70E-06 .1.62E-03 7.40E-05 

PA231 9.10E+OO 3.00E-01 3.62E-01 0. 1.62E+OO 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+OO 4.36E-05 

U233 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03EM05 

U234 5.22E-02 0. 3.75E-03 0. 1.07E-02 3.49E-01 3.95E-05 

U235 5.01E-02 0. 3.52EM03 0. 1.01E-02 . 3.28E-01 5.02E-05 

U236 5.01E-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 1.31 E-05 

U238 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05 

NP237 3.03E+OO 2.32E-01 1.26E-01 0: 7.69E-01 3.49E-01 5.10E-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+OO 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05 

PU239 5.50E+OO 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05 

PU240 6.49E+OO 6.71E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05 

PU241 1.55E-01 6.69E-03 3.11E-03 0. 1.15E-02 7.62E-04 8.97EM07 

PU242 5.09E+OO 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05 

PU244 5.95E+OO 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05 

AM241 1.84E+OO 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05 

AM242M 1.90E+OO 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01E-05 

AM243 1.82E+OO 8.10E-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05 

CM242 8.58E-02 7.44E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.10E-05 

CM243 1.73E+OO 7.94E-01 1.06E-01 0. 3.91 E-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+OO 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05 

CM246 2.24E+OO 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05 

CM247 2.18E+OO 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05 

CM248 1.82E+01 7.12E+OO 1.10E+OO 0. 4.24E+OO 3.23E+OO 9.43E-04 

CF292 4.26E+OO 0. 1.01E-01 0. 0. 1.37E+OO 1.85E-04 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 5of16 

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 

BE10 8.43E-04 9.83E-OS 2.12E~os 0. 0. 7.41E-04 1.72E-OS 

C14 9.70E-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.~SE-07 0. 0. 0. 3.37E-07 

NA22 4.41E-OS 4.41 E-OS 4.41E-OS 4.41E-OS 4.41E-OS 4.41 E-OS 4.41E-OS 

NA24 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 4.3SE-06 

P32 7.04E-04 3.09E-OS 2.67E-OS 0. 0. 0. 1.14E-OS 

AR39 0. 0. 0. 0. 0. 4.89E-09 0. 

AR41 0. 0. 0. 0. 0. 1.68E-08 0. 

CA41 7.06E-OS 0. 7.70E-06 0. 0. 7.21E-02 2.94E-07 

SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.4SE-OS 

CRS1 0. 0 .. 4.17E-08 2.31E-08 6.S7E-09 4.S9E-06 2.93E-07 

MNS4 0. 1.16E-OS 2.S7E-06 0. 2.71E-06 4.26E-04 6.19E-06 

MNS6 0. 4.48E-10 8.43E-11 0. 4.S2E-10 3.SSE-06 3.33E-OS 

FESS 1.28E-OS 6.BOE-06 2.10E-06 0. 0. 3.00E-OS 7.7SE-07 

FES9 S.S9E-06 9.04E-06 4.S1E-06 0. 0. 3.43E-04 1.91 E-OS 

COS? 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.SBE-06 

COSS 0. 4.79E-07 8.SSE-07 0. 0. 2.99E-04 9.29E-06 

C060 0. 3.SSE-06 6.12E-06 b. 0. 1.91 E-03 2.60E-OS 

NIS9 1.66E-OS 4.67E-06 2.83E-06 0. 0. 2.73E-OS 6.29E-07 

Nl63 2.22E-04 1.2SE-OS 7.S6E-06 0. 0. 7.43E-OS 1.71E-06 

Nl6S 8.0BE-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-OS 

CU64 0. S.39E-10 2.90E-10 0. 1.63E-09 2.S9E-06 9.92E-06 

ZN65 1.1SE-OS 3.06E-OS 1.90E-OS 0. 1.93E-OS 2.69E-04 4.41E-06 

ZN69M 4.26E-09 7.28E-09 8.S9E-10 0. 4.22E-09 7.36E-06 2.71E-OS 

ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.SBE-11 3.84E-07 2.7SE-06 

· SE79 0. 1.23E-06 2.60E-07 0. 1.71E-06 1.49E-04 3.43E-06 

BR82 0. 0. S.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. 

BR8S 0. 0. 6.84E-09 0. 0. 0. 0. 

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

KR8SM o .. 0. 0. 0. 0. 6.SBE-09 0. 

KR8S 0. 0. 0. 0. 0. S.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.SSE-08 0. 

RB86 0. S.36E-OS 3.09E-OS 0. 0. 0. 2.16E-06 

RB87 0. 3.16E-OS 1.37E-OS 0. 0. 0. 2.96E-07 

RB88 0. 1.o2E-07 9.90E-08 0. 0. 0. 4.66E-09 

RB89 0. 9.33E-08 7.83E-08 0. 0. 0. S.11E-10 

SR89 1.62E-04 0. 4.66E-06 0. 0. S.83E-04 4.S2E-OS 

SR90 2.73E-02 0. 1.74E-03 0. o, 3.99E-03 9.28E-OS 

SR91 3.28E-08 0. 1.24E-09 0. 0. 1.44E-OS 4.70E-OS 

SR92 3.S4E-09 0. 1.42E-10 0. 0. 6.49E-06 6.SSE-OS 

*Includes a SO% increase to account for percutaneous transpiration. 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 6of16 

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

Y90 1.11 E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 

Y91M 1.37E-10 0. 4.98E-12 0. 0. 7.606-07 4.64E-07 

Y91 2.47E-04 0. 6.59E-06 o. 0. 7.10E-04 4.97E-05 

Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 

Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01E-05 1.05E-04 

ZR93 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.10E-04 1.47E-05 

ZR95 5.13E-05 1.13E-05 1.00E-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 

NB95 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.00E-05 

NB97 1.16E-10 2.08E-11 9.74E-12 0. 2.31 E-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 

TC101 2.19E-14 2.30E-14 2.91E-13 0. 3.92E-13 1.58E-07 4.41E-09 

RU103 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21 E-05 

RU105 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 

RU106 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 

RH105 3.91E-09 2.10E-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 

PD107 0. 2.65E-07 2.51E-08 0. 1.97E-06 3.16E-05 7.26E-07 

PD109 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 

AG110M 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71E-05 

AG111 1.81 E-07 5.68E-08 3.75E-08 0. 1.71 E-07 7.73E-05 2.98E-05 

CD113M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 

CD115M 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 2.00E-07 5.41E-06 3.41E-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 1.00E-08 0. 2.86E-04 5.67E-05 

SB127 1.36E-07 2.09E-09 4.70E-08 1.51 E-09 0. 6.17E-05 3.826-05 

TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 

TE127M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.00E-04 1.93E-05 

TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-10 1.91 E-09 2.71E-06 1.52E-05 

TE129M 5.19E-06 1.85E-06 8.22E-07 1.71 E-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 

TE131M 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 1.01E-10 1.60E-06 4.77E-06 

TE134 1.53E-11 8.81E-12 9.40E-12 1.24E-11 5.71 E-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 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 7of16 

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/SOY PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

1132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 

1133 4.48E-06 5.49E-06 2.0BE-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 

XE131M 0. 0. 0. 0. 0. 3.30E-09 0. 

XE133M 0. 0. 0. 0. 0. 4.36E-09 0. 

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

XE135M 0. 0. 0. 0. 0. 4.48E-09 0. 

XE135 0. o. 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~oa 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 1.71 E-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-10 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05 

BA140 2.00E-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05 

BA141 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 

LA140 1.74E-07 6.0BE-08 2.04E-08 0. 0. 4.94E-05 6.10E-05 

LA141 2.28E-09 5.31E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 

LA142 3.50E-10 1.11E-10 3.49E-11 0. 0. 2.35E-06 2.05E-05 

CE141 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 1.83E-03 5.72E-04 9.77E-05 o: 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 8.10E-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-Q5 

PM147 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 

PM148M 3.31E-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 6.01E-05 

PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 

PM151 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~o5 1.87E-05 

EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.nE-04 9.00E-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 

TB160 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. 4.01E-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 1.11 E-05 

W187 4.41E-09 2.61E-09 1.17E-09 0. 0. 1.11 E-05 2.46E-05 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 8of16 

CHILD INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROIO KIDNEY LUNG GI-LLI 

PB210 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05 

81210 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 3.00E-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 1.21 E-04 0. 1.99E-04 7.37E-02 2.67E-04 

AC227 4.96E+OO 8.05E-01 3.07E-01 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+OO 3.59E-04 

TH229 1.28E+01 1.76E-01 6.31 E-01 0. 8.68E-01 1.04E+01 3.27E-04 

TH230 3.30E+OO 1.73E-01 9.20E-02 0. 8.52E-01 1.85E+OO 3.84E-05 

TH232 3.68E+OO 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+OO 3.27E-05 

TH234 6.94E-06 3.07E-07 2.00E-07 0. 1.62E-06 6.31E-04 7.32E-05 

PA231 8.62E+OO 2.86E-01 3.43E-01 0. 1.56E+OO 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 4.00E-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. 7.01E-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+OO 2.21 E-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+OO 6.05E-01 1.21 E-01 0. 4.47E-01 6.0BE-01 4.65E-05 

PU239 5.24E+OO 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05 

PU240 5.23E+OO 6.436-01 1.27E-01 0. 4.77E-01 5.71E-01 4.33E-05 

PU241 1.46E-01 6.33E-03 2.93E-03 0. 1.10E-02 5.06E-04 8.90E~07 

PU242 4.85E+OO 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05 

PU244 5.67E+OO 7.10E-01 1.41 E-01 0. 5.27E-01 6.30E-01 6.20E-05 

AM241 1.74E+OO 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05 

AM242M 1.79E+OO 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05 

AM243 1.72E+OO 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+OO 7.33E-01 9.95E-02 0. 3.74E-01 2.10E-01 4.98E-05 

CM244 1.33E+OO 6.48E-01 8.31E-02 0. 3.06E-01 2.02E-01 4.82E-05 

CM245 2.14E+OO 8.16E-01 1.28E-'01 0. 5.03E-01 1.95E-01 4.49E-05 

CM246 2.13E+OO 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05 

CM247 2.07E+OO 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.BOE-05 

CM248 1.72E+01 6.61E+OO 1.04E+OO 0. 4.08E+OO 1.61E+OO 9.35E-04 

CF252 3.92E+OO 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04 
INHALATION DOSE COMMITMENT FACTORS 

Proc NoODCM 

Attachment 5 

Revision 26 

Page 9of16 

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

H3* 0. 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 1.S9E-07 

BE10 2.78E-04 4.33E-OS 7.09E-06 0. 0. 3.84E-04 1.77E-OS 

C14 3.2SE-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 

N13 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 8.6SE-09 

F18 6.S2E-07 0. 7.10E-08 0. 0. 0. 3.89E-08 

NA22 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 1.76E-OS 

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-OS 8.9SE-06 0. 0. 0. 1.16E-OS 

AR39 0. 0. 0. 0. 0. 4.00E-09 0. 

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

CA41 4.0SE-OS 0. 4.38E-06 0. 0. 1.01E-01 3.03E-07 

SC46 7.24E-OS 1.41E-04 4.18E-OS 0. 1.3SE-04 0. 2.98E-OS 

CRS1 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.7SE-07 

MNS4 0. 6.39E-06 1.0SE-06 0. 1.S9E-06 2.48E-04 8.3SE-06 

MNS6 0. 2.12E-10 3.1SE-11 0. 2.24F-10 1.90E-06 7.18E-06 

FESS 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.SSE-OS 7.99E-07 

FES9 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91 E-04 2.23E-OS 

COS7 0. 1.18E-07 1.1SE-07 0. 0. 7.33E-OS 3.93E-06 

COSS 0. 2.S9E-07 3.47E-07 0. 0. 1.68E-04 1.19E-OS 

C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-OS 

NIS9 S.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-OS 6.48E-07 

Nl63 7.2SE-OS S.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06 

Nl6S 2.73E-10 3.66E-11 1.S9E-11 0. 0. 1.17E-06 4.S9E-06 

CU64 0. 2.S4E-10 1.06E-10 0. 8.01E-10 1.39E-06 7.68E-06 

ZN6S 4.82E-06 1.67E-OS 7.BOE-06 0. 1.08E-OS 1.SSE-04 S.83E-06 

ZN69M 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-OS 

ZN69 6.04E-12 1.1SE-11 8.07E-13 0. 7.S3E-12 1.98E-07 3.S6E-08 

SE79 0. S.43E-07 8.71E-08 0. 8.13E-07 7.71E-OS 3.S3E-06 

BR82 0. 0. 2.28E-06 0. 0. 0. 0. 

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

BR84 0. 0. S.41E-08 0. 0. 0. 0. 

BR8S 0. 0. 2.29E-09 0. 0. 0. 0. 

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

KR8SM 0. 0. 0. 0. 0. S.46E-09 0. 

KR8S 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. S.81E-08 0. 

KR89 0. 0. 0. 0. 0. 3.BSE-08 0. 

RB86 0. 2.38E-OS 1.0SE-OS 0. 0. 0. 2.21E-06 

RB87 0. 1.40E-OS 4.SBE-06 0. 0. 0. 3.0SE-07 

RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.6SE-1S 

RB89 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17 

SR89 S.43E-OS 0. 1.S6E-06 o. 0. 3.02E-04 4.64E-OS 

SR90 1.3SE-02 0. 8.3SE-04 0. 0. 2.06E-03 9.S6E-OS 

SR91 1.10E-08 0. 4.39E-10 0. 0. . 7.S9E-06 3.24E-OS 

SR92 1.19E-09 0. S.OBE-11 0. 0. 3.43E-06 1.49E-OS 

*Includes a SO% increase to account for percutaneous transpiration. 
INHALATION DOSE COMMITMENT FACTORS 

Proc NoODCM 

Attachment 5 

Revision 26 

Page 10of16 

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

Y90 3.73E-07 0. 1.00E-08 0. 0. 3.66E-05 6.99E-05 

Y91M 4.63E-11 0. 1.77E-12 0. 0. 4.00E-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 

N893M 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 

N895 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21 E-05 

N897 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. 2.11 E-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 

TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 

RU103 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 

RU105 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1.13E-05 

RU106 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.01E-03 1.20E-04 

RH105 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 

PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 

PD109 0. 6.56E-10 1.66E-10 0. 3.36E"09 3.19E-06 1.96E-05 

AG110M 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41E-05 

AG111 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 

CD113M 0. 2.17E-04 7.10E-06 0. 2.43E-04 3.59E-04 1.68E-05 

CD115M 0. 3.48E-05 1.14E-oe 0. 2.82E-05 3.03E-04 5.10E-05 

8N123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 

8N125 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 

8N126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05 

88124 5.38E-06 9.92E-OB 2.10E-06 1.22E-08 0. 4.81E-04 4.98E-05 

88125 9.23E-06 1.01 E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 

88126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01E-05 

88127 4.64E-08 9.92E-10 1.75E-08 5.21 E-10 0. 3.31E-05 3.94E-05 

TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 

TE127M 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 9.10E-10 1.40E-06 1.01 E-05 

TE129M 1.74E-06 8.23E-07 2.81E-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 

TE131M 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 5.61E-05 5.79E-05 

TE133M 1.01E-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 3.306-06 1.83E-03 1.05E-05 0. 8.11 E-07 
INHALATION DOSE COMMITMENT FACTORS 

Proc NoODCM 

Attachment 5 

Revision 26 

Page 11of16 

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 

1133 1.52E-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 

XE131M 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. 

CS134M 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 1.51 E-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. 1.11E-13 8.08E-07 8.06E-07 

BA140 6.84E-06 . 8.38E-09 4.4.0E-07 0. 2.85E-09 2.54E-04 2.86E-05 

BA141 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.11E-07 9.33E-14 

BA142 4.62E-12 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 

LA140 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 

LA141 7.63E-10 2.35E-10 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 

CE141 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. 1.51 E-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 1.10E-05 4.50E-06 0. 2.10E-05 1.14E-04 5.87E-06 

PM148M 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.10E-05 

PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 

PM149 4.91E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 

PM151 1.20E-08 1.99E-09 1.01E-09 0. 3.57E-09 6.56E-06 2.27E-05 

SM151 1.07E-:04 2.10E-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 

SM153 2.43E-08 2.01E-08 1.47E-09 0. 6.56E-09 7.11 E-06 1.77E-05 

EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.01E-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 2.00E-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51 E-03 5.97E-05 

EU156 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 

TB160 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. 2.00E-04 6.24E-04 1.68E-05 

W181 8.90E-09 2.88E-09 3.01E-10 o, 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 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 12of16 

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

PB210 3.09E-02 8.28E-03 1.0?E-03 0. 2.95E-02 4.52E-02 3.87E-05 

81210 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. 4.21 E-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-01 3.11E-04 

RA228 5.34E-02 1.74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E~05 

AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81E-02 2.?0E-04 

AC227 2.49E+OO 3.69E-01 1.48E-01 0. 1.0?E-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+OO 3.?0E-04 

TH229 9.06E+OO 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+OO 3.36E-04 

TH230 2.34E+OO 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05 

TH232 2.61E+OO 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+OO 2.00E-01 2.0?E-01 0. 1.12E+OO 9.91E-02 4.71E-05 

PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.00E-05 

U232 7.31E-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. 3.41E-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. 8.10E-04 0. 3.12E-03 7.89E-02 3.62E-05 

NP237 1.77E+OO 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 8.11 E-06 1.65E-05 

PU238 2.86E+OO 4.06E-01 7.22E-02 0. 3.1 OE-01 3.12E-01 4.79E-05 

PU239 3.31E+OO 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05 

PU240 3.31E+OO 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+OO 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05 

PU244 3.59E+OO 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05 

AM241 1.06E+OO 4.0?E-01 7.10E-02 0. 5.32E-01 1.05E-01 4.88E-05 

AM242M 1.07E+OO · 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05 

AM243 1.06E+OO 3.92E-01 6.95E-02 0. 5.21E-01 9.91E-02 5.72E-05 

CM242 2.12E-02 2.14E-02 1.41 E-03 0. 6.40E-03 6.76E-02 5.21E-05 

CM243 8.45E-01 3.50E-01 5.00E-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+OO 4.11E-01 7.53E-02 0. 3.52E-01 1.01E-01 4.63E-05 

CM246 1.31E+OO 4.11E-01 7.52E-02 0. 3.51 E-01 1.03E-01 4.54E-05 

CM247 1.28E+OO 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05 

CM248 1.06E+01 3.33E+OO 6.11E-01 0. 2.85E+OO 8.32E-01 9.63E-04 

CF252 1.29E+OO 0. 3.0?E-02 0. 0. 3.43E-01 1.89E-04 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 13of16 

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 

BE10 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 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 

NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-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. 

CA41 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07 

SC46 5.51E-05 1.07E-04 3.11E-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-11 0. 1.63E-10 1.18E-06 2.53E-06 

FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.01E-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 

Nl59 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11E-07 

Nl63 5.40E-05 3.93E-06 1.81 E-06 0. 0. 2.23E-05 1.67E-06 

Nl65 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.00E-07 1.54E-06 

CU64 0. 1.83E-10 7.69E-11 0. 5.76E-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 3.336-06 

BR82 0. 0. 1.69E-06 0. 0. 0. 1.30E-06 

BR83 0. 0. 3.01E-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. 2.91E-09 0. 

KR85 0. 0. 0. 0. 0. 2.41E-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. 1.75E-04 4.37E-05 

SR90 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. 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 14of16 

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

Y90 2.61E-07 0. 7.01E-09 0. 0. 2.12E-05 6.32E-05 

Y91M 3.26E-11 0. 1.27E-12 0. 0. 2.40E-07 1.66E-10 

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-10 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 1.51 E-06 

ZR95 1.34E-05 4.30E-06 2.91E-06 0. 6.77E-06 2.21E-04 1.88E-05 

ZR97 1.21 E-08 2.45E-09 1.13E-09 0. 3.71E-09 9.84E-06 6.54E-05 

NB93M 3.10E-05 1.01E-05 2.49E-06 0. 1.16E-05 3.11 E-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 3.00E-07 3.02E-08 

M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.11E-05 3.79E-06 

M099 0. 1.51E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.10E-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 1.01 E-04 7.54E-06 

TC101 5.22E-15 7.52E-15 7.38E-14 0. 1.35E-13 4.99E-08 1.36E-21 

RU103 1.91 E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 1.38E-05 

RU105 9.88E-11 0. 3.89E-11 0. 1.27E-10 1.37E-06 6.02E-06 

RU106 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 

RH105 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05 

PD107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 

PD109 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 

AG110M 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 

AG111 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 

CD113M 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.SOE-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 6.00E-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. 3.10E-04 5.0SE-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 6.01E-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 1.31 E-07 1.55E-06 3.92E-05 8.83E-06 

TE127M 1.58E-06 7.21E-07 1.96E-07 4.11 E-07 5.72E-06 1.20E-04 1.87E-05 

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 

TE131 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 2.11E-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 o. 7.85E-07 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 15of16 

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-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 

XE131M 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. 

CS134M 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 9.10E-05 0. 3.59E-05 1.22E-05 1.30E-06 

CS1.35 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-b6 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. 6.00E-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-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 

BA140 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E-05 

BA141 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 

LA140 4.30E-08 2.17E-08 5.73E-09 0. 0. . 1.70E-05 5.73E-05 

LA141 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 

CE141 2.49E-06 1.69E-06 1.91 E-07 0. 7.83E-07 4.52E-05 1.50E-05 

CE143 2.33E-08 1.72E-08 1.91 E-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 

PM148M 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 

PM151 8.50E-09 1.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.00E-05 

SM151 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 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 

EU154 7.40E-04 9.10E-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 

EU155 1.01E-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 

TB160 2.21E-05 0. 2.75E-06 0. 9.10E-06 1.92E-04 2.68E-05 

H0166M 3.37E-04 1.05E-04 8.00E-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 3.10E-10 0. 0. 3.63E-06 1.94E-05 
INHALATION DOSE COMMITMENT FACTORS 

Proc No ODCM 

Attachment 5 

Revision 26 

Page 16of16 

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

PB210 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05 

81210 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.BOE-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 3.01E-04 

RA225 3.00E-04 3.56E-07 5.99E-05 0. 1.01 E-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 4.41E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61E-01 5.00E-05 

AC225 4.23E-04 5.82E-04 2.84E-05 0. 6.63E-05 2.21E-02 2.52E-04 

AC227 2.30E+OO 3.05E-01 1.36E-01 0. 9.82E-02 2.41E-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 2.00E-01 3.39E~03 6.77E-03 0. 1.89.E-02 1.01E+OO 3.49E-04 

TH229 8.88E+OO 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+OO 3.17E-04 

TH230 2.29E+OO 1.31E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3.73E-05 

TH232 2.56E+OO 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+OO 1.91E-01 1.98E-01 0. 1.076+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 1.00E-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05 

U236 1.00E-02 0. 6.20E-04 0. 2.39E-03 5.00E-02 3.57E-05 

U237 3.67E-08 0. 9.77E-09 0. 1.51 E-07 1.02E-05 1.20E-05 

U238 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41 E-05 

NP237 1.69E+OO 1.47E-01 6.87E-02 0. 5.10E-01 5.22E-02 4.92E-05 

NP238 2.96E-07 8.00E-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+OO 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05 

PU239 3.19E+OO 4.31E-01 7.75.E-02 0. 3.30E-01 1.72E-01 4.13E-05 

PU240 3.18E+OO 4.30E-01 7.73E-02 0. 3.29E-01 1.72E-01 4.21E-05 

PU241 6.41 E-02 3.28E-03 1.29E-03 0. 5.93E-03 1.52E-04 8.65E-07 

PU242 2.95E+OO 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05 

PU244 3.45E+OO 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05 

AM241 1.01E+OO 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05 

AM242M 1.02E+OO 3.46E-01 6.73E-02 0. 5.01 E-01 2.44E-02 5.79E-05 

AM243 1.01E+OO 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 4.91E-05 

CM243 7.86E-01 2.97E-01 4.616-02 0. 2.15E-01 6.31E-02 4.84E-05 

CM244 5.90E-01 2.54E-01 3.51E-02 0. 1.64E-01 6.06E-02 4.68E-05 

CM245 1'.26E+OO 3.59E-01 7.14E-02 0 .. 3.33E-01 5.85E-02 4.36E-05 

CM246 1.25E+OO 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05 

CM247 1.22E+OO 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05 

CM248 1.01 E+01 2.91 E+OO 5.79E-01 0. 2.70E+OO 4.82E-01 9.096-04 

CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04 
Proc No ODCM 

Attachment 6 

Revision 26 

Page 1of2 

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l 

(mrem/hr per pCi/m2

) 

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.BOE-09 6.80E-09 

Mn-56 1.10E-08 1.30E-08 

Fe-55 0.0 0.0 

Fe-59 8.00E-09 9.40E-09 

Co-58 7.00E-09 8.20E-09 

Co-60 1.70E-08 2.00E-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 4.00E-09 4.60E-09 

Zn-69 0.0 0.0 

Br-83 6.40E-11 9.30E-11 

Br-84 1.20E-08 1.40E-08 

Br-85 0.0 0.0 

Rb-86 6.30E-10 7.20E-10 

Rb-88 3.50E-09 4.00E-09 

Rb-89 1.50E-08 1.80E-08 

Sr-89 5.60E-13 6.50E-13 

Sr-91 7.10E-09 8.30E-09 

Sr-92 9.00E-09 1.00E-08 

Y-90 2.20E-12 2.60E-12 

Y-91m 3.BOE-09 4.40E-09 

Y-91 2.40E-11 2.70E-11 

Y-92 1.60E-09 1.90E-09 

Y-93 5.70E-10 7.80E-10 

Zr-95 5.00E-09 5.80E-09 

Zr-97 5.50E-09 6.40E-09 

Nb-95 5.10E-09 6.00E-09 

Mo-99 1.90E-09 2.20E-09 

Tc-99m 9.60E-10 1.10E-09 

Tc-101 2.70E-09 3.00E-09 
Proc No ODCM 

Attachment 6 

Revision 26 

Page 2 of 2 

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1l 

(mrem/hr per pCi/m2

) 

ELEMENT TOTAL BODY SKIN 

Ru-103 3.60E-09 4.20E-09 

Ru-105 4.50E-09 5.10E-09 

Ru-106 1.50E-09 1.80E-09 

Ag-110m 1.80E-08 2.10E-08 

Te-125m 3.50E-11 4.80E-11 

Te-127m · 1.10E-12 1.30E-12 

Te-127 1.00E-11 1.10E-11 

Te-129m 7.70E-10 9.00E-10 

Te-129 7.10E-10 8.40E-10 

Te-131m 8.40E-09 9.90E-09 

Te-131 2.20E-09 2.60E-06 

Te-132 1.70E-09 2.00E-09 

1-130 1.40E-08 1.70E-08 

1-131 2.80E-09 3.40E-09 

1-132 1.70E-08 2.00E-08 

1-133 3.70E-09 4.50E-09 

1-134 1.60E-08 1.90E-08 

1-135 1.20E-08 1.40E-08 

Cs-134 1.20E-08 1.40E-08 

Cs-136 1.50E-08 1.70E-08 

Cs-137 4.20~-09 4.90E-09 

Cs-138 2.10E-08 2.40E-08 

Ba-139 2.40E-09 2.70E-09 

Ba-140 2.10E-09 2.40E-09 

Ba-141 4.30E-09 4.90E-09 

Ba-142 7.90E-09 9.00E-09 

La-140 1.50E-08 1.70E-08 

La-142 1.50E-08 1.80E-08 

Ce-141 5.50E-10 6.20E-10 

Ce-143 2.20E-09 2.50E-09 

Ce-144 3.20E-10 3.70E-10 

Pr-143 0.0 0.0 

Pr-144 2.00E-10 2.30E-10 

Nd-147 1.00E-09 1.20E-09 

W-187 3.10E-09 3.60E-09 

Np-239 9.50E-10 1.10E-09 
ELEMENT 

H 

c 

NA 

p 

CR 

MN 

FE 

co 

NI 

cu 

ZN 

BR 

RB 

SR 

y 

ZR 

NB 

MO 

TC 

RU 

RH 

~TE 

I 

cs 

BA 

LA 

CE 

PR 

ND 

w 

NP 

BIOACCUMULATION FACTORS 

uCi/gm per uCi/ml 

Proc NoODCM 

Attachment 7 

Revision 26 

Page 1 of 1 

FRESHWATER 

FISH 

9.0E-01 

4.6E 03 

1.0E 02 

1.0E 05 

2.0~ 02 

4.0E 02 

1.0E 02 

5.0E 01 

1.0E 02 

5.0E 01 

2.0E 03 

4.2E 02 

2.0E 03 

3.0E 01 

2.5E 01 

3.3E 00 

3.0E 04 

1.0E 01 

1.5E 01 

1.0E 01 

1.0E 01 

4.0E 02 

1.5E 01 

2.0E 03 

4.0E 00 

2.5E 01 

1.0E 00 

2.5E 01 

2.5E 01 

1.2E 03 

1.0E 01 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 1 of 16 

INGESTION DOSE COMMITMENT FACTORS 

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/SOY 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 

BE10 1.71 E-OS 2.49E-06 S.16E-07 0. 1.64E-06 0. 2.78E-OS 

C14 2.37E-OS S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 S.06E-06 

N13 S.8SE-08 S.8SE-08 S.8SE-08 S.83SE-08 S.8SE-08 S.8SE-08 S.8SE-08 

F18 S.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06 

NA22 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 9.83E-OS 

NA24 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 1.01 E-OS 

P32 1.70E-03 1.00E-04 6.S9E-OS 0. 0. 0. 2.30E-OS 

AR39 0. 0. 0. 0. 0. 0. 0. 

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

CA41 3.74E-04 0. 4.08E-OS 0. 0. 0. 1.91 E-07 

SC46 3.7SE-08 S.41 E-08 1.69E-08 0. 3.S6E-08 0. 3.S3E-OS 

CRS1 0. 0. 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-07 

MNS4 0. 1.99E-OS 4.S1E-06 0. 4.41E-06 0. 7.31E-06 

MNS6 0. 8.18E-07 1.41E-07 0. 7.03E-07 0. 7.43E-OS 

FESS 1.39E-OS 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06 

FES9 3.08E-OS S.38E-OS 2.12E-OS 0. 0. 1.S9E-OS 2.S7E-OS 

COS7 0. 1.1SE-06 1.87E-06 0. 0. 0. 3.92E-06 

COS8 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06 

C060 0. 1.08E-OS 2.SSE-OS 0. 0. 0. 2.S7E-OS 

NIS9 4.78E-OS 1.4SE-OS 8.17E-06 0. 0. 0. 7.16E-07 

Nl63 6.34E-04 3.92E-OS 2.20E-OS 0. 0. 0. 1.9SE-06 

Nl6S 4.70E-06 S.32E-07 2.42E-07 0. 0. 0. 4.0SE-OS 

CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.2SE-OS 

ZN6S 1.84E-OS 6.31E-OS 2.91E-OS 0. 3.06E-OS 0. S.33E-OS 

ZN69M 1.SOE-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-OS 

ZN69 9 .. 33E-08 1.68E-07 1.2SE-08 0. 6.98E-08 0. 1.37E-OS 

SE79 0. 2.10E-OS 3.90E-06 0. 2.43E-OS 0. S.S8E-07 

BR82 0. 0. 1.27E-OS 0. 0. 0. 0. 

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

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

BR8S 0. 0. 1.94E-08 0. 0. 0. 0. 

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

KR8SM 0. 0. 0. 0. 0. 0. 0. 

KR8S 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-OS 0. 0. 0. 4.3SE-06 

RB87 0. 8.88E-OS 3.S2E-OS 0. 0. 0. S.98E-07 

RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.8SE-07 

R889 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08 

SR89 2.S1E-03 0. 7.20E-OS 0. 0. 0. S.16E-OS 

SR90 1.8SE-02 0. 4.71E-03 0. 0. 0. 2.31E-04 

SR91 S.OOE-OS 0. 1.81 E-06 0. 0. 0. S.92E-OS 

SR92 1.92E-OS 0. 7.13E-07 0. 0. 0. 2.07E-04 
Proc NoODCM 

Attachment 8 

Revision 26 

Page 2of16 

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 

Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 

Y91M 8.10E-10 0. 2.76E-11 0. 0. 0. 2.70E-06 

Y91 1.13E-06 0. 3.01E-08 0. 0. 0. 8.10E-05 

Y92 7.65E-09 0. 2.15E-10 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. 5.41E-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. 1.21 E-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 

TC101 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 

RU103 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 

RU105 1.36E-07 0. 4.58E-08 0. 1.00E-06 0. 5.41 E-05 

RU106 2.41E-05 0. 3.01E-06 0. 2.85E-05 0. 1.83E-04 

RH105 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 

PD107 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 

AG110M 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05 

AG111 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 

CD115M 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 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11E-04 

SN126 5.53E-04 7.26E-06 1.80E-05 1.91 E-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 

TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.11E-05 

TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05 

TE127 1.00E-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.10E-05 

TE129M 1.00E-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 

TE131M 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. 7.11E-06 

TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.81E-05 

TE133M 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 6.00E-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 NoODCM 

Attachment 8 

Revision 26 

Page 3of16 

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 

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 

XE131M 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. o. 0. 

CS134M 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 7.10E-05 0. 1.81 E-04 7.42E-05 1.91 E-06 

CS135 1.33E-04 1.21 E-04 6.30E-06 0. 3.44E-05 1.31 E-05 4.37E-07 

CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.10E-05 2.05E-06 

CS137 5.22E-04 6.11E-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91 E-06 

CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 

CS139 3.10E-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 

BA140 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 

LA140 2.11 E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05 

LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61E-05 

LA142 1.10E-09 4.04E-10 9.67E-11 0. 0. 0. 6.86E-05 

CE141 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. 1.71 E-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 o, 4.93E-06 

Nb147 5.53E-08 5.68E-08 3.48.E-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 

PM148M 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 1.81 E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05 

PM151 6.18E-09 9.01E-10 4.56E-10 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 1.51 E-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 

TB160 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 26 

Page 4of16 

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 

PB210 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05 

81210 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05 

P0210 3.10E-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 3.29E-05 2.91E-03 0. 6.00E-04 0. 3.86E-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. 8.71E-04 0. 3.44E-04 

RA228 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05 

AC225 3.92E-05 5.03E-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 2.01E-06 3.45E-06 0. 7.41 E-06 0. 5.70E-04 

TH228 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04 

TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31E-04 

TH230 3.80E-03 1.90E-04 1.06E-04 0. 9.12E-04 0. 6.24E-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 2.00E-08 0. 1.39E-07 0. 1.19E-04 

PA231 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 0. 7.44E-05 

PA233 3.11E-08 6.09E-09 5.43E-09 0. 1.67E-08 0. 1.46E-05 

U232 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05 

U233 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.51E-05 

U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.37E-05 

U235 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.10E-05 

U236 4.67E-03 0. 3.64E-04 0. 1.01 E-03 0. 5.98E-05 

U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.11E-05 

U238 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.71E-05 

NP237 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.23E-05 

NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.17E-05 

NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05 

PU238 1.34E-03 1.69E-04 3.40E-05 0. 1.21E-04 0. 7.57E-05 

PU239 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.91E-05 

PU240 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 7.04E-05 

PU241 4.38E-05 1.90E-06 8.82E-07 0. 3.17E-06 0. 1.45E-06 

PU242 1.35E-03 1.70E-04 3.41E-05 0. 1.23E-04 0. 6.77E-05 

PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41 E-04 0. 1.01 E-04 

AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 0. 7.70E-05 

AM242M 1.58E-03 7:02E-04 1.13E-04 0. 6.64E-04 0. 9.69E-05 

AM243 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.03E-05 

CM242 1.37E-04 1.24E-04 9.10E-06 0. 2.62E-05 0. 8.23E-05 

CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.10E-05 

CM244 1.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05 

CM245 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.30E-05 

CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31E-04 0. 7.17E-05 

CM247 1.82E-03 7.36E-04 1.11E-04 0. 4.24E-04 0. 9.43E-05 

CM248 1.51E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.52E-03 

CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 5of16 

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 Gl-LLI 

H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 

BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05 

C14 1.21 E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 

N13 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-08 3.10E-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.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-06 5.BOE-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. 

CA41 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. 3.00E-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 6.10E-06 1.89E-06 . o. 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.BOE-06 5.51E-06 0. 0. 0. 1.05E-05 

C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05 

Nl59 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.10E-07 

Nl63 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06 

Nl65 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. 6.41E·06 

ZN69M 7.10E-07 1.21 E-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. 5.11 E-05 

SR90 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 26 

Page 6of16 

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 Gl-LLI 

Y90 4.11 E-08 0. 1.10E-09 0. 0. 0. 1.17E-04 

Y91M 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07 

Y91 6.02E-07 0. 1.61 E-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 1.01 E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04 

NB93M 1.05E-07 2.62E-08 8.61E-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. 1.21 E-05 

M093 0. 2.41 E-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. 1.10E-05 

TC99M 9.23E-10 1.81 E-09 3.00E-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 

TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91 E-08 5.92E-10 3.56E-09 

RU103 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E-05 

RU105 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05 

RU106 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 

RH105 5.14E-07 2.76E-07 2.36E-07 0. 1.10E-06 0. 1.71 E-05 

PD107 0. 4.72E-07 4.01E-08 0. 3.95E-06 0. 9.37E-07 

PD109 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 

AG110M 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05 

AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05 

CD113M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 

CD115M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.01E-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 1.59E-06 5.55E-07 0. 0. 1.10E-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. 2.10E-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. 1.10E-05 

TE127M 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0. 2.34E-05 

TE127 4.71E-07 1.27E-07 1.01E-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. 1.01 E-04 

TE131 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07 

TE132 1.01 E-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 5.37E-07 0. 5.89E-07 

1.129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 

1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 

1131 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0. 1.54E-06 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 7of16 

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 Gl-LLI 

1132 8.00E-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. 

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. 

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 8.10E-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 2.01E-07 0. 2.23E-07 2.40E-08 1.46E-07 

CS139 1.45E-07 1.61E-07 7.74E-08 0. 1.21 E-07 1.22E-08 1.45E-11 

BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 

BA140 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05 

BA141 2.00E-07 1.12E-10 6.51E-09 0. 9.69E-11 6.58E-10 1.14E-07 

BA142 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09 

LA140 1.01 E-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 

CE141 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-10 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. 6.39E-09 0. 4.24E-05 

PR144 1.29E-10 3.99E-11 6.49E-12 0. 2.11E-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. 4.01E-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 

PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05 

SM151 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 5.62E-08 3.01E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05 

TB160 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. 1.61 E-05 

W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 8of16 

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 Gl-LLI 

PB210 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.576-05 

81210 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.1.7E~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. 3.21E-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. 5.81E-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 7.00E-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~o5 0. 8.67E-04 0. 6.19E-05 

TH232 3.96E-03 1.52E-04 3.01E-04 0. 7.41E-04 0. 5.27E-05 

TH234 3.42E-07 1.51 E-08 9.88E-09 0. 8.01E-08 0. 1.18E-04 

PA231 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05 

PA233 1.81 E-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 b. 6.10E-04 0. 6.45E-05 

U234 3.57E-03 0. 2.21E-04 0. 5.98E-04 0. 6.32E-05 

U235 3.42E-03 0. 2.07E-04 0. 5.61E-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. 6.81E-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 1.81 E-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 4.00E-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. 1.00E-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. 4.10E-04 0. 7.11E-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. 1.51 E-03 

CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04 
Proc NoODCM 

Attachment 8 

Revision 26 

Page 9of16 

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 Gl-LLI 

H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E~07 

BE10 4.48E-06 6.94E-07 1.13E-07 0. S.30E-07 0. 2.84E-OS 

C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 

N13 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 1.1SE-08 

F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08 

NA22 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 2.34E-OS 

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-OS 1.07E-OS 0. 0. 0. 2.32E-OS 

AR39 0. 0. 0. 0. 0. 0. 0. 

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

CA41 1.97E-04 0. 2.13E-OS 0. 0. 0. 1.9SE-07 

SC46 7.24E-09 1.41 E-08 4.18E-09 0. 1.3SE-08 0. 4.80E-OS 

CRS1 0. 0. 3.60E-09 2.00E-09 7.89E-10 S.14E-09 6.0SE-07 

MNS4 0. S.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-OS 

MNS6 0. 1.S8E-07 2.81E-08 0. 2.00E-07 0. 1.04E-OS 

FESS 3.78E-06 2.68E-06 6.2SE-07 0. 0. 1.?0E-06 1.16E-06 

FES9 S.87E-06 1.37E-OS S.29E-06 0. 0. 4.32E-06 3.24E-OS 

COS? 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06 

COS8 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-OS 

C060 0 2.81E-06 6.33E-06 0. 0. 0. 3.66E-OS 

NIS9 1.32E-OS 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07 

Nl63 1.77E-04 1.2SE-OS 6.00E-06 0. 0. 0. 1.99E-06 

Nl6S 7.49E-07 9.S?E-08 4.36E-08 0. 0. 0. S.193-06 

CU64 0. 1.1SE-07 S.41 E-08 0. 2.91E-07 0. 8.92E-06 

ZN6S S.76E-06 2.00E-05 9.33E-06 0. 1.28E-OS 0. 8.47E-06 

ZN69M 2.40E-07 S.66E-07 S.19E-08 0. 3.44E-07 0. 3.11E-OS 

ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. S.16E-08 

SE79 0. 3.73E-06 6.27E-07 0. 6.SOE-06 0. S.?OE-07 

BR82 0. 0. 3.04E-06 0. 0. 0. 0. 

BR83 0. 0. S.74E-08 0. 0. 0. 0. 

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

BR8S 0. 0. 3.0SE-09 0. 0. 0. 0. 

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

KR8SM 0. 0. 0. 0. 0. 0. 0. 

KR8S 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-OS 1.40E-OS 0. 0. 0. 4.41E-06 

RB87 0. 1.7SE-OS 6.11E-06 0. 0. 0. 6.11E-07 

RB88 0. 8.S2E-08 4.S4E-08 0. 0. 0. 7.30E-1S 

RB89 0. S.SOE-08 3.89E-08 0. 0. 0. 8.43E-17 

SR89 4.40E-04 0. · 1.26E-OS 0. 0. 0. S.24E-OS 

SR90 8.30E-03 0. 2.0SE-03 0. 0. 0. 2.33E-04 

SR91 8.0?E-06 0. 3.21E-07 0. 0. 0. 3.66E-OS 

SR92 3.0SE-06 0. 1.30E-07 0. 0. 0. 7.77E-OS 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 10of16 

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 Gl-LLI 

Y90 1.37E-08 0. 3.69E-10 0. 0. 0. 1.13E-04 

Y91M 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09 

Y91 2.01E-07 0. 5.39E-09 0. 0. 0. 8.24E~05 

Y92 1.21 E-09 0. 3.50E-11 0. 0. 0. 3.32E-05 

Y93 3.83E-09 0. 1.05E-10 0. 0. 0. 1.17E-04 

ZR93 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 

ZR95 4.12E-08 1.30E-08 8.94E-09 0. 1.91 E-08 0. 3.00E-05 

ZR97 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.27E-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 6.68E-12 0. 2.14E-11 0. 4.37E-07 

M093 0. 1.06E~05 2.90E-07 0. 3.04E-06 0. 1.29E-06 

M099 0. 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.08E-05 

TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.08E-07 

TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.44E-06 

TC101 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.75E-17 

RU103 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05 

RU105 2.18E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 

RU106 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 

RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31E-07 0. 1.59E-05 

PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 

PD109 0. 2.51E-07 5.706-08 0. 1.45E-06 0. 2.53E-05 

AG110M 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 

AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 

C0113M 0. 4.51E-06 1.45E-07 0. 4.99E-06 0. 2.71E-05 

CD115M 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 5.84E-07 0. 0. 6.71E-05 

SN125 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.12E-04 

SN126 1.16E-04 2.16E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 

SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.386-06 7.80E-05 

SB125 2.48E-06 2.71E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 

SB126 1.59E-06 3.25E-08 5.71E-07 8.99E-09 0. 1.14E~06 9.41E-05 

SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 

TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1.13E-05 

TE127M 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41E-05 

TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 

TE129M 1.63E-05 6.05E-06 2.58E-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 

TE131M 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 

TE131 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 

TE132 3.49E-06 2.21E-06 2.08E-06 2.33E-06 2.12E-05 0. 7.00E-05 

TE133M 6.44E-08 3.66E-08 3.56E-08 5.11 E-08 3.62E-07 0. 1.48E-07 

TE134 4.47E-08 2.87E-08 3.00E-08 3.67E-08 2.74E-07 0. 1.66E-09 

1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01E-06 0. 4.57E-07 

1130 1.036-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 

1131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41 E-05 0. 1.62E-06 
Proc NoODCM 

Attachment 8 

Revision 26 

Page 11of16 

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 Gl-LLI 

1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07 

1133 2.01E-06 3.41 E-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 6.10E-07 0. 5.10E-09 

1135 6.10E-07 1.57E-06 5.82E-07 1.01 E-04 2.48E-06 0. 1.74E-06 

XE131M 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. 

CS134M 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. 1.10E-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 

BA140 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05 

BA141 6.71E-08 5.01E-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 

LA140 3.48E-09 1.71 E-09 4.55E-10 0. 0. 0. 9.82E-05 

LA141 4.55E-10 1.40E-10 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 

CE141 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 1.31 E-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. 1.01E-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 

PM148M 4.14E-08 1.05E-08 8.21E-09 0. 1.59E-08 0. 6.61E-05 

PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05 

PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05 

PM151 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05 

SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 

SM153 1.22E-09 1.01 E-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 

TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05 

H0166M 3.57E-07 1.10E-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 1.91 E-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 26 

Page 12of16 

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 Gl-LLI 

PB210 1.81E-02 5.44E-03 7.01E-04 0. 1.72E-02 0. 5.74E-05 

81210 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 7.11E-03 1.08E-05 1.42E-03 0. 3.10E-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 1.10E-05 1.876-03 0. 3.15E-04 0. 3.27E-04 

RA226 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51E-04 

RA228 1.37E-01 4.41 E-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. 8.81E-05 0. 8.68E-05 

TH227 1,96E-05 3.52E-07 5.65E-07 0. 2.01E-06 0. 5.75E-04 

TH228 6.80E-04 1.14E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 

TH229 8.39E-03 1.26E-04 4.11E-04 0. 6.10E-04 0. 5.43E-04 

TH230 2.16E-03 1.23E-04 6.00E-05 0. 5.99E-04 0. 6.38E-05 

TH232 2.42E-03 1.05E-04 1.63E-04 0. 5.11 E-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. 9.10E-04 0. 7.60E-05 

PA233 7.33E-09 1.41 E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-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 o. 7.09E-05 0. 2.73E-04 0. 6.11 E-05 

U237 7.89E-08 0. 2.10E-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 2.01E-05 0. 8.57E-05 0. 7.06E-05 

PU240 8.26E-04 1.12E-04 2.01E-05 0. 8.56E-05 0. 7.19E-05 

PU241 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1 :48E-06 

PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.256-05 0. 6.92E-05 

PU244 8.95E-04 1.236-04 2.22E-05 0. 9.45E-05 0. 1.03E-04 

AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31E-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. 1.91 E-04 0. 8.28E-05 

CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.00E-05 

CM245 1.07E-03 3.33E-04 6.10E-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 6.00E-05 0. 2.80E-04 0. 9.63E-05 

CM248 8.606-03 2.69E-03 4.95E-04 0. 2.31E-03 0. 1.55E-03 

CR252 3.51E-04 0. 8.37E-06 0. 0. 0. 3.05E-04 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 13of16 

INGESTION DOSE COMMITMENT FACTORS 

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

H3 0. 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 1.0SE-07 

BE10 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. 

CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07 

SC46 5.51E-09 .1.07E-08 3.11 E-09 0. 9.99E-09 0. 5.21E-05 

CR51 0. 0. 2.66E-09 1.59E-09 5.86E-10 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 

FESS 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 2.91E-07 0. 0. 0. 4.44E-06 

C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05 

C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05 

Nl59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07 

Nl63 1.30E-04 9.01E-06 4.36E-06 0. 0. 0. 1.88E-06 

Nl65 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06 

CU64 0. 8.33E-08 3.91E-08 0. 2.10E-07 0. 7.10E-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. o, 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. 6.0SE-08 3.21E-08 0. 0. 0. 8.36E-19 

RB89 0. 4.01E-08 2.82E-08 0. 0. 0. 2.33E-21 

SR89 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05 

SR90 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 26 

Page 14of16 

INGESTION DOSE COMMITMENT FACTORS 

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 

Y91M 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-10 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-10 0. 5.12E-10 0. 1.05E-04 

N893M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 

N895 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.10E-05 

N897 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. 4.31E-06 8.20E-07 0. 9.766-06 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 

TC101 2.54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 1.10E-21 

RU103 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05 

RU105 1.54E-08 0. 6.08E-09 0. 1 ."99E-07 0. 9.42E-06 

RU106 2.75E-06 0. . 3.48E-07 0. 5.31E-06 0 . 1.78E-04 

RH105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 

PD107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11E-07 

PD109 0. 1.77E-07 3.99E-08 0. 1.01 E-06 0. 1.96E-05 

AG110M 1.60E-07 1.48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05 

AG111 5.81E-08 2.43E-08 1.21 E-08 0. 7.84E-08 0. 4.46E-05 

CD113M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 

CD115M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E~05 

8N123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 

8N125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 

8N126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 

88124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E-05 

88125 1.79E-06 2.00E-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 

88126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 

88127 2.58E-07 5.65E-09 9.90E-08 3.10E-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 1.10E-07 3.95E-08 2.38E-08 8.156-08 4.48E-07 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 

TE131M 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 2.676-07 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 2.81E-06 9.21E-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 26 

Page 15of16 

INGESTION DOSE COMMITMENT FACTORS 

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-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-10 

1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31 E-06 

XE131M 0. 0. 0. 0. 0. 0. 0. 

XE133M o. 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. 

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 2.11 E-06 

CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01E-08 7.91E-09 4.65E-13 

CS139 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.10E-30 

BA139 9.70E-08 6.91 E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07 

BA140 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05 

BA141 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 3.00E-26 

LA140 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 

CE141 9.36E-09 6.33E-09 7.18E-10 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. 1.21 E-07 0. 1.65E-04 

PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05 

PR144 3.01E-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.QSE-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 

PM151 6.97E-10 1.17E-10 5.91 E-11 0. 2.09E-10 0. 3.22E-05 

SM151 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 

TB160 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 3.01E-08 0. 0. 0. 2.82E-05 
Proc No ODCM 

Attachment 8 

Revision 26 

Page 16of16 

INGESTION DOSE COMMITMENT FACTORS 

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR) 

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI 

PB210 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05 

81210 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 1.61 E-03 3.90E-06 3.23E-04 0. 1.10E-04 0. 3.40E-04 

RA225 6.56E-03 7.78E-06 1.31 E-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 1.11E-04 0. 8.00E-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 1.00E-04 1.50E-04 0. 4.82E-04 0. 5.12E-05 

TH234 8.01E-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04 

PA231 4.10E-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 8.71E-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 8.01E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05 

U236 8.01E-04 0. 4.96E-05 0. 1.91 E-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. 8.11E-05 0. 6.66E-05 

PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.10E-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 2.11E-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 2.10E-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 1.01 E-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 
PALISADES 10 YEAR X/Q- DIQ DATA 

USNRC COHPUTER CODE - .XOQDOQ, ·v'ERS ION 2 • 0 RUN DATE: 28FEB14 

***•:·~ PALISADES XOQDOQ82 **H* USING 01/01/2004 - l2/-31/20"13 HE.T' DATA *·~*** 

GROUND LEVEL RELEAS.E - TO? OF :coN'.rAINl~NT BUILDING 

iSP15Cil!'lC POJ:NT.S OF J:'NTI!:RE.3:" 

REL.El1SE TYPE OF QIREC.TION DISTl\NCE XIQ X/.Q 

ID LOCATION F~OH SI'rE (MILES) (METERS) \ SEC°Jccs. ~lETER} (SE•::!/CUB.METER) 

NO DECAY, 2.260 DAY DECAY. 

UNDEPLETED UfTDEPLETED 

A SITE BOUNDARY NNE 0 .50 805. l.58E-{)6 I. 5_7E-0:6 

A. SITE 'BOUNDARY NE 0. 65 1046. 1.23E-06 1.23E-06 

A SITE BOUNDARY EN.f; 0.87 140.0. 5. 88E-07 5.86E:-07 

A SITE BOUNDARY E 0.82 1320. 6_.99E-07 6.96E-07 

'A SITE BOUNDARY ESE 0.76 1223. 8.34E-07 8 •. 3.lE-07 

A ~ITE ~qUNDARY ·SE 0.63 1014 .• l. 39:£0:.06 l •. 3.BE-06 

A .SITE :soUNDARY S;5E 0-.<18 772. 2, 28E-OG '2', 28E.-.o·6 

A SITE BOUNDARY ·s. 0 •. 42 676. 1. 96E-0 .. 6 1. 95E'...06 

A SITE BOUNDARY SSW 0.48 772. 1. 26E-06 1. 25E,-06 

A RE.SI DENCE NNE 1.68 ;;:704. 2. 59E-07 2.57E-07 

.A RE.SI DENCE NE l. l•l 1835. 5, 32E-0.7 5.30E-07 

A RESIDENCE ENE 1 .. I.Si 1915. 3.70E-07 3.67E-07 

A RESIDENCE E 1.67 2688. 2. 43E-0.7 2.4fa..,.07 

f.. REp!DENCE J;;SE 0.99 1593. 5 .60E-07 5-.58E-07 

. A ·RESIDE!~CE SE 0.90 1448 • a .'ozE-67 7 •. 98E-07 

A ·RESIDENCE SSE 0;80 1287. 1.0SE-06 1.04E-06 

A JIBSIDENCE s p.77 1239. i. 87E.-Cr7 7. S<lE-07 

A 'RESIQENCE SSW 0.49 7.89 - l.22E-06 l.21E-06 

A .GARDEN NNE 1. 75 :2816. 2 .45E-0.7 2.43E-07 

A QJ;RDEN ·NE 1 .• 67 2688. 3.03E-07 3.0lE-o'7 

A GARDEN ENE 2.62 4216. l.16E-07 l.HE-07 

A ·GARDEN E :2.68 4313 •. l .21E-07 1. 20E-07 

A GARDEN ·ESE 1. 83 2945. 2. 24E-07 2.22E-07 

A Gl\RDEN SE 1.49 2398. 3. 7.7E-07 .3. 75E.-07 

A GARDEN SSE 0.69 11'10. l.JlE-06 L31E-06 

A ,GARPEN SSW ·4 :a2 7757. 4. 54E-08 •l .43E-08 

A GOAT ENE 2.62 4216. l .16E-07 1. 14E-07 

A GOAT E 4.25 6840. 6 .• 17E-08 6'. 05E-0.8 

A l3EE,F .CATTLE SE 4.27 6872. 8.0lE-08 7.85E-OB 

X/Q 

(SEC/CUB.METER) 

8.000 DAY DECAY 

DEPLETED 

l -44J>-06 

l.llE-06 

5 .• 19E-07 

6;19E-07 

7 .• 42E-07 

1.25E-06 

2. 09E-0.6 

L 89.E-06 

l;15E-06 

2. HE-07 

t,.61E-0-7 

3.19E-07 

2 .ME-07 

~.!)OE-07 

7. 06E-07 

9.28E-07 

6.99E-07 

l .llE-06 

2 .. 0SE-07 

2.54E_.:07 

9.·. 29E'-08 

9.7QE-08 

1.86E-07 

3 .. 20E-0.7 

LI 7E-06 

3, 2'8E-08 

'9.29E-08 

t,.67E-08 

6:. Q6E,...08 

D/Q 

Proc No ODCM 

Attachment 9 

Revision 26 

Page 1of1 

(PER SQ.ME.TER) 

7. 61E,...09 

8.80E-09 

4 .• 27E-09 

5·. 29E-09 

.6 .• ·93E-09 

L-25E-0,8. 

':2 .• O}E-.08 

1. llE-(i8 

6.25E-09 

9 •. 83E-10 

·3. 39E-0.9 

'2 .. 50E-0.9 

; 1. 56E;..09 

4. 43E.:. . .'a9. 

6.86E-09 

·8.64E-09 

:4 .12E-09 

6.04E-09 

9.16E-10 

1. 76E-09 

6.34E-10 

6.83E-10 

1.54E-0.9 

·i.a9E-<i9 

l. llE-,08 

1.17E"'l0 

6.34E-10 

3 .• 0lE...,10 

4.~3E'.'..lO 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

ODCM 

Appendix A 

Revision 18 

Issued Date 11/17/14 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

I Process Applicability Exclusion D 

CLJones I 11/13/14 

Procedure Sponsor Date 

CLJones I 9/17/14 

Technical Reviewer Date 

AL Williams I 11/11/14 

General Manager Plant Operations Date 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table of Contents 

ODCM 

Appendix A 

Revision 18 

Page i 

I. INTRODUCTION ............................................................................................................ 1 

II. DEFINITIONS ................................................................................................................. 1 

A. CHANNEL CALIBRATION ............................................................................ 1 

B. CHANNEL CHECK ........................................................................................ 1 

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 

Ill. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table of Contents 

ODCM 

Appendix A 

Revision 18 

Page ii 

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 

I. TOTAL DOSE ..............................•............................................................... 32 

1. Requirement .......................................................................... 32 

2. Action ..................................................................................... 32 

3. Surveillance Requirements .................................•................ 33 

4. Bases ..................................................................................... 34 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table of Contents 

ODCM 

Appendix A 

Revision 18 

Page iii 

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 ................................... 52 

1. Requirement ................................................................ , ....... ,. 52 

2. Action ..................................................................................... 52 

3. Surveillance Requirement .................................................... 52 

4. Bases ................................................................•.................... 53 

L. SURVEILLANCE REQUIREMENT TIME INTERVALS ............................... 53 

1. Requirement .......................................................................... 53 

2. Action ............................................................ · ......................... 53 

3. Surveillance Requirements .................................................. 54 

4. Bases ..................................................................................... 54 

M. SEALED SOURCE CONTAMINATION ....... ; ............................................... 54 

1. Requirement .......................................................................... 54 

2. Action ..................................................................................... 54 

3. Surveillance Requirements .................................................. 55 

4. Bases ..................................................................................... 55 

IV. REPORTING REQUIREMENTS .................................................................................. 56 

A. RADIOLOGICAL EFFLUENT RELEASE REPORT .................................... 56 

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT ................... 57 

C. NONROUTINE REPORTS ........................................................................... 57 

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE 

TREATMENT SYSTEMS ............................................................................................. 59 

A. LICENSEE MODIFICATIONS ...................................................................... 59 

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION ............. 60 

VI. ONSITE GROUND WATER MONITORING ................................................................. 61 
TABLES 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table of Contents 

A-1 Radioactive Gaseous Effluent Monitoring Instrumentation 

A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance 

Requirements 

8-1 Radioactive Gaseous Waste Sampling and Analysis Program 

C-1 Radioactive Liquid Effluent Monitoring Instrumentation 

ODCM 

Appendix A 

Revision 18 

Page iv 

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 

E-4 Radiological Environmental Monitoring Program Locations 

F-1 Environmental Radiological Monitoring Program Summary 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

I. INTRODUCTION 

ODCM 

Appendix A 

Revision 18 

Page 1of61 

The NRC, through 1 OCFR50.36a, 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 

procectural reporting requirements follow below. Programmatic controls are retained 

in the Administrative Controls section of the Technical Specification to satisfy the 

regulatory requirements of 1 OCFR50.36a. 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. 

II. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

C. CHANNEL FUNCTIONAL TEST 

- a Channel Functional Test shall be: 

ODCM 

Appendix A 

Revision 18 

Page 2 of 61 

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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

H. PROCESS CONTROL PROGRAM (PCP) 

ODCM 

Appendix A 

Revision 18 

Page 3 of 61 

- 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 1 OCFR Part 20, 1 OCFR Part 71 and Federal and State 

regulations and other requirements governing the disposal of the radioactive 

waste. 

I. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 4 of 61 

Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 

1. Requirement 

The radioactive gaseous effluent monitoring instrumentation channels 

shown in Table A-1 shall be operable with their alarm/trip setpoints set 

to ensure that the limits of requirement 111.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-1. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 5 of 61 

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 1 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 1 OCFR Part 50. 
1. 

2. 

3. 

4. 

5. 

6. 

* 

** 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

ODCM 

Appendix A 

Revision 18 

Page 6 of 61 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

TableA-1 

Radioactive Gaseous Effluent Monitoring Instrumentation 

Minimum 

Instrument Operable Applicability 

Channels 

WASTE GAS HOLDUP SYSTEM 

a. Noble Gas Activity Monitor (RIA 1113) Providing 

Alarm and Automatic Termination of Release (1) At All Times 

CONDENSER EVACUATION SYSTEM (RIA 0631) 

a. Noble Gas Activity Monitor (1) Above 210°F 

Modes 1, 2, 3, 4 

Above 210°F 

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

STACK GAS EFFLUENT SYSTEM 

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

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

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

d. Hi Range Noble Gas (RIA 2327)* (1) Above 210°F 

Modes 1, 2, 3, 4 

STEAM GENERA TOR SLOWDOWN VENT SYSTEM 

a. ·Noble Gas Activity Monitor (RIA 2320) (1) Above 210°F 

Modes 1, 2, 3, 4 

MAIN STEAM SAFETY AND DUMP VALVE 

DISCHARGE LINE 

a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 

(RIA 2323 and 2324) Steam Line Modes 1, 2, 3 

ENGINEERED SAFEGUARDS PUMP ROOM 

VENTILATION HIGH RADIATION SYSTEM 

a. Noble Gas Activity Monitor ** 1 per Room Above 210°F 

(RIA 1810 and 1811) Modes 1, 2, 3, 4 

Setpomts for these instruments are exempted from 111.B.1 limits, but are governed by 

Emergency Implementing Procedures or Operating procedures. 

Setpoints for these instruments are exempted from 111.B.1 limits, but are governed by 

Technical Specifications SR 3.3.1 Q.3. 

Action 

1 

3 

3 

6 

2 

4 

3 

4 

5 

*** Documentation of operability not required. 
ACTION 1 -

ACTION 2 -

ACTION 3 -

ACTION4 -

ACTION 5 -

ACTION 6 -

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table A-1 (Cont'd) 

TABLE NOTATION -ACTION STATEMENTS 

ODCM 

Appendix A 

Revision 18 

Page 7 of 61 

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 tank's 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. 

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 hours. 

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 hours and these samples are analyzed for gross activity within 

24 hours. 

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 hours, 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. 

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.) 

With the number of channels operable less than required by the Minimum Operable Channels 

requirement, effluent releases via the affected pathway may continue provided samples are 

continuously collected with auxiliary sampling equipment as required in Table B-1. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table A-2 

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 

Channel Instrument Check 

1. WASTE GAS HOLDUP SYSTEM 

a. Noble Gas Activity Monitor-Providing Alarm and 0(4) Automatic Termination of Release · 

2. CONDENSER EVACUATION SYSTEM 

a. Noble Gas Activity Monitor D 

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

c. Evacuation Flow Indicator (Fl-0631) *** 

3. STACK GAS EFFLUENT SYSTEM 

a. Noble Gas Activity Monitor D 

b. Iodine Particulate Sampler/Monitor w 

C. Sampler Flow Rate Monitor D 

d. Hi Range Noble Gas D 

4. STEAM GENERATOR SLOWDOWN VENT SYSTEM 

a. Noble Gas Activity Monitor D 

5. MAIN STEAM SAFETY AND DUMP VALVE 

DISCHARGE LINE 

D 

a. Gross Gamma Activitv Monitor 

6. ENGINEERED SAFEGUARDS PUMP ROOM 

VENTILATION HIGH RADIATION. SYSTEM 

a. Noble Gas Activity Monitor 12 hours 

(Technical Specifications SR 3.3.1 O and 

SR 3.7.13.1) 

* At all times other than when the hne 1s valved out and locked. 

** Sampler not applicable 

*** This type of Flowmeter doesn't have any surveillance requirements. 

Source Channel Channel 

Functional Check Calibration Test 

p R(3) Q(1 )(2) 

M R(3) Q(2) 

*** *** *** 

*** *** *** 

M R(3) Q(2) 

M** R(3)** NA 

NA R NA 

M R(3) Q(2) 

M R(3) Q(2) 

M R(3) Q(2) 

31 days 18 months (3) 31 days(1)(2) 

ODCM 

Appendix A 

Revision 18 

Page 8 of61 

Modes in Which 

Surveillance 

Required 

* 

Above 210°F 

Modes 1, 2, 3, 4 

* 

* 

* 

Above 210°F 

Modes 1, 2, 3, 4 

Above 210°F 

Modes 1, 2, 3, 4 

Above 325°F 

Modes 1, 2, 3 

Above 210°F 

Modes 1, 2, 3, 4 
Table A-2 (Cont'd) 

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Table Notation 

ODCM 

Appendix A 

Revision 18 

Page 9 of 61 

(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 hours on days on which continuous or batch releases are made. 

TABLE FREQUENCY NOTATION 

S At least once per 12 hours 

D At least once per 24 hours 

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 
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8. GASEOUS EFFLUENTS DOSE RA TE 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 10 of 61 

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 lodine-131, for lodine-133, 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 8.1.a in accordance with 

the methodology and parameters in the ODCM. 

b. The dose rate due to lodine-131, lodine-133, 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 8.1.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 8-1. 
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4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 11 of 61 

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 1 OCFR Part 20 to Unrestricted 

Areas. The annual dose limits are the doses associated with the 

concentrations of 10 times 1 OCFR 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 1 OCFR 50, Appendix I, Section 11.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 

(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). 
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C. NOBLE GASES DOSE 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 12 of 61 

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 

NRG 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. 
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4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 13 of 61 

This requirement is provided to implement the requirements of 

Sections 11.B, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The 

limiting Condition for Operation implements the guides set forth in 

Section 11.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 Ill.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 1 OCFR 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. 
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D. 1-131, 1-133, TRITIUM, AND PARTICULATES 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 14 of 61 

The dose to a Member of the Public from lodine-131, lodine-133, 

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, lodine-133, 

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 lodine-131, lodine-133, 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. 
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4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 15 of 61 

This requirement is provided to implement the requirements of 

Sections 11.C, Ill.A, and IV.A of Appendix I, 10CFR Part 50. The 

requirements are the guides set forth in Section 11.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 II.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 1 OCFR 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. 
Gaseous Release Type 

A. Waste Gas Storage Tank 

B. Containment PURGE 

C. Stack Gas Effluent 

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Table B-1 

Radioactive Gaseous Waste Sampling and Analysis Program 

Sampling Minimum Type of 

Frequency Analysis Activity Analysis 

Frequency 

p 

Each Tank p 

Grab Sample Each Tank Principal Gamma Emittersb 

p 

Each PURGE p 

Grab Sample Each PURGE Principal Gamma Emittersb 

\,J\f•e 

Continuousc Charcoal 1-131,1-133 

Sample 

\,/\f•e 

Continuousc Particulate Principal Gamma Emittersb 

Sample 

Q 

Continuousc Composite Sr-89, Sr-90, and 

Particulate Gross Alpha 

Sample 

Noble Gas Noble Gases 

Continuousc Monitor Gross Beta or Gamma 

ODCM 

Appendix A 

Revision 18 

Page 16 of 61 

Lower Limit 

Detection (LLD)a 

(μCi/ml) 

1 x 104 

1 x 104 

1 x 10·12 

1x10·11 

1 x 10"11 

1E-06 
Gaseous Release Type 

D. Condenser Evacuation 

System 

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Sampling Minimum Type of 

Frequency Analysis Activity Analysis 

Frequency 

Continuous Noble Gas Noble Gases 

Monitor 

wt 

Principal Gamma Emittersb Grab w 

ODCM 

Appendix A 

Revision 18 

Page 17 of 61 

Lower Limit 

Detection (LLD)a 

(μCi/ml) 

1 x 1 o-6 

1 x 104 
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Appendix A 

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table 8-1 (Cont'd) 

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-135, and Xe-138 for 

gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, 

Cs-137, Ce-141, and Ce-144 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. 

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 111.B.1, 111.C.1, and 111.D.1. 

d Samples shall be changed at least once per 7 days and analyses shall be completed 

within 48 hours after changing or after removal from sampler. 

e With channels operable on iodine monitor RIA 2325 less than required per 111.A.1, 

sampling shall also be performed at least once per 24 hours 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 hours of changing. When samples collected for 24 hours 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. 

f Obtain and analyze a gas sample weekly for noble gas quantification. 
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Appendix A 

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Page 19 of 61 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

E. GASEOUS WASTE TREATMENT SYSTEM 

1. Requirement 

When gaseous waste exceeds a Xe-133 concentration of 

1 E-05 μCi/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 

dose consequence 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 111.B, C, and D. 

3. Surveillance Requirements 

Not Applicable. 
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Appendix A 

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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 11.D of Appendix I to 10CFR50. 

It is expected that releases of radioactive materials in effluents shall be 

kept at small fractions of the limits specified in 20.1302 of 1 OCFR20. 

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 111.B, C, 

and D. 

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 

1. Requirement 

The radioactive liquid effluent monitoring instrumentation channels 

shown in Table C-1 shall be operable with their alarm/trip setpoints 

set to ensure that the limits of 111.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). 
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Appendix A 

Revision 18 

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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-1. 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 1 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 1 OCFR Part 50. 
1. 

2. 

3. 

4. 

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Appendix A 

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table C-1 

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 Slowdown Effluent Line (1) For Effluent Releases 2 

(RIA 0707) 

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) 

FLOW RATE MEASUREMENT DEVICES 

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

1050) 

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 Slowdown Effluent (1) For Effluent Releases 3 
ACTION 1 -

ACTION 2-

NOTE: 

ACTION 3-

ACTION 4-

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Appendix A 

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table C-1 (Cont'd) 

TABLE NOTATION 

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. 

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 hours. 

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. 

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 hours, 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. 

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 hours during 

actual releases. Pump performance curves or tank levels may be used to 

estimate flow. 
1. 

2. 

3. 

4. 

5. 

6. 

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Table C-2 

ODCM 

Appendix A 

Revision 18 

Page 24 of 61 

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 

Channel Source Channel Channel 

Instrument Functional Check Check Calibration Test 

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 Slowdown Effluent Line (RIA 0707) D M R(3) Q(1)(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) 

FLOW RA TE MEASUREMENT DEVICES (5) 

a. Liquid Radwaste Effluent Line (FIC 1051 or 1050) 0(4) NA R NA 

TURBINE SUMP EFFLUENT COMPOSITER 0(4) NA NA NA 

SERVICE WATER SYSTEM EFFLUENT COMPOSITE SAMPLER 0(4) NA NA NA 

STEAM GENERA TOR SLOWDOWN EFFLUENT COMPOSITER 0(4) NA NA NA 
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Table C-2 (Cont'd) 

TABLE NOTATION 

ODCM 

Appendix A 

Revision 18 

Page 25 of61 

(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 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 (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 hours on days on which continuous or batch releases are made. 

(5) Turbine Sump Discharge Flow Meter FQl-5210 was calibrated at factory and doesn't require recalibration. 

D 

M 

p 

TABLE FREQUENCY NOTATION 

At least once per 24 hours 

At least once per 31 days 

Prior to radioactive batch release 

Q 

R 

w 

At least once per 92 days 

At least once per 18 months 

At least once per week 
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G. LIQUID EFFLUENTS CONCENTRATION 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 26 of 61 

The concentration of radioactive material released in liquid effluents to 

Unrestricted Areas shall be limited to 10 times the concentrations 

specified in 1 OCFR Part 20, Appendix 8, 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 10-4 microcuries/ml 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. 
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OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

4. Bases 

ODOM 

Appendix A 

Revision 18 

Page 27 of 61 

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 

1 OCFR 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 II.A design objectives of Appendix I, 10CFR Part 50, to a 

Member of the Public. The concentration limit for dissolved or 

entrained noble gases is based upon the assumption that Xe-135 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). 
A. 

B. 

Liquid Release Type 

Batch Waste Release Tanksu 

Continuous Releasese 

(Turbine Sump, Steam Generator 

Slowdown, and Service Water) 

Frequency Notation 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table D-1 

Radioactive Liquid Waste Sampling and Analysis Program 

Sampling Minimum Analysis Type of Activity Analysis 

Frequency Frequency 

p p Principal Gamma Emittersc 

Each Batch Each Batch 1-131 

p M Dissolved and Entrained Gases 

One Batch/M (Gamma Emitters) 

p M H-3 

Each Batch Composited Gross Alpha 

p Q Sr-89, Sr-90 

Each Batch Composited Fe-55, Ni-63 

Continuous' w Principal Gamma Emittersc 

Composite1 1-131 

M M Dissolved and Entrained Gases 

Grab Sample (Gamma Emitters) 

Continuous' M H-3 

Composite1 Gross Alpha 

Continuous' Q Sr-89, Sr-90 

Composite1 

P Prior to batch release 

M Calendar month 

Q Calendar quarter 

W Calendar week 

ODCM 

Appendix A 

Revision 18 

Page 28 of 61 

Lower Limit 

Detection (LLD)a 

(μCi/ml) 

5x10"7 

1 x 10"6 

1x10"5 

1 x 10-5 

1x10"7 

5 x 10"8 

1x10"6 

5x10"7 

1x10"6 

1 x 10"5 

1 x 10"5 

1x10·7 

5 x 10"8 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table D-1 (Cont'd) 

TABLE NOTATION 

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

ODCM 

Appendix A 

Revision 18 

Page 29 of 61 

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, Mo-99, Cs-134, 

Cs-137, Ce-141, and Ce-144*. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

H. LIQUID EFFLUENT DOSE 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 30 of 61 

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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 31of61 

This requirement is provided to implement the requirements of 

Sections II.A, Ill.A, and IV.A of Appendix I, 1 OCFR Part 50. The 

Limiting Condition for Operation implements the guides set forth in 

Section II.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 40CFR 

Part 141. The dose calculation methodology and parameters in the 

ODCM implement the requirements in Section Ill.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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

I. TOTAL DOSE 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 32 of 61 

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 111.C.1.a, 

111.C.1.b, 111.D.1.a, 111.D.1.b, 111.H.1.a, or 111.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 1 OCFR 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 

40CFR Part 190 has not already been corrected, the Special Report 

shall include a request for a variance in accordance with the provisions 

of 40CFR 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 750~0) 

3. Surveillance Requirements 

ODCM 

Appendix A 

Revision 18 

Page 33 of 61 

a. Cumulative dose contributions from liquid and gaseous effluents 

shall be determined in accordance with 111.C.1, 111.D.1, and 

111.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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 34 of 61 

This requirement is provided to meet the dose limitations of 

40CFR Part 190 that have been incorporated into 1 OCFR 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 40CFR 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 40CFR 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 40CFR Part 190, the Special 

Report with a request for a variance (provided the release conditions 

resulting in violation of 40CFR Part 190 have not already been 

corrected), in accordance with the provisions of 40CFR Part 190.11 

and 1 OCFR Part 20.2203, is considered to be a timely request and 

fulfills the requirements of 40CFR Part 190 until NRC staff action is 

completed. The variance only relates to the limits of 40CFR Part 190 

and does not apply in any way to the other requirements for dose 

limitation of 1 OCFR 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

J. RADIOLOGICAL ENVIRONMENTAL MONITORING 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 35 of 61 

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 NRG, 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 NRG 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 111.C.1, 

111.D.1, and 111.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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 36 of 61 

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 m2 (500 tt2) 

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 lnterlaboratory Comparison Program that has been 

approved by the NRC. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

ODCM 

Appendix A 

Revision 18 

Page 37 of 61 

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 

lnterlaboratory 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 IV.B.2 

of Appendix I to 1 OCFR 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 

OFFSITE DOSE CA LC ULA TION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

b. Land Use Census: 

ODCM 

Appendix A 

Revision 18 

Page 38 of 61 

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 I to 1 OCFR Part 50. Restricting the 

census to gardens of greater than 50 m2 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 kg/m2

. 

c. lnterlaboratory Comparison Program: 

The requirement for participation in an approved lnterlaboratory 

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 10CFR Part 50. 
Exposure Pathway 

and/or Sample 

1. DIRECT RADIATIONb 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-1 

Radiological Environmental Monitoring Program 

Number of Representative Sampling and 

Samples and Sample Locations3 Collection Frequency 

23 routine monitoring stations either with two or Quarterly 

more dosimeters or with one instrument for 

measuring and recording dose rate continuously, 

placed as follows: 

One on site TLD in the vicinity of the Plant. 

An inner ring of stations, one in each overland 

meteorological sector (9) in the general area of 

the Site Boundary and one additional location 

near the State Park camping area in the NE 

sector. 

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. 

ODCM 

Appendix A 

Revision 18 

Page 39 of 61 

Type and Frequency 

of Analysis 

Gamma dose quarterly 
Exposure Pathway 

and/or Sample 

2. AIRBORNE 

Radioiodine and 

Particulates 

3. WATERBORNE 

a. Lake (surface) 

b. Lake (drinking) 

'-

c. Well (drinking) 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Number of Representative Sampling and 

Samples and Sample Locationsa Collection Frequency 

Samples from 5 locations. Continuous sample 

operation with sample 

3 samples from within 6 km of the Site Boundary collection weekly or more 

in different sectors (2.5 km-SSW, 5.8 km-ESE frequently if required by 

and .96 km-NE). dust loading. 

1 sample from the vicinity of a community having 

the highest calculated annual average ground 

level D/Q (Covert-6.2 km-SE). 

1 sample from a control location in the least 

prevalent wind directionc (Grand Rapids 

82 km-NE)h. 

Plant lake water inlet. Composite sample over 

1-month periodt. 

1 sample of South Haven drinking water supply. Composite sample over 

1-month periodt. 

1 sample from a control location (Ludington Composite sample over 

Pumped Storage 201 km N) 1-month periodt. 

1 grab sample per month when Palisades Park 1 grab sample per month 

community drinking water well is in operation when operational 

(Park is seasonal in operations and is only open 

for the summer months) 

ODCM 

Appendix A 

Revision 18 

Page 40 of 61 

Type and Frequency 

of Analysis 

Radioiodine Canister: 

1-131 analysis weekly for 

each filter change. 

Particulate Sam12ler: 

Gross beta radioactivity 

analysis following filter 

changed. Gamma isotopice 

analysis on quarterly 

composite 

Gamma isotopice and tritium 

analyses monthly. 

Gamma isotopice, gross 

beta, and tritium analyses 

monthly. 

Gamma isotopice, gross 

beta, and tritium analyses 

monthly. 

Gamma isotopice and tritium 

analyses monthly when 

Park is operational. 
Exposure Pathway 

and/or Sample 

d. Sediment from 

shoreline 

4. INGESTION 

a. Milk 

b. Broad leaf 

vegetation 

c. Fish 

d. Food Products 

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OFFSITE DOSE CALCULATION MANUAL 

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NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Number of Representative Sampling and 

Samples and Sample Locationsa Collection Frequency 

1 sample from between north boundary and Van Semiannually 

Buren State Park beach, approximately Yz mile 

north of the Plant discharge. 

Samples from milking animals in 3 locations Monthly 

between 5-8 km distance. 

1 sample from milking animals at a control location, Monthly 

15-30 km distance. 

Samples of 3 different kinds of broad leaf vegetation Monthly during growing 

grown nearest each of two different offsite locations season 

of highest predicted annual average ground level 

D/Q if milk sample is not performed. (SE or SSE 

sectors near site.) 

1 sample of each of the similar broad leaf vegetation Monthly during growing 

grown 15-30 km distance in the least prevalent wind season 

direction if milk sampling is not performed. (NNE or 

NE sectors.) 

Sample 2 species of commercially and/or Sample in season or 

recreationally important species in vicinity of Plant semiannually if they are 

discharge area. 1 sample of same species in areas not seasonal. 

not influenced by Plant discharge. 

1 sample each of two principal fruit crops At time of harvest9 

(blueberries and apples). 

ODCM 

Appendix A 

Revision 18 

Page 41 of61 

Type and Frequency 

of Analysis 

Gamma isotopice analysis 

semiannually. 

Gamma isotopic0 and 1-131 

analyses monthly. 

Gamma isotopic0 and 1-131 

analyses monthly. 

Gamma isotopic0 and 1-131 

analyses 

Gamma isotopic0 and 1-131 

analyses 

Gamma isotopic0 analysis 

Gamma isotopic0 and 1-131 

analyses. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

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NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-1 (Cont'd) 

Table Notation 

ODCM 

Appendix A 

Revision 18 

Page42 of 61 

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 instruments, 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 hours 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. 

f 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. 

h The Control Air sample results from Cook Nuclear Plant, except Coloma, may be used as a backup of the Grand Rapids control. 
* 

Analysis 

H-3 

Mn-54 

Fe-59 

Co-58 

Co-60 

Zn-65 

Zr-Nb-95 

1-131 

Cs-134 

Cs-137 

Ba-La-140 

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OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 {TAC NO 75060) 

Table E-2 

ODCM 

Appendix A 

Revision 18 

Page 43 of 61 

Reporting Levels for Radioactivity Concentrations in Environmental Samples 

Reporting Levels 

Water Airborne Particulates Fish Milk Food Products 

(pCi/I) or Gases (pCi/m3

) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) 

20,000* 

1,000 30,000 

400 10,000 

1,000 30,000 

300 10,000 

300 20,000 

400 

2 0.9 3 100 

30 10 1,000 60 1,000 

50 20 2,000 70 2,000 

200 300 

For drinking water samples. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may 

be used. 
* 

Analysis Water 

(pCi/I) 

Gross Beta 4 

H-3 2,000* 

Mn-54 15 

Fe-59 30 

Co-58 15 

Co-60 15 

Zn-65 30 

Zr-95 30 

Nb-95 15 

1-131 1d 

Cs-134 15 

Cs-137 18 

Ba-140 60 

La-140 15 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

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NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-3 

Detection Capabilities for Environmental Sample Analysisa 

Lower Limit of Detection (LLD)bc 

Airborne Particulates Fish Milk Food Products 

or Gases (pCi/m3

) (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) 

0.01 

130 

260 

130 

130 

260 

0.07 1 60 

0.05 130 15 60 

0.06 150 18 80 

60 

15 

If no drinking water pathway exists, a value of 3,000 pCi/I may be used. 

ODCM 

Appendix A 

Revision 18 

Page 44 of61 

Sediment 

(pCi/kg, Dry) 

150 

180 
a 

b 

c 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-3 (Cont'd) 

TABLE NOTATION 

ODCM 

Appendix A 

Revision 18 

Page 45 of 61 

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. 

Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13. 

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 x Sb 

Ex V x 2.22 x Y x Exp(-A-M) 

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. 

LH 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 Lit should be used in the calculation. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-3 (Cont'd) 

Table Notation 

ODCM 

Appendix A 

Revision 18 

Page 46 of 61 

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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table E-4 

ODCM 

Appendix A 

Revision 18 

Page 47 of 61 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS 

Seven Mile Map 

• .. ' ·{~_ 'J. •··. ' ~ 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 48 of 61 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS 

Four Mile Map 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 49 of 61 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS 

TLDs 

Location Coordinates Distance (miles) DeQrees Sector 

Stack N 42 19 22.5 

w 86 18 50.8 

1 N 42 19 20.5 0.213 100.36 E 

w 86 18 36.1 

Inner Ring 

13 N 42 19 47.2 0.530 26.56 NNE 

w 86 18 34.1 

8 N 42 19 46.8 0.602 39.19 NE 

w 861824.0 

14 N 42 19 41.1 0.551 49.64 NE 

w 8618 21.2 

15 N 42 19 41.7 0.834 63.76 ENE 

w 86 17 58.1 

16 N 42 19 28.0 0.804 82.45 E 

w 86 17 54.6 

17 N 42 19 10.5 0.572 113.74 ESE 

w 86 18 13.9 

18 N 42 19 4.2 0.469 138.49 SE 

w 86 18 28.9 

19 N42190.9 0.443 159.19 SSE 

w 86 18 39.7 

20 N 42 19 1.1 0.412 176.05 s 

w 86 18 48.8 

21 N42193.4 0.382 196.40 SSW 

w 86 18 58.4 

Outer Ring - Displayed on 7 mile map 

7 N 42 22 40.8 4.115 22.35 NNE 

w 86 17 0.4 

6 N 42 22 30.6 5.314 47.18 NE 

w 86 14 15.9 

23 N 42 20 44.6 3.189 60.37 ENE 

w 8615 35.4 

24 N 42 19 59.5 6.021 83.19 E 

w 86 11 49.4 

5 N 42 18 27.6 3.475 107.63 ESE 

w 8614 57.5 

4 N 42 17 10.8 3.668 133.54 SE 

w 86 15 43.5 

3 N 42 14 37.9 5.684 163.92 SSE 

w 86 16 60.0 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

ODCM 

Appendix A 

Revision 18 

Page 50 of 61 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS 

TLDs 

Location Coordinates Distance (miles) Degrees Sector 

2 N 42 14 33.4 S.560 183.7S s 

W861916.4 

9 N 4218 1.73 1.670 201.86 SSW 

W8619 34.6 

Control TLDs 

10 N 42 53 16.7 S0.746 39.49 NE 

was 40 3S.9 

11 N 42 1S 24.S 39.472 96.39 E 

was 32 49.3 

12 N 41 S6 54.3 27.971 1S7.61 SSE 

W86 6 24.S 

TLD 10 is located within the Consumers Energy Grand Rapids service facility attached to a 

pole located adjacent to the south fence. 

TLD 11 is located within Consumers Energy Kalamazoo service facility attached to a pole in 

the far NE corner of the facility, past the employee parking lot. 

TLD 12 is located approximately 30 yards from the road, NE and next to a private residence 

located at S8399 Wilbur Road, Dowagiac, Ml. ' 

A" Ir S ample I St a1ons f 

Location Coordinates Distance (miles) Degrees Sector 

AB (State Park) N 42 19 46.8 O.S95 38.34 NE 

w 86 18 24.8 

A9 (Township N42184.6 1.S2S 191.38 SSW 

Park) w 86 19 12.0 

A4 (Covert) N421712.1 3.882 130.12 SE 

w 861S 21.7 

AS (Rood) N 42 18 30.5 3.590 106.12 ESE 

W861447.8 

A10 (Grand N 42 S3 16.7 S0.765 39.S2 NE 

Rapids) was 40 33.8 

Air Sample Station 10 is located within Consumers Energy Grand Rapids service facility, 

south side, next to a small service building and due east of TLD 10. 

Control fish and water samples are normally obtained from the Consumers Energy Pump 

Storage Facility located in Ludington, Ml or another location not influenced by Palisades plant 

discharges. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 51of61 

Palisade Park Wells 

Location Coordinates Distance (miles) Degrees Sector 

Community Well N 42 18 47.5 0.729 203.63 SSW 

w 86 19 11.4 

Commercial Well N 42 18 48.5 .652 175.06 s 

w 86 18 46.8 

The Community Well services the community residents with well water to their homes; the 

Commercial Well services the community gardens and drinking fountains on the east side of 

the property. 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

K. SIRW OR TEMPORARY LIQUID STORAGE TANK 

1. Requirement 

ODCM 

Appendix A 

Revision 18 

Page 52 of 61 

The concentration of radioactive material (excluding tritium and noble 

gases) 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 

1 OCFR Part 20, Appendix B, Table 2, Column 2 . 

.Qg + ~ ... + ~ = < 1000 

ECa ECb ECi 

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 hours 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 tank's contents at least once 

per 7 days when radioactive materials are being added to the tank. 

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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

4. Bases 

ODCM 

Appendix A 

Revision 18 

Page 53 of 61 

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 1 OCFR 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. 

NOTE: 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 

1. 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 hours to permit the completion of the surveillance when the allowed 

outage time limits of the action requirements are less than 24 hours. 

Surveillance Requirements do not have to be performed on inoperable 

equipment. 
PALISADES NUCLEAR PLANT 

CFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

3. Surveillance Requirements 

ODCM 

Appendix A 

Revision 18 

Page 54 of 61 

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-1, B-1, C-1, 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

3. Surveillance Requirements 

ODCM 

Appendix A 

Revision 18 

Page 55 of 61 

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 ari 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

IV. REPORTING REQUIREMENTS 

A. RADIOLOGICAL EFFLUENT RELEASE REPORT 

ODCM 

Appendix A 

Revision 18 

Page 56 of 61 

The Radioactive Effluent Release Report (RERR) shall be submitted in 

accordance with 1 OCFR 50.36a prior to May 1 of each year. The report shall 

include a summary of the quantities of liquid and gaseous effluents and solid 

waste released as outlined in Regulatory Guide 1.21, R1, Measuring, 

Evaluating and Reporting Radioactivity in Solid Wastes and Releases of 

Radioactive Material in Liquid and Gaseous Effluents from Light Water 

Cooled Nuclear Power Plants, with data summarized on a quarterly basis 

following the format of Appendix B, thereof. 

The following information shall also be included in the RERR: 

• Assessment of the radiation doses due to the liquid and gaseous 

effluents released during the previous year 

• Inoperable effluent radiation monitors that exceeded 30 continuous 

days; explain causes of inoperability and actions taken to prevent 

reoccurrence 

• Evaluation to show conformance with 40 CFR 190, Environmental 

Radiation Protection Standards for Nuclear Power Operation 

• Unplanned releases of radioactive materials in gaseous or liquid 

effluents to unrestricted areas on a quarterly basis 

• Any changes to this procedure made during the reporting period 

• Groundwater monitoring results taken in support of the Groundwater 

Protection Initiative, but are not part of the REMP 

Solid radioactive waste data shall be reported as follows: 

• Type of waste (example: spent resin, dry waste. Irradiated 

components) 

• Volume in cubic meters, include estimated error 

• Curie quantity per type of waste, include estimated error 

• Principal radionuclides in each category 

• Disposition of waste shipments and irradiated fuel shipments (identify 

number of shipments mode of transport and destination) 
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

B. RADIOLOGICAL ENVIRONMENTAL OPERA TING REPORT 

ODCM 

Appendix A 

Revision 18 

Page 57 of 61 

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, IV.B.3, 

and IV.C of Appendix 1 to 1 OCFR50. 

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 111.J.3.c. 

The Annual Radiological Environmental Operating Reports shall include 

summarized and tabulated results in the format of Table F-1 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 111.J.3.c and results of the lnterlaboratory Comparison Program 

required by 111.J.3.e. 

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 111.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. 
Medium or Pathway Type/Total 

Number of Sampled Analyses (Unit of Measure) Performed 

Air Particulates Gross r.. 416 

(pCi/m3

) 

y-Spec 32 

Cs-137 

Ba-140 

Sr-89 40 

Sr-90 40 

Fish y-Spec 8 

pCi/kg (dry weight) 

Cs-137 

Cs-134 

Co-60 

PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

Table F-1 

Environmental Radiological Monitoring Program Summarv 

ODCM 

Appendix A 

Revision 18 

Page 58 of 61 

Name of Facility Docket No 

Location of Facility Reporting Period ______ _ 

(County, State 

Lower Limit All Indicator Control Locations Number of of Locations Name Mean (~b 

Detectiona Mean (~b Distance & Direction Mean<!t REPORTABLE Range Range OCCURRENCES (LLD) Range 

0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104)- 1 

(200/312) 5 miles 340° (0.08-2.0) (0.05-1.40) 

(0.05-2.0) 

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) 

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) 

0.002 <LLD -- -- <LLD 0 

0.0003 <LLD -- -- <LLD 0 

<LLD 

80 -- <LLD 90 (1/4) 0 

<LLD 

80 -- <LLD <LLD 0 

120 (3/4) 

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.ofTable 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 59 of 61 

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 1 OCFR 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 

1 OCFR 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

ODCM 

Appendix A 

Revision 18 

Page 60 of 61 

8. 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 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER 

NRC GENERIC LETTER 89-01 (TAC NO 75060) 

VI. ONSITE GROUND WATER MONITORING 

ODCM 

Appendix A 

Revision 18 

Page 61of61 

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 B 

DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT 

REQUEST TO RETAIN SOIL IN ACCORDANCE WITH lOCFR 20.302 

Revision 0 

August 1, 1991 

Approved KM Haas 8/20/91 MRN 

Manager - ~adiological Services Date 

TP Neal 8/1/91 

RMC Administrator Date 

ML Grogan 8/14/91 

Tech Review Date 

PF Bruce 9l-082d 8/14/91 

Date 

Applicability Reviewed: ---'Tu...P.u.:Ne=aw....l _-=5~/~5/~9~3 __ 

Gerald B. Slade 11/30/93 

Pl ant General Manager . . Date 

Applicability Reviewed: ~ s-,/(ffe-
Request to Retain Soil in Accordance with lOCFR 20.302 

ODCK 

Appendix B 

Page 1 

Consumers Power Company correspondence dated November 12, 1987 and January 25, 

1988 requested authorization to dispose of contaminated soil in place as 

specified by lOCFR 20.302. The area known as the South Radwaste Area has been 

contaminated by numerous cooling tower overflows and contamination was 

redistributed by heavy rain showers. Although the majority of the radioactive 

material has been packed for waste shipment, a large volume of very low activity 

radioactive material remains. This volume of material would be very expensive 

to ship as waste. 

The specific area contaminated is noted as Area B on the attached survey grid map 

in reference 1. The entire area is fenced and is about 12,000 sq ft of soil 

exposed with the remainder buildings and asphalt. The inhalation pathway is for 

breathing suspended soil from this area. The radworker could receive 8.03E-04 

mRem/50-year maximum organ (liver) dose and the infant could receive 3.16E-05 

mRem/50-year maximum organ (liver) dose, both of which are insignificant. Direct 

dose to a radworker is less than 2E-03 mRem/hr. Occupancy in this area should 

not average more than 2 hours/week or 100 hours/year, which would result in a 

dose of <1 mRem/year. 

The radwaste activities which caused the contamination of the soil were 

completely relocated to a new east radwaste area. The South Building has been 

deconned and is being used for non-radwaste activities. Some fixed contamination 

is present in floor cracks and vaults. This has been documented for plant 

decommissioning. No further contamination will be added to the south area from 

the South Radwaste Building. In spite of this commitment, revocation of Michigan 

shipping privileges in November 1990 require the use of this area to store 

packaged low level radioactive waste (LLW). Use of this building is addressed 

in CPCo's letter to NRC Document_ Control Desk, April 24, 1991 which is entered 

as reference 6. 

This LLW, in the form of dry active waste (DAW) will be packaged in metal boxes 

and labeled, ready for future shipment to burial sites. The DAW metal shipping 

boxes will be stored off the floor to prevent water damage. The metal shipping 

boxes are strong, tight containers designed to prevent any leakage of radioactive 

material during transportation. Incidental water contact will not result in the 

spread of contamination. Radioactive waste will not be processed in the South 

Radwaste Building and the bullding will be maintained as a normally clean 

(radiologically) area. 

Rev 0 

8-1-91 
References 

ODCH 

Appendix B 

Page 2 

(1) CPCo's letters, T.C. Bordine to NRC Document Control Desk, November 12, 

1987 and January 25, 1988. 

(2) Memorandum from L.J. Cunningham, DREP to T.R. Quay, T.V. Vambach, "Request 

for Additional Information (RAI)", March 15, 1988, April 7, 1989, and 

January 12, 1990. · 

(3) CPCo's supplement to Reference (1), J.L. Kuemin to NRC Document Control 

Desk, June 27, 1988. 

(4) CPCo's supplement to References (1, 2), G.B. Slade to NRC Document Control 

Desk, August 31, 1990. 

(5) CPCo's letter, T.P. Neal to B. Holian, October 23, 1990. (Typo of 10/13/90 

in original reference). 

(6) CPCo's letter, G.B. Slade to NRC Document Control Desk, April 24, 1991. 

"Use of South Storage Building as an Interim Radi6active Yaste Storage Building". 

(7) NRC Letter, Brian Holian to G.B. Slade, CPCo, June 7, 1991, "Approval and 

Conditions to Retain Soil in Place". 

Rev O 

8-1-91 
. • ' 

N 

consumers 

Power 

POWERING 

MICHlliAN'S l'IUIGllES5 

ODCM - APPENDIX B 

REFERENCE 1 

General Offlc .. : 1945 Wen Pernell Roed, Jackson, Ml 49201 • (5171 788-0550 

November 12, 1987 

Nuclear Regulatory Commission 

Document Control Desk 

Washington, DC 20555 

DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT -

REQUEST TO RETAIN SOIL IN ACCORDANCE WITH IOCFR20.302 

The Code of Federal Regulations, Title IO, section 20.302 allows for approval 

of proposed procedures to dispose of licensed material in a manner not otherwise authorized in the regulations. Flooding of the South Radwaste Building 

has caused contamination of 4,173 cubic feet of soil with 2,992.6 μCi of 

Cs-137 and 79.3 μCi of Co-60. The area is approximately 30 meters from Lake 

Michigan. Site hydrology (Attachment 2, FSAR 2.2) indicates most of the 

activity will ~!grate to Lake Michigan in a few years. In July, 1986 a 

two-fold evaluation began to identify and map the extent of the ground 

contamination in the flood plain. The initial findings and evaluation were 

provided to NRC and the Michigan Department of Public Health by internal 

letter dated September 26, 1986, to LHueter, NRC, Region III. 

Consumers Power Company requests authorization to dispose of this soil inplace 

as the costs of disposal at a burial ground is estimated at $270,000 while 

radiological consequences to the general public and site employees is very 

low. The activities in the contaminated soil were input as a single radioactive liquid release to Lake Michigan into the NRC LADTAP Code. The output 

indicated an estimated wholebody dose to the general public (50 mile radius 

population l.05E06) of I.69E-02 manRem or I.6E-OS millirem per person. The 

maximum estimated wholebody dose to an individual would be 5.13E-03 millirem 

and maximum organ dose (teenage liver) would be 8.67E-03 millirem. The 

maximum whole body dose rate was assumed to be at 18 inches from contaminated 

soil. The maximum whole body dose rate calculated using the Microshield Code 

was I.02E-02 mR/hr. Occupancy of this area is controlled by the Radiological 

Safety Department and secured by a locked fence. Average yearly occupancy is 

approximately 8 hours per week per individual for 4 to 5 individuals. ·A 

radiation worker should not exceed an additional wholebody dose of 4.08 

millirem/year. 

Flooding of the South Radwaste Building as a result of the cooling tower 

overflows is being addressed in two stages. "For the short term the cooling 

tower bypass valve is now electrically isolated during cooling tower operation. Most previous flooding has been due to instrument failures that cause 

the valve to open during normal operation. In addition the South Radwaste 

Building has been decontaminated to eliminate ~r minimize contamination that 

TPN-HPOl-~01 Rev O 

8-1-9"1 
Nuclear Regulatory Commission 

Palisades Plant 

10CFR20.302 Request 

November 12, 1987 

could be transported to the environment. A long term solution to remove 

radwaste activities from this area is being included in the Five-Year Plan. 

2 

The activity released to the environment from a flooding release prior to 1986 

was estimated and added to the liquid section of the Semi-Annual Radiological 

Effluent Release Report dated February 28, 1986. Following approval of this 

application, it is proposed .to account for current activity as an abnormal 

liquid release included in the semi-annual effluent report. A background, 

evaluation and survey results discussion follows in Attachment A. Attachment 

1 is the Microshield Code output and Attachment 2 is FSAR section 2.2 

(including referenced tables and figures) on site hydrology. 

Pursuant to 10CFR170.12(c) a check in the amount of $150 is attached. 

Thomas C Bordine (Signed) 

Thomas C Bordine 

Administrator, Nuclear Licensing 

('"'. CC Administrator, Region III, NRC 

NRC Resident Inspector - Palisades 

Attachment 

TPN-HPOl-NLOl Rev 0 

8-1-91 
TPN-HPOl-NLOl 

ATTACHMENT A 

Consumers Power Company 

Palisades Plant 

Docket 50-255 

EVALUATION AND SURVEY RESULTS 

November 12, 1987 

10 Pages 

Rev O 

8-1-91 
1 

Background 

In 1986, a soil survey was conducted south of the Turbine Building which 

included the South Radwaste area. The survey was conducted due to the South 

Radwaste Building being in the main flowpath of 'A' Cooling Tower, which has 

overflowed on three separate occasions in 8 years. The survey found that 

radioactive material was deposited in the soil due to the flooding of contamination and radioactive material areas inside the South Radwaste Building. 

Other areas sampled that were not in the flood plain were; liquid radwaste 

storage tanks, T-90, T-91, storm drains, the beach and the sand dunes. The 

survey included a survey grid, surface sample results and core sample results. 

All contaminated areas found in Are~ A (Figure 1) were packaged as radwaste. 

In addition, the highest activity areas adjoining the South Radwaste Building 

were also packaged. A total of 16-98 cubic foot boxes were packaged containing 

over 85 percent of the estimated activity. 

· Evaluation 

In August of 1987, the survey was conduc.ted again to prepare this report and to 

verify the location of the ground contamination and if any contamination 

migrated further into the ground since the 1986 su~ey. The survey was a two 

phase evaluation with the first phase being a mapped area consisting of 25' x 

25' ~quares south of the Turbine Building. Once mapped out, surface samples 

were taken in this area. The intent of this phase was to accurately map the 

location and determine the activity in μCi/gram of all ground surface contami~ 

nation. Each surface sample consisted of approximately 20 grams of soil taken 

MI0987-0066A-NL02 

Rev 0 

8-1-91 
2 

from the top l / 211 of gr·ound and placed in a petri dish for analysis on the 

Multi-Channel Analyzer (MCA). Over 275 samples were collected and analyzed 

with two surface samples being taken in each sector. All.samples were counted 

on MCA, Intrinsic Detector #1. Figure 2 shows the sector where activity was 

detected and their highest levels in μCi/gram. 

Phase II was initiated after completion of the "surface" sample analysis. This 

consisted of taking core samples in 6" increments where activity was detected. 

Core samples were taken until two consecutive core ~amples reflected no activity. Core samples were also taken below the activity levels found in the 1986 

soil survey until two consecutive core samples revealed no activity. 

,...... 

Figure 3 indicates the depth level where activity was no longer detectable. 

For example, 6 inches is indicated in H-10 on Figure 3. This indicates that 

activity was only detected on the surface. H-9 and I-10 indicate 18" which 

tn means activity was detected only at 1211 • Table 1 shows the results summary in 

μCi/gram of the highest activity at all sample locations. The sector numbers 

respond to grid coordinates shown on Figures 1, 2 and 3. 

In addition to the sample sectors shown on Figure 1, 25 samples were collected 

at various locations on site. These include surface and core samples around 

T-90, and T-91 on the Northwest side of the Turbine Building (location not 

shown on figures). Surface samples were taken under the asphalt around the 

South Radwaste Building. These are indicated by a hexagon on Figure 1 in F-11, 

I-12 and K-10 sectors. Core samples taken under the South Radwaste Building 

are indicated by circles on Figure 1. Of the areas sampled above activity was 

Rev a· 

MI0987-0066A-NL02 8-1-91 
!.n 

3 

found only under the East side of the So.uth Radwaste Building in sector I-9 

(Table 1). 

In ·the 1986 soil survey other areas were sampled that were not in the flood 

plain of the South Radwaste Building. Those included Feedwater Purity Building, North Storage Building, beach areas North and South of Plant, North and 

Northeast sand ·dunes and various storm drains. In all of these areas no 

activity was detected. Therefore, they were not sampled in the 1987 soil 

survey as they were not in ·the flood plain. 

Since the 1986 soil survey, asphalt has been placed over various locations in 

the protected area. Asphalt was placed around all storm drains and approx!-

mately 50% of the South end of the Turbine Building. Before asphalt was laid 

down. about 3-6" of the top soil was removed and taken offsite. The soil 

before leaving site was sampled and counted with no activity detected. 

Results 

To quantify activity and determine impact, the areas of ground contamination 

were separated into two areas. Area A which contains all the sectors (A-L, 

1-8) North of the "black top" to the Turbine Building. Area B contains all 

sectors (C-L. 9-14) South of "black top" in the vicinity of the South Radwaste 

Build.ing. In Area A no activity was detected, therefore it was not used in 

determining activity or impact. 

MI0987-0066A-NL02 

Rev 0 

8-1-91 
,-.. 

4 

In ·Area B activity was detected in almost all sectors to the East of the South 

Ra_dwaste Building (Figur'e 2). Activities r~nged from 2 .07E-6 μCi/gram (E-11) 

to 3.75E-5 μCi/gram (H-11). Cs-137 was the primary radionuclide present in all 

samples with two other samples containing Co~60 l.12E-5 μCi/gram at 6" and 

5.80E-6 μCi/gram at 12" (I-9 East Figure 2). The greatest depth where activity 

was detected was in sector H..:11 at 18" and when compared to the 1986 soil 

survey the activity has migrated down into the soil 6" inches further. 

Activity was detected at the surf~ce in sectors E-11, E-13, J-12 and L-9 and at 

6" in L-9. This was a result of moving the sand deposited on the asphalt 

during the flood to these sectors and the movement of soil during the grading 

and dumping during the asphalting of the South Radwaste area. 

Activity in μCi was calculated for each sector (Table 2) by the following 

formula: sector ft 2 x depth of activity ft x *48144 grams/ft 3 x activity 

(μCi/gram) ~ μCi. *Average liter of soil weighed 1700 grams x 28.32 L/ft 3 • 

tn 48144 grams/ft 3 • The first level at which no activity was detected was used to 

~ determine depth of activity. In a few sectors, activity was only detected on 

the first 1/2" of soil, but for determining cubic feet and activity a depth of 

6" was use_d. For example, activity for .H-10 was calculated as follows: 625 

ft 2 x .5 ft. depth x 48144 grams/ft 3 x 2.6E-6 μCi/gram activity of surface 

sample equals 39.12 μCi. 

Total volume in cubic feet and total activity in μC~ were calculated for each 

sector of Area B. For sectors with activity, the highest activity detected per 

sector was used in· the μCi calculation. 

MI0987-0066A-NL02 

Total contaminated area in Area B is 

Rev 0 

8-1-91 
5 

4173 ft 3 , total activity is 3071.9 μCi. Sector H-11 contains 73.5% of the · 

total activity which comprises 14.5% of the total contaminated area of Area B. 

To quantify the dose to the population projections, 2992.6 μCi of Cs-137 and 

79.3 μCi of Co-60 was entered into the LADTAP computer program. Assuming that 

the total 3071.9 μCi was eventually released to Lake Michigan thru the water 

table, and the uptake pathways which included fish, drinking, swimming, boating 

and shoreline the 50 mile population estimated at l.05E6 would receive a total 

body dose of l.69E-2 manRem, or l.61E-5 millirem per person. The maximum 

wholebody do.se to an individual· would be 5 .13E-3 millirem and maximum organ 

dose (teenage liver) would be 8.67E-03 millirem. 

Direct dose to an individual working in the affected areas was calculated using 

the MICROSHIELD code. The activities from sec;ors H-11 and I-9 were used for a 

dose 18 inches above the surface. The dose rates from H-11 and I-9 are 

tn 8.75E-06 R/hr .and l.02E•05 R/hr respectively (Attachment 1). Therefore, a 50 

hour occupancy in one week could result in a maximum exposure of 0.51 millirem. 

Normal occupancy of this area is on an as needed bases and averages less than 8 

hours/week per individual in contact with contaminated soil. 

MI0987-0066A-NL02 

Rev O 

8-1-91 
0 

'° 'N 

0 

'."') co ::ti 

I CD 

I-' < 

I 

\0 0 

I-' 

Table 1 

Soil Sample Core Results Cuci/gram) 

Sector 

' Surf ace 6 .. 1211 1811 24 3011 3611 

E-11 2.07£-6 <HDA <HDA <HDA 

E-13 4.39E-6 <HDA <HDA <HDA 

H-9 4 .19E-6 <HDA 4.79E-6 <HDA <HDA <HDA 

H-10 2.60£-6 <HDA <HDA 

H-11 3. 75E-5 <HDA <HDA 8.45E-6 <HDA <HDA <HDA 

I-9 1.24£-5 <HDA <HDA 

I-10 <HDA <HDA 5.39£-6 <HDA <HDA <HDA <HDA 

J-9 5.39E-6 <HDA <HDA 

J-12 6.39E-6 <HDA <HDA 

L-9 · <HDA 6. 77£-6 <HDA <HDA 

T-90 <HDA <H~A 

T-91 <HDA <HDA 

**I-9 #1 <HDA <HDA <HDA' <HDA <Hl>A <HDA <HDA 

**I-9 #2 <HDA l.40E-5* 5.80E-6+ <HDA <HDA <HDA <HDA 

**I-10 #3 <HOA <HDA 

**I-11 #4 <HDA <HDA 

***K-10 <HDA 

>h'n':J-12 <HDA 

*>""''F-11 <HDA 

+ Activity is all Co-60 

* Includes l.12E-5 μCi/gram of Co-60. All other activities listed were identified 

as Cs-137. 

'°'* Core samples unde.r foundation of the South Radwaste Building. 

*** Surface ~amples ~nder asphalt in South Radwaste area. 

H10986-0062A-HP01 

42" 48" 

<HDA 
'° N 

0 

Ln 

'q" 

1' 

~ 

Area B 

Sector IJ Sq.ft. x 

E-11 375 

E-13 375 

H-9 625 

H-10 625 

H-11 625 

I-9 527 

I-10 275 

J-9 450 

J-12 200 

L-9 150 

I-9 east 98 

4325 

HI0986-0062A-HP01 

Table 2 

Activity Calculations per Sector 

Depth ::z ft 3 x g/ft 3 X uCi/g = 

0.5 187.5 48144 2. 07E-6 

0.5 187.5 48144 4.39E-6 

1.5 937.5 48144 4. 79E-6 

o.s 312.5 48144 2.60E-6 

2.0 1250.0* 48144 3.75E-5 

0.5 263.5 48144 l.24E-5 

1.5 412.5 48144 5 .39E-6 

0 .5 225 48144 5·.39E-6 

0.5 100 48144 6.39E-6 

1.0 150 48144 6.77E-6 

1.5 147 48144 l.40E-5 

4173 

*1250 = 

7 

Total uCi. 

18.7 

39.6 

216.2 

39.l 

2256.8* 

157.3 

107 .o 

58.4 

30.8 

48.9 

. 99.1 

3071.9 

*2256.8 = 

73.5% of 

total activity 

Rev 0 

8-1-91 
FIGURE~ 

SURVEY 

GRID 

LEGEND 

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TPN-HPOl-NLOl 

ATTACHMENT l 

Consumers Power Company 

Palisades Plant 

Docket 50-255 

MICROSHIELD CODE OUTPUT 

November 12, 1987 

8 Pages 

Rev O 

8-1-91 
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TPN-HPOl-NLOl 

ATTACHMENT 2 

Consumers Power Company 

Palisades Plant 

Docket 50-255 

FSAR SECTION 2.2 - SITE HYDROLOGY 

November 12, 1987 

10 Pages 

Rev 0 

8-1-91 
r.n 

2.2 HYDROLOGY 

The Palisades Plant site is surrounded on the north, east and south sides 

by sand dunes. The west side of the site is the Lake Michigan shoreline. 

As a result of this local topography, the site drainage is independent of 

the Brandywine Creek drainage basin which drains the hinterland. All surface water runoff drains directly to the lake and the percolating runoff 

also discharges to the lake (see Reference 3). There are no data available 

to verify the amount of surface runoff from the site; however, the flow 

from the Brandywine Creek drainage basin should be useful for the putpose 

of comparison: 

Data obtained to establish base flow.figures for Van Buren County streams 

indicate that the Brandywine Cree~drainage basin is about 17 square miles 

(see Reference 4). The average annual rainfall for the area is 34 inches. 

During the period September 1962 to O~tober 1963, the base flow measurements varied from a minimum of 0.90 cubic feet per second (ft3 /s) to a 

maximum of 11.4 ft 3/s. This resulted in a mean annual 7-day minimum flow 

of 1.6 ft 3 /s or 0.094 ft3 /s/sq mi (cubic feet per second per square mile). 

The period of stream measurements was representatiye of drought conditions. 

The deposits of Brandywine Creek drainage basin are of low permeability 

which results in ~ nearly total runoff to Lake Michigan. This runoff probably occurs soon after precipitation. Minor groundwater storage in the oLd 

beach and reworked older.sandy lake deposits observed on the surface to the 

east of the site area probably maintain Brandywine Creek during periods of 

low rainfall •. 

2.2.1 GROUNDWATER 

Almost all the water used in Van Buren County is obtained from wells. 

Exceptions are the City of South Haven that obtains its municipal suppiy 

from Lake Mi;chigan and some irrigation supplies th.a.t are obtained from 

streams, lakes and local ditches (see Reference 4). 

The glacial drift.is the only known source of fresh groundwater in the 

county. All the glacial deposits are capable of yielding some water to 

wells, but the sand and gravel outwash deposits yield the largest 

quantities (see Reference 4). 

The area of sand dunes along Lake Michigan is not generally favorable for 

obtaining large supplies of groundwater. Probably most of the dune sand is 

above the water table and most wells must be drilled into the underlying,, 

lake deposits (see Reference 4). · 

1. General 

Groundwater levels were established by the 1966 Geology and Groundwater 

Investigation conducted by Bechtel Company for Consumers Power Company (see 

Reference 3). The results of the investigation are shown on Figure 2-9. 

It is rea·dily apparent that subsurface drainage is generally westward 

fsl281-129la-09-72 2.2-1 Rev 0 

8-1-91 
ATTACH.'1E~T ' 

toward the lake (see Profile A-A). Minor variations; ie, flow toward 

surface streams, may exist but are not considered significant. 

An average hydraulic gradient toward the lake of about 13 feet per mile was 

obtained along Profile A·A as shown on Figure 2·9. This gradient represents only the upper surface of unconfined groundwater. Water released on 

the surface would move toward the lake at an estimated rate of 650 feet per 

year (see Reference 3). 

The nearest domestic wells to the site are located one-half mile to the 

east and south. The data indicates that groundwater in the vicinity of the 

eastern wells is flowing west toward the site. Local groundwater in the 

area of the southern wells is also flowing west toward the lake, perpendicular to the shoreline. 

There are no major sources of groundwater withdrawal, eg, large-scale 

industrial or agricultural pumping, that might reverse the direction of 

groundwater flow and cause groundwater to flow from the Plant area toward 

any existing domestic wells. Without such pumping, it is difficult to 

envis1on a condition which would cause sufficient groundwater lowering at 

any of the domestic wells such that the direction of flow might be 

reversed. 

2. Plant Site 

Groundwater levels in the vicinity of the site are shown on Figure 2-9. 

The water table generally slopes toward the lake. During the site inve~tigations, groundwater elevations averaged 580 feet MSL beneath the building 

site. This elevation corresponds to the approximate mean level of Lake 

Michigan. As shown by water levels measured during drilling, groundwater 

levels rise ·to the east to approximately 604 feet MSL beneath the switch• 

yard and 601 fee~ MSL near the eastern site boundary (see Reference 3). 

Field permeability tests performed during the 1965 exploratory drilling 

yielded values ranging from 30 to 1,720 feet per year in the site area, 

Table 2-11. In Drill Hole S, located approximately 500 feet northwest of 

the containment ~uilding, the permeability values ranged from 30.4 feet per 

year to 143 feet per year. In Drill Hole 7, located approximately 650 feet 

south of the containment building,- the permeability values ranged from 

156 feet per year to 1,720 feet per year. 

3. Groundwater Movement 

. An unconfined aquifer is present in the dune area with groundwater levels 

controlled by the level of Lake Michigan. The rate of movement of groundwater downward into material underlying the dunes appears to be very slow. 

Nine samples from Drill Hole 22 in the site area were tested (or sodium absorption ratio (SAR), Table 2·12. A high SAR indicates poor downward percolation of water due to sodium deposition on and between soil particles. 

At the Plant site, the SAR is considered to be high between elevations 596 

and 566 feet MSL and low between 566 and 555 feet MSL (see Reference 3). 

fsl281-129la-09-72 2.2-2 Rev 0 

8-1-91 
t.n 

Groundwater levels and permeability data from the sandy lake deposits 

underlying the dunes indicate a slow rate of discharge into Lake ~ichigan . 

. 4. Conclusions 

a. Groundwater in the unconfined aquifer moves westerly from the 

Brandywine Creek basin to Lake Michigan. 

b. The hydraulic gradient is approximately 13 feet per mile and flow 

is essentially perpendicular to the shoreline. 

c. Water discharged on the ground surface at the Plant site will 

percolate downward at a slow rate and mix with groundwater moving 

toward Lake Michigan. 

d. Infiltration of surface water from the site to domestic wells 

offsite does not appear to be possible under present groundwater 

conditions. 

2.2.2 GENERAL LAI<E HYDROLOGY 

1. Lake Levels 

The level of Lake Michigan is cyclic and is expected to fluctuate with time 

and is dependent on long·term above-normal or below-normal amounts of pre- · cipitation. The highest monthly mean stage of Lake Michigan was 

583.68 feet MSL in 1886. Subsequent modifications in the St Clair River 

and the opening of the diversion out of the basin at Chicago have tended to 

reduce the maximum level attainable. During the recent period of record 

(1900 to present), the highest recorded monthly mean stage was 582.6 feet 

MSL in July 1974, and the lowest monthly mean stage was 576.91 feet MSL in 

March and April 1964 (see Reference 5). Great Lakes levels are reported 

using International Great Lakes Datwn which is converted to MSL at the 

Palisades site by adding 1.558 feet. The l.558•foot correction factor is 

taken from the reference point at St Joseph, Michigan. 

Short·time variations in lake levels (seiches), caused by meteorological 

factors and measured in hours rath.er than days, occur occasionally. The 

greatest level change of this type on record over a 105•year period in• 

volved a sudden.rise of 6 feet at Michigan City, Indiana (8:10 AM, June 26, 

1954) and a rise of 8 feet at Montrose Harbor, Chicago (9:30 AM on the same 

date) (see Reference 6). These seiches were reported in the "Science" 

article by Ewing, Press and Donn (Vol 120, Page 684). On passing into tGe 

shallow water at Michigan City, the wave was reflected and refracted to 

reach the Chicago shore of the lake. The US Lake Survey gauge at Holland, 

Michigan, which is 30 miles north of the Palisades site and has similar 

lake geometry to the site, indicated no surge on June 26, 1954. 

As part of the Syst.ematic Evaluation Program (SEP Topic II-3.B), the maximum probable surge elevation, was reevaluated. The offshore sur.ge value was 

reevaluated to produce an onshore surge height of 10.9 feet. The maximum 

monthly mean level was also· reduced from 583.6 feet MSL to 582.6 feet MSL. 

fs1281-1291a-09-72 2.2•3 Rev 0 

8-1-91 
This resulted in a probable maximum flood protection level for the 

Palisades Plant of 593.5 ·feet MSL. 

The service water pump motors at 594.7 feet MSL provide the basis for 

determining the minimum flood protection requirements for the Plant. 

Therefore, the resultant wave surges from Lake Michigan do not present a 

problem at Palisades. 

2. Water Movements 

Conclusions from a study of lake hydrology in the Palisades Park, Michigan 

area by Dr J L Hough (see Reference 6) indicate that surface currents generated by wind conditions and .modified by the earth's rotation and lake 

configuration will provide adequate mixing of Plant liquid effluents into 

the lake. The study included actual measurements of lake water movement in 

the area near the.Plant site, and water mixing where the Black River enters 

Lake Michigan at South Haven. 

A summary of the study is as follows: 

Lake water is almost constantly moving past the Palisades site, with an appreci~ble velocity of flow, under the influence of winds. It is estimated, on the basis of wind records, that an alongshore current flows 

northward about 33\ o·f the time and an alongshore current flows southward about 23% of the time. Offshore drift of surface water should 

occur about 38% of the time, according to frequency of offshore winds, 

but these would have a minimal effect close to shore, which is bordered 

by a high dune ridge. It is likely, therefore, that the alongshore 

currents would tend to persist, once set up, while offshore winds were 

blowing. Thus, the frequency of alongshore current flow is probably 

greater· than the 33% and 23% based on wind directions. 

Under the procedure of taking water from a depth of about 20 feet, 

3,500 feet offshore, raising its temperature as it is used for service 

water and dilution of c~oling tower blowdown, and returning the efflu~ 

ent to the lake near shore, the effluent water will almost always be 

warmer than the lake water into which it is discharged. This is 

because- a sin-gle take Michigan water mass is involved during most. of 

the year. When the effluent is warmer, it will tend to float at the 

surface, to drift with the surface current, and to be mixed by surface 

turbulence due to wave action. On rare occasions, during the spring wa~ing period when the upper layer of lake water is less than 20 feet 

deep, and during the summer when strong offshore winds ·cause a thinning 

of the normally deep surface mass to less· than 20 feet, the intake · water coming from a colder layer may not be warmed in the Plant suf ficiently to have a temperature higher than that of the surface lake 

water. At such times, the effluent water will tend to sink to the 

thermocline and it will not be subject to vigorous turbulence caused by 

surface wave action. It will tend to mix more slowly. 

Surveys of the performance of Black River water, entering Lake Michigan 

at South Haven under various weather conditions, have indicated that 

fsl281-129la-09-72 2.2-4 Rev 0 

8-l-9l 
r.n 

the river water is diluted rapidly, reaching a concentration of ab~ut 

only 1% in ~he lake witbin a mile of the river mouth. 

The disch~rge of the Black River was evaluated because the rate was determined to be nearly the same as the discharge· rate from the Palisades Plant 

with once-through coolidg. Since th~ Plant is now operated with cooling 

towers, the discharge to the lake has been reduced to approximately 

60,000 gpm or about 1/7 the original rate. The mixing and dilution factors 

are considered to be as great as during the higher discharge periods and 

the discharge concentrations should be diluted at least 1,000 times by the 

time the discharge could reach the public water intake at South Haven, 

Michigan. 

3. Conclusions 

a. The level of Lake Michigan is cyclic; howeve.r, the recorded high of 

1886 is unlikely to be exceeded. High lake levels are not expected 

to present a problem at the Plant site. 

b. There is no recorded evidence of short-time variations in lak·e 

levels (s.eiches) along the eastern shore of Lake Michigan which 

would be expected to affect the Plant site. 

c. Surface currents generated by wind conditions and modified by the 

earth's rotation and lake c~.nfiguration will provide adequate 

mixing of Plant liquid effluents into the lake. 

fs128l-1291a-09·72 2.2-S Rev 0 

B-1-91 
Drill Hole Elevation 

Number of Test 

5 576 

570 

565 

560 

555 

550 

545 

0 7 580 

575 

Q) 570 

565 

:'t 560 

,,.... 550 

545 

540 . '· 535 

t.n .. , 

v 

r.... 

l"?. 

fs1281·129ln-09-72 

..\TT .. .\Cfil!.E~! ) 

TABU 2-U 

FIELD PERMEABILITY TEST RESULTS 

Flow "Q" Head "H" 

( G12m) (Feet) 

Permeabil ity3"K" 

(ft/Yr) (cm /s) 

0.0029 12.3 30.4 

0.0101 12.3 106.0 

0.0088 12.3 92.0 

0.0035 12.3 36.8 

0.0136 12.3 143.0 

0.0064 12.3 67.0 

0.0033 12.3 34.6 

Average 72.8 

0.0303 25 156 

0.0477 25 246 

0.0588 25 303 

0.0588 25 303 

0.0834 25 430 

0.3333 25 1,720 

0.0677 25 350 

0.2500 25 1,290 

0.2000 25 11035 

Average 648 

. ~. 

0.3 x 

l. 1 l( 

0.89 l( 

0.36 x 

1.4 x 

0.65 x 

0.34 l( 

0. 72 x 

1.5 x 

2. 4 l( 

2.9 l( 

2.9 l( 

4.2 x 

16.7 x 

3.4 x 

12.5 l< 

10. 1 l( 

6.3 x 

10-4 

_, 10 '+ 

10-4 

10-~ 

10-... 

10-4 

10-4 

10 "' 4 

l0- 4 

10"'4 

10-4 

10-4 

10-4 

10-4 

lo"' 4 

lo-·4 

10-4 

10"'4 

Rev 0 

8-l-9l 
N 

tn 

v 

TABLE 2·12 

ANALYSES OF SOIL SA...'1PLES 

Saturation Extract Values 

Millieguivalents Eer Liter 

Sample No ....£!L ECe Caldwn Magnesium Sodium 

1 8.2S 1.2 0.5 Trace 11. 7 

·2 8.4 1.4 0.5 Trace 13.0 

J 8.3 1.3 o.s Trace 12.3 

4 8.45 1.4 0.5 Trace 14.4 

5 8.5 1.5 0.5 0.1 14.8 

6 8.3 1.5 0.5 Trace 14.8 

·7 8.5 1.3 0.5 0.05 12: 7 

8 8.2 0.5 J,O 0.4 1. 1 

9 8.1 0.6 3.4 0.7 2.4 

ECe ~ Millimhos per centimeter 

SAR = Sodium adsorption ratio on saturation extract 

. ,.., 

fsl281-129lo-09-72 

SAR 

23.5 

26 

24.5 

29 

27 

29.5 

24 

1 

1.5 

Sample 

DescriEtion 

DH 22 El 596 

DH 22 El 59 l. 

DH 22 El 586 

DH 22 El 581 

DH 22 El 576 

DH 22 El 571 

DH 22 El 566 

DH 22 El 561 

DH 22 El 555 

Rev 0 

8-1-91 
N 

co 

N 

0 

CP ~ 

I ro 

1-'<l 

I 

\0 0 

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. ·' --· . ,.,,. 

677 METEIS IEAREST ACCESS ROAD 

19UIOARY POllT TO COllTA1114ENT 

LEGEllD 

...V TO ARGENTA 

I SITE PROPERTY BOUMDARY & EXCLUSION AREA 

2 l'GWER BLOCK PUN 

3 CIRCULATING WATER COOLIMG TOWERS 

' SITE COllTOUR INTERVALS Of 20' IMCREHENTS 

5 3300 FOOT INTAKE PIPE TO CRIB 

Ii DISCHARGE STRUCTURE 

1 PARllllG 

8. TOl'OGllAPlllC ELEVATIONS IN FEET ABOVE 

MUI SU LEVEL 

"""L.- TO lVIM BRANCH 

~ llN (A.E.P.) CO. 

'-,, 10 COOl llN 

(A.E.P.) CO 

CONSUMERS POWER COMPANY 

PALISADES PLANT 

FSAR UPDATE 

SITE LAYOUT 

f IGURE 110 2-2 

ATTACllMENT l 
tn· 

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•5•80lllN6 LOCAJIOll AND NllNllEK 

•:.-...., ,.._..!/ SEISMl.C PIOFILE LOCATION 

< ' ·C::::::~ ., • 

CONSUMERS POWER COMPANY 

PALISADES PLANT 

FSAR UPDATE 

SITE TOPOGKAfHY, 

IOl116 LOCATIOllS, AID SEISMIC PllOFILU 

FIGURE MO 2-3 

RUISIOM MO 0 

AT'l'ACllMEN'J' 2 
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CONSUMERS POWER COMPANY 

PALISADES PLANT 

FSAR UPDATE 

GROUllDWATER ELEVATIONS 

ANO AREA GRADIENTS 

FIGURE 110 2-9 

REVISION NO . 0 

ATTACllMENT 2 
' 

consumers 

Power 

POWERING 

MICHlliAN"S PROGRESS 

General Offices: 1945 West Parnell Road, Jackson, Ml 49201 • (517) 788·0550 

January 25, 1988 

Nuclear Regulatory Co1m11ission 

Document Control Desk 

Washington, DC 20555 

DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT -

SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH lOCFR.20.302 

Consumers Power Company letter dated November 12, 1987, requested authorization to dispose of soil in place as specified by lOCFR.20.302. The letter 

·included the results of a survey and evaluation performed in·August, 1987. 

Following submittal of that letter, a cooling tower overflow on 

November 13, 1987 again flooded the South Radwaste Building. The flooding 

caused additional activity that necessitated Consumers Power Company to 

request placing our November 12, 1987 request on hold until further evaluation 

and surveys could be completed. This letter includes the results of our 

evaluation and survey of the November 13, 1987 flooding incident and is 

intended to supplement our original November 12, 1987 request. 

Following the cooling tower overflow, a survey indicated additional activity 

had been released from the building. The building was being maintained in a 

non~contaminated condition to prevent this type of occurrence; however, during 

this period a destructive testing program on waste packages was being conducted in a small area of the building. The survey clearly showed the release 

of activ~ty from the building adjoining the testing area, The top six inches 

of soil from the sectors adjoining the building were removed"and packaged (588 

cubic feet) to prevent additional dispersion of radioactivity. The area was 

then completely resurveyed. 

An evaluation of the August 1987 and November 1987 (post packaging) activities 

is att.ached. The survey indicates a drop of 49% in activities between the 

August and.November surveys. We propose the activities specified in the 

November 12, 1987 submittal be used ~s jμstification for the request because 

they are consei::vative. In addition since the November 13, 1987 flooding and 

following the most recent survey the area was subject to.heavy rains which 

could have diluted some activities to below minimum detectable activity (MDA 

is nominally lE-06 μCi/g), 

OC0188-0018-NL02 

Rev 0 

8-1-91 
·Nuclear Regulatory Commission 

Palisades Nuclear Plant 

Retain Soil in Accord. with 10CFR20.302 

January 25, 1988 

2 

The one non-conservative value from our August survey and evaluation is· the 

maximum dose rate at 18 inches above the surface. The November survey value 

from MICROSHIELD is 1.17 mR/hr as opposed to 1.02 mR/hr. This small increase 

only slightly changes the radiation workers' conservative dose estimate from 

4.08 mR/year to 4.7 mR/year. 

·Following approval of this application, it is p·roposed to account for the most 

conservative values of activity, which was stated in the November 12, 1987 

submittal, as an abnormal release in the semi-annual report. In order to 

prevent recurrence of these releases to the environment, Consumers Power 

Company is also committing to transfer radwaste activities from this area, 

except for high level vault use which is not a potential flooding release 

problem. 

Relocation of these activities to a new radwaste facility is currently 

scheduled to.be completed in 1988. 

A check in the amount of $150.00 was attached to our November 12, 1987 

submittal pursuant to 10CFR170.12(c). 

Thomas C Bordine (Signed) 

Thomas C Bordine 

Administrator, Nuclear Licensing 

CC Administrator, Region III, NRC 

NRC Resident Inspector - Palisades 

Attachment 

OC0188-0018-NL02 

Rev O 

8-1-9.1 
I .. 

1·:· 

Attachment A 

Consumers Power Company 

Palisades Nuclear Plant 

Docket 50-255 

Evaluation and Survey Results Comparison Post November 

Flood and Packaging Versus the November 12, i987 Submittal 

MI0188-0001A-HP01 

Rev 0 

8-1-91· 
,. 

,. 

' 

,.A' Cooling Tower - South Radwaste Flood 

In August of 1987, a resurvey was conducted of the soil at the South Radwaste 

Building and its adjacent areas. The resurvey was conducted to verify the 

location of ground contamination and if any .contamination migrated further into 

the ground since the 1986 survey. 

After submittal of the 1987 soil results and request to retain, in accordance 

with 10CFR20.302, 'A' Cooling Tower Basin overflowed again flooding the South 

Radwaste Building and outlying areas. Immediately following the occurrence, 

one liter sample was taken with no activity detected on the Multi-Channel 

Analyzer (MCA). Then, another complete survey was conducted which included at 

least two surface samples and core samples in every sector (Figures 1 and 2). 

Surface sample results showed that activities have increased as well as new 

sectors contaminated. The most heavily affected sectors were I-10, I-11, J-9 

and K-9 (Figure lA). To keep these areas from spreading, the top 6" of each of 

these sectors was removed and placed in 6 LSA boxes (approx. 588 cu.ft) and 

stored for disposition at a later date. 

After removal of soil, the sectors were resurveyed (Figure lB) and core samples 

were taken in each sector in 6-inch increments. Core samples were taken as far 

down as in the 1986 and August 1987 surveys, and in some instances even further 

in this survey. ·Results showed that no activity was detected below 6 inches as 

shown in Figure 2. 

Table 1 and Table 2 show comparisons between the August and November 1987 soil 

surveys. Table 1 compares the depths, the activities, the total cu.ft. and 

total μCi per sector. After the removal of soil, the November 1987 soil survey 

results showed approximately a 49.3% drop in total contaminated soil (cu.ft.) 

and a 51.1% drop in total μCi in comparison to the August 1987 survey results. 

In Table 2 the comparison is between sectors affected in each survey and the 

depth at which each of these sectors were sampled. No activity was detected 

past 6 inches in the November 1987 soil survey, in comparison to that of 18 

inches detected in August 1987. 

Direct dose to an individual working in the affected areas was calculated using 

the MICROSHIELD code. The activities from sectors H-9 and J-9 were used for a 

dose at 18" inches above the surface. The dose rates from H-9 and J-9 are 

·9.97E-6 R/hr and l.17E-5 R/hr, respectively. Therefore, a SO-hour occupancy in 

one week could result in a maximum exposure of .59 millirem. Normal occupancy 

of this are~ is on an "as needed basis" and averages less than 8 hours/week per 

individual in contact with the contaminated soil. 

In reviewing the soil results between August and November 1987, the August 1987 

soil survey remains more conservative based on the information shown on Tables 

1 and 2. Therefore, the August 1987 soil survey is still valid in support of 

our request to retain the soil in accordance with 10CFR20.302. 

MI0188-0001A-HP01 

Rev 0 

S-1-91 
Table 1 

Comparison Table Between Total Cu. 

August 1987 

Sector fl sg.ft. ·X DeEth = ft 3 x g/ft 3 

E-11 375 0.5 187.5 48144 

E-13 375 0.5 187.5 48144 

H-9 625 1.5 937.5 48144 

H-10 625 0.5 312.5 48144 

H-11 625 2.0 1250* 48144 

I-9 527 0.5 263.5 48144 

I-10 275 1.5 412.5 48144 

J-9 450 0.5 225 48144 

J-12 200 0.5 100 48144 

L-9 150 1.0 150 48144 

I-9 East 98 1.5 147 48144 

4325 4173 

~ 

' *1250 

) 

November 1987 

E-11 375 0.5 187.5 48144 

H-9 625 0.5 312.5 48144 

H-10 625 0.5 312.5 48144 

r H-11 625 0.5 312.5 48144 

H-12 250 0.5 125 48144 

,. I-9 ·527 0.5 263.5 48144 

I-12 220 0.5 110 48144 

J-9 450 0.5 225 48144 

l. J-1·2 200 0.5 100 48144 

K-9 216 0.5 108 48144 

iUl 20~6!5 

MI0188-0001A-HP01 

Ft. 

x 

and Total μCi 

μCi/g .. Total μCi 

2.07E-6 18.7 

4.39E-6 39.6 

~.79E-6 216.2 

2.60E-6 39.1 

3.75E-5 2256.8 

l.24E-5 157.3 

5.39E-6 107.0 

5.39E-6 58.4 

6.39E-6 30.8 

6.77E-6 48.9 

l .40E-5 99.1 

3011.2 

*2256.8 m 

73.5% of 

total activity 

l.80E-6 

4.35E-5 

3.20E-6 

3.22E-5 

2.20E-6 

6.79E-6 

3.0E-6 

2.05E-5 

2.60E-6 

3.39E-6 

16.25 

654.46 

48.14 

484.45 

13.24 

86.14 

15.89 

222.06 

12.52 

17.63 

1570.78 

Rev 0 

8-l-9l 
Table 2 

Survey Comparison Between August and November 1987 Soil Surveys 

August 1987 

November 1987 

Sector Surface 6" 1211 18" 2411 3011 3611 42" 

E-11 2.07E-6 <MDA <MDA <MDA 

l.SOE-6 <MDA <MDA <MDA 

E-13 4.39E-6 <MDA <MDA <MDA 

<MDA H/A <MDA <MDA 

H-9 4.19E-6 <MDA 4.79E-6 <MDA <HDA <HDA 

4.JSE-5 <MDA <MDA <MDA <MDA <HDA 

H-10 2.60E-6 <MDA <MDA 

3·.20E-6 <MDA <MDA 

H-11 J.75E-5 <MDA <MDA 8.45E-6 <MDA <MDA <HDA 

3.22E-5 <MDA <MDA <MDA <MDA <MDA <MDA 

H-12 <MDA Nf A 

2.20E-6 N/A 

I-9 l.24E~5 <HOA <MDA 

6.79E-6 <MDA <MDA 

I-10 <MDA <MDA 5.39E-6 <MDA <MDA <MDA <MDA <MDA 

<MDA <MDA <MDA <MDA <MDA <MDA <MDA <HDA 

I-11 <MDA Nf A 

<MDA <MDA <MDA <MDA 

I-12 <MDA N/A 

3.00E-6 N/A 

J-9 5.39E-6 <MDA <MDA 

2.0SE-5 <MDA <MDA . J-12 6.39E-6 <MDA <MDA· 

2.60E-6 N/A <MDA 

lC-9 <MDA Nf A 

3.J9E-6 <MDA <MDA <MDA <MDA <MDA <MDA 

L-9 <MDA 6. 77E-6 <MDA <MDA 

a:> ?:d <MDA N/A <MDA <MDA 

I CD 

I-'< 

I 

\00 

I-' 

MI0188-0001A-HP01 
., 

o· 

Microshield 3.02 

===;============= 

(ConsuMer's Power CoMpany - #037) 

Page 1 

File SOIL1 .MSH 

Run date: January 18, 1988 

Run tiMe: 4:17 p.M. 

CASE: CONTAMINATED SOIL@ H-9 LOCATION <6 INCHES DEEP> 

GEOMETRY 11: Rectangular solid source. - slab shields 

Distance to detector ......................... x 60.960 

Source width• • t • I C II II II I' 11 II 11 11 11 II I II I I 11 °1 11 I I • II II S II • II • w 762. 

Source length ... I.•.• I.· ••••• · ••• I I I ••••••••••• I L 762. 

Rectangular solid, thickness toward dose pt •• Tl 15.240 

Thickness ci f second ~hield .................... T2 45.720 

Source Volul'le: B.84901e+6 cubic centit11eters 

Material 

Air 

Alut11inuP1 

Carbon 

Concrete 

Hydrogen 

Iron 

Lead 

LithiuPI 

Nickel 

Tin 

Ti taniul"I 

Tungsten 

Urania 

UraniuPI 

Water 

Zirconiul"I 

MATERIAL DENSITIES (g/cc>: 

Source Shield 2 

.001220 .001220 

1. 70 

1.0 

CM, 

II 

" 

" 

" 

Rev O 

8-1-91 
-; 

:r: 

, 

:'.). 

Page 2 File: SOIL1 .MSH 

CASE: CONTAMINATED SOIL@ H-9 LOCATION (6 INCHES DEEP> 

BUILDUP FACTOR: based on TAYLOR Method. 

Using the characteristics of the Materials in shield 1 · 

INTEGRATION PARAMETERS: 

NuMber or lateral angle segPlents (Nthetal..... 5 

NuMber of aziMuthal angle segMents <Npsi)..... 5 

NuP1ber of radial segMents (Nradius)........... 5 

SOURCE NUCLIDES: 

Ba-137M: 3.8493e-04 curies 

RESULTS: 

Group 

# 

Energy 

<MeVl 

Activity 

(photons/sec) 

Do3e point flux 

MeV/(sq cpi)/sec 

Dose rate 

( l'lr/hr > 

1 

2 

3 

4 

5 

6 

7 

8 

9 

10 

. 1 1 

12 

13 

14 

15 

16 

17 

18 

19 

20 

.664 

TOTALS: 

I. 282e+07 4.908e+00 9.969e-03 

1. 282e+07 4.808e+00 9.969e-03 

Rev 0 

8-1-91 
.. 

, 

:r 

,.. 

' 

Microshield 3.02 

================= 

(ConsuMer's Power CoMpany - #037) 

Page 1 

File SOIL2.MSH 

Run date: January 18, 1988 

Run tiMe: 4:26 p.M. 

CASE: CONTAMINATED SOIL@ J-9 LOCATION {6 INCHES DEEP> 

GEOMETRY 11: Rectangular solid source - slab shields 

Distance to detector ..•.. ,.,.· •••.•. ~ .••....• , .)( 

Source width ........... , ...................... lJ 

Source length ..................•.............. L 

Rectangular solid, thickness toward dose pt •. Tl 

Thickness of second shield', ..•..•.•••...•••• , T2 

60.960 

762. 

548.640 

15.240 

45.720 

Source VoluMe: 6.37129e+6 cubic centi111eters 

Material 

Air 

Alu111inufll 

Carbon 

Concrete 

Hydrogen 

·Iron 

Lead 

Li thiul'I 

Ni'ckel 

Tin 

T1taniuP1 

Tungsten 

Urania 

Uraniu111 

Water 

Zirconiul"I 

MATERIAL DENSITIES (g/cc): 

Source Shield 2 

.001220 .001220 

f. 70 

1.0 

CM, 

II 

II 

II 

Rev O 

8-1-9], 
., 

l'" 

,.. 

, 

~. 

Page 2 File: SOIL2.MSH 

CASE: CONTAMINATED SOIL @ J~g LOCATION CS INCHES DEEPl 

BUILDUP FACTOR: based on TAYLOR Method. 

Using the characteristics of the Materials in shield 1. 

INTEGRATION PARAMETERS: 

NuMber of lateral angle segMents CNthetal..... 5 

NuMber of aziMuthal angle segMents (Npsil..... 5 

NuMber of radial segl'lents (Nradius).. ......... 5 

. SOURCE NUCLIDES: 

Co-80: 8.9198e-05 curies 

RESULTS: 

Group ·Energy Activity Dose point Hux 

MeV/(sq cP1)/sec; 

Dose rate 

# <MeV) (photons/sec) <Mr/hr> 

1 

2 

3 

4 

5 

6 

7 

a 

9 

10 

11 

12 

13 

14 

15 

16 

17 

10 

19 

20 

1 .336 

1 • 180 

.695 

TOTALS: 

. 3 .300e+06 

3.300e+~6 

5.303e+02 

6.S01e+06 

3.411 e+00 

2.958e+00 

2.aase-04 

6.370e+00 

6 .1 SSe-03 

5.497e-03 

5.950e-07 

1 .165e-02 

Rev 0 

8-1-91 
:1GURE 1A 

SURFACE 

~ESULTS 

rl 

00\ 

I 

> rl 

ID I 

P'.i <X) 

... ACE ACTMTYOFSECTOR 

ASPHALT AMAS 

•1xA11PLI: ONLY 

... 
:1GURE 1B • 

. 

SURFACE . 

L 

I. 

. . ./ ,~ r 

i.EGEND I~ A. ~r.a:::.~~s::thr¥:i:i=~-

. ~~ 

· ~~~~rr ~ ·L-~~~U-~-~~~~~+-~M~- Ql · IURMCI! AMA IN>ER ASPHALT 't/'"" . · . &J CORE SAMPLE UNDER FOUNDATION. 

/~ 

· 

ri 

00\ 

(° 

> rl 

Q) I 

i:r:: co 

SURFACE ACTIVITY OF SECTOR 

ASPHALT AflEAS 

•EXAMPLE: ONLY 
I . 

. Ei~END 

::-I Lat IUt llJ-cawr.tN ::J ........ ... 

~ OIPTM 1.DIL AT.WllCll NO Ll ICllVlirWAIMNCTID 

~ _AINIALT A~ 

J ,.--.,,..-~ 

i1 

L 

c. 
ODCM - APPENDIX B 

REFERENCE 2 

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, D. C. 20555 

/>woa/OB>eg 

~-

MAN 1 fi ,988 

Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road 

Jackson, Michigan 49201 

Dear Mr. Berry: 

March 15, 1988 

NUCt!AI uaNSING 

SUBJECT: PALISADES PLANT - REQUEST TO .RETAIN CONTAMINATED SOIL IN ACCORDANCE 

WITH 10 CF.R 20.302 (TAC NO. 67408) 

The subject request submitted by Consumers Power Company by letter dated 

November 12, 1987 and supp1emented by information forwarded by letter dated 

January 25, 1988 contains detailed information evaluating the radiation doses 

via the liquid pathways for very low levels of contamination presently in 

areas of soil near the Palisades Plant South Radwaste Building. Detailed 

evaluations are also presented of potential occupational doses from this 

contaminated so.i l . 

One additional dose pathway should, however,·be evaluated to complete the 

analysis of the impact viz., the inhalation pathway. In your submittals, you have presented diagrams showing areas in which contamination has been 

detected. It appears that for some of these areas 611 of soil has been 

removed, others are now covered by black top, and still others have not been 

disturbed. In order for the staff to complete the evaluation under 10 CFR 

20.302, we ask that you submit a diagram indicating all contaminated soil 

surface areas included in this request, the condition of this soil surface, 

and an evaluation of the radiation dose.s via the inhalation pathway associated with these soil surfaces. The request in this letter affects 

fewer than ten respondents; therefore, OMB clearance is not required under PL 

96-511. 

cc; Sse· ·Next. -Rage 

Sincerely, 

~1(~ Thomas V. Wambach, Project Manager Project Directorate III-1 

Division of Reactor Projects - III, IV, V 

& Special Projects 
I 

,. 

, 

l. 

·Mr. Kenneth W. Berry Consumers Power Company 

cc: 

M. I. Miller, Esquire Isham, Ljncoln & Beale 

Slst Floor 

Three First National Plaza 

Chicago, Illinois 60602 

Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue 

Jackson, Michigan 49201 

Judd L. Bacon, Esquire · Consumers Power Company 212 West Michigan Avenue 

Jackson, Michigan 49201 

Regional Administrator. Region III 

U.S. Nuclear Regulatory Commission 

799 Roos·eve 1 t Road 

Glen Ellyn, Illinois 60137 

Jerry Sarno 

Township Supervisor Covert Townsh1 p 36197 M-140 Highway Covert, Michigan 49043 

Office of the Governor 

Room 1 - Capitol Building Lansing, Michigan 48913 

Mr. David P. Hoffman 

Plant General Manager Palisades Plant 

27780 Blue Star Memorial Hwy. Covert, Michigan 49043 

Resident Inspector c/o U.S. Nuclear Regulatory Commission 

Palisades Plant 

27782 Blue Star Memorial Hwy. Covert, Michigan 49043 

Palisades Plant 

Nuclear Facilities and 

Environmental Monitoring Section Office 

Division of Radiological Health 

P.O. Box 30035 

Lansing, Michigan 48909 

Rev O 

8-'l-91 
Lt# 5ooe89 

llEt:c;1vED 

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON, D. C. 20555 

JAN 1 ~ f93~ 

January 12, 1990 '' 11r.1 FL\O ~ '':FN~INn 

Docket No. 50-255 

Serial No. PAL 90-002 

Mr. Kenneth W. Berry Director, Nuclear Licensing Consumers Power Company 1945 West Parnall Road 

Jackson, Michigan 49201 

Dear Mr. Berry: 

SUBJECT: PALISADES PLANT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 

10 CFR 20.302 (TAC NO. 67408) 

By letters dated November 12, 1987 and January 25 1 1988, Consumers Power Company requested authorization under the provisions of 10 CFR 20.302 to dispose . contaminated soil in place. The NRC staff replied with a request for additional 

information which was forwarded to you on March 15 1 1988. · • ~· .. 

By letter dated June 27, 1988, Consumers Power Company provided additional·~ 1 

information in response to ou.r request. Howeve.r, in that response, CPCo 

expanded the original request to include the entire South Radwaste area as a 

contingency against future spread of co.ntamination and to obviate the· need for 

additional requests under 10 CFR 20.302. For the staff to complete its review 

of this request, additional specific information is required. This is because 

NRC approval under 10 CFR 20.302 is for the disposa'l of specifically identified and characterized slightly contaminated material by the applicant. 

We request that you provide a revised submittal describing the licensed material 

for disposal and the analysis and evaluation called for under 10 CFR 20.302. 

The attached request for additional information provides additional detail for 

the content of the revised submittal. 

The reporting and/or recordkeepfng requirements of this letter affect fewer 

·than ten respondents; therefore, OMB clearance under Pl 96-511 is not required. 

cc: See next page 

Sincerely, 

Albert 

~/~ W. De Ag;~-a,-~;:ject Manager Project Directorate III-1 . Division of Reactor Projects - III, 

IV, V & Special Projects Office of Nuclear Reactor Regulation 

Rev 0 

8-1-91 
r' 

Mr. Kenneth w. Berry Consumers Power Company 

cc: 

M. I. Miller, Esquire Sidley & Austin 

54th Floor 

One First National Plaza 

Chicago, Illinois 60603 

Mr. Thomas A. McNish, Secretary Consumers Power Company 212 West Michigan Avenue 

·Jackson, Michigan 49201 

Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue 

Jackson, Michigan 49201 

Regional Administrator, Region III 

U.S. Nuclear Regulatory Con111ission 

799 Roosevelt Road 

Glen El~yn, Illinois 60137 

Jerry Sarno 

Township Supervisor Covert Township 36197 M·140 Highway Covert, Michigan 49043 

Office of the Governor 

Room 1 - Capitol Building Lansing, Michigan 48913 

Mr. Gerald B. Slade 

Plant General Manager Palisades Plant 

27780 Blue Star Memorial Hwy. Covert, Michigan 49043 

Resident Inspector c/o U.S. Nuclear Regulatory Conmiss1on 

Pa 1 i sades Pl ant 

27782 Blue Star Memorial Hwy. Covert, Michigan 49043 

Palisades Plant 

Nuclear Facilities and 

Environmental Monitoring Section Office 

Division of Radiological Health 

P.O. Box 30035 

Lansing, Mfch1gan 48909 

Rev 0 

8-1-91 
I 

SECOND REQUEST FOR ADDITIONAL INFORMATION (RAI) 

ON THE CONSUM.ERS POWER COMPANY 

PALISADES PLANT REQUEST 

TO RETAIN SOIL IN ACCORDANCE 

WITH 10 CFR 20.302 

ENCLOSURE 

The subject request submitted by Consumers Power Company (licensee) by letter 

dated November 12, 1987 and supplemented by information forwarded by letter 

dated January 25, 1988 contained detailed infor~ation evaluating the radiation 

doses via the liquid pathways for very low levels of contamination presently in 

areas of soil near the Palisades Plant South R.adwaste Building. Detailed 

evaluations were also presented of potential occup~tional doses from this 

contaminated soil. 

Three significant questions arose during the staff evaluation of this request: 

1. The inhalation pathway for doses from the contaminated soil was not 

addressed. 

2. The proposals contain no delineation of the specific contaminated areas 

covered by the disposal request. 

3. The licensee's Technical Specifications for radiological environmental 

-1 monitoring require an LLD of 2 x 10 μCi/gm for 13 7Cs determinations in 

sediment - yet all of the measurements reported in the request were made 

with equipment 5 to 10 times less sensitive for these gamma radiations. 

Re-v 0 

8-1-91 
By letter dated June 27, 1988 the licensee submitted additional information in 

response to the staff's RAI of March 15, 1988. This submittal was unacceptable . . in that it addressed potentially contaminated areas and hypothetical maximum 

contamination parameters rather than measured licensed material to be disposed 

of under the regulations. 

It is requested that. the licensee submit a complete, revised 20.302 request 

incorporating the dose evaluation information of the measured contamination 

considered in the No.vember 12, 1987 and January 25, 1988 submissionsand updated 

if appropriate with dose evaluations of the inhalation pathway based on the 

same measured contamination. As part of the proposal the licensee should 

record exactly what areas of measured contamination are covered by the request 

for which disposal under 10 CFR 20.302 is proposed. 

2 

Rev O 

8-l-9l 
, 

r 

... 

consumers 

Power 

POWERING 

MICHlliAN-S PROGRSS 

.ODCM - APPENDIX B 

REFERENCE 3 

General Offices: 1945 West Parn11ll Road, Jackson, Ml 49201 • (517) 788-0550 

June 27, 1988 

Nuclear Regulatory Commission 

Document Control Desk 

Washington, DC 20555 

DOCKET 50-255 - LICENSE DPR-20-- PALISADES PLANT -

SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH 10CFR20.302 

Consumers Power Company correspondence dated November 12, 1987 and January 25, 

1988 requested authorization to dispose contaminated soil inplace as specified 

by 10 CFR 20.302. The area, known as the South Radwaste Area, has been 

contaminated by numerous cooling tower overflows and redistributed by heavy 

rain showers. Although the majority of the radioactive material has been 

packaged for waste ·shipment, a large volume of very low ac_tivity radioactive 

material remains. This volume of material would be very expensive to ship as 

waste. The NRC, by letter of March 15, 1988 to Consumers Power Company, 

requested additional inhalation dose information and clarification of the 

contaminated area • 

A generic inhalation dose evaluation is described in Attachment A. Conservative assumptions have been made to get the maximum organ dose possible from 

inhalation of contaminated soil. The inhalation doses are not significant. 

Consumers Power Comp·any requests to expand this 10 CFR 20.302 request to 

_include the entire South Radwaste Area •. Periodic cooling tower overflows and 

occasional heavy rains have caused redistribution of radioactive material to 

-areas which were below Lower Limits of Detection (LLD) during previous evaluations. Expanding the area would eliminate the need for a new 10 CFR 20.302 

submittal if radioactive material is redistributed within the South Radwaste 

Area. The South Radwaste Are~ is completely fenced and located directly South 

of tpe Plant South Security fence. Area fence is shown in dark outline on 

Figure 1. 

As desc~ibed in our January 25, 1988, letter we intend to transfer the 

radwaste activities which caused the contamination of soil from the South 

Radwaste Area, except for the high level· vault use which is not a potential 

flooding release problem. 

OC0688-0049-NL02 

Rev 0 

8-1-91 
') 

'l 

,. 

' 

~ .. 

Nuclear Regulatory Commission 

Palisades Nuclear Plant 

Retain Soil in Accordance w/10CFR20.302 

June 27, 1988 

Consumers Power Company requests approval to dispose of inplace low level 

radioactive materials which meet the following conditions ~ithout further 10 

CFR 20.302 submittals. 

1. Material contained in the fenced area described as South Radwaste Area. 

2. Direct dose to a radiation worker would not exceed SE-02 mRem/hour.from 

contaminated soil. · 

3. Average gross beta/gamma concentration not to exceed SE-05 μCi/gm so 

in~alation doses to a radiation worker or at the site boundary would not 

exceed the values contained in Attachment 1. 

2 

4. Additional radioactive material releases shall be identified in liquid Semi-Annual 

Effluents Reports as an 'Abnormal Release'. 

Sampling, analyses and Semiannual Effluent Report inclusions of 'Abnormal 

Release' will be performed only when further flooding of the area occurs. 

James L Kuemin (Signed) 

James L Kuemin 

Staff Licensing Engineer 

CC Administrator, Region III,° NRC 

NRC Resident Inspector - Palisades 

Attachment 

OC0688-0049-NL02 

Rev 0 

8-1-91 
0 

0 

T 

-

., 

Attachment 1 

The inhalation doses have been calculated on a generic worst case basis. A 

generic basis has been selected to compensate for the elevated Lower Limit of 

Detection (LLD) in analysis and also to address movement of radioactivity 

within the South Radwaste Area. The assumptions made are the worst case Dose 

Conversion Factor (DCF) used (see Table 3), a total average activity concentration.of 5E-05 μCi/gram and the entire area (500 m2 ) used instead of the indicated contaminated area (117 m2 ). 

Increasing the area is self-explanatory. The total average activity concentration is being used il!tstead of actual to account for dose important isotopes 

which may be present near the analysis LLD of lE-0~ μCi/gm, but not detected. 

The worst case D9F is used to demonstrate a maximum organ dose. A variation in 

isotope mixes could shift the maximum dose to a different organ but could not 

exceed the dose indicated. 

Radworker and site boundary inhalation dose calculat~ons are attached. 

OC0688-0049-NL02 

.Rev 0 

8-1-91 
... 

., 

r 

-

"" ., 

·Table 1 

Inhalation Dose From Contaminated Soil - Adult Radiation Worker· 

Where: CS = concentration of waste: 5.0E04 pCi/Kg. 

Ef .. occupancy factor: 2080 worker hours + 8760 hrs/yr = 0.2.37 

f

18 =areal mass available for resuspension (top 1 cm of soil): 16 

Kg/m2 

f 14 = resuspension. factor: 8.5E-9/m 

f

15 = adult annual inhalation rate: 7300 m3 (RG 1.109) 

DCF i =- 7 .46E-04 mRem/ (50 yr • pCi): adult lung (RG 1.109) 

Substituting: 

DW = 8.78E-03 mRem/50 yr: maxim.um organ dose 

Reference: AIF/NESP-035 Evaluation of the Potential for De-Regulated·Disposal 

of Very Low Level Wastes From Nuclear Power Plants 

OC0688-0049-NL02 

Rev O 

8-1-91 
, 

T 

-

., . 

"" ·' 

Table 2 

Inhalation Dose At Site Boundary.-

Infant Most Limiting 

X/Q μ A 

Where: Terms are identified in Table 1 and 

F

16 = 2045 ms: infant annual breathing rate (RG 1.109) 

X/Q ~ 1.4 E-6 sec/ms: actual 5 year site average 

μ = 3.8 m/sec averag~ wind speed: actual 1986 

A = 500 m2 : contaminated area 

DCFi = 3.22E-03 mR/(50 yr. pCi): infant lung (RG 1.109) 

Subs ti tu ting 

DSB = 1.19E-04 mRem/50 yr: ~aximum organ dose 

OC0688-0049-NL02 

Rev O 

8-1-91 
-· 

Table 3 

Dose Conversion Factors for Inhalation: Committed dose (mRem) over 50 years 

per pCi inhaled, per Regulatory Guide 1.109. 

Onsite - Radiation Worker 

Bone Liver Kidney Lung GI 

Cs-134 4.66E-05 l .06E-04 3.59E-05 l.22E-05 l.30E-06 

Cs-137 5.98E-05 7.76E-05 2.78E-05 9.40E-06 l.05E-06 

Ba.:..140+D 4.88E-06 6.13E-09 2.09E-09 l.59E-04 2.73E-05 

Sr-90* l.24E-02 0.0 o.o l.20E-Ol 9.02E-05 

Co-60** o.o l.44E-06 o.o 7.46E-04 3.56E-05 

* Sr-90 is a factor of 5E-Ol lower than Cs-137 based upon 10 CFR 61 sampling 

analysis and cannot be limiting. Cs-137 was present in all samples where 

activity was identified. 

** Given the concentration restriction on Sr-90 noted above, Co-60 lung dose is 

most limiting. 

Offsite ,.. Infant Most Limiting for Inhalation 

Cs-134 2.83E-04 5.02E-04 . l.36E-04 5.69E-05 9.53E-07 

Cs-137 3.92E-04 4.37E-04 l.23E-04 5.09E-05 9.53E-07 

Ba-140 4.00E-05 4.00E-08 9.59E-09 l.14E-03 2.74E-05 

Sr-90* 2.92E-02 o.o o.o 8.03E-03 9.36E-05 

Co-60** 0.0 5.73E-06 o.o 3.22E-Ol 2.28E-5 

* Sr-90 is a factor of 5E-03 lower than Cs-137 based upon 10 CFR 61 sampling 

analy~is and cannot be limiting. Cs-137 was present in all samples where 

activity was identified. · 

** Given the concentration restriction on Sr-90 noted above, Co-60 lung 

dose is most limiting. 

OC0688-0049-NL02 

Rev 0 

8-1-91 
"" ' . ·..,,. . ,, ~ ·~ ~~,., - q~ -~ . ~ . "• ., ~"' 

"-... " 

> " " . ' ' 

> 

w 

c • ! 

c e 

a: 

Ill 

CJ 

cc c Ill • :c ,... (A m 

.. • Q " -' 'I ·u c ~ c 

:l a: z f IC Ill 

J: • ~ c c 

w c c c. 

:J Cl . Rev 0 

CJ M . Cl~ , 'tii~ nmrcJ 8-1-91 

-

•• 
consumers 

Power 

POWERING 

M.IClllGAN"S l'llll&llUS 

ODCM - APPENDIX B 

REF~CE 4. 

Palisades Nuclear Plant: 27780 Blue Star Memorial Highway, Covert. Ml 49043 

August 31, 1990 

Nuclear Regulatory Commission 

Document Control Desk 

Washington, D C 20555 

DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT 

G BSlade 

General Managft 

SUPPLEMENT - REQUEST TO RETAIN SOIL IN ACCORDANCE WITH lOCFR 20.302 

Consumers Power Company correspondence dated November 12, 1987 and January 25, 

1988 requested authorization to dispose of contaminated soil in place as 

specified by lOCFR 20.302. The area known as the South Radwaste Area has been 

contaminated by numerous cooling tower overflows and contamination was 

· redistributed by heavy rain showers. Although the majority of the radioactive 

material has-been packed for waste shipment, a large volume of very low 

activity radioactive material remains. This volume of material would be very 

expensive to ship as waste. The NRC, by letter of March 15, 1988 to Consumers 

Power Company, requested additional inhalation dose information and 

clarification of the contaminated area. 

After discussions with the NRC reviewer, a supplement was submitted on June 

2.7, 1988 which was based on generic approval. It proposed that further 

submittals would not be required if flooding moved activity from an identified 

to an unidentified sector. Subsequently, on January 12, 1990, the NRC Staff 

requested additional information. The information request required the licensee 

to submit a revised proposal incorporating the dose evaluation information of 

the measured contamination considered in the November 12, 1987 and January 25, 

1988 submittals and updated, if appropriate, with dose evaluations of the 

inhalation pathway based on the same measured contamination. As part of the 

proposal, the licensee was asked to record exactly what areas of measured 

contamination are covered by the request for which disposal under lOCFR 20.302 

is proposed, 

The attached material supplie~ the requested information. The specific area 

contaminated is noted as Area Bon the attached survey grid map. The entire 

area is fenced· and is about 12 ,000 sq ft of soil exposed with the remainder 

buildings and asphalt. The inhalation pathway is for breathing suspended soil 

from this area. Table 2 addresses a radworker in Area B, and Table 3 

addresses an infant on the site boundary. The radworker could receive 

8.03E-04 mRem/50-year maximum organ (liver) dose and the infant could receive 

3.16E-05 mRem/50-year maximum organ (liver) dose, both of which are insignificant. 

OC0890-0074A-NL03 . 

Rev O 

8-1-91 
4 

. When the flooding problem was discovered and planning for a formal survey was 

done, the environmental sediment LLD was not considered, as this was a nuclear 

plant site. We attempted.to get the best LLDj we could usi~g our equipment 

and the number of samples we were going to have to run. With the hundreds of 

samp·les run, we felt rn .... 06 uCi/gm was adequate. To be conservative, we . 

expanded the August and November 1987 surveys to use l.OE-06 uci/gm Cs-137 in 

any sector which showed LLD. This will increase the radioactivity to 5,006 

uCi from 4,643 uCi, an increase of 8%. The activities are on Table 1 and lA. 

If this submittal is approved, we will add the released activity to the Liquid 

Semi-annual Effluent Report as an aQnormal release, and the approval to retain 

the soil in place will be documented in the FSAR. 

In summation, Consumers Power Company requests approval to dispose of 

i~ place the low-level radioactive materials which are contaminated soil contained· 

in the fenced area described as South Radwaste Area (Area B). Direct dose to 

a radiation worker would not exceed l.7E-02 mRem/hour from this contaminated 

soil. Inhalation doses to a radiation worker or at the site boundary would. 

not exceed 8.03E-04 mRem/50-year. Tables 1 and lA radioactive material 

release shall be identified in liquid Semi-an~ual Effluent Reports as an 

'abnormal release'. The disposal in place would be documented in the FSAR. 

The radwaste activities which caused the contamination of the soil have bee·n 

completely relocated to a new east radwaste area. The South Building has 

been deconned and is being useQ. for non-radwaste activities. Some fixed 

contamination is present in floor cracks and vaults. This has been documented 

for plant decommissioning. No further contamination will be added to the 

south area from the South Radwaste Building. 

Gerald B Slade (Signed) 

Gerald B Slade 

General Manager 

pc: Administrator, Regio~ III, USNRC 

NRC Resident Inspector, Palisades 

OC0890-0074A-NL03 

Rev 0 

8-1-91 
MI0890-00 74A-liPOl 

Attachment A 

Consumers Power Company 

Palisades Nuclear Plant 

Docket 50-255 · 

Tables l and lA,. Survey Results 

Microshield Direct Dose Calculation 

Table 2 - Radworker Inhalation Dose 

Table 3 - Site Boundary Inhalation Dose 

Figure l - Survey Crid 

Figure 2 - Survey Results 

Rev 0 

8-1-91 
, I 

Sector (} S9.ft. x De 2th = 

E-11 375 o.5 

E-13 375 0.5 

H-9 625 1.5 

H-10 625 o.5 

H-11 6·25 2.0 

I-9 527 0.5 

I-10 275 1.5 

J-9 450 0.5 

J-12 200 0.5 

l.-9 150 1.0 

I-9 East ~ 1.5 

Subtotals 4325 

Remainder 7613 0.5 

i: Section 

TOTAL 11, 938 

MI0890-0074A-HP01 

Table 1 

August 1987 Survey 

ft) x g/ ft l x 

187.5 48144 

187.5 48144 

937.5 48144 

312.5 48144 

1250* 48144 

263.5 48144 

412.5 48144 

225 48144 

100 48144 

150 48144 

147 48144 

4173 

3807 48144 

~Ci/g = 

2.07E-6 

4.39E-6 

4.79E-6 

2.60E-6 

3.75E-5 

l.24E-5 

5.39E-6 

5· .39E-6 

6.39E-6 

·6.77E-6 

l.40E-5 

l .OE-06 

Total ~Ci 

18.7 

39.6 

216.2 

39.l 

2256.8 

15 7 .3 

107.0 

58.4 

30.8 

48.9 

99.l 

3071.9 

183 

3,255. 

Rev 0 

a..:.1-91 
Sector ~ Sg. ft. x Deeth 

B-9 125 0.5 

C-9 625 0.5 

c-10 500 0.5 

D-9 500 0.5 

.D-10 625 0.5 

D-11 550 o.5 

D~l2 75 0.5 

E-10 125 0.5 

E-11 375 0.5 

E-12 625 0.5 

E-13 550 0.5 

F-12 300 0.5 

F-13 625 0.5 

G-12 750 0.5 

C-13 625 0.5 

H-9 625 0.5 

H-10 625 0.5 

H-11 600 0.5 

H-12 250 0.5 

H-13 625 0.5 

I-9 527 0.5 

I-10 275 0.5 

I-11 250 0.5 

I-12 220 0.5 

J-9 450 0.5 

J-12 200 0.5 

K-9 216 0.5 

L-9 150 0.5 

L-10 150 0.5 

L-11 150 0.5 

L-12 150 0.5 

Subtotals 11,938 ft 2 

HI0890-0074A-HP01 

Table lA 

November 1987 SurveI 

= ft J x ~)ft J x 

62.5 48144 

312 •. 5 48144 

250 48144 

250 48144 

312.5 48144 

275 48144 

37.5 48144 

62.5 48144 

187.5 48144 

312.5 48144 

275 48144 

150 48144 

312.5 48144 

125 48144 

312.5 48144 

312.5 48144 

312.5 48144" 

300 48144 

125 48144 

312.5 48144 

263.5 48144 

137. 5 48144 

125 48144 

110 48144 

225 48144 

100 48144 

108 48144 

75 48144 

75 48144 

75 48144 

75 48144 

\ 

5,969 ft 3 Maximum 

Average 

~Ci/g = 

lE-06 

lE-06 

lE-06 

lE-06 

lE-06 

lE-0"6 

lE-06 

lE-06 

l.8E-06 

l.E-06 

lE-06 

lE-06 

lE-06 

lE-06 

lE-06 

4.4E-05 

3.2E-06 

3.2E-05 

2.2E-06 

1. OE-06 

6.8E-06 

l.OE-06 

l.OE-06 

3.0E-06 

2. lE-05· 

2.6E-06 

3.4E-06 

·i.oE-06 

l.OE-06 

l.OE-06 

l.OE-06 

4.4E-05 

6. lE-06 

Total ~Ci 

3 

15 

12 

12 

15 

13 

2 

3 

16 

15 

13 

7 

15 

6 

15 

662 

48 

462 

13 

15 

86 

7 

6 

16 

227. 

13 

18 

4 

4 

4 

4 

1751 

Re-v 0 

8-l-91 
Microsh1eld 3.~2 

<Consu111er's Power Co111pany - #037l 

Page I 

File SOIL! .MSH 

Run date: January 19, 1999 

Run ti111e: 4:17 p.111. 

CASE: CONTAMINATED SOIL ~ H-9 LOCATION (6 INCHES DEEP> 

GEOMETRY 11: Rectangular solid !ource - !lab shields 

Distance to detector ••••••••••••••••••••••••• X 

Source widtti .•.••.. , ....••..•........ ~ ....... W 

Source length ..•...•.....•........•.......... L 

Rectangular solid, th1cknese toward dose pt •• ft 

Thickness o.f second shield ••••.••.••..•.••..• TZ 

60.960 

762. 

762. 

15.240 

45.720 

Source Volul'le: 8.84901e+6 cubic centil'leters 

Materh! 

Air 

Alul!linul'I 

Carbon 

Concrete 

Hydrogen 

Iron 

Lead. 

L1 tl"liUl'I 

Nickel 

Tin 

TitaniuPI 

Tungsten 

Urania 

Uraniul'I 

MATERIAL DENSITIES Cgicc): 

Source Sh1e!d 2 

-------- -------- .001220 .001220 

!. 70 

Water 1.0 

Zi.rconiu111 

CPI, 

" 

Rev 0 

8-1-9.1 
·--

8U[L0UP FACrCR: oased on rAvLOR Met~od. 

!J!lnQ tlie clier-acte1"15t1cs or· tl'le l'li!ter-lcds tn 9h1eld I· 

INrEGRAT[ON PARAMErERS: 

Nul'lber or later-al angle seQMent5 <Ntnetal,,, .. 5 

!\Ju111cer- or ~Zll"lutnal angle segMenh <Npul..... 5 

Nul'lt1er- or '.ad1 al seg111ent ! < Nrad11.Js l., ... ,.,,., 5 

SOURCE NUCUOES: 

Sa-137,.,,: · 3. S493e-04 cur us .Actual 

6.SlE-04.Ci 

(4 •. 4E-05 uCi/gm) 

Gr-ou~ 

# 

f 

z 

3 

4 

s 

s 

7 

s 

s 

10 

1 I 

12 

13 

14 

15 

rs 

17 

I 8 

19 

ZI 

RESULTS: 

Energy 

(MeVl 

l'ict1111ty 

<gnotonstsecJ 

------ ------------- .664 I .282e+07 

--------- TOTALS: I. 282e+07 

6.51 Ci 

Dose point rlux 

MeV/(s~ cll\Jtsec 

---------------- 4.S08e+00 

--------- 4.8081+00 

· Ratio of 3.85 Ci= 1.69 x 9.969E-03 = l.7E-02 ?:lR/hr 

Dose rate 

(I'll'"/ hr-) 

---------

9.969e-03 

9.969e-03 

Rev 0 

8-1-91 
Dw = Cg f14 

Table 2 

Inhalation Dose From Contaminated Soil -

Adult Radiation Worker 

Where: Cs = concentrati.on of waste - 4.4E04 pCi/Kg Cs-137 (actual max concentration) 

Ef = occupancy factor - 2080 worker hours ~ 8760 hrs/yr = 0.237 

f18 = a real/mass available for resuspension (top l cm of soil) - 16 

Kg/m2 

f14 = resuspension factor - 8.SE-9/m 

f15 = adult annual inhalation rate - 7300 m

3 (RC 1.109) 

DCFi = 7.76E-o5· mRem/50 yr· pCi - Cs-137 adult liver (RG 1.109) 

:substituting: 

Ow = 8.03E-04 mRem/50 yr - maximum organ dose 

· ~ference: AIF/NESP-035 Evaluation of the Potential for De-regulated Disposal 

of Very Low Level Wastes From Nuclear Power Plants 

HI0890-0Q74A-HP0l 

Rev O 

8-l-91 
Dse = cs f18 

Table 3 

Inhalation Dose At Site Boundary -

Infant Most Limiting 

X/Q μ A DCFi 

Where: Terms are identified in Table 1 and 

F16 = 2045 ml - infant annual breathing rate (RG 1.109) 

X/Q = 1.4 E-6 sec/ml - actual 5 year site average 

μ = 3.8 m/sec average wind speed -'actual 1986 

A - 1110 m2 - contaminated area 

DCFi - 4.37E-04 mR/50 yr • pCi - Cs-137 infant liver (RG 1.109) 

>stituting: 

Dss = 3.16E-05 mRem/50 yt - maximum organ dose 

MI0890-0074A-HP01 

Rev 0 

B-1-91 
FIGUIE ~B 

SURFACE 

RESULTS 

rl 

0.0\ 

I 

> rl 

<LI I 

P'.i co 

AINALT MEAS 

-EXAMPLI : ONLY 

' 
FIGURE ~ 

SURVEY 

GRID 

LEGEND 

~ ASPHALT AREAS 

D ·.· 21• x zs· SECTORS 

I~ Contaminnted 

IL_j AREA •9• 

0 ~llEA °A' 

rl 

OO'i 

I 

>- rl 

ID I 

μ:;co 

• I 
TO 

From 

Date 

Subject 

cc 

BHolian 

ODCM - APPENDIX B 

REFERENCE 5 

'_ TPNeal .Jl>n 

October 23, 1990 

PALISADES PLANT10CFR20. 302 SOIL SUBMITTAL 

RLSmedley 

KMHaas 

CONSUMERS 

POWER 

COMPANY 

TPN90*028 

The following samples were obtained from sectors H-9 and J-9 on 

October 23, 1990. 

Sample Location 

H9-l 

H9-2 

H9-3 

H9-4 

H9-5 

J9-1 

J9-2 

J9-3 

J9-4 

J9-5 

uCi/gm 

-3.92E-6 

3.70E-6 

1. 26E-6 

<MDA 

<MDA 

1. 90E--6 

<MDA 

<MDA 

2.28E-6 

5.86E-6 

Sector H-9 was the highest reading in 1988 at 4.4E-05 uCi/gm and 

J-9, 2.lE-05. - Both areas are now showing a factor of 10 drop in 

activity. Sector H-11 could not be resampled because of equipment 

stored in this location. The data indicates direct dose would be 

less than 2E-03 mR/hr. Occupancy in this area should not exceed 2 

hours/week or 1O0 weeks/year, which is less than 1 inR/year. Sample 

and analysis by MAWillers and GStama, review by TPNeal. 

Rev 0 

8-1-91 
consumers 

Power 

POWERING 

MICHIGAtn l'IUIGRESS 

ODCM - APPENDIX B 

REFERENCE 6 

Palisades Nuclnr Plant: 27780 Blue Star M~1I Mi;hWlly. Covert. Ml 49043 

April 24, 1991 

Nuclear Regulatory Conmission 

Document Control Desk 

Washington, DC 20555 · 

DOCKET 50-255 - LICENSE DPR-20 - PALISADES PLANT -

G 8 Slade 

GrMTal Managrr 

USE OF SOUTH STORAGE BUILDING AS AN INTERIM RADIOACTIVE WASTE STORAGE BUILDING 

On November 10, 1990, radioactive waste generators in the State of Michigan 

were banned from the three currently active burial sites. As a result of this 

ban action must be taken to ensure that Palisades maintains the capability to 

store radioactive waste until such time as we are again able to gain access to 

the burial sites. We believe our actions are consistent with NRC guidance received in Generic letter 90-09. Therefore, the South Storage Building will 

be utilized as an interim storage facility for low level radioactive waste 

(LLW). 

The South Storage Building (then referred to as the South Radwaste Building) had been previously used for all processing and storing of radioactive waste 

produced at Palisades from 1976 to 1989. During that period several cooling 

tower overflows occurred which resulted in flooding this building and 

spreading contamination from the processing area to the surrounding soil. 

This spread in contamination resulted in NRC Open Items (85019-01 and 89025- · 0l) which required implementation of actions to prevent future flooding. In 

1988 it was decided to relocate the radwaste processing functions performed in 

the South Radwaste Building to a new addition at the East Radwaste Building to 

prevent the spread of contamination in the event of future cooling tower 

overflows. All radwaste processing equipment was relocated to the East 

Radwaste Building and the South Radwaste Building was decontaminated. The 

South Radwaste Building (then re-named the South Storage Building) has since 

been used for non-radiological m.aterial storage. 

As a result of increases in radioactive waste, the-South Storage Building is 

now needed to store low level radioactive waste (LLW). This LLW, in the form 

of dry active waste (DAW) will be packaged in metal boxes and labelled, ready for future shipment to burial sites. The DAW metal shipping boxes will be 

stored off the floor to prevent water damage. The metal shipping boxes are 

strong, tight containers designed to prevent any leakage of radioactive 

material during transportation. Incidental water contact will not result in 

the spread of contamination. Radioactive waste will not be processed in the 

A atS" ENE'R6Y COMPANY 

Rev O 

8-1-91 
,, South Radwaste Building and the building will be maintained as a·normally clean {radiologically) area. 

The current Palisades Radwaste Storage Plan requires low dose-rate DAW boxes 

to be placed adjacent to the walls of the South Radwaste Building to limit 

dose rates outside the building. All DAW boxes and the storage building will 

be inspected quarterly in accordance with Palisades Health Physics Procedure 

HP 6.27. This procedure incorporates the storage and inventory guidelines contained in NRC Information Notice No. 90-09, "Extended Interim Storage of 

Low Level Radioactive Waste by Fuel Cycle and Material licensee". 

The same radiological and security controls currently in force at the East 

Radwaste Building will apply at the South Radwaste Building. The South 

Radwaste Building is surrounded by a locked fence and all building access 

doors will normally be locked, with keys controlled by Radiation Safety Department. All access to the building will be controlled through the 

Radiation Safety Office and the Palisades RWP/Oosimetry System. Building 

status sheets will be updated on a monthly basis or whenever radiological conditions change. Any areas outside the building reaching Smr/hr or greater shall be posted in accordance with current HP Procedures. 

Since the South Radwaste Building will be used for the storage of low level 

radioactive waste and not for radioactive waste processing, it is believed 

that the public health and safety will not be adversely affected. 

It is Palisades' intent to continue to use the South Radwaste Building to 

·store low level radioactive waste {LLW) until such time when radwaste 

generators in Michigan are again allowed to ship radioactive waste to the 

burial sites. Upon resumption of shipping to the burial sites the South 

Radwaste Building will be emptied, surveyed and returned to the plant for nonradiological material storage. 

~J~~- Gerald B Slade 

General Manager 

CC Administrator, Region III, USNRC 

Resident Inspector, Palisades 

Rev O 

8-1-91 
.A 

/ 

I .. - .. . .... 

' I 

· 1. \ 

. I 

···L 

' 

" 

I 

I 

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co !:t1 

I CD 

I-' <l 

I 

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I-' 

•' 

·· .. 

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Docket No. 50-255 

ODCM - APPENDIX B 

REFERENCE 7 .. UNITED STATES 

NUCLEAR REGULATORY COM1 

WA.SHINGTON. D.C. 20555 

June 7, 1991 

TPNeal, P~l 

JUN 12199·, 

Mr. Gerald B. Slade 

Plant General Manager 

Palisades Plant 

Consumers PQwer Company 

27780 BNe .st~r Memoria 1 Highw~y 

Covert, Michigan 49043 

Dear Mr. Slade: 

SUBJECT: REQUEST UNDER 10 CFR 20.302 TO RETAIN CONTAMINATED SOIL ONSITE AT 

PALISADES PLANT (TAC NO. 67408) 

By letters dated N·avember 12, 1987, and January 25, 1988, (Reference 1 of the 

enclosed Safety Evaluation (SE)), Consumers Power Company submitted a request 

pursuant to 10 CFR 20.302(a) for the disposal of contaminated soil onsite at 

the Palisades Plant. We have completed our review of the request and find your 

procedures, (~,!,th. comnitmeJJt~. -~.~ dQc.~m~o~~cl.~lP-"~~f e.r:-ence l) to be acceptable. Ttf'ls:' a.· . _ r ., · .,. ·.. ·, : ·:. t ·: · · · · -·- -. ~: l'" ··c:::- • :- • ·• ,~safet ~ .• N, .. :r,,~J~l!.r.t?i ,:;· • ' • < ~ Ev'~Ili~J1cr~; • • • a · · 

Minucfl':;(r .A .. Also-:~fir ure mo 

shall'be"''reporte(:f to''ttie NRC. in accordance with the applicable ODCM. change 

protocol. We fu.rther find that the radiological environmental impact of the 

proposed action meets the staff criteria as reflected in Reference 6 of the 

enclosed Safety Evaluation. 

Enclosure: 

As stated 

Sincerely, 

Brian Holian, Project Manager 

Project Directorate JII .. 1 

Division of Reactor Projects III/IV/V 

Office of Nuclear Reactor Regulation 

Rev o 

8-1-91 
Mr. Gerald B. Slade 

Consumers Power Company 

cc: 

M. I. Miller, Esquire Sidley & Austin 

54th Floor 

One First National Plaza 

Chicago, Illinois 60603 

Mr. Thomas ~. McNish, Secretary Consumers Power Company 212 West Michigan Avenue 

Jackson, Michigan 49201 

Judd L. Bacon, Esquire Consumers Power Company 212 West Michigan Avenue 

Jackson, Michigan 49201 

Regional Administrator, Region III 

U.S. Nuclear Regulatory Conmission 

799 Roosevelt Road 

Glen Ellyn, Illinois 60137. 

Jerry Sarno 

Township Supervisor Covert Township 36197 M-140 Highway Covert, Michigan 49043 

Office of the Governor 

Room 1 - Capitol Building Lansing, Michigan 48913 

Mr. Patrick M. Donnelly Director, Safety and Licensing Palisades Plant 

27780 Blue Star Memorial Hwy. Covert, Michigan 49043 

Resident Inspector c/o U.S. Nuclear Regulatory Conmission 

Pa 11 sades Plant 

27782 Blue Star Memorial Hwy. Covert, Michigan 49043 

Palisades Plant 

Nuclear Facilities and 

Environmental Monitoring Section Office 

Division of Radiological Health 

P.O. Box 30035 

Lansing, Michigan 48909 

Gerald Charnoff, P.C. 

Shaw, Pittman, Potts & 

Trowbridge 2300 N. Street, N.W. 

Washington, D.C. 20037 

Hr. David L. Brannen 

Vice President 

Palisades Generating Company c/o Bechtel Power Corporation 15740 Shady Grove Road 

Gaithersburg, Maryland 20877 

Roy w. Jones 

Manager, Strategic Program Development Westinghouse Electric Corporation 4350 Northern Pike 

Monroeville, Pennsylvania 15146 

Rev 0 

8-1-91 
INTRODUCTION 

UNITED STATES 

NUCLEAR REGULATORY COMMISSION 

WASHINGTON. D. C. 20555 

SAFETY EVALUATION RELATED TO 

THE PALISADES NUCLEAR PLANT 

RETENTION OF CONTAMINATED SOIL ONSITE 

In reference (1). Consumers Power Company {CPCo) requested approval pursuant to 

Section 20.302 of Title 10 of the Code of Federal Regulations {CFR) for the 

disposal of licensed material not previously considered by the NRC in the 

Palisades Final Environmental Statement (FES). dated June 1972. The petition submitted contains a detailed description of the licensed material {i.e •• 

contaminated so;1) subject to this 10 CFR 20.302 request. The 6,000 cubic feet 

of onsite contaminated soil contains a total radionuclide inventory of 5.1 mCi. 

based on radioactive material that was deposited in the soil due to the flooding of the South Radwaste Building. The contaminated area is located inside the 

security fences, and is on company controlled land. This area {South Radwaste 

Area) is fenced in, within the plant's south security fences. Thus it·is 

inaccessible to the public {see Figures 1 and 2). 

In the submittals (References 1-5), the licensee addressed specific information 

requested in accordance with 10 CFR 20.302(a), provided a detailed description of the licensed material, thoroughly analyzed and evaluated the environmental 

effects relative to retention of the contaminated soil onsite, and coD111itted 

to follow specific procedures to minimize the risk of unexpected exposures. Although the environmental impact of the proposed action is well within the dose 

criteria contained in the Conmission's Below Regulatory Concern {BRC) Policy Statement, dated July 3, 1990. the licensee has not requested. and the staff has 

not considered, the act.tons described:-herein to be exempt from NRC regulation. 

CPCo plans to dispose of the 6,000 cubic feet of contaminated soil ons;te 

pursuant to 10 CFR 20.302. The area, known as thd South Radwaste Area, has 

been contaminated by several cooling tower overflows (three times in an eightyear period), and has subsequently been redistributed by heavy rain showers. 

The cooling tower overflows were caused by instrument failures that opened the 

cooling tower bypass valve during.normal operation. This valve is now electrically isolated during cooling tower operation. The licensee conducted a soil 

survey because the South Radwaste Building was in the main path of the water 

overflows from the cooling tower. Survey results indicated that radioactive 

material was deposited in the soil. Although the majority of the radioactive 

material has been packaged as radwaste and will be subsequently shipped offsite 

(16 boxes each having a volume of 98 cubic feet, containing 85% of the estimated 

activity), a large volume of. low level contaminated soil is contained in the 

fenced area described as the South Radwaste Area. 

Rev 0 

8-1-91 
-2-

The specific area contaminated is noted as Area B on the survey grid map (sed Figure 2). The total activity of this area (5.1 mCi) is based on 6,000 cubic 

feet of soil contaminated with the spoils from the South Radwaste Building. Table 1 lists the principal nuclides identified in the contaminated soil. The 

activity in this table is based on measurements in 1987; see data from a recent 

submittal (Reference 5) shows that activity concentrations in the contaminated 

area have decreased by approximately 10 percent. The radionuclide half-lives, 

which are dominated by 30.-year Cs-137, meet the staff's 10 CFR 20.302 guidelines (Reference 6, which applies to radionuclides with half-lives less than 35 years). 

Nuclide 

Co-60 

Cs-137 

RADIOLOGICAL IMPACTS 

Tab le 1 

Average Concentration (pCi/g) 

0.05 

30 

Total Activity (mCi) 

0.079 

5.0 

Total r.n7§ 

The licensee has evaluated the following potential exposure pathways to members 

of the general public from the radionuclides in the contaminated soil: (1) external exposure caused by direct radiation from radionuclides in the soil; and 

(2) internal exposure from inhalation of resuspended radionuclides. The staff 

has reviewed the licensee's calculational methods and assumptions and finds that 

they are consistent with NRC 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, 11 Revision 1, October 1977. 

The staff finds the assessment methodology_acceptable. The dose assessments are 

based on the following: 

1. 5.1 mCi of contaminated soil distributed over 12,000 square foot 

planar source having a thickness of 0.5 feet {6000 cubic feet 

source volume). 

2. Direct radiation exposure of 2000 hours per year. 

3. Inhalation exposure based on 2000 hours per year is minimized due 

to six-inch layer of gravel {which inhibits wind erosion.) 

4. Groundwater not considered because there are no domestic wells in 

the area down~gradient from the plant. 

Doses calculated from these pathways are shown in Table 2. The total dose of 

0.85 mrem per year is within the staff's guideline of 1 mrem per year {Reference 6). 

Rev 0 

8-l-9l 
Pathway 

Groundshine 

Inhalation 

Groundwater Ingestion 

-3-

Table 2 

Whole Body Dose Received by Maximally Exposed Individual 

(mrem/year} 

0.85 

0.00081 

o.o 

TOTAL 0.85 

The above doses are a small fraction of the 300 mrem received annually by members of the general public in the United States and Canada from sources of 

natural background radiation (Reference 7}. 

Based on our review of the proposed disposal of contaminated soil onsite, we 

conclude that: 

(l} 

(2} 

(3} 

(4} 

(5} 

The radioactive material will be disposed in a manner such that it is 

unlikely that the material will be recycled; 

Doses to the total whole body and any body organ of a maximally exposed individual (a member of the general public or a 

non-occupationally exposed member} from the probable pathways of 

exposure to the disposed material will be less than l mrem per year; 

Doses to the total whole body and any body organ of an inadvertent 

intruder from the probable pathways·of exposure will be less than 5 

mrem per year since the burial location is on company-controlled land; 

The radiation exposures to the nuclear station workers are small 

compared to the routine occupational exposures at the Palisades 

Plant; 

The possible radiation risks to members of the general public as a 

result of such disposal are well below regulatory limits and small in 

comparison to the doses they receive each year from natural background radiation. 

The licensee's procedures and conmitments as documented in the submittal are 

acceptable, provided that they are permanently incorporated into the licensee ~ffsite Dose Calculation Manual (ODCM} as an Appendix, and that future 

modifications be reported to NRC in accordance with the applicable ODCH change protocol. 

Rev 0 

8-1-91 
-4-

REFERENCES 

(1) CPC0 1s letters, T. C. Berdine to NRC Document Control Desk, November 12, 1987 and January 25, 1 988. 

(2) Memorandum from L. J. Cunningham, DREP to T. R. Quay, T. V. Wambach, 11Request for Additiona 1 Information (RAI), 11 March 15, 1988, Apri 1 7, 1989, and January 12, 1990. 

(3) CPCo's supplement to Reference (1), J. L. Kuemin to NRC Document 

Control Desk, June 27, 1988. 

(4) CPCo's supplement to References (1, 2), G. B. Slade to NRC Document 

Control Desk, August 31, 1990. 

( 5) CPCo's letter, T. P. Neal to B. Holian, October 13, 1990. 

(6) E. F. Branagan, Jr. and F. J. Congel, "Disposal of Slightly Contaminated 

Radioacthe Wastes from Nuclear Power Plants," presented at CONF-860203, 

Health Physics Considerations Decontamination Deconmissioning, Knoxville, 

TN, February, 1986. 

(7) National Counci 1 on Radiation Protection and Measurements, "Exposure of the Population in the United States and Canada from Natural 

Background Radiatfon, 11 NCRP Report No. 94, Bethesda, MD. Deceni>er 30, 1987. 

Principal Contributor: J. L. Minns 

Rev O 

8-1-91 
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ATTACHMENT 2 

BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 

2015 RADIOACTIVE EFFLUENT RELEASE REPORT 

This report provides information relating to radioactive effluent releases and solid 

radioactive waste disposal at Big Rock Point (BRP) for the year 2015. The report 

format is detailed in the BRP Offsite Dose Calculation Manual (ODCM). Effluent 

releases from BRP are controlled by the Defueled Technical Specifications and the 

ODCM requirements. The ODCM was not revised in 2015. 

2015 Operating History 

On January 8, 2007, the Nuclear Regulatory Commission (NRC) approved release of 

the former BRP nuclear plant property for unrestricted use in accordance with the BRP 

License Termination Plan 1

• On April 11, 2007, the license for BRP, DPR-06, was 

transferred to Entergy Nuclear Operations, Inc. 

During 2015, normal independent spent fuel storage installation (ISFSI) operations 

continued. There were no operational activities that generated any solid radioactive 

waste. 

Liquid and gaseous effluent monitoring is no longer conducted as the former BRP 

nuclear plant property has been released from the license. Short-lived radionuclides, 

including iodine and noble gas, are neither expected nor reported. 

1. Supplemental Information 

A. Batch Releases 

There were no batch releases of gaseous or liquid effluents during 

2015. All batch releases of radioactive liquids as described in the 

ODCM ceased in 2004. 

B. Abnormal Releases 

There were no abnormal releases from BRP during 2015. 

C. Radioactive Effluent Monitoring Instrumentation 

BRP ODCM currently specifies required actions when less than the 

minimum numbers of radioactive effluent monitoring instrument 

channels are operable. The ODCM also specifies these actions be 

taken when installed effluent monitoring systems are removed from 

service for decommissioning. 

All plant-installed liquid and gaseous radioactive effluent monitoring 

instrument channels have been permanently removed and dismantled. 

1 Letter from the USN RC dated January B, 2007, "Release of Land from Part 50 License for Unrestricted Use" 

Page 1 of 2 
2. Gaseous Effluents 

Although there were no gaseous effluents released during 2015, Table 2 

provides a summary of all gaseous radioactive effluent monitoring conducted 

during the reporting period as required by the ODCM. 

3. Liquid Effluents 

There were no liquid effluent batch releases during 2015. Table 3 lists and 

summarizes liquid effluent releases in accordance with the ODCM. 

4. Solid Waste 

There was no solid radioactive waste generated or shipped during 2015. 

5. Summary of Radiological Impact on Man 

The ODCM specifies that the annual effluent release report provide potential dose 

calculations based on measured effluent to liquid and gaseous pathways, if 

estimates of dose exceed one millirem to an organ or total body of any individual or 

more than one person-rem to the population within 50 miles. During 2015, there 

were no releases. Therefore, no calculations were required. 

6. Offsite Dose Calculation Manual 

The ODCM describes the radiological release requirements for the BRP site. 

There were no revisions to the ODCM in 2015. 

7. Process Control Program (PCP) 

The Process Control Program (PCP) describes solid waste processing and 

disposal methods utilized at the BRP site. The PCP was not revised during 2015. 

Page 2 of 2 
A.GASEOUS 

Number of Releases 

Total Release Time 

Maximum Release Time 

Average Release Time 

Minimum Release Time 

B. LIQUID 

Number of Releases 

Total Release Time 

Maximum Release Time 

Average Release Time 

Minimum Release Time 

TABLE 1 

Big Rock Point 

Batch Releases 

January 1, 2015 to December 31, 2015 

Units 1ST QTR 2NDQTR 3RD QTR 

N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Units 1ST QTR 2NDQTR 3RD QTR 

N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Page 1 of 1 

4TH QTR 

N/A 

N/A 

N/A 

N/A 

N/A 

4TH QTR 

N/A 

N/A 

N/A 

N/A 

N/A 
TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1, 2015 to December 31, 2015 

1ST 2ND 

A. FISSION AND ACTIVATION GASES Units QTR QTR 

1. Total release Ci N/A N/A 

2. Average release rate for period μCi/sec N/A N/A 

3. Percent of annual ava EC % N/A N/A 

B. IODINES 

1. Total iodine Ci N/A N/A 

2. Averaqe release rate for period μCi/sec N/A N/A 

3. Percent of annual avi:i EC % N/A N/A 

C. PARTICULATES 

1. Particulates with half-life >8 dav Ci N/A N/A 

2. Averaae release rate for period uCi/sec NIA NIA 

3. Percent of annual avi:i EC % NIA NIA 

4. Gross alpha radioactivity Ci NIA NIA 

D. TRITIUM 

1. Total Release Ci NIA NIA 

2. Averaae release rate for period uCi/sec NIA NIA 

3. Percent of annual avi:i EC % NIA NIA 

E. WHOLE BODY DOSE 

1. Beta Air dose at Site Boundary due to Noble Gases 

(ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA 

2. Percent limit % NIA NIA 

3. Gamma Air dose at Site Boundary due to Noble 

Gas (ODCM Section 1, 1.3.2 a (1) (2)) mrads NIA NIA 

4. Percent limit % N/A N/A 

F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2)) 

1. Maximum organ dose to pubic based on Critical 

Receptors (child bone) mrem NIA NIA 

2. Percent of limit (7.5 mrem/quarter) % N/A NIA 

Page 1 of 3 

3RD 4TH Es!Total 

QTR QTR Error% 

N/A N/A 

N/A N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A N/A 

N/A N/A 

N/A N/A 

NIA NIA NIA 

NIA NIA 

NIA NIA 

NIA NIA 

NIA NIA 

NIA NIA 

NIA NIA 

N/A NIA 

NIA NIA 

NIA NIA 

NIA NIA 

NIA NIA 
1. FISSION GASES 

Krypton-85m 

Krvoton-87 

Krvoton-88 

Xenon-133 

Xenon-133m 

Xenon-135 

Xenon-135m 

Xenon-138 

Total for Period 

2. IODINES 

lodine-131 

lodine-132 

lodine-133 

lodine-134 

lodine-135 

Total for Period 

TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1, 2015 to December31, 2015 

Units 1STQTR 2ND QTR 3RDQTR 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Page 2 of 3 

4TH QTR 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 
3. PARTICULATES* 

Chromium-51 

Manrianese-54 

Cobalt-58 

lron-59 

Cobalt-60 

Zinc-65 

Silver-11 Om 

Cesium-134 

Cesium-137 

Barium-140 

Europium-152 

Strontium-89 

Stronlium-90 

Net unidentified beta 

Total 

TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1, 2015 to December 31, 2015 

Units 1STQTR 2NDQTR 3RDQTR 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

* Particulates with half-life >8 days 

Page 3 of 3 

4TH QTR 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 
TABLE 3 

Big Rock Point 

Liquid Effluent Releases 

January 1, 2015 to December 31, 2015 

A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2ND QTR 

1. Total release (not includina tritium, aases, aloha) Ci N/A N/A 

2. Averaae diluted concentration durina period uCi/ml N/A N/A 

3. Percent of EC % N/A N/A 

B TRITIUM 

1. Total release Ci N/A N/A 

2. Averaae diluted concentration durina oeriod uCi/ml N/A N/A 

3. Percent of EC % N/A N/A 

C DISSOLVED AND ENTRAINED GASES 

1. Total release Ci N/A N/A 

2. Averaae diluted concentration durina period uCi/ml N/A N/A 

3. Percent of EC % N/A N/A 

D. GROSS ALPHA RADIOACTIVITY Ci N/A N/A 

E. VOLUME OF WASTE RELEASED 

(Prior to dilution) Liters N/A N/A 

F. VOLUME OF DILUTION WATER USED DURING 

PERIOD Liters N/A N/A 

G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem N/A N/A 

' 

Percent of ODCM Section 1, 2.3.2 a (1.5 mrem) % N/A N/A 

H. MAXIMUM DOSE COMMITMEtilT - ORGAN Mrem N/A N/A 

Percent of ODCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A 

Page 1 of 2 

Es!Total 

3RD QTR 4TH QTR Error% 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 
1. NUCLIDES 

RELEASED 

Chromium-51 

Manoanese 54 

Cobalt-58 

lron-59 

Cobalt-60 

Zinc-65 

Strontium-89 

Strontium-90 

Molvbdenum-99 

Silver-110m 

lodine-131 

Cesium-134 

Cesium-137 

Antimony-125 

Tin-113 

Net Unidentified Beta 

Fission & Activation 

Product Total 

Xenon-133 

Tritium 

Grand Total 

TABLE 3 

Big Rock Point 

Liquid Effluent Releases 

January 1, 2015 to December 31, 2015 

Units 1STQTR 2NDQTR 3RD QTR 

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Ci -- -- --

Page 2 of 2 

4THQTR 

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