Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant E’ntei 27780 Blue Star Memorial Highway

Covert, Ml 49043

Tel 269 764 2000

Otto W. Gustafson

Licensing Manager

PNP 2012-032

April 26, 2012 10 CFR 50.36a

U. S. Nuclear Regulatory Commission

ATTN: Document Control Desk

Washington, DC 20555-0001

Subject: 2011 Annual Radioactive Effluent Release and Waste Disposal Report

Palisades Nuclear Plant Big Rock Point

Docket 50-255 Dockets 50-1 55 and 72-043

License No. DPR-20 License No. DPR-6

Dear Sir or Madam:

Attached are the Entergy Nuclear Operations, Inc. 2011 Annual Radioactive Effluent

Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock

Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are

submitted in accordance with 10 CFR 50.36a(a)(2).

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, 2011, through December 31, 2011.
Document Control Desk

Page 2

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

Sincerely,

OWG/bed

Attachment 1: Palisades Nuclear Plant 2011 Radioactive Effluent Release Report

Attachment 2: Big Rock Point Independent Spent Fuel Storage Installation 2011

Radioactive Effluent Release Report

CC Administrator, Region Ill, USNRC

Project Manager, Palisades, USNRC

Resident Inspector, Palisades, USN RC

NRC NMSS Project Manager

American Nuclear Insurers (ANI)
ATTACHMENT 1

PALISADES NUCLEAR PLANT

2011 RADIOACTIVE EFFLUENT RELEASE REPORT

2011 Plant Oneratina History

Palisades Nuclear Plant (PNP) entered the reporting period on line on January 1, 2011,

at nominal full power (NFP). PNP reduced power to approximately 54% on

January 8, 2011, due to failure of breaker 252-302, that resulted in loss of cooling tower

pump P-39A. On January 16, 2011, the plant returned to NFP. PNP tripped on

January 22, 2011, due to a ground fault from one of the main generator cables. The

unit returned to NFP on January 25, 2011. PNP reduced power to 52% on

March 16, 2011, to perform electrical cable testing for startup transformers. The unit

returned to NFP on March 18, 2011. PNP began reducing power and subsequently

manually tripped the unit on September 16, 2011, due to exceeding 10 gallons per

minute unidentified leakage from the primary coolant system. The unit returned to NFP

on September 21, 2011. An automatic reactor trip occurred on September 25, 2011,

due to a loss of two of the four preferred AC buses. The unit returned to NFP on

October 3, 2011. The unit was manually tripped on December 14, 2011, due to main

feed pumps tripping on low suction pressure. The unit returned to NFP on

December 17, 2011. PNP was on line for the remainder of 2011. The unit generated

6,641,013 MWHrs of net electrical energy during 2011.

A. Gaseous Effluents

Tables A-i, “Gaseous Effluents — Summation of All Discharges,” A-iA, “Gaseous

Effluents — Ground-Level Release — Batch Mode,” and A-i B, “Gaseous Effluents —

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

released during this reporting period.

B. Liquid Effluents

Tables A-2, “Liquid Effluents — Summation of All Discharges,” A-2A, “Liquid

Effluents — Batch Mode,” and A-2B, “Liquid Effluents — Continuous Mode,” list and

summarize liquid effluents released during this reporting period.

C. Solid Waste Storage and Shipments

Table A-3, “Low-Level Waste for Waste Classification A, B and C, summarizes

solid radioactive waste shipped for processing or burial in 2011 for the following

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

components, other waste, and sum of all waste.

Page 1 of 6
D. Dose Assessments

Tables A-4, “Dose Assessments, 10 CFR Part 50, Appendix li” and A-5, “EPA

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

members of the public.

E. Sulemental Information

Abnormal Discharges

In December 2007, tritium was detected in a groundwater monitoring well at

a level of 22,000 pCi/L. The source of the activity is leakage associated with

T-91, the utility water storage tank, and associated piping. T-91 is used to

store processed liquid waste prior to discharge. No radionuclides other than

tritium have been detected in the groundwater.

Additional repair of underground piping was performed during the spring of

2011. The overflow line to T-91 was sleeved to ensure piping integrity. This

line was assumed to be dry, based on all indication, but contained highly

tritiated water of which a small amount was expelled during the sleeving

operation. This resulted in an additional release of tritiated water to the

groundwater which caused spiking in monitoring well 3. This event is further

discussed under section 9 of this report.

Monitoring of the groundwater tritium plume continues in order to determine

repair effectiveness and to ensure the accuracy of the site hydrology.

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

Classification of Subsurface Aquifers — Not used for drinking water.

Expected Movement/Mobility of Groundwater Plume — Westerly direction

down-gradient toward Lake Michigan at approximately two feet per day.

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

irrigation.

NRC Notification, Date and Contact Organization — The NRC was notified on

December 10, 2007, by PNP.

2. Non-Routine Planned Discharges

None.

Page 2 of 6
3. Radioactive Waste Treatment System Changes

None.

4. Annual Land Use Census Changes

The garden critical receptor is now located in the southeast sector at 1.47

miles. The residence critical receptor is unchanged. Also unchanged is that

there are no beef cattle, dairy cows or goats located within five miles of the

plant.

5. Effluent Monitoring System Inoperability

There were no effluent monitors that were out of service for greater than 30

days.

6. Offsite Dose Calculation Manual (00CM) Changes

The Offsite Dose Calculation Manual was revised during the report period.

The Offsite Dose Calculation Manual, Appendix A, was revised twice during

the report period. The General Manager Plant Operations approval is

documented on the procedure cover page.

These revisions did not reduce the accuracy or reliability of dose calculations

or setpoint determinations. Enclosure 1 contains a copy of the ODCM

revision, as well as copies of ODCM, Appendix A revisions 16 and 17, with

changes indicated by marginal markings.

7. Process Control Program Changes

None.

8. Errata/Corrections to Previous Reports

Attachment 1, Table A-i B, Gaseous Effluents - Ground Level Release,

Continuous Mode Revised for 2010 data is supplied here in its entirety and

is associated with CR-PLP-201 1-05094. The 2010 data for Table A-i,

Gaseous Effluents - Sum of all releases remains correct.

Page 3 of 6
Section E. Supplemental Information, 1. Abnormal Discharges to the 2010

report was updated per the guidance of CR-PLP-201 1-5094 and is provided

here as follows:

In December 2007, tritium was detected in a groundwater monitoring well at

a level of 22,000 pCiIL. The source of the activity is leakage associated with

T-91, the utility water storage tank, and associated piping. T-91 is used to

store processed liquid waste prior to discharge. No radionuclides other than

tritium have been detected in the groundwater. Tritium is still being released

to the environment (Lake Michigan) via an unmonitored pathway, as

demonstrated by the continued detection of monitoring well sample

activityPiping leaks associated with T-91 have been repaired and monitoring

of the groundwater tritium plume continues in order to determine repair

effectiveness and to ensure site hydrology accuracy. However, repairs h-ave

been made and tlritium concentrations have dropped to approximately 90%

of values detected in previous years. A definitive release rate or total activity

released cannot be determined.

Section D. Dose Assessments, of the 2010 report was updated per the

guidance of CR-PLP-2011-5094 and is provided here as follows:

Tables A-4, “Dose Assessments, 10 CFR Part 50, Appendix I,” and A-5,

“EPA 40 CFR Part 190, Individual in the Unrestricted Area,” lists annual

dose to the members of the public. A methodology change was made in

determining the radionuclides released through the Main Stack. The Stack

radionuclides were linked directly to PrimaR’ Coolant System gas sample

results instead of being considered all Xe-133. This change led to

approximately seven additional radionuclides being considered as released.

These additional radionuclides have different dose conversion factors which

had a direct impact on the calculated beta and gamma doses.

Conceriatively, 0.5% of the total tritium activity roleacod via batch releases,

or half of the percentage that was used in 2007, 2008, and 2009, was used

for 2010 effluent calculations.

9. Other

Groundwater Monitoring

PNP installed five groundwater monitoring wells in 2007, and added an

additional nine wells in 2008. These wells were strategically placed within

the owner controlled area, both inside and outside the protected area to

allow detection of radioactive contamination of ground water due to leaks or

spills from plant systems. Monitoring well (MW) 3 is most indicative of the

leak described in the Abnormal Discharges section. Tritium levels for 2011

Page 4 of 6
in MW3 ranged from less than minimum detectable activity (MDA) to 19,854

pCi/L. Monitoring wells MW2 and MW1 1 tritium levels ranged from <MDA

to 1,888 and 3,850 pCi/L respectively. The remaining wells showed no

activity throughout the year. The spike in MW3 was associated with

additional work done on T-91 piping during 2011. Well locations are

depicted in Figure 1.

Carbon-14

In 2010, PNP and other facilities participated in an EPRI task force to build a

model to accurately estimate gaseous C-14 releases, given some key sitespecific plant parameters (mass of the primary coolant, average thermal

neutron cross section, rated MW, etc). This work was completed in

November 2010. The estimates for C-i 4 were constructed using the

aforementioned EPRI methodology contained with EPRI 1021106,

Estimation of Carbon-i4 in Nuclear Power Plant Gaseous Effluents. Using

the C-14 curie estimates, the annual dose to man was derived from

guidance contained within Regulatory Guide 1.109. Because the dose

contribution of C-14 from liquid radioactive waste is much less than that

contributed by gaseous radioactive waste, evaluation of C-14 in liquid

radioactive waste is not required. (Reg Guide 1.21, Rev 2)

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

Total Gaseous C-14 Released Curies = 8.13

Gaseous C-14 as C02 Curies = 2.44

Effective Child TB Dose, C-14 mrem 0.0219

Effective Child Bone Dose, C-14 mrem = 0.110

The quarterly curies released are provided in Tables A-iA and A-lB.

Airborne doses due to C-14 are grouped under the category of Particulate,

Iodine, and Tritium, which are contained in Table A-4.

Page 5 of 6
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ATTACHMENT 1

Palisades -Table A-i

2011 Gaseous Effluents — Sum of All Releases

Summation of

Units Quarter Uncertainty All Releases 1 Quarter 2 Quarter 3 Quarter 4 Total (%)

Fission and

Activation

Gases Ci 4.97E-01 9.47E-01 5.30E+00 3.65E+00 1.04E+O1

Average

Release Rate pCi/s 6.40E-02 1 .20E-O1 6.66E-01 4.60E-01 3.30E-O1

% of Limit 7.46E-04 8.57E-04 1 .60E-03 6.81 E-03 2.52E-03

Total 1-131 Ci 7.47E-05 2.66E-05 6.27E-05 8.29E-05 2.47E-04

Average

Release Rate pCi/s 9.61 E-06 3.38E-06 7.88E-06 1.04E-05 7.83E-06

% of Limit 1.16E-05 408E-06 9.50E-06 1.26E-05 9.43E-06

Particulates Ci 8.1 1 E-07 1 .01 E-07 4.91 E-05 0.OOE+00 5.OOE-05

Average

Release Rate pCi/s 1.04E-07 1.28E-08 6.17E-06 0.OOE÷00 1.58E-06

% of Limit % 1 .24E-07 3.80E-08 5.93E-05 0.OOE+00 1 .50E-05

Tritium Ci 5.37E÷00 4.84E÷00 4.48E+00 3.96E-i-00 1 .87E÷01

Average

Release Rate pCi/s 6.91E-01 6.16E-01 5.64E-01 4.98E-01 5.91E-01

4.08

% of Limit 1 .66E-03 1 .48E-03 1 .36E-03 1 .20E-03 1 .43E-03

GrossAlpha Ci ND 1.89E-06 1.19E-07 1.70E-07 2.18E-06

C-14 Ci 1.96E+00 2.15E+00 1.92E+00 2.1OE+00 8.13E+00

Average

Release Rate pCi/s 2.52E-01 2.73E-01 2.42E-01 2.64E-01 2.58E-01

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

Page 1 of 1
ATTACHMENT 1

Palisades - Table A-i A

2011 Gaseous Effluents — Ground Level Release, Batch Mode

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

Gases

Ar-41 Ci ND ND ND ND

Kr-85 Ci ND ND ND ND

Kr-85m Ci ND ND ND ND

Kr-87 Ci ND ND ND ND

Kr-88 Ci ND ND ND ND

Xe-131m Ci 4.29E-04 1.23E-02 3.08E-02 2.79E-03

Xe-133 Ci 1.96E-02 3.11E-01 3.70E+00 2.39E-01

Xe-133m Ci ND ND 3.13E-02 2.95E-03

Xe-135 Ci ND ND 1.39E-01 ND

Xe-135m Ci ND ND ND ND

Xe-i 38 Ci ND ND ND ND

Total Ci 2.01 E-02 3.23E-01 6.85E+00 2.45E-01

Units

Ci

Ci

Ci

Ci

Ci

Quarter 1

ND

ND

ND

ND

ND

Ci 0.OOE+00

Quarter 3

9.54E-07

ND

9.21 E-07

ND

ND

1 .88E-06

Quarter 4

1 .68E-06

ND

ND

ND

ND

1 .68E-06

Quarter 1

ND

ND

ND

ND

ND

ND

0.00E+00

Quarter 3

2.1 9E-05

3.39E-06

1.08E-05

5. 64E-06

9.34E-06

ND

4.91 E-05

Quarter 4

ND

ND

ND

ND

ND

ND

0.000E+00

Tritium Ci NA NA 2.21 E-01 NA

I Gross Alpha Ci NA NA NA I NA

C-14 J Ci NA NA NA NA

ND Measurements performed but no activity detected.

NA = Analysis not required and not performed.

lodines/Halogens

1-131

1-132

1-133

1-134

Quarter 2

1-135

ND

Total

ND

ND

ND

Particulates

Co-58

ND

Co-60

Units

0.OOE+00

Cr-Si

Ci

Nb-95

Ci

Quarter 2

Zr-95

Ci

ND

Cs-i 37

Ci

ND

Total

Ci

ND

Ci

ND

Ci

ND

ND

0.OOE+00

Page 1 of 1
2011 Gaseous

ATTACHMENT 1

Palisades -Table A-i B

Effluents — Ground Level Release, Continuous Mode

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

Gases

Ar-41 Ci 8.03E-02 3.27E-02 4.66E-02 i.38E+OO

Kr-85 Ci ND ND ND ND

Kr-85m Ci 3.86E-03 i.03E-02 4.73E-03 2.27E-02

Kr-87 Ci i.61E-02 3.50E-02 2.18E-02 3.92E-02

Kr-88 Ci 4.59E-02 6.76E-02 i.03E-O1 2.81E-O1

Xe-131m Ci ND ND ND ND

Xe-133 Ci 7.45E-03 i.35E-02 ND 6.28E-02

Xe-133m Ci ND ND ND ND

Xe-135 Ci l.29E-Oi 1.80E-O1 8.08E-O1 6.33E-O1

Xe-135m Ci 6.13E-02 8.58E-02 2.35E-O1 2.44E-Oi

Xe-138 Ci 1.33E-O1 i.99E-Oi 1.75E-O1 7.42E-Ol

Total Ci 4.77E-O1 6.24E-Oi 1.39E+OO 3.41 E+OO

dines/Halogens

1-13 1

1-132

1-133

1-134

1-135

Total

U n its

Ci

Ci

Ci

Quarter 1

7.47E-05

ND

9.23E-05

ND

ND

7.47E-05

Quarter 2

2.66E-05

ND

5.23E-05

ND

ND

7.89E-05

Quarter 3

6.1 7E-05

ND

1 .76E-04

ND

ND

2.38E-04

Ci

Ci

Ci

Quarter 4

8.12E-05

ND

1 .98E-04

ND

ND

2.80E-04

Particulates

Co-58

Co-60

Sr-89

Ag-hOrn

Cs-i 34

Cs-i37

Total

Tritium jCi j 5.37E+OO 4.84E+OO 4.26E+OO 3.96E+OO

GrossAlpha Ci ND 1.89E-06 1.19E-07 i.70E-07

C-14 Ci 1.96E÷OO 2.i5E+OO 1.92E+OO 2.iOE+OO

ND = Measurements performed but no activity detected.

Units

Ci

Quarter 1

Ci

1.51 E-08

Quarter 2

ND

Ci

ND

Quarter 3

ND

Ci

ND

4.90E-08

Quarter 4

ND

Ci

ND

ND

ND

Ci

ND

ND

ND

5.20E-08

Ci

ND

ND

ND

7.96E-07 ND

ND

8.iiE-07

ND

ND

ND

1.01 E-07

ND

0.OOE+OO O.OOE+0O

Page 1 of 1
ATTACHMENT 1

Palisades -Table A-i B

I 2011 2010 Revised Gaseous Effluents — Ground Level Release, Continuous Mode

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

Gases

Ar-41 1560E-Oi 2.785E-Oi 5.591E+OO 1.800E÷OO

Kr-85 ND ND ND ND

Kr-85m 6.227E-02 5.112E-02 2.851E-O1 i.149E-03

Kr-87 Ci 1 .638E-Oi 1 .397E-Oi 9.585E-Oi 3.328E-03

Kr-88 2.030E-Oi 1.343E-Oi i.126E+OO 5.918E-O1

Xe-i 31 m ci ND ND ND

Xe-i33 9.i62E-Oi 5.23iE+OO 1,497E+OO 1.O3iE÷Oi

Xe-i33m Gi ND ND ND ND

Xe-i35 Ci 7048E-Oi i.816E+OO 3.8i3E÷OO 3.728E÷OO

Xe-i35m 2.594E-Oi 9.343E-Oi i.529E+OO 2.423E-02

Xe-i 38 6697E-Oi 4.755E-Oi 4.066E÷OO 7499E-02

Total Ci 3.135E+OO 9.O6iE+OO 1.887E+Oi i.653E+O1

lodines/Haloaens

1-131

1-132

1-133

1-134

1-135

Total

Particulates

Co-58

Co-60

Sr-89

Sr-90

Cs-i 34

Cs-i 37

Total

Units

Ci

Ci

Ci

Ci

Ci

Ci

Units

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Quarter 1

7.439E-05

ND

Quarter 1

2.007E-04

ND

ND

2.75 1 E-04

ND

ND

ND

ND

ND

1 .094E-08

1 .094E-08

Quarter 2

6.465E-04

ND

2.990E-04

ND

ND

9.455E-04

Quarter 2

ND

ND

ND

ND

ND

ND

O.000E+OO

Quarter 3

6.027E-04

ND

2.389E-04

ND

ND

8.41 6E-04

Quarter 3

ND

8.61 OE-08

ND

ND

ND

ND

8.61 OE-08

Quarter 4

3.872E-03

3.975E-03

2.300E-04

ND

ND

8.077E-03

Quarter 4

1 .510E-06

ND

ND

ND

ND

ND

1 .510E-06

I Tritium I 5.144E+OO 4.693E+OO 4.873E+OO 7.726E+OO

Gross Alpha Ci 5.125E-O7jND ND 5511 E-07

C-14 I C 2.117E+OO 1.980E+OO 2.099E+OO i.495E+OO

ND = Measurements performed but no activity detected.

Page 1 of 1
ATTACHMENT 1

Palisades - Table A-2

2011 Liquid Effluents — Sum of All Releases

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

Summation of All

Liquid Releases Uncertainty

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 Total (%)

Fission and

Activation

Products

(excluding tritium,

gases, and gross

alpha) Ci 4.55E-03 1.65E-03 1.56E-03 1.29E-02 2.06E-02

Average

Concentration pCi/mi 1.17E-10 4.28E-11 4.1OE-11 5.73E-10 1.50E-10

% of Limit % 1 .26E-03 7.09E-04 6.34E-04 4.04E-03 1 .39E-03

Tritium Ci 6.98E÷01 5.47E+01 1.63E÷02 3.12E+02 6.OOE+02

Average

Concentration pCi/mi 1 .79E-06 1 .42E-06 4.30E-06 1 .39E-05 4.34E-06

% of Limit % 1 .79E-01 1 .42E-01 4.30E-01 1 .39E÷00 4.34E-01

Dissolved and

Entrained Gases Ci 0.OOE+00 0.OOE+00 0.OOE÷00 6.08E-04 6.08E-04

Average

Concentration pCi/mi 0.OOE÷00 0.OOE÷00 0.OOE÷00 2.71E-11 4.41E-12

% Of Limit 0.OOE+00 0.OOE÷00 0.OOE+00 1 .35E-05 2.20E-06

Gross Alpha Ci 7.85E-06 0.OOE+00 2.OOE-05 1 .69E-05 4A8E-05

Average

Concentration pCi/mi 2.O1E-13 0.OOE+00 5.27E-13 7.54E-13 3.24E-13

Volume of

Primary System

Liquid Effluent

(Before Dilution) Liters 3.49E+05 2.34E+05 8.22E+05 1 .07E+06 2.48E+06

Dilution Water

Used for Above Liters 3.90E÷1 0 3.86E÷1 0 3.79E+1 0 2.25E+1 0 1 .38E+1 1

Volume of

Secondary or

Balance-of-Plant

Liquid Effluent

(e.g., low-activity

or unprocessed)

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

Average Stream

Flow m3/s 5.02E+00 4.91 E+00 4.77E+00 2.83E÷00 4.38E+00

Page 1 of 1
ATTACHMENT 1

Palisades -Table A-2A

2011 Liquid Effluents — Batch Mode

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

Products

Cr-51 Ci ND ND ND ND

Mn-54 Ci ND ND ND 2.35E-04

Fe-55 Ci 7.82E-04 i.80E-04 2.86E-04 4.80E-04

Fe-59 Ci ND ND ND ND

Co-57 Ci ND ND ND ND

Co-58 Ci i.67E-03 1.56E-04 9.77E-05 4.19E-03

Co-60 Ci 9.68E-04 5.29E-04 4.11E-04 1.40E-03

Sr-89 Ci ND 1.24E-05 4.08E-06 2.50E-05

Sr-90 Ci ND ND ND 4.90E-05

Nb-95 Ci i.31E-04 ND ND ND

Ag-il Om Ci 2.45E-04 4.99E-04 3.30E-04 2.09E-04

Sn-1i3 Ci ND ND ND ND

Sb-124 Ci ND ND ND ND

Sb-125 Ci ND ND ND ND

1-131 Ci ND ND ND ND

1-133 Ci ND ND ND ND

1-135 Ci ND ND ND ND

Cs-134 Ci ND ND ND ND

Cs-137 Ci ND ND 2.43E-05 1.89E-05

Ni-63 Ci 6.25E-04 1.12E-04 3.90E-04 6.27E-03

Zn-65 Ci ND ND ND ND

Zr-95 Ci 2.49E-04 ND ND ND

La-140 Ci ND ND ND ND

Totals Ci 4.53E-03 i.49E-03 i.54E-03 1.29E-02

Quarter 2

ND

ND

ND

ND

ND

Quarter 3

ND

ND

ND

ND

ND

0.00E÷00

Quarter 4

ND

ND

6.08E-04

ND

ND

6.08E-04

Tritium j Ci 6.98E÷Oi 5.47E÷01 1.63E+02 3.12E+02

, Gross Alpha Ci 7.85E-06 ND 2.OOE-05 1 .69E-05

ND = None Detected

Dissolved and

Entrained Gases

Kr-85

Un its

Xe-i 31rn

Quarter 1

Ci

Xe-i 33

ND

Ci

Xe-i 33m

Ci

ND

Xe-i35

Totals

Ci

ND

Ci

ND

ND

0.00E+00 0.OOE+00

Page 1 of 1
ATTACHMENT 1

Palisades -Table A-2B

2011 Liquid Effluents — Continuous Mode

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

Products

Cr-51 Ci ND ND ND ND

Mn-54 Ci ND ND ND ND

Fe-55 Ci ND ND ND ND

Co-58 Ci ND ND ND ND

Co-60 Ci 8.78E-07 ND ND ND

Sr-89 Ci ND ND ND ND

Sr-90 Ci ND ND ND ND

Nb-95 Ci ND ND ND ND

Ag-ibm Ci ND ND ND ND

Sn-113 Ci ND ND ND ND

Sb-124 Ci ND ND ND ND

Sb-125 Ci ND ND ND ND

1-131 Ci ND ND ND ND

1-133 Ci ND ND ND ND

1-135 Ci ND ND ND ND

Cs-i 34 Ci ND ND ND ND

Cs-137 Ci 2.iOE-05 ND i.20E-05 ND

Ni-63 Ci ND i.63E-4 ND ND

Totals Ci 2.19E-05 i.63E-4 120E-05 O.OOE-i-OO

Dissolved and

Entrained Gases

Kr-85

Xe-i 33

Xe-i 33m

Xe-i 35

Xe-i 35m

Totals

Un its

Ci

Ci

Ci

Ci

Ci

Quarter 1

ND

ND

ND

ND

ND

O.000E+OO

ND

ND

Tritium Ci 2.59E-02 4.07E-02 I 4.41 E-02 8.i2E-03

Gross Alpha Ci ND ND ND ND

ND = None Detected

Quarter 2 Quarter 3

ND

Quarter 4

ND

ND

ND

ND

ND

ND

ND

ND

ND

ND

ND

O.000E+OO

ND

0. 000E+00 0.000E+00

Page 1 of 1
ATTACHMENT 1

Palisades - Table A-3

2011 Low Level Waste

Resins, Filters, and Volume Curies Shipped

Evaporator Bottoms

Waste Class ft3 m3 Curies

A 3.41 E÷02 9.66E+00 8.80E-04

B 1 .60E÷02 4.53E÷00 2.74E+02

C 0.OOE+00 0.OOE+00 0.OOE+00

ALL 5.01 E+02 i.42E+0i 2.74E+02

Major Nuclides for the Above Table: Mn-54 (2%), Fe-55 (2%), Co-58 (16%), Co-60 (45%),

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

Dry Active Waste Volume Curies Shipped

Waste Class ft3 m3 Curies

A 8.95E+03 2.54E+02 7.43E-01

B 1.47E+01 4.16E-Oi 1.03E+00

C 9.32E+00 2.64E-0i 3.20E+00

ALL 8.97E÷03 2.55E÷02 4.97E+00

Major Nuclides for the Above Table: H-3 (13%), C-i 4 (2%), Fe-55 (14%), Co-58 (1 %), Co-60 (7%), Ni-63 (59%), Sr-gO (1%), Ag-ibm (1%), & Cs-i 37 (2%)

Irradiated Components Volume Curies Shipped

Waste Class ft3 m3 Curies

A 0.OOE+00 0.OOE÷00 0.OOE+00

B 0.OOE+00 0.OOE+0O 0.OOE+00

C 0.OOE÷00 0.OOE+00 0.OOE+00

ALL 0.OOE+00 0.OOE+00 0.OOE+00

Major Nuclides for the Above Table:

Other Waste: Used oil & soil Volume Curies Shipped

Waste Class ft3 m3 Curies

A 1 .73E+03 4.90E+01 3.23E+00

B 0.OOE÷00 0.OOE+00 0.OOE+00

C 0.OOE+00 0.OOE+00 0.OOE+00

ALL 1.73E÷03 4.90E÷01 3.23E÷00

Major Nuclides for the Above Table: H-3 (47%), Fe-55 (7%), Co-58 (ii %), Co-60 (7%),

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

Page 1 of 2
ATTACHMENT 1

Palisades -Table A-3

2011 Low Level Waste

Sum of All Low-Level Volume Curies Shipped

Waste Shipped from

Site

Waste Class ft3 m3 Curies

A 1.1OE+04 3.13E+02 3.97E+OO

B 1 .75E+02 4.95E--OO 2.75E+02

C 9.32E+OO 2.64E-O1 3.20E+OO

ALL 1.12E+04 3.18E÷02 2.82E+02

Major Nuclides for the Above Table: H-3 (1%), Mn-54 (3%), Fe-55 (2%), Co-58 (16%),

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

Page 2 of 2
ATIACHMENT 1

Palisades -Table A-4

2011 Dose Assessments, 10 CFR Part 50, Appendix I

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly

Liquid Effluent Dose Limit, Total 1 .5 mrem 1.5 mrem 1.5 mrem 1 .5 mrem 3 mrem

Body

Total Body Dose 4.66E-04 2.74E-04 3.05E-04 1 .45E-03 2.50E-03

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

Liquid Effluent Dose Limit, Any 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem

Organ

Organ Dose 9.74E-04 2.80E-04 3.53E-04 2.62E-03 4.23E-03

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

Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad

Gamma Air

Gamma Air Dose 2.48E-04 3.17E-04 5.87E-04 2.01 E-03 3.16E-03

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

Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad

Beta Air

Beta Air Dose 1 .22E-04 1 .90E-04 6.1 OE-04 8.70E-04 1 .79E-03

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

Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem

Organ (Iodine, Tritium,

Particulates with >8 day half-life)

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

>8-Day half-life)

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

Palisades -Table A-5

2011 EPA 40 CFR Part 190, Individual in the Unrestricted Area

Whole Body Thyroid Any Other Organ

Dose Limit 25 mrem 75 mrem 25 mrem

Dose 6.29E-02 6.82E-03 4.23E-03

% of Limit 0.25% 0.01% 0.02%

Page 1 of 1
ENCLOSURE 1

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL, REVISION 25

OFFSITE DOSE CALCULATION MANUAL, APPENDIX A, REVISION 16

OFFSITE DOSE CALCULATION MANUAL, APPENDIX A, REVISION 17

202 Pages Follow
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

ODCM

Revision 25

Issued Date 12129111

TITLE: OFFSITE DOSE CALCULATION MANUAL

Process Applicability Exclusion Li

DWFoster I 12128/11

Procedure Sponsor Date

JJMiller I 12115111

Technical Reviewer Date

JHager I 12I1 5111

User Reviewer Date

DHamilton

General Manager Plant Operations

I 12/19111

Date
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Table of Contents

GASEOUS EFFLUENTS I

A. ALARMITRIP SETPOINT METHOD I

1. Allowable Concentration 2

2. Monitor Response 3

B. DOSE RATE CALCULATION 4

C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION 19

1. System Description 19

2. Determination of Satisfactory Operation 19

D. RELEASE RATE FOR OFFSITE EC 20

E. PARTICULATE AND IODINE SAMPLING 20

F. NOBLE GAS SAMPLING 21

G. TRITIUM SAMPLING 21

H. FIGURE — GASEOUS EFFLUENTS FLOW PATHS 22

LIQUID EFFLUENTS 23

A. CONCENTRATION 23

1. Requirements 23

2. Prerelease Analysis 23

3. Effluent Concentration (EC) - Sum of the

Ratios 24

B. INSTRUMENT SETPOINTS 25

1. Setpoint Determination 25

2. Composite Samplers 25

3. Post-Release Analysis 26

C. DOSE 26

1. RETS Requirement 26

2. Release Analysis 26

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT 30

E. RELEASE RATE FOR OFFSITE EC (50 MREMIYR) 30

F. FIGURES 31
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Table of Contents

III. URANIUM FUEL CYCLE DOSE 33

A. SPECIFICATION 33

B. ASSUMPTIONS 33

C. DOSE CALCULATION 34

IV. SOURCE REFERENCE DOCUMENTS 34

Attachment 1, “Palisades Gaseous And Liquid Source Terms, Curies/Year”

Attachment 2, “Basic Radionuclide Data”

Attachment 3, “Dose Factors for Submersion in Noble Gases”

Attachment 4, “Stable Element Transfer Data”

Attachment 5, “Inhalation Dose Commitment Factors”

Attachment 6, “External Dose Factors for Standing on Contaminated Ground (DFG)

(mrem/hr per pCi/m 2)”

Attachment 7, “Bioaccumulation Factors (pCi/gm per pCi/mI)”

Attachment 8, “Ingestion Dose Commitment Factors”
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

GASEOUS EFFLUENTS

A. ALARMITRIP SETPOINT METHOD

Appendix A, Section lII.B.1 requires that the dose rate due to radioactive materials

released in gaseous effluents from the site to areas at and beyond the SITE

BOUNDARY shall be limited to the following:

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

less than or equal to 3000 mrems/yr to the skin, and

- For iodine-I 31, for iodine-I 33, for tritium, and for all radionuclides in

particulate form with half lives greater than 8 days: Less than or equal to

1500 mrems/yr to any organ.

Appendix A, Section lll.A.I requires gaseous effluent monitors to have alarm/trip

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

be greater than Appendix A, Section lll.B.1. This section of the ODCM describes the

methodology that will be used to determine these setpoints.

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

The first consists of calculating an allowable concentration for the nuclide mixture to

be released. The second consists of determining monitor response to this mixture in

order to establish the physical settings on the monitors.

I
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Allowable Concentration

NOTE: If a batch release is made while a continuous release or another batch release is

in progress, the sum of all values of Rk must be less than 10.0.

The total EC-fraction (Rk) for each release point will be calculated by the

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

Rk=XIQXFXZCj/EC10.0 (1.1)

where:

C = Actual or measured concentration, at ambient temperature and

pressure of nuclide i (j.tCilcc)

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

R(k) = The total EC-fraction for release point k

XIQ = Most conservative sector site boundary dispersion (sec/rn 3)

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

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

considerations; variable for other monitors

2
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

2. Monitor Response

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

Therefore, monitor response calibrations are performed to fission gas typical

of normal releases (mainly Xe-133). Response of monitors used to define

fission product release rates under accident conditions may vary from that of

Xe-I 33, however. Monitor response for the two categories of monitor is

determined as follows:

a. Normal Release (aged fission gasses)

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

detector response to isotopic activities (cpm/iCi/cc) is applied to

determine cpm expected. The setting for monitor alarms is established

at some factor (b) greater than 1 but less than 1/Rk (Equation 1.1)

times the measured concentration (c):

sbxc (1.2)

b. Accident Releases

Monitors are preset to alarm at or before precalculated offsite dose

rates would be achieved under hypothetical accident conditions.

These setpoints are established in accordance with Emergency Plan

requirements for defining Emergency Action Levels and associated

actions. Emergency Implementing Procedures contain

monitor-specific curves or calibration constants for conversion between

cpm and iCi/cc (or RIhr and 1iCilcc), depending on monitor type, for

fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions,

either an appropriately decayed “accident” conversion curve may be

used, or a decayed fission gas calibration factor may be applied. In

these cases, setpoints are established as in 1 .A above.

Setpoints of accident monitors (if set to monitor normal releases) are

reset to the accident alarm settings at the end of normal release.

Setpoints of other release monitors are maintained at the level used at

the latest release (well below the level which would allow 10 times EC

to be exceeded at the site boundary), or are reset to approximately

three times background in order to detect leakage or inadvertent

releases of low level gases.

3
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

B. DOSE RATE CALCULATION

Dose rates are calculated for (1) noble gases and (2) iodines and particulates.

Dose rates as defined in this section are based on 10 CFR 50 Appendix I

limits of mrem per quarter and millirem per year. All dose pathways of major

importance in the Palisades environs are considered. NRCDose is the

Effluent Dose Calculation software that supports LADTAP, GASPAR, and

XOQDOQ which perform the actual dose calculations using the equations

supplied here.

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

as follows:

1) Assumptions

a) Doses to be calculated are the maximum offsite point in

air, total body and skin.

b) Exposure pathway is submersion within a cloud of noble

gases.

c) Noble gas radionuclide mix is based on the historically

observed source term given in Attachment 2, plus

additional nuclides.

d) Basic radionuclide data are given in Attachment 2.

e) All releases are treated as ground-level.

f) Meteorological data expressed as joint-frequency

distribution of wind speed, wind direction, and

atmospheric stability for the period resulting in X)Q’s and

DIQ’s shown in site procedure CH 6.41, Land Use

Census.

g) Raw meteorological data consists of wind speed and

direction measurements at 1Dm and temperature

measurements at lOm and 60m.

h) Dose is to be evaluated at the offsite exposure points

where maximum concentrations are expected to exist

(overland sector site boundaries), and nearest residents.

4
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

i) Potential maximum population (resident) exposure points

are identified in site procedure CH 6.41, Land Use

Census.

j) A semi-infinite cloud model is used.

k) Radioactive decay is considered for the plume.

I) Building wake effects on effluent dispersion are

considered.

m) A sector-average dispersion equation is used.

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

Wind Speed

ClassNumber

I

2

3

4

5

6

7

o)

Rancie (mis)

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

The stability classes that will be used are the standard A

through G classifications. The stability classes 1-7 will

correspond to A1, B=2, ..., G7.

p) Terrain effects are not considered.

Midpoint (mis)

0.2

0.95

2.25

4.0

6.25

8.75

5
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

2) Equations

To calculate the dose for any one of the exposure points, the

following equations are used.

For determining the air concentration of any radionuclide:

x Jk Q1 P

exp 2i (1.3)

j=1 k1 jr) zkUJ (2zx/n) U)

where:

XI = Air concentration of radionuclide i, jiCilm 3.

fjk = Joint relative frequency of occurrence of winds in

wind speed class j, stability class k, blowing

toward this exposure point, expressed as a

fraction.

QI = Average release rate of radionuclide i, jiCils.

p = Fraction of radionuclide remaining in plume.

zk = Vertical dispersion coefficient for stability

class k (m).

U1 = Midpoint value of wind speed class interval j, rn/s.

x = Downwind distance, m.

n = Number of sectors, 16.

= Radioactive decay coefficient of radionuclide i, sc’.

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

6
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

For determining the total body dose rate:

Dm Xj DFB (1.4)

where:

DTB = Total body dose rate, mrem/y.

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

DFB = Total body dose factor due to gamma radiation,

mrem/y per iiCilm 3(Attachment 3).

For determining the skin dose rate:

(1.5)

where:

D = Skin dose rate, mrem/y.

XI = Air concentration of radionuclide i,

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

1iCi/m 3(Attachment 3).

1.11 = The average ratio of tissue to air energy

absorption coefficients, mrem/mrad.

DFY = Gamma-to-air dose factor for

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

For determining dose rate to a point in air:

Daj (DFYIOrDFBI) (1.6)

where:

Da = Air dose rate, mrad/yr.

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

7
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

b. Equations and assumptions for calculating doses from radioiodines

and particulates are as follows:

1) Assumptions

a) Dose is to be calculated for the critical organ, thyroid, and

the critical age groups (adult, teen, child, infant), infant

(milk) and child (green, leafy vegetables).

b) Exposure pathways from iodines and particulates are

milk ingestion, ground contamination, green leafy

vegetables from home gardens, and inhalation.

c) The radioiodine and particulate mix is based on the

historically observed source term given in Attachment 2.

d) Basic radionuclide data are given in Attachment 3.

e) All releases are treated as ground-level.

f) Mean annual average XIQ’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

1Gm and temperature measurements at 1Gm and 6Gm.

h) Dose is to be evaluated at the potential offsite exposure

points where maximum doses to man are expected to

exist.

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

j) Potential maximum exposure points (site procedure

CH 6.41, Land Use Census) considered are the nearest

cow, goat, and home garden locations in each sector.

k) Terrain effects and open terrain recirculation factors are

not considered.

I) Building wake effects on effluent dispersion are

considered.

m) Plume depletion and radioactive decay are considered

for air-concentration calculations.

8
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

n) Radioactive decay is considered for

ground-concentration calculations.

o) Deposition is calculated based on the curves given in

Figure 1.2.

p) Milk cows and goats obtain 100% of their food from

pasture grass May through October of each year. Use

default values of 0.58 for cows and 0.67 for goats for

fraction of year on pasture.

2) Eciuations

To calculate the dose for any one of the potential

maximum-exposure points, the following equations in

Section 1.2.2 are used.

a) Inhalation

Equation for calculating air concentration, X is the same

as in the Noble Gas Section (Equation 1.3).

For determining the organ dose rate:

D1X1O 6X1DFI BR (1.7)

where:

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

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

DElI = Inhalation dose factor, mrem/pCi

(Attachment 5).

BR = Breathing rate 1400 m3/y infant;

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

adult.

lxi 06 = pCi/iCi conversion factor.

9
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

b) Ground Contamination

For determining the ground concentration of any nuclide;

7

G=3.15x1O 7 fQDR

[1-exp(—,Itb)] (1.8)

k=1 (22rx!n)2 1

where:

= Ground concentration of radionuclide i,

jiCi/m 2.

k = Stability class.

fk = Joint relative frequency of occurrence of

winds in stability class k blowing toward this

exposure point, expressed as a fraction.

Q• = Average release rate of radionuclide

pCi/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

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

= Radioactive decay coefficient of

radionuclide i, y1.

tb = Time for buildup of radionuclides on the

ground, 15y.

3.15x10 7 s/y conversion factor.

10
RELATIVE DEPOSITION RATE (PER METER)

-n

‘if

;tiI

0

0

I

I-.

CI—

C

-

‘ii

—I

inI

Vin

zin

0

—0I

0

0

0

CD0

0I

0

‘.1‘1

Cl)-Im00Ci)m

C) 3,,

I

C)CI-I0z

zCI-

-aICl)Vm

Cl)

z

CC)Im-uI

z-I

C-)0

na
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

For determining the total body or organ dose rate from

ground contamination:

DG = (8,760)(1 X i0)(0.7) G1DFG (1.9)

where:

D0 = Dose rate due to ground contamination,

mrem/y.

= Ground concentration of radionuclide i,

iCiIm 2.

DFG = Dose factor for standing on contaminated

ground, mrem/h per pCi/rn 2(Attachment 6).

8,760 = Occupation time, h/y.

lxi 06 pCi/jiCi conversion factor.

0.7 = Shielding factor accounting for a distance of

1.0 meter above ordinary ground,

dimensionless.

C) Milk and Vegetation Ingestion

For determining the concentration of any nuclide (except

C-14 and H-3) in and on vegetation:

CV1 3,600 fk Qi DR r[1 -exp (2E1 t)1 + B1[1 — exp(—2Itb)} [[exp(—2 1th)]] (1.10)

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

where:

CV Concentration of radionuclide i in and on

vegetation, j.tCi/kg.

k = Stability class.

fk = Frequency of this stability class and wind

direction combination, expressed as a

fraction.

12
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

QI = Average release rate of radionuclide i,

jiCi/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

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

r = Fraction of deposited activity retained on

vegetation (1.0 for iodines, 0.2 for

particulates).

Ei = Effective removal rate constant,

2Ei = + ,where A is the radioactive

decay coefficient, h1, and 2 is a measure

of physical loss by weathering

(2 = 0.0021 h).

te = Period over which deposition occurs, 720 h.

Y, = Agricultural yield, 0.7 kg/rn 2.

B = Transfer factor from soil to vegetation of

radionuclide i (Attachment 4).

= Radioactive decay coefficient of

radionuclide i, h1.

tb = Time for buildup of radionuclides on the

ground, 1.31x10 5h(15Y).

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

3,600 = s/h conversion factor.

th = Holdup time between harvest and

consumption of food (2,160 hours for stored

food).

13
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

For determining the concentration of C-14 in vegetation:

cv14 =lx io3x14(0.11/0.16) (1.11)

where:

CV14 = Concentration of C-14 in vegetation, pCi/kg.

X14 = Air concentration of C-14, iCiIm 3.

0.11 = Fraction of total Plant mass that is natural

carbon.

0.16 = Concentration of natural carbon in the

atmosphere, g/m3.

1x10 3 = g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

CV1”X1OXT(O. 75)(O.5/H) (1.12)

where:

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

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

0.75 = Fraction of total Plant mass that is water.

0.5 = Ratio of tritium concentration in Plant water

to tritium concentration in atmospheric

water.

H = Absolute humidity of the atmosphere, g/m3.

lxi = g/kg conversion factor.

14
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

For determining the concentration of any nuclide in cow’s

or goat’s milk:

CM = CV1 FM1 Qf exp (-2. tf) (1.13)

where:

CM Concentration of radionuclide i (including

C-14 and H-3) in milk, jiCi/I.

CV = Concentration of radionuclide i in and on

vegetation, j.iCilkg.

FM = Transfer factor from feed to milk for

radionuclide i, d/l (Attachment 4).

Q’ = Amount of feed consumed by the milk

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

goat 6 kg/d).

A, = Radioactive decay coefficient of

radionuclide i, d1.

tf = Transport time of activity from feed to milk

to receptor, 2 days.

15
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

For determining the organ dose rate from ingestion of

green leafy vegetables and milk:

D=1x1o 6CM1DFUM (1.14)

where:

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

CM1 Concentration of radionuclide i in

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

DF Ingestion dose factor, mrem/pCi

(Attachment 8).

UM Ingestion rate for milk, 330 IIy; for

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

infant.

lxi 06 = pCi/pCi conversion factor.

d) Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal

flesh:

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

where:

Cfi = Concentration of nuclide i in the animal

flesh, pCi/kg.

Ffl = Fraction of animal’s daily intake which

appears in each kg of flesh, days/kg

(Attachment 4).

CV = Concentration of radionuclide i in the

animal’s feed (Equation 1.10).

16
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Q = Amount of feed consumed by the cow per

day, 50 kg/d.

t = Average time from slaughter to

consumption, 20 days.

To determine the organ dose from ingestion of beef:

DCflDfiUf (1.16)

where:

Dfj = Ingestion dose factor for age group,

mrem/pCi (Attachment 8) for nuclide i.

Uf = Ingestion rate of meat for age group,

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

e) Organ Dose Rates

For determining the total body and organ dose rate from

iodines and particulates:

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

where:

D = Total organ dose rate, mrem/y.

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 25

3) The maximum organ dose rate, maximum total body dose rate,

and maximum skin dose rate calculated in the previous section

(Sec l.B) are used to calculate design basis quantities as

described in Section l.B.1.3.

c. Land Use Census

Appendix A, Sections J.3.b and J.3.c describe the requirements for an

annual land use census. Changes will be effective on January 1 of the

year following the year of the survey.

d. Gaseous Releases From the Steam Generator Blowdown Vent and

Atmosphere Release Valves

Releases from the steam generator blowdown vent and atmospheric

relief valves are difficult to quantify as there are no sampling

capabilities on these steam release systems. However, neither system

is a normal release path. The steam generator blowdown vent is

normally routed to the main condenser and recirculated. Radioactive

releases will be calculated by analyzing steam generator blowdown

liquid and assuming that 100 percent of Noble Gases, 10 percent of

the lodines and 1 percent of the Particulates will be released to the

environment in the steam phase. Volumes will be released to the

environment in the steam phase. Volumes will be calculated using

water balances or alternate means as available.

18
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

C. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION

The gaseous radwaste treatment system (GRTS) described below shall be

maintained and operated to keep releases ALARA.

1. System Description

A flow diagram for the GRTS is given in Figure 1-1. The system consists of

three waste-gas compressor packages, six gas decay tanks, and the

associated piping, valves, and instrumentation. Gaseous wastes are received

from the following: degassing of the reactor coolant and purging of the

volume control tank prior to a cold shutdown and displacing of cover gases

caused by liquid accumulation in the tanks connected to the vent header.

Design of the system precludes hydrogen explosion by means of ignition

source elimination (diaphragm valves, low flow diaphragm compressors and

system electrical grounding), and minimization of leakage outside the system.

Explosive mixtures of hydrogen and oxygen have been demonstrated

compatible with the system by operational experience.

2. Determination of Satisfactory Operation

Doses will be calculated for batch and continuous releases as described in

Section lB. These calculations will be used to ensure that the GRTS is

operating as designed. Because the Plant was designed to collect and hold

for decay a vast majority of the high level gases generated within the primary

system, and because the operating history of the Plant has demonstrated the

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

operability requirements are specified.

19
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

D. RELEASE RATE FOR OFFSITE EC

10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be in

concentrations less than the limits specified in Appendix B, Table 2 when averaged

over a period not to exceed one year. (Note: there are no unrestricted areas

anywhere within the site boundary as defined by Figure 1-1.) Concentrations at this

level if inhaled or ingested continuously for one year will result in a dose of 50 mrem

whole body except for submersion dose isotopes (gaseous tritium and noble gasses)

which will results in a dose of 100 mrem whole body. 10 CFR 50.36a requires that

the release of radioactive materials be kept as low as reasonably achievable.

However, the section further states that the licensee is permitted the flexibility of

operation, to assure a dependable source of power even under unusual operating

conditions, to release quantities of material higher than a small percentage of

10 CFR 20.1302 limits but still within those limits. Appendix Ito 10 CFR 50 provides

the numerical guidelines on limiting conditions for operations to meet the as low as

reasonably achievable requirement.

The GASPAR code has been run to determine the dose due to external radiation

and inhalation. The source term used is listed in Attachment 2. The meteorology

data is given in site procedure CH 6.41, Land Use Census. Dose using annual

average meteorology, to the most limiting organ of the person assume to be residing

at the site boundary with highest XIQ, is 2.15E-02 mrem (for one year). The release

rate which would result in a dose rate equivalent to 50 mrem/year (using the more

conservative total body limit) is the curies/year given in Attachment 2 multiplied by

50/2.15E-02 or 0.11 Ci/sec.

E. PARTICULATE AND IODINE SAMPLING

Particulate and iodine samples are obtained from the continuous sample stream

pulled from the Plant stack. Samples typically are obtained to represent an

integrated release from a gas batch (waste gas decay tank or Containment purge,

for example), or a series of samples are obtained to follow the course of a release.

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

Because HEPA filters are present between most source inputs to the stack and the

sample point, releases of particulates normally are significantly less than pre-release

calculations indicate. This provides for conservatism in establishing setpoints and in

estimation of pre-release dose calculations. However, for the sake of maintaining

accurate release totals, monitor results (for gases) and sample results

(for particulates and iodines) utilized rather than the pre-release estimates, for

cumulative records.

20
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Gamma analytical results for particulate and halogen filters are combined for

determination of total activity of particulates and halogens released. Sampling and

analysis will be performed per Appendix A, Table B-I requirements.

F. NOBLE GAS SAMPLING

Noble gases will be sampled from Waste Gas Decay Tanks prior to release and the

Containment prior to purging. Analysis of these samples will be used for

accountability of noble gases. Off gas will be sampled at least weekly and used to

calculate monthly noble gas releases. Non-routine releases will be quantified from

the stack noble gas monitor (RE 2326) which has a LLD of 1 E-06 tCi/cc. Sampling

and analysis will be performed per Appendix A, Table B-I requirements.

G. TRITIUM SAMPLING

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

The major contributors to tritium effluents are evaporation from the fuel pool and

reactor cavity (when flooded). Because of the low dose impact, gaseous tritium

sampling will not be required. Tritium effluents will be estimated using conservative

evaporation rate calculations from the fuel pool and reactor cavity.

21
I

‘1

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C)Cl)

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‘1Cl),

-I,m

0’

m

0

>

I

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C

I

-I

0

z>

z

CIPALISADES GASEOUS EFFLUENTS -fi OFF GAS (ft

0UI

p

Cl)

p

rn

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z-4

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

F1.ON

S NOT lteNAflO

PAIJSADES EFFLUENT FLOW PATHS

GASEOUS
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

LIQUID EFFLUENTS

A. CONCENTRATION

Requirements

Appendix A, Section IlI.G requires that the concentration of radioactive

material released at any time from the site to unrestricted areas shall be

limited to ten times the Effluent Concentration (EC) specified in 10 CFR 20,

Appendix B, Table 2, Column 2 for nuclides other than dissolved or entrained

noble gases. For dissolved or entrained noble gases, the concentration shall

be limited to 2E-04 jiCi/mi total activity. To ensure compliance, the following

approach will be used for each release.

2. Prerelease Analysis

Most tanks will be recirculated through two volume changes prior to sampling

for release to the environment to ensure that a representative sample is

obtained. The appropriate recirculation time for those tanks too large to

provide two volume changes will be the time that the suspended particulate

concentration reaches steady state. Either a one-time test, or prior sampling

data, may be used to determine appropriate recirculation time.

Prior to release, a grab sample will be analyzed for each release, and the

concentration of each radionuclide determined.

n

C = ZCI (2.1)

i=1

where:

C = Total concentration in the liquid effluent at the release

point, iCi/mI.

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

23
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

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

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

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

= —--10.O (2.2) EC

where:

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

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

Column 2 - .tCi/ml.

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

The sum of the ratios at the discharge to the lake must be 10 due to the

releases from any or all concurrent releases. The following relationship will

assure this criterion is met:

fi (Ri -1) + f2 (R2 -1) + f(R3 -1) F (2.3)

where:

fi,f 2,f3 = The effluent flow rate (gallons/minute) for the respective

releases, determined by Plant personnel.

R1,R23 = The Total EC-Fractions for the respective releases as

determined by Equation 2.2.

F = Minimum required dilution flow rate. Normally, a

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

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

greater than 1.0.

24
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

B. INSTRUMENT SETPOINTS

Setpoint Determination

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

monitor will be established using Plant instructions to ensure the

requirements of Appendix A, Section llI.G are not exceeded. Concentration,

flow rate, dilution, principal gamma emitter, geometry, and detector efficiency

are combined to give an equivalent setpoint in counts per minute (cpm). The

identification number for each liquid effluent radiation detector is contained in

Figure 2-2.

The respective alarm/trip setpoints at each release point will be set such that

the sum of the ratios at each point, as calculated by Equation 2.2, will not be

exceeded. The value of R is directly related to the total concentration

calculated by Equation 2.1. An increase in the concentration would indicate

an increase in the value of R. A large increase would cause the limits

specified in Section 2.1.1 to be exceeded. The minimum alarm/trip setpoint

value is equal to the release concentration, but for ease of operation it may be

desired that the setpoint (S) be set above the effluent concentration (C) by the

same factor (b) utilized in setting dilution flow. That is:

S = bxC (2.4)

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

2. Composite Samplers

Effluent pathways, Turbine Sump and Service Water, are equipped with

continuous compositors to meet the requirements of Appendix A, Table D-1.

These compositors are adjustable and normally set in a time mode and

collect three to six samples hourly, 24 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-i,

Action 3.

25
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

3. Post-Release Analysis

A post-release analysis will be done using actual release data to ensure that

the limits specified in Section 1 were not exceeded.

A composite list on concentrations (C), by isotope, will be used with the

actual liquid radwaste (f) and dilution (F) flow rates (or volumes) during the

release. The data will be substituted into Equation 2.3 to demonstrate

compliance with the limits in Section 1. This data and setpoints will be

recorded in auditable records by Plant personnel.

C. DOSE

RETS Requirement

Appendix A, Section Ill.H.1 requires that the quantity of radionuclides

released by limited such that the dose or dose commitment to an individual

from radioactive materials in liquid effluents release to unrestricted areas from

the reactor (see Figure 2-1) will not exceed:

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

any organ, and

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

any organ.

To ensure compliance, quantities of activity of each radionuclide released will

be summed for each release and accumulated for each quarter as follows in

Section 2.

2. Release Analysis

Dose calculations shall be performed for each batch release, and weekly for

continuous releases unless documentation exists to demonstrate an activity

below which dose limits of Section ll.C.1 will not be exceeded.

a. Water Ingestion

The dose to an individual from ingestion of radioactivity from any

source as described by the following equation:

(DCFxI (2.5)

26
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

where:

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

= The organ of interest.

(DCF)IJ = Ingestion dose commitment factor for the jth organ from

the jth radionuclide mrem/pCi, see Attachment 8.

I. = Activity ingested of the radionuclide, pCi.

I is described by:

(A)(V)(365) (1E06) (2.6) (1 000)(d)

where:

365 = Days per year.

A = Annual activity released of radionuclide, 1iCi.

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

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

d = Dilution water flow for year, ml.

1000 = Dispersion factor from discharge to nearest drinking

water supply.

I E06 = Conversion jiCi to pCi.

The dose equation then becomes:

D (3.6505) (DCF)xAmrem (2.7)

27
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

b. Fish Ingestion

The dose to an individual from the consumption of fish is described by

Equation 2.10. In this case, the activity ingested of the ith radionuclide

(I,) is described by:

AB1F(1EO9) =pCi (2.8)

where:

A = Annual released of i’ radionuclide, pCi.

B = Fish concentration factor of th radionuclide

pCi/gm

pCi/mi

(see Attachment 7).

F = Amount of fish eaten per year (21 kg adult, 16 kg teen,

6.9 kg child, none infant).

15 = Dispersion factor from discharge to fish exposure point.

d = Dilution water flow for year, ml.

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

Substitution of Equation 2.8 into Equation 2.5 gives:

(6.7E07)F D AxB 1xDCFmrem (2.9)

i=1

28
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

c. Annual Analysis

A complete analysis utilizing the NRC computer code LADTAP with the

total source release will be done annually in conjunction with the

annual environmental report. This analysis will provide estimates of

dose to the total body and various organs in addition to the dose

limiting organs considered in the method of Section 2. The following

approach is utilized on LADTAP. The dose to the Jth

organ from m

radionuclides, Dj, is described by:

m

D= D11mrem (2.10)

1=1

m

= (DCFxImrem (2.11)

1=1

where:

D1 = Dose to the Jth

organ from the i radionuclide, mrem.

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

kidney, lung, or total body).

(DCF) 1 = Adult ingestion dose commitment factor for the th organ

from the ith radionuclide, mrem/pCi (see Attachment 8).

Ii = Activity ingested of the radionuclide, jiCi.

I for water ingestion is described by:

1.AiVr pCi (2.12) vd

and for fish ingestion Ii is described by:

AiBiFrj (2.13) vd

29
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

where:

A1 = Activity release 0f1th radionuclide during the year, Ci.

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

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

v = Dispersion factor from point of discharge to point of

exposure.

d = Dilution water volume (ml).

B Fish concentration factor of the radionuclide,

p CIgm

Attachment 7, p Cl/mI

F = Amount of fish eaten per day (57.5 gmld).

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT

The Palisades liquid radwaste system is designed to reduce the radioactive

materials in liquid wastes prior to their discharge (through deep bed filtration and ion

exchange) so that radioactivity in liquid effluent releases to unrestricted areas (see

Figure 2-1)will not exceed the limits of Appendix A, III.H.1.

E. RELEASE RATE FOR OFFSITE EC (50 MREMIYR)

10 CFR 20.1302 requires radioactive effluent releases to unrestricted areas be less

than the limits specified in Appendix B, Table 2 when averaged over a period not to

exceed one year. Concentrations at this Effluent Concentration (EC) level, if

ingested for one year, will result in a dose of 50 millirem to the total body. In

addition, 10 CFR 50.36a requires that the release of radioactive materials be kept as

low as is reasonably achievable. Appendix Ito 10 CFR 50 provides the numerical

guidelines on limiting conditions for operations to meet the as low as is reasonably

achievable requirement.

The LADTAP code has been run to determine the dose due to drinking water at

Plant discharge concentration (1,000 x nearest drinking water intake concentration).

The nominal average source term used is given in Attachment 2. Dose to the most

limiting organ of the person hypothetically drinking this water is 3.88E-03 mrem.

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

30
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I” 21S M1TIEIS

SITE ENVIRONMENT

TLO STATIONS

PALISADES NIJCLEAR PLANT

SITE BOUNDARY

FIGuRE 2-I
PALISADES RADWASTE EFFLUENTS - LIQUID

CT rAN

SYS

WASrE

I IM STEAM GEN

-J

PRIMARY TANK

BLOWOOWN

z SYSTEM 1799

STORAGE

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DILUTION FLOW S

1

SERVICE WATER LAKE INLET
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 25

Ill. URANIUM FUEL CYCLE DOSE

A. SPECIFICATION

In accordance with Appendix A, Section 111.1.1, if either liquid or gaseous quarterly

releases exceed the quantity which would cause offsite doses more than twice the

limit of Appendix A, Sections lII.C.1, IIl.D.1, or llI.H.1, then the cumulative dose

contributions from combined release plus direct radiation sources (from the reactor

unit and radwaste storage tanks) shall be calculated. The dose is to be determined

for the member of the public protected to be the most highly exposed to these

combined sources.

B. ASSUMPTIONS

1. The full time resident determined to be maximally exposed individual

(excluding infant) is assumed also to be a fisherman. This individual is

assumed to drink water and ingest local fish at the rates specified in

Sections II.C.2.1 and II.C.2.2.

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

fence) is conservatively assumed as 48 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 25

C. DOSE CALCULATION

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

determined by use of LADTAP and GAS PAR computer codes, and doses to like

organs and total body summed. Added to this sum will be a mean dose rate,

calculated or measured for the shoreline due to Plant present curing the quarter in

question, times the assumed fishing time.

D40 = DG + DL + (RT)(T) (2.15)

where:

D40 40 CFR 190 dose (mrem).

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

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

RT = Mean dose rate calculated to be applicable to Lake Michigan shoreline

adjacent to Plant site (mrem/hr).

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

IV. SOURCE REFERENCE DOCUMENTS

1. Regulatory Guide 1.21, Measuring, Evaluating, and Reporting Radioactivity in

Solid Wastes and Releases of Radioacitve Materials in Liquid and Gaseous

Effluents from Light-Water-Cooled Nuclear Power Plants, Ri.

2. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine

Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10

CFR Part 50, Appendix I, RI.

3. NUREG-1301, Offsite Dose Calculation Manual Guidance: Standard Radiological

Effluent Controls for Pressurized Water Reactors, April 91.

4. NUREG-0472, Standard Radiological Effluent Technical Specifications for

Pressurized Water Reactors, R3.

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

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

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

34
Proc No ODCM

Attachment I

Revision 25

Page 1 of I

PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESIYEAR (1)

Nuclide Gaseous(2) Liciuid(2)

H-3 5.5 159

Kr-85 4.1 NA

Kr-85m 0.12 NA

Kr-87 8.4E-02 NA

Kr-88 2.1E-01 NA

Ar-41 3.IE-02 NA

Xe-131m 2.2 NA

Xe-133 1493 NA

Xe-i 33m 0.43 NA

Xe-135 1.11 NA

Xe-135m 0.3 NA

1-131 0.025 3.21E-03

1-132 2.91E-03 NA

1-133 6.5E-03 4.7E-05

1-134 4.8E-04 NA

1-135 l.84E-02 NA

Na-24 1.5E-06 NA

Cr-51 2.5E-04 3.9E-03

Mn-54 4.IE-04 7.8E-03

Co-57 2.IE-06 3.2E-05

Co-58 8.6E-04 2.9E-02

Fe-59 6.6E-06 4.1E-04

Co-60 1.1 E-03 1 .24E-02

Se-75 3.7E-06 NA

Nb-95 2.4E-05 4.53E-04

Zr-95 4.7E-06 I .79E-04

Mo-99 I .5E-07 NA

Ru-103 0.3E-07 0.1E-05

Sb-127 NA 3.5E-05

Cs-i 34 4.5E-05 0.7

Cs-136 NA 1.8E-06

Cs-137 2.6E-04 i.36E-02

Ba-140 2.8E-07 NA

La-140 7.5E-07 1.1E-04

Unidentified beta 3.9E-04 3.3E-03

(1) Data derived from taking the effluents released during July-December 1978 through

January-June 1982 and dividing by 4.

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

streams.
Proc No ODCM

Attachment 2

Revision 25

Page 1 of 2

BASIC RADIONUCLIDE DATA

NUCLIDE HALF-LIFE

(days)

LAMBDA BETA 1 GAMMA 1

(MEV/DIS) (MEV/DIS)

1 Tritium 4.49E 03 1 .79E-09 5.68E-03 0.0

2 C-14 2.09E 06 3.84E-12 4.95E-02 0.0

3 N-13 6.94E-03 1.16E-03 4.91E-01 1.02E00

4 0-19 3.36E-04 2.39E-02 1.02E 00 1.05E 00

5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E00

6 NA-24 6.33E-01 1.27E-05 5.55E-01 4.12E 00

7 P-32 1.43E 01 5.61E-07 6.95E-01 0.0

8 AR-41 7.63E-02 1.05E-04 4.64E-01 1.28E 00

9 CR-51 2.78E 01 2.89E-07 3.86E-03 3.28E-02

10 MN-54 3.03E 02 2.65E-08 3.80E-03 8.36E-01

11 MN-56 I .07E-01 7.50E-05 8.29E-01 I .69E 00

12 FE-59 4.50E01 1.78E-07 1.18E-01 1.19E00

13 C0-58 7.13E 01 1.12E-07 3.41 E-02 9.78E-01

14 C0-60 1.92E 03 4.18E-09 9.68E-02 2.50E 00

15 ZN-69m 5.75E-01 1.39E-05 2.21E-02 4.16E-01

16 ZN-69 3.96E-02 2.03E-04 3.19E-01 0.0

17 BR-84 2.21E-02 3.63E-04 1.28E 00 1.77E 00

18 BR-85 2.08E-03 3.86E-03 1.04E 00 6.60E-02

19 KR-85m 1.83E-01 4.38E-05 2.53E-01 1.59E-01

20 KR-85 3.93E 03 2.04E-09 2.51 E-01 2.21E-03

21 KR-87 5.28E-02 1 .52E-04 1 .32E 00 7.93E-01

22 KR-88 1.17E-01 6.86E-05 3.61E-01 1.96E 00

23 KR-89 2.21 E-03 3.63E-03 1.36E 00 1.83E 00

24 RB-88 1.24E-02 6.47E-04 2.06E00 6.26E-01

25 RB-89 1.07E-02 7.50E-04 1.O1E 00 2.05E-00

26 SR-89 5.20E 01 1.54E-07 5.83E-01 8.45E-05

27 SR-90 1.03E 04 7.79E-10 1.96E-01 0.0

28 SR-91 4.03E-01 1.99E-05 6.50E-01 6.95E-01

29 SR-92 1.13E-01 7.1OE-05 1.95E-01 1.34E 00

30 SR-93 5.56E-03 1.44E-03 9.20E-01 2.24E 00

31 Y-90 2.67E 00 3.OOE-06 9.36E-01 0.0

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

33 Y-91 5.88E01 1.36E-07 6.06E-01 3.61E-03

34 Y-92 1.47E-01 5.46E-05 1.44E 00 2.50E-01

35 Y-93 4.29E-01 1.87E-05 1.17E 00 8.94E-02

36 ZR-95 6.50E01 1.23E-07 1.16E-01 7.35E-01

37 NB-95m 3.75E00 2.14E-06 1.81E-01 6.06E-02

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

39 MO-99 2.79E 00 2.87E-06 3.96E-01 I .50E-01

40 TC-99m 2.50E-01 3.21E-05 1.56E-02 1.26E-01
Proc No ODCM

Attachment 2

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Page 2 of 2

BASIC RADIONUCLIDE DATA

NUCLIDE HALF-LIFE

(days)

LAMBDA BETA 1 GAMMA 1

(us) (MEV/DIS) (MEV/DIS)

41 TC-99 7.74E 07 i.04E-13 8.46E-02 0.0

42 TC-104 i.25E-02 6.42E-04 i.60E 00 1 .95E 00

43 RU-106 3.67E02 2.19E-08 1.O1E-02 0.0

44 TE-132 3.24E00 2.48E-06 1.OOE-01 2.33E-01

45 1-129 6.21E09 1.29E-15 5.43E-02 2.46E-02

46 1-131 8.05E00 9.96E-07 1.94E-01 3.81E-01

47 1-132 9.58E-02 8.37E-05 4.89E-01 2.24E 00

48 1-133 8.75E-01 9.17E-06 4.08E-01 6.02E-01

49 1-134 3.61 E-02 2.22E-04 6.16E-01 2.59E 00

50 1-135 2.79E-01 2.87E-05 3.68E-0i 1.55E 00

51 XE-i 3im 1.i8E 01 6.80E-07 1.43E-01 2.O1E-02

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

53 XE-133 5.27E00 1.52E-06 1.35E-01 4.60E-02

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

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

56 XE-137 2.71E03 2.96E-03 1.77E00 1.88E-01

57 XE-i 38 9.84E-03 8.15E-04 6.65E-01 1.1OE 00

58 CS-134 7.48E 02 1.07E-08 i.63E-Oi 1.55E 00

59 CS-135 1.1OE 09 7.29E-15 5.63E-02 0.0

60 CS-i 36 1.30E 01 6.17E-07 1.37E-01 2.15E 00

61 CS-137 1.10E04 7.29E-iO 1.71E-01 5.97E-Oi

62 CS-138 2.24E-02 3.58E-04 i.20E00 2.30E00

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

64 BA-140 1.28E01 6.27E-07 3.i5E-Oi i.71E-Oi

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

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

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

68 PR-144 1.20E-02 6.68E-04 1.2iE 00 3.18E 00

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

Radionuclide Transformations: Enemy and Intensity of Emissions 1983 and

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

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

Attachment 3

Revision 25

Page 1 of I

DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

Gamma body Gamma air Beta skin Beta air

dose 1 dose 2 dose 1 dose 2

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

Kr-85 1.61E1 1.72E1 1.34E3 1.95E3

Kr-87 5.92E3 6.17E3 9.73E3 1.03E4

Kr-88 1.47E4 1.52E4 2.37E3 2.93E3

Kr-89 1.66E4 1.73E4 1.01E4 1.06E4

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

Xe-133m 2.51E2 3.27E2 9.94E2 1.48E3

Xe-133 2.94E2 3.53E2 3.06E2 1.05E3

Xe-135m 3.12E3 3.36E3 7.11E2 7.39E3

Xe-135 1.81E3 1.92E3 1.86E3 2.46E3

Xe-137 1.42E3 1.51E3 1.22E4 1.27E4

Xe-138 8.83E3 9.21E3 4.13E3 4.75E3

Ar-41 8.84E3 9.30E3 2.69E3 3.28E3

I. mrem/y per jiCi/m 3

2. mrad/y per pCi/rn 3

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

USNRC Regulatory Guide 1.109, Revision 1 (October 1977).
Proc No ODCM

Attachment 4

Revision 25

Page 1 of I

STABLE ELEMENT TRANSFER DATA

Fm - MILK (COW) Fm - MILK (GOAT) Ff - MEAT B1

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

H 1.OE-02 1.7E-O1 1.2E-02 4.8E-OO

C t2E-02 1.OE-O1 3.1E-02 5.5E-OO

Na 4.OE-02 4.OE-02 3.OE-02 5.2E-02

P 2.5E-02 2.5E-O1 4.6E-02 1.1E-OO

Cr 2.2E-03 2.2E-03 2.4E-03 2.5E-04

Mn 2.5E-04 2.5E-04 8.OE-04 2.9E-02

Fe 1.2E-03 1.3E-04 4.OE-02 6.6E-04

Co 1.OE-03 1.OE-03 1.3E-02 9.4E-03

Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02

Cu 1.4E-02 1.3E-02 8.OE-03 1.2E-O1

Zn 3.9E-02 3.9E-02 3.OE-02 4.OE-O1

Rb 3.OE-02 3.OE-02 3.IE-02 1.3E-O1

Sr 8.OE-04 1.4E-02 6.OE-04 1.7E-02

Y 1.OE-05 1.OE-05 4.6E-03 2.6E-03

Zr 5.OE-06 5.OE-06 3.4E-02 1.7E-04

Nb 2.5E-03 2.5E-03 2.8E-O1 9.4E-03

Mo 7.5E-03 7.5E-03 8.OE-03 1.2E-O1

Tc 2.5E-02 2.5E-02 4.OE-O1 2.5E-O1

Ru 1.OE-06 1.OE-06 4.OE-O1 5.OE-02

Rh 1.OE-02 1.OE-02 1.5E-03 1.3E+O1

Ag 5.OE-02 5.OE-02 1.7E-02 1.5E-O1

Te 1.OE-03 1.OE-03 7.7E-02 1.3E-OO

I 6.OE-03 6.OE-02 2.9E-03 2.OE-02

Cs 1.2E-02 3.OE-O1 4.OE-03 1.OE-02

Ba 4.OE-04 4OE-O4 3.2E-03 5.OE-03

La 5.OE-06 5.OE-06 2.OE-04 2.5E-03

Ce 1.OE-04 1.OE-04 1.2E-03 Z5E-03

Pr 5.OE-06 5.OE-06 4.7E-03 2.5E-03

Nd 5.OE-06 5.OE-06 3.3E-03 2.4E-03

W 5.OE-04 5.OE-04 1.3E-03 1.8E-02

Np 5.OE-06 5.OE-06 2.OE-04 2.5E-03
Proc No ODCM

Attachment 5

Revision 25

Page 1 ofl6

INHALATION DOSE COMMITMENT FACTORS

INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07 4.62E-07

BEIO 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05

C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06

N13 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08 4.39E-08

F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.1OE-07

NA22 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05 7.37E-05

NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06 7.54E-06

P32 1.45E-03 8.03E-05 5.53E-05 0. 0. 0. 1.15E-05

AR39 0. 0. 0. 0. 0. 1.OOE-08 0.

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

CA4I 7.48E-05 0. 8.16E-06. 0. 0. 6.94E-02 2.96E-07

SC46 3.75E-04 5.41E-04 1.69E-04 0. 3.56E-04 0. 2.19E-05

CR51 0. 0. 6.39E-08 4.1IE-08 9.45E-09 9.17E-06 2.55E-07

MN54 0. 1.81E-05 3.56E-06 0. 3.56E-06 7.14E-04 5.04E-06

MN56 0. 1.IOE-09 1.58E-1O 0. 7.86E-10 8.95E-06 5.12E-05

FE55 1.41E-05 8.39E-06 2.38E-06 0. 0. 6.21E-05 7.82E-07

FE59 9.69E-06 1.68E-05 6.77E-06 0. 0. 7.25E-04 1.77E-05

C057 0. 4.65E-07 4.58E-07 0. 0. 2.71 E-04 3.47E-06

C058 0. 8.71E-07 1.30E-06 0. 0. 5.55E-04 7.95E-06

C060 0. 5.73E-06 8.41 E-06 0. 0. 3.22E-03 2.28E-05

N159 1.81E-05 5.44E-06 3.1OE-06 0. 0. 5.48E-05 6.34E-07

N163 2.42E-04 1.46E-05 8.29E-06 0. 0. 1.49E-04 1.73E-06

N165 1.71E-09 2.03E-10 8.79E-11 0. 0. 5.80E-06 3.58E-05

CU64 0. 1.34E-09 5.53E-1O 0. 2.84E-09 6.64E-06 1.07E-05

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

ZN69M 8.98E-09 1.84E-08 1.67E-09 0. 7.45E-09 1.91 E-05 2.92E-05

ZN69 3.85E-11 6.91E-11 5.13E-12 0. 2.87E-11 1.05E-06 9.44E-06

SE79 0. 2.25E-06 4.20E-07 0. 2.47E-06 2.99E-04 3.46E-06

BR82 0. 0. 9.49E-06 0. 0. 0. 0.

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

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

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

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

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

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

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

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

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

RB86 0. 1.36E-04 6.30E-05 0. 0. 0. 2.17E-06

RB87 0. 7.11E-05 2.64E-05 0. 0. 0. 2.99E-07

RB88 0. 3.98E-07 2.05E-07 0. 0. 0. 2.42E-07

RB89 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08

SR89 2.84E-04 0. 8.15E-06 0. 0. 1.45E-03 4.57E-05

SR9O 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05

SR9I 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05

SR92 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 1.OOE-04

*lncludes a 50% increase to account for percutaneous transpiration.
Proc No ODCM

Attachment 5

Revision 25

Page 2 of 16

INHALATION DOSE COMMITMENT FACTORS

INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

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

Y9IM 2.91E-1O 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06

Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05

Y92 1.17E-08 0. 3.29E-10 0. 0. 1.75E-05 9.04E-05

Y93 1.07E-07 0. 2.91E-09 0. 0. 5.46E-05 1.19E-04

ZR93 2.24E-04 9.51E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05

ZR95 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05

ZR97 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.OOE-04

NB93M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06

NB95 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06

NB97 2.44E-10 5.21E-11 1.88E-11 0. 4.07E-11 2.37E-06 1.92E-05

M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06

M099 0. 1.18E-07 2.31E-08 0. 1.89E-07 9.63E-05 3.48E-05

TC99M 9.98E-13 2.06E-12 2.66E-11 0. 2.22E-11 5.79E-07 1.45E-06

TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06

TC1OI 4.65E-14 5.88E-14 5.80E-13 0. 6.99E-13 4.17E-07 6.03E-07

RUIO3 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05

RU1O5 8.74E-1O 0. 2.93E-1O 0. 6.42E-1O 1.12E-05 3.46E-05

RUIO6 6.20E-05 0. 7.77E-06 0. 7.61E-05 8.26E-03 1.17E-04

RH105 8.26E-09 5.41E-09 3.63E-09 0. 1.50E-08 2.08E-05 1.37E-05

PDIO7 0. 4.92E-07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07

PDIO9 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05

AG11OM 7.13E-06 5.16E-06 3.57E-06 0. 7.80E-06 2.62E-03 2.36E-05

AG1I1 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05

CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 1.40E-03 1.65E-05

CDII5M 0. 1.73E-04 6.19E-06 0. 9.41E-05 1.47E-03 5.02E-05

SN123 2.09E-04 4.21E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.08E-05

SN125 1.O1E-05 2.51E-07 6.OOE-07 2.47E-07 0. 6.43E-04 7.26E-05

SN126 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05

SB124 2.71E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05

SB125 3.69E-05 3.41E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05

SB126 3.08E-06 6.OIE-08 1.11E-06 2.35E-08 0. 6.88E-04 5.33E-05

SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05

TEI25M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06

TE127M 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05

TE127 1.59E-09 6.81E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05

TEI29M 1.OIE-05 4.35E-06 1.59E-06 3.91E-06 2.27E-05 1.20E-03 4.93E-05

TE129 5.63E-11 2.48E-11 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05

TE13IM 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51E-05

TEI3I 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06

TE132 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05

TEI33M 6.13E-11 3.59E-11 2.74E-11 5.52E-11 1.72E-10 3.92E-06 1.59E-05

TE134 3.18E-11 2.04E-11 1.68E-11 2.91E-11 9.59E-11 2.93E-06 2.53E-06

1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 0. 2.12E-07

1130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06

1131 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0. 7.56E07
Proc No ODCM

Attachment 5

Revision 25

Page 3 of 16

INHALATION DOSE COMMITMENT FACTORS

INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI

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

1133 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 0. 1.54E-06

1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21E-07

1135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31E-06

XEI31M 0. 0. 0. 0. 0. 6.77E-09 0.

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

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

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

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

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

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

CS134M 1.32E-07 2.1OE07 1.IIE-07 0. 8.50E-08 2.OOE-08 1.16E-07

CS134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07

CS135 1.00E-04 8.66E-05 4.73E-06 0. 2.58E-05 1.O1E-05 2.18E-07

CS136 3.45E-05 9.61E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06

CS137 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07

CS138 3.61 E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07

CS139 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08

BA139 1.06E-09 7.03E-13 3.07E-11 0. 4.23E-13 4.25E-06 3.64E-05

BAI4O 4.OOE-05 4.OOE-08 2.07E-06 0. 9.59E-09 1.14E-03 2.74E-05

BAI4I 1.12E-10 7.70E-14 3.55E-12 0. 4.64E-14 2.12E-06 3.39E-06

BA142 2.84E-11 2.36E-14 1.40E-12 0. 1.36E-14 1.IIE-06 4.95E-07

LA14O 3.61E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05

LA141 4.85E-09 1.40E-09 2.45E-1O 0. 0. 1.22E-05 5.96E-05

LA142 7.36E-10 2.69E-1O 6.46E-11 0. 0. 5.87E-06 4.25E-05

CEI4I 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05

CE143 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05

CE144 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04

PR143 1.OOE-05 3.74E-06 4.99E-07 0. 1.41E-06 3.09E-04 2.66E-05

PR144 3.42E-11 1.32E-11 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06

ND147 5.67E-06 5.81 E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05

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

PMI48M 5.OOE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05

PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05

PM149 3.1OE-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.OIE-05

PMI5I 7.52E-08 1.IOE-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05

SM151 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06

SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05

EU152 7.83E-04 1.77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06

EU154 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05

EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05

EU156 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05

TBI6O 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.IIE-03 2.14E-05

H0166M 1.45E-03 3.07E-04 2.51E-04 0. 4.22E-04 2.05E-03 1.65E-05

W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07

W185 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05

W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05
Proc No ODCM

Attachment 5

Revision 25

Page 4 of 16

INHALATION DOSE COMMITMENT FACTORS

INFANT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB2IO 8.62E-02 2.02E-02 3.43E-03 0. 6.85E-02 1.76E-01 3.79E-05

BI21O 0. 1.33E-05 1.18E-06 0. 1.03E-04 9.96E-03 3.27E-05

P0210 2.98E-03 5.63E-03 7.12E-04 0. 1.30E-02 2.40E-01 4.36E-05

RN222 0. 0. 0. 0. 0. 9.88E-06 0.

RA223 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04

RA224 1.77E-04 4.OOE-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04

RA225 2.57E-03 2.88E-06 5.13E-04 0. 5.31E-05 2.57E-O1 2.87E-04

RA226 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04

RA228 1.60E-01 7.61E-06 1.80E-01 0. 1.53E-04 1.09E-00 5.19E-05

AC225 3.69E-03 4.72E-03 2.48E-04 0. 3.49E-04 1.96E-01 2.71E-04

AC227 5.29E+00 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+00 5.27E-05

TH227 1.82E-03 3.03E-05 5.24E-05 0. 1.13E-04 3.27E-01 3.53E-04

TH228 8.46E-01 1.1OE-02 2.86E-02 0. 5.61E-02 4.65Ei-00 3.62E-04

TH229 1.34E+01 1.82E-01 6.62E-01 0. 8.99E-01 1.22E+01 3.29E-04

TH230 3.46E+00 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+00 3.87E-05

TH232 3.86E+00 1.53E-01 2.29E-01 0. 7.54E-01 2.09E+00 3.29E-05

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

PA231 9.1OE+00 3.OOE-01 3.62E-01 0. 1.62E+00 3.85E-01 4.61E-05

PA233 6.84E-06 1.32E-06 1.19E-06 0. 3.68E-06 2.19E-04 9.04E-06

U232 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+00 4.36E-05

U233 5.44E-02 0. 3.83E-03 0. 1.09E-02 3.56E-01 4.03E-05

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

U235 5.O1E-02 0. 3.52E-03 0. 1.OIE-02 3.28E-01 5.02E-05

U236 5.O1E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05

U237 3.25E-07 0. 8.65E-08 0. 8.08E-07 9.13E-05 1.31E-05

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

NP237 3.03E+00 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.1OE-05

NP238 2.67E-06 6.73E-08 4.16E-08 0. 1.47E-07 9.19E-05 2.58E-05

NP239 2.65E-07 2.37E-08 1.34E-08 0. 4.73E-08 4.25E-05 1.78E-05

PU238 5.02E+00 6.33E-01 1.27E-01 0. 4.64E-01 9.03E-01 4.69E-05

PU239 5.50E+00 6.72E-01 1.34E-01 0. 4.95E-01 8.47E-01 4.28E-05

PU240 6.49E+00 6.71 E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05

PU241 1.55E-01 6.69E-03 3.IIE-03 0. 1.15E-02 7.62E-04 8.97E-07

PU242 5.09E+00 6.47E-01 1.29E-01 0. 4.77E-01 8.15E-01 4.20E-05

PU244 5.95E+00 7.40E-01 1.48E-01 0. 5.46E-01 9.33E-01 6.26E-05

AM241 1.84E+00 8.44E-01 1.31E-01 0. 7.94E-01 4.06E-01 4.78E-05

AM242M 1.90E+00 8.24E-01 1.35E-01 0. 8.03E-01 1.64E-01 6.01 E-05

AM243 1.82E+00 8.1OE-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05

CM242 8.58E-02 744E-02 5.70E-03 0. 1.69E-02 2.97E-01 5.IOE-05

CM243 1.73E+00 7.94E-01 1.06E-01 0. 3.91E-01 4.24E-01 5.02E-05

CM244 1.43E+00 7.04E-01 8.89E-02 0. 3.21 E-01 4.08E-01 4.86E-05

CM245 2.26E+00 8.80E-01 1.36E-01 0. 5.23E-01 3.92E-01 4.53E-05

CM246 2.24E+00 8.79E-01 1.36E-01 0. 5.23E-01 3.99E-01 4.45E-05

CM247 2.18E+00 8.64E-01 1.33E-01 0. 5.15E-01 3.92E-01 5.85E-05

CM248 1.82E+01 7.12E+00 1.1OE+00 0. 4.24E+00 3.23E+00 9.43E-04

CF252 4.26E+00 0. 1.OIE-01 0. 0. 1.37E+00 1.85E-04
Proc No ODCM

Attachment 5

Revision 25

Page 5 of 16

INHALATION DOSE COMMITMENT FACTORS

CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07

BEIO 8.43E-04 9.83E-05 2.12E-05 0. 0. 7.41E-04 1.72E-05

C14 970E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06

N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08

F18 1.88E-06 0. 1.85E-07 0. 0. 0. 3.37E-07

NA22 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05

NA24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06

P32 7.04E-04 3.09E-05 2.67E-05 0. 0. 0. 1.14E-05

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

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

CA4I 7.06E-05 0. 7.70E-06 0. 0. 7.21 E-02 2.94E-07

SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.45E-05

CR51 0. 0. 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07

MN54 0. 1.16E-05 2.57E-06 0. 2.71E-06 4.26E-04 6.19E-06

MN56 0. 4.48E-1O 8.43E-11 0. 4.52E-1O 3.55E-06 3.33E-05

FE55 1.28E-05 6.80E-06 2.1OE-06 0. 0. 3.OOE-05 7.75E-07

FE59 5.59E-06 9.04E-06 4.51 E-06 0. 0. 3.43E-04 1.91 E-05

C057 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.58E-06

C058 0. 4.79E-07 8.55E-07 0. 0. 2.99E-04 9.29E-06

C060 0. 3.55E-06 6.12E-06 0. 0. 1.91E-03 2.60E-05

NI59 1.66E-05 4.67E-06 2.83E-06 0. 0. 2.73E-05 6.29E-07

N163 2.22E-04 1.25E-05 7.56E-06 0. 0. 7.43E-05 1.71E-06

NI65 8.08E-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-05

CU64 0. 5.39E-10 2.90E-1O 0. 1.63E-09 2.59E-06 9.92E-06

ZN65 1.15E-05 3.06E-05 1.90E-05 0. 1.93E-05 2.69E-04 4.41E-06

ZN69M 4.26E-09 7.28E-09 8.59E-1O 0. 4.22E-09 7.36E-06 2.71E-05

ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.58E-11 3.84E-07 2.75E-06

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

BR82 0. 0. 5.66E-06 0. 0. 0. 0.

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

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

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

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

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

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

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

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

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

RB86 0. 5.36E-05 3.09E-05 0. 0. 0. 2.16E-06

RB87 0. 3.16E-05 1.37E-05 0. 0. 0. 2.96E-07

RB88 0. 1.52E-07 9.90E-08 0. 0. 0. 4.66E-09

RB89 0. 9.33E-08 7.83E-08 0. 0. 0. 5.IIE-10

SR89 1.62E-04 0. 4.66E-06 0. 0. 5.83E-04 4.52E-05

SR9O 2.73E-02 0. 1.74E-03 0. 0. 3.99E-03 9.28E-05

SR9I 3.28E-08 0. 1.24E-09 0. 0. 1.44E-05 4.70E-05

SR92 3.54E-09 0. 1.42E-10 0. 0. 6.49E-06 6.55E-05

*Includes a 50% increase to account for percutaneous transpiration.
Proc No ODCM

Attachment 5

Revision 25

Page 6 of 16

INHALATION DOSE COMMITMENT FACTORS

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

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

Y91M 1.37E-1O 0. 4.98E-12 0. 0. 7.60E-07 4.64E-07

Y91 2.47E-04 0. 6.59E-06 0. 0. 7.1OE-04 4.97E-05

Y92 5.50E-09 0. 1.57E-1O 0. 0. 6.46E-06 6.46E-05

Y93 5.04E-08 0. 1.38E-09 0. 0. 2.OIE-05 1.05E-04

ZR93 2.07E-04 7.80E-05 5.55E-05 0. 3.OOE-04 7.1OE-04 1.47E-05

ZR95 5.13E-05 1.13E-05 1.OOE-05 0. 1.61E-05 6.03E-04 1.65E-05

ZR97 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05

NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06

N895 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.OOE-05

NB97 1.16E-1O 2.08E-11 9.74E-12 0. 2.31E-11 9.23E-07 7.52E-06

M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06

M099 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05

TC99M 4.81E-13 9.41E-13 1.56E-11 0. 1.37E-11 2.57E-07 1.30E-06

TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06

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

RUIO3 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21E-05

RUIO5 4.13E-1O 0. 1.50E-10 0. 3.63E-1O 4.30E-06 2.69E-05

RU1O6 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04

RHIO5 3.91E-09 2.1OE-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05

PDIO7 0. 2.65E-07 2.51E-08 0. 1.97E-06 3.16E-05 7.26E-07

PDIO9 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05

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

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

CDII3M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05

CDI15M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05

SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05

SN125 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05

SN126 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05

SB124 1.55E-05 2.OOE-07 5.41 E-06 3.41 E-08 0. 8.76E-04 4.43E-05

SB125 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05

SB126 1.72E-06 2.62E-08 6.16E-07 1.OOE-08 0. 2.86E-04 5.67E-05

SB127 1.36E-07 2.09E-09 4.70E-08 1.51E-09 0. 6.17E-05 3.82E-05

TEI25M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06

TEI27M 6.72E-06 2.31E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05

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

TE129M 5.19E-06 1.85E-06 8.22E-07 1.71E-06 1.36E-05 4.76E-04 4.91E-05

TE129 2.64E-11 9.45E-12 6.44E-12 1.93E-11 6.94E-11 7.93E-07 6.89E-06

TE13IM 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05

TE131 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07

TE132 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05

TE133M 2.93E-11 1.51E-11 1.50E-11 2.32E-11 1.OIE-10 1.60E-06 4.77E-06

TE134 1.53E-11 8.81E12 9.40E-12 1.24E-11 5.71E-11 1.23E-06 4.87E-07

1129 1.05E-05 6.40E-06 5.71E-06 4.28E-03 1.08E-05 0. 2.15E-07

1130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0. 1.38E-06

1131 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07
Proc No ODCM

Attachment 5

Revision 25

Page 7 of 16

INHALATION DOSE COMMITMENT FACTORS

CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 5.72E-07 1.1OE-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07

1133 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0. 1.48E-06

1134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07

1135 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06

XEI31M 0. 0. 0. 0. 0. 3.30E-09 0.

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

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

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

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

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

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

CS134M 6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08

CS134 1.76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06

CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07

CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.13E-06

CS137 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81E-05 9.78E-07

CS138 1.71E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08

CS139 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12

BA139 4.98E-1O 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05

BAI4O 2.OOE-05 1.75E-08 1.17E-06 0. 5.71E-09 4.71E-04 2.75E-05

BAI4I 5.29E-11 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08

BA142 1.35E-11 9.73E-15 7.54E-13 0. 7.87E-15 4.44E-07 7.41E-10

LA14O 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.IOE-05

LAI41 2.28E-09 5.31E-1O 1.15E-10 0. 0. 4.48E-06 4.37E-05

LA142 3.50E-1O 1.IIE-1O 3.49E-11 0. 0. 2.35E-06 2.05E-05

CEI4I 1.06E-05 5.28E-06 7.83E-07 0. 2.31E-06 1.47E-04 1.53E-05

CE143 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05

CE144 t83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04

PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11E-07 1.17E-04 2.63E-05

PR144 1.61E-11 4.99E-12 8.IOE-13 0. 2.64E-12 4.23E-07 5.32E-08

ND147 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05

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

PMI48M 3.31 E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05

PM148 1.61E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.O1E-05

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

PMI5I 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05

SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06

SM153 7.24E-08 4.51E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05

EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.73E-04 9.OOE-04 1.14E-05

EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05

EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51E-04 2.79E-04 5.39E-05

EU156 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05

TBI6O 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05

H0166M 1.34E-03 2.81E-04 2.37E-04 0. 4.O1E-04 1.13E-03 1.63E-05

W181 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71E-06 2.61E-07

W185 8.31E-07 2.08E-07 2.91E-08 0. 0. 1.86E-04 1.1IE-05

W187 4.41E-09 2.61E-09 1.17E-09 0. 0. 1.11E-05 2.46E-05
Proc No ODCM

Attachment 5

Revision 25

Page 8 of 16

INHALATION DOSE COMMITMENT FACTORS

CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05

B1210 0. 5.11E-06 5.65E-07 0. 5.76E-05 3.70E-03 3.21E-05

P0210 1.70E-03 2.76E-03 4.09E-04 0. 8.85E-03 1.05E-01 4.32E-05

RN222 0. 0. 0. 0. 0. 4.82E-06 0.

RA223 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.OOE-04

RA224 8.44E-05 1.53E-07 1.69E-05 0. 4.06E-06 2.92E-02 3.34E-04

RA225 1.28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9.74E-02 2.84E-04

RA226 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04

RA228 1.49E-01 3.94E-06 1.68E-01 0. 1.04E-04 5.37E-01 5.14E-05

AC225 1.81E-03 1.87E-03 1.21E-04 0. 1.99E-04 7.37E-02 2.67E-04

AC227 4.96E+00 8.05E-01 3.07E-O1 0. 1.77E-01 8.04E-01 5.22E-05

TH227 9.24E-04 1.26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04

TH228 8.06E-01 1.04E-02 2.72E-02 0. 5.41E-02 3.34E+00 3.59E-04

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

TH230 3.30E+00 1.73E-01 9.20E-02 0. 8.52E-01 1.85E+00 3.84E-05

TH232 3.68E+00 1.47E-01 1.28E-01 0. 7.28E-01 1.77E+00 3.27E-05

TH234 6.94E-06 3.07E-07 2.OOE-07 0. 1.62E-06 6.31 E-04 7.32E-05

PA231 8.62E+00 2.86E-01 3.43E-01 0. 1.56E+00 1.92E-01 4.57E-05

PA233 4.14E-06 6.48E-07 7.25E-07 0. 2.38E-06 9.77E-05 8.95E-06

U232 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05

U233 4.64E-02 0. 2.82E-03 0. 7.62E-03 1.77E-01 4.OOE-05

U234 4.46E-02 0. 2.76E-03 0. 7.47E-03 1.74E-01 3.92E-05

U235 4.27E-02 0. 2.59E-03 0. 7.01 E-03 1.63E-01 4.98E-05

U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05

U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1.29E-05

U238 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51E-05

NP237 2.88E+00 2.21E-01 1.19E-01 0. 7.41E-01 1.74E-01 5.06E-05

NP238 1.26E-06 2.56E-08 1.97E-08 0. 8.16E-08 3.39E-05 2.50E-05

NP239 1.26E-07 9.04E-09 6.35E-09 0. 2.63E-08 1.57E-05 1.73E-05

PU238 4.77E+00 6.05E-01 1.21E-01 0. 4.47E-01 6.08E-01 4.65E-05

PU239 5.24E+00 6.44E-01 1.28E-01 0. 4.78E-01 5.72E-01 4.24E-05

PU240 5.23E+00 6.43E-01 1.27E-01 0. 4.77E-01 5.71E-01 4.33E-05

PU241 1.46E-01 6.33E-03 2.93E-03 0. 1.1OE-02 5.06E-04 8.90E-07

PU242 4.85E+00 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05

PU244 5.67E+00 7.1OE-01 1.41E-01 0. 5.27E-01 6.30E-01 6.20E05

AM241 1.74E+00 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05

AM242M 1.79E+00 7.65E-01 1.27E-01 0. 7.71E-01 8.14E-02 5.96E-05

AM243 1.72E+00 7.53E-01 1.20E-01 0. 7.42E-01 1.92E-01 5.55E-05

CM242 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05

CM243 1.61E+00 7.33E-01 9.95E-02 0. 3.74E-01 2.IOE-01 4.98E-05

CM244 1.33E+00 6.48E-01 8.31 E-02 0. 3.06E-01 2.02E-01 4.82E-05

CM245 2.14E+00 8.16E-01 1.28E-01 0. 5.03E-01 1.95E-01 4.49E-05

CM246 2.13E+00 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05

CM247 2.07E+00 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.80E-05

CM248 1.72E+01 6.61E÷00 1.04E+00 0. 4.08E+00 1.61E+00 9.35E-04

CF252 3.92E+00 0. 9.33E-02 0. 0. 6.62E-01 1.84E-04
Proc No ODCM

Attachment 5

Revision 25

Page 9 of 16

INHALATION DOSE COMMITMENT FACTORS

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07 1.59E-07

BEIO 2.78E-04 4.33E-05 7.09E-06 0. 0. 3.84E-04 1.77E-05

C14 3.25E-06 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07 6.09E-07

N13 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09 8.65E-09

F18 6.52E-07 0. 7.10E-08 0. 0. 0. 3.89E-08

NA22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05

NA24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06

P32 2.36E-04 1.37E-05 8.95E-06 0. 0. 0. 1.16E-05

AR39 0. 0. 0. 0. 0. 4.OOE-09 0.

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

CA4I 4.05E-05 0. 4.38E-06 0. 0. 1.01 E-01 3.03E-07

SC46 7.24E-05 1.41E-04 4.18E-05 0. 1.35E-04 0. 2.98E-05

CR51 0. 0. 1.69E-08 9.37E-09 3.84E-09 2.62E-06 3.75E-07

MN54 0. 6.39E-06 1.05E-06 0. 1.59E-06 2.48E-04 8.35E-06

MN56 0. 2.12E-1O 3.15E-11 0. 2.24F-1O 1.90E-06 7.18E-06

FE55 4.18E-06 2.98E-06 6.93E-07 0. 0. 1.55E-05 7.99E-07

FE59 1.99E-06 4.62E-06 1.79E-06 0. 0. 1.91E-04 2.23E-05

C057 0. 1.18E-07 1.15E-07 0. 0. 7.33E-05 3.93E-06

C058 0. 2.59E-07 3.47E-07 0. 0. 1.68E-04 1.19E-05

C060 0. 1.89E-06 2.48E-06 0. 0. 1.09E-03 3.24E-05

N159 5.44E-06 2.02E-06 9.24E-07 0. 0. 1.41E-05 6.48E-07

N163 7.25E-05 5.43E-06 2.47E-06 0. 0. 3.84E-05 1.77E-06

N165 2.73E-1O 3.66E-11 1.59E-11 0. 0. 1.17E-06 4.59E-06

CU64 0. 2.54E-10 1.06E-10 0. 8.O1E-1O 1.39E-06 7.68E-06

ZN65 4.82E-06 1.67E-05 7.80E-06 0. 1.08E-05 1.55E-04 5.83E-06

ZN69M 1.44E-09 3.39E-09 3.11E-10 0. 2.06E-09 3.92E-06 2.14E-05

ZN69 6.04E-12 1.15E-11 8.07E-13 0. 7.53E-12 1.98E-07 3.56E-08

SE79 0. 5.43E-07 8.71E-08 0. 8.13E-07 7.71E-05 3.53E-06

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

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

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

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

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

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

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

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

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

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

RB86 0. 2.38E-05 1.05E-05 0. 0. 0. 2.21E-06

RB87 0. 1.40E-05 4.58E-06 0. 0. 0. 3.05E-07

RB88 0. 6.82E-08 3.40E-08 0. 0. 0. 3.65E-15

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

SR89 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05

SR9O 1.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05

SR91 1.1OE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05

SR92 1.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05

*Includes a 50% increase to account for percutaneous transpiration.
Proc No ODCM

Attachment 5

Revision 25

Page 10 of 16

INHALATION DOSE COMMITMENT FACTORS

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 373E-07 0. 1.OOE-08 0. 0. 3.66E-05 6.99E-05

Y91M 4.63E-11 0. 1.77E-12 0. 0. 4.OOE-07 3.77E-09

Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.11E-05

Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05

Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05

ZR93 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05

ZR95 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05

ZR97 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05

NB93M 4.14E-05 1.36E05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06

N695 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21E-05

NB97 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91E-07 2.71E-07

M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81E-05 3.99E-06

M099 0. 2.IIE-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05

TC99M 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07

TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06

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

RUIO3 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05

RUIO5 1.40E-1O 0. 5.42E-11 0. 1.76E-1O 2.27E-06 1.13E-05

RU1O6 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.O1E-03 1.20E-04

RHIO5 1.32E-09 9.48E-1O 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05

PD1O7 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07

PDIO9 0. 6.56E-1O 1.66E-10 0. 3.36E-09 3.19E-06 1.96E-05

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

AG11I 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.OOE-05 3.OOE-05

CDII3M 0. 2.17E-04 7.1OE-06 0. 2.43E-04 3.59E-04 1.68E-05

CD115M 0. 3.48E-05 1.14E-06 0. 2.82E-05 3.03E-04 5.IOE-05

SN123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05

SN125 1.66E-06 4.42E.-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05

SN126 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05

SB124 5.38E-06 9.92E-08 2.1OE-06 1.22E-08 0. 4.81E-04 4.98E-05

SB125 9.23E-06 1.OIE-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05

SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.OIE-05

SB127 4.64E-08 9.92E-10 1.75E-08 5.21E-10 0. 3.31E-05 3.94E-05

TEI25M 6.IOE-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06

TEI27M 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05

TE127 2.51E-10 1.14E-10 5.52E-11 1.77E-10 9.IOE-10 1.40E-06 1.OIE-05

TE129M 1.74E-06 8.23E-07 2.81 E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05

TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07

TEI31M 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05

TE131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09

TE132 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05

TE133M 1.O1E-11 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71E-07 1.23E-07

TE134 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-11 6.75E-07 1.37E-09

1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07

1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06

1131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 8.1IE-07
Proc No ODCM

Attachment 5

Revision 25

Page 11 ofl6

INHALATION DOSE COMMITMENT FACTORS

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. t59E-07

1133 t52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0. 1.29E-06

1134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09

1135 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07

XEI3IM 0. 0. 0. 0. 0. 2.70E-09 0.

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

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

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

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

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

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

CSI34M 2.20E-08 4.35E-08 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08

CS134 6.28E-05 1.41E-04 6.86E-05 0. 4.69E-05 1.83E-05 1.22E-06

CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07

CS136 6.44E-06 2.42E-05 1.71E-05 0. 1.38E-05 2.22E-06 1.36E-06

CS137 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51E-05 1.06E-06

CS138 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11

CS139 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23

BA139 1.67E-10 1.18E-13 4.87E-12 0. 1.1IE-13 8.08E-07 8.06E-07

BA14O 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05

BAI4I 1.78E-11 1.32E-14 5.93E-13 0. 1.23E-14 4.IIE-07 9.33E-14

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

LA14O 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05

LAI4I 7.63E-10 2.35E-1O 3.87E-11 0. 0. 2.31E-06 1.54E-05

LA142 1.20E-10 5.31E-11 1.32E-11 0. 0. 1.27E-06 1.50E-06

CEI4I 3.55E-06 2.37E-06 2.71E-07 0. 1.11E-06 7.67E-05 1.58E-05

CE143 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05

CE144 6.11E-04 2.53E-04 3.28E-05 0. 1.51E-04 1.67E-03 1.08E-04

PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05

PR144 5.37E-12 2.20E-12 2.72E-13 0. 1.26E-12 2.19E-07 2.94E-14

ND147 9.83E-07 1.07E-06 6.41E-08 0. 6.28E-07 4.65E-05 2.28E-05

PM147 1.15E-04 1.IOE-05 4.50E-06 0. 2.1OE-05 1.14E-04 5.87E-06

PM148M 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.IOE-05

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

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

PMI5I 1.20E-08 1.99E-09 1.O1E-09 0. 3.57E-09 6.56E-06 2.27E-05

SM15I 1.07E-04 2.1OE-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06

SM153 2.43E-08 2.O1E-08 1.47E-09 0. 6.56E-09 7.1IE-06 1.77E-05

EU152 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.O1E-04 1.35E-05

EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05

EU155 2.OOE-04 1.96E-05 1.21E-05 0. 7.65E-05 1.51E-03 5.97E-05

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

TB16O 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05

H0166M 4.40E-04 1.36E-04 9.87E-05 0. 2.OOE-04 6.24E-04 1.68E-05

W181 8.90E-09 2.88E-09 3.O1E-10 0. 0. 2.95E-06 2.69E-07

W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05

W187 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 2.21E-05
Proc No 00CM

Attachment 5

Revision 25

Page 12 of 16

INHALATION DOSE COMMITMENT FACTORS

TEEN INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB2IO 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05

B1210 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91E-03 3.19E-05

P0210 5.68E-04 1.22E-03 1.37E-04 0. 4.21E-03 5.41E-02 4.45E-05

RN222 0. 0. 0. 0. 0. 3.94E-06 0.

RA223 2.57E-04 3.93E-07 5.14E-05 0. 1.12E-05 4.39E-02 3.04E-04

RA224 2.83E-05 6.77E-08 5.65E-06 0. 1.93E-06 1.51 E-02 3.29E-04

RA225 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04

RA226 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-O1 3.I1E-04

RA228 5.34E-02 1.74E-06 5.88E-02 0. 4.97E05 2.78E-01 5.30E-05

AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81 E-02 2.70E-04

AC227 2.49E+00 3.69E-01 1.48E-01 0. 1.07E-01 4.16E-01 5.38E-05

TH227 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04

TH228 2.60E-01 4.37E-03 8.78E-03 0. 2.45E-02 1.69E+00 3.70E-04

TH229 9.06E+00 1.36E-01 4.45E-01 0. 6.67E-01 5.05E+00 3.36E-04

TI-1230 2.34E+00 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05

TH232 2.61E+00 1.14E-01 9.21E-02 0. 5.60E-01 8.60E-01 3.36E-05

TH234 2.32E-06 1.35E-07 6.71E-08 0. 7.73E-07 3.26E-04 7.49E-05

PA231 5.32E+00 2.OOE-01 2.07E-01 0. 1.12E+00 9.91E-02 4.71E-05

PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.OOE-05

U232 7.31 E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05

U233 1.55E-02 0. 9.42E-04 0. 3.63E-03 9.18E-02 4.12E-05

U234 1.48E-02 0. 9.23E-04 0. 3.55E-03 8.99E-02 4.04E-05

U235 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05

U236 1.42E-02 0. 8.86E-04 0. 3.41 E-03 8.62E-02 3.79E-05

U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05

U238 1.36E-02 0. 8.1OE-04 0. 3.12E-03 7.89E-02 3.62E-05

NP237 1.77E+00 1.54E-01 7.21E-02 0. 5.35E-01 8.99E-02 5.22E-05

NP238 4.23E-07 1.13E-08 6.59E-09 0. 3.88E-08 1.75E-05 2.38E-05

NP239 4.23E-08 3.99E-09 2.21E-09 0. 1.25E-08 8.11E-06 1.65E-05

PU238 2.86E+00 4.06E-01 7.22E-02 0. 3.1OE-01 3.12E-01 4.79E-05

PU239 3.31E+00 4.50E-01 8.05E-02 0. 3.44E-01 2.93E-01 4.37E-05

PU240 3.31E+00 4.49E-01 8.04E-02 0. 3.43E-01 2.93E-01 4.46E-05

PU241 6.97E-02 3.57E-03 1.40E-03 0. 6.47E-03 2.60E-04 9.17E-07

PU242 3.07E+00 4.33E-01 7.75E-02 0. 3.31 E-01 2.82E-01 4.29E-05

PU244 3.59E+00 4.96E-01 8.88E-02 0. 3.79E-01 3.23E-01 6.39E-05

AM241 1.06E+00 4.07E-01 7.1OE-02 0. 5.32E-01 1.05E-01 4.88E-05

AM242M 1.07E+00 3.93E-01 7.15E-02 0. 5.30E-01 4.21E-02 6.14E-05

AM243 1.06E+00 3.92E-01 6.95E-02 0. 5.21E-01 9.91 E-02 5.72E-05

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

CM243 8.45E-01 3.50E-01 5.OOE-02 0. 2.34E-01 1.09E-01 5.13E-05

CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81 E-01 1.05E-01 4.96E-05

CM245 1.32E+00 4.IIE-01 7.53E-02 0. 3.52E-01 1.O1E-01 4.63E-05

CM246 1.31E+00 4.11E-01 7.52E-02 0. 3.51E-01 1.03E-01 4.54E-05

CM247 1.28E+00 4.04E-01 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05

CM248 1.06E+01 3.33E+00 6.11E-01 0. 2.85E+00 8.32E-01 9.63E-04

CF252 1.29E+00 0. 3.07E-02 0. 0. 3.43E-01 1.89E-04
Proc No ODCM

Attachment 5

Revision 25

Page 13 of 16

INHALATION DOSE COMMITMENT FACTORS

ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI H3* 0. 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07 1.58E-07

BEIO 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05

C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07

N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09

F18 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09

NA22 I .30E-05 1 .30E-05 1 .30E-05 I .30E-05 1 .30E-05 I .30E-05 1 .30E-05

NA24 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 I.28E-06 1.28E-06

P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05

AR39 0. 0. 0. 0. 0. 2.08E-09 0.

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

CA4I 3.83E-05 0. 4.13E-06 0. 0. 3.83E-06 2.86E-07

SC46 5.51E-05 1.07E-04 3.I1E-05 0. 9.99E-05 0. 3.23E-05

CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07

MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06

MN56 0. 1.55E-10 2.29E-1I 0. 1.63E-10 1.18E-06 2.53E-06

FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.OIE-06 7.54E-07

FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05

C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06

C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05

C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05

N159 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.1IE-07

N163 5.40E-05 3.93E-06 1.81E-06 0. 0. 2.23E-05 1.67E-06

N165 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.OOE-07 1.54E-06

CU64 0. 1.83E-10 7.69E-11 0. 5.78E-10 8.48E-07 6.12E-06

ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06

ZN69M 1.02E-09 2.45E-09 2.24E-10 0. 1.48E-09 2.38E-06 1.71E-05

ZN69 4.23E-12 8.14E-12 5.65E-13 0. 5.27E-12 1.15E-07 2.04E-09

SE79 0. 3.83E-07 6.09E-08 0. 5.69E-07 4.47E-05 3.33E-06

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

BR83 0. 0. 3.01 E-08 0. 0. 0. 2.90E-08

BR84 0. 0. 3.91E-08 0. 0. 0. 2.05E-13

BR85 0. 0. 1.60E-09 0. 0. 0. 0.

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

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

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

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

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

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

RB86 0. 1.69E-05 7.37E-06 0. 0. 0. 2.08E-06

RB87 0. 9.86E-06 3.21E-06 0. 0. 0. 2.88E-07

RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19

RB89 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21

SR89 3.80E-05 0. 1.09E-06 0. 0. I.75E-04 4.37E-05

SR9O 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05

SR91 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05

SR92 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06

*Includes a 50% increase to account for percutaneous transpiration.
Proc No ODCM

Attachment 5

Revision 25

Page 14 of 16

INHALATION DOSE COMMITMENT FACTORS

ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 2.61E-07 0. 7.O1E-09 0. 0. 2.12E-05 6.32E-05

Y9IM 326E-11 0. 1.27E-12 0. 0. 2.40E-07 166E-1O

Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81E-05

Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06

Y93 1.18E-08 0. 3.26E-1O 0. 0. 6.06E-06 5.27E-05

ZR93 5.22E-05 2.92E-06 1.37E-06 0. 1.11E-05 2.13E-05 1.51E-06

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

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

NB93M 3.IOE-05 1.O1E-05 2.49E-06 0. 1.16E-05 3.11E-05 2.38E-06

NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31E-05 1.30E-05

NB97 2.78E-11 7.03E-12 2.56E-12 0. 8.18E-12 3.OOE-07 3.02E-08

M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.IIE-05 3.79E-06

M099 0. 1.51E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.1OE-05

TC99M 1.29E-13 3.64E-13 4.63E-12 0. 5.52E-12 9.55E-08 5.20E-07

TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01E-04 7.54E-06

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

RUIO3 1.91E-07 0. 8.23E-08 0. 7.29E-07 6.31E-05 1.38E-05

RUIO5 9.88E-11 0. 3.89E-11 0. 1.27E-10 1.37E-06 6.02E-06

RUIO6 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04

RHIO5 9.24E-10 6.73E-10 4.43E-10 0. 2.86E-09 2.41E-06 1.09E-05

PDIO7 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07

PD1O9 0. 4.63E-10 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05

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

AGI11 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05

CDII3M 0. 1.54E-04 4.97E-06 0. 1.71E-04 2.08E-04 1.59E-05

CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.80E-05

SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05

SN125 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05

SN126 1.58E-04 4.18E-06 6.OOE-06 1.23E-06 0. 1.17E-03 1.59E-05

SB124 3.90E-06 7.36E-08 1.55E-06 9.44E-09 0. 3.IOE-04 5.08E-05

SB125 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05

SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.O1E-05

SB127 3.30E-08 7.22E-10 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05

TE125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06

TE127M 1.58E-06 7.21E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E05

TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06

TE129M 1.22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05

TE129 6.22E-12 2.99E-12 1.55E-12 4.87E-12 2.34E-11 2.42E-07 1.96E-08

TE131M 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05

TEI31 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09

TE132 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05

TE133M 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08

TE134 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11

1129 2.48E-06 2.1IE-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07

1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0. 9.61E-07

1131 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.85E-07
Proc No ODCM

Attachment 5

Revision 25

Page 15 of 16

INHALATION DOSE COMMITMENT FACTORS

ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08

1133 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11E-06

1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10

1135 3.35E-07 8.73E-07 3.21E-07 5.60E-05 1.39E-06 0. 6.56E-07

XEI3IM 0. 0. 0. 0. 0. 1.40E-09 0.

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

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

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

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

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

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

CSI34M 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09

CS134 4.66E-05 1.06E-04 9.1OE-05 0. 3.59E-05 1.22E-05 1.30E-06

CS135 1.46E-05 1.29E-05 5.99E-06 0. 5.11E-06 1.57E-06 2.11E-07

CS136 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-06 1.46E-06

CS137 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06

CS138 4.14E-08 7.76E-08 4.05E-08 0. 6.OOE-08 6.07E-09 2.33E-13

CS139 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31

BA139 1.17E-1O 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07

BA14O 4.88E-06 6.13E-09 3.21E-07 0. 2.09E-09 1.59E-04 2.73E-05

BAI4I 1.25E-11 9.41E-15 4.20E-13 0. 8.75E-15 2.42E-07 1.45E-17

BA142 3.29E-12 3.38E-15 2.07E-13 0. 2.86E-15 1.49E-07 1.96E-26

LA14O 4.30E-08 2.17E-08 5.73E-09 0. 0. 1.70E-05 5.73E-05

LAI41 5.34E-10 1.66E-10 2.71E-11 0. 0. 1.35E-06 7.31E-06

LA142 8.54E-11 3.88E-11 9.65E-12 0. 0. 7.91E-07 2.64E-07

CEI41 2.49E-06 1.69E-06 1.91E-07 0. 7.83E-07 4.52E-05 1.50E-05

CE143 2.33E-08 1.72E-08 1.91E-09 0. 7.60E-09 9.97E-06 2.83E-05

CE144 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04

PR143 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51E-05 2.50E-05

PR144 3.76E-12 1.56E-12 1.91E-13 0. 8.81E-13 1.27E-07 2.69E-18

ND147 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05

PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06

PMI48M 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05

PM148 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91E-05 5.80E-05

PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21E-06 2.50E-05

PMI51 8.50E-09 1.42E-09 7.21E-10 0. 2.55E-09 3.94E-06 2.OOE-05

SMI5I 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06

SM153 1.70E-08 1.42E-08 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05

EU152 2.38E-04 5.41E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05

EU154 7.40E-04 9.1OE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05

EU155 1.O1E-04 1.43E-05 9.21E-06 0. 6.59E-05 9.46E-05 5.95E-06

EU156 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05

TB16O 2.21E-05 0. 2.75E-06 0. 9.1OE-06 1.92E-04 2.68E-05

H0166M 3.37E-04 1.05E-04 8.OOE-05 0. 1.57E-04 3.94E-04 1.59E-05

W181 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71E-06 2.53E-07

W185 1.95E-07 6.47E-08 6.81E-09 0. 0. 5.57E-05 1.07E-05

W187 1.06E-09 8.85E-10 3.1OE-10 0. 0. 3.63E-06 1.94E-05
Proc No ODCM

Attachment 5

Revision 25

Page 16 of 16

INHALATION DOSE COMMITMENT FACTORS

ADULT INHALATION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05

B1210 0. 1.59E-06 1.32E-07 0. 1.92E-05 1.11E-03 2.95E-05

P0210 3.97E-04 8.60E-04 9.58E-05 0. 2.95E-03 3.14E-02 4.19E-05

RN222 0. 0. 0. 0. 0. 2.05E-06 0.

RA223 1.80E-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04

RA224 1.98E-05 4.78E-08 3.96E-06 0. 1.35E-06 8.77E-03 3.O1E-04

RA225 3.OOE-04 3.56E-07 5.99E-05 0. 1.OIE-05 2.92E-02 2.71E-04

RA226 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04

RA228 4.41 E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61 E-01 5.OOE-05

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

AC227 2.30E+00 3.05E-01 1.36E-01 0. 9.82E-02 2.41 E-01 5.08E-05

TH227 2.17E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04

TH226 2.OOE-O1 3.39E-03 6.77E-03 0. 1.89E-02 1.O1E+O0 3.49E-04

TH229 8.88E+00 1.33E-01 4.36E-01 0. 6.52E-01 3.49E+00 3.17E-04

TH230 2.29E+00 1.31E-01 6.36E-02 0. 6.40E-01 6.21E-01 3.73E-05

TH232 2.56E+00 1.12E-01 9.04E-02 0. 5.47E-01 5.96E-01 3.17E-05

TH234 1.63E-06 9.56E-08 4.70E-08 0. 5.41E-07 1.89E-04 7.03E-05

PA231 5.08E+00 1.91E-01 1.98E-01 0. 1.07E+00 5.75E-02 4.44E-05

PA233 1.21E-06 2.42E-07 2.09E-07 0. 9.15E-07 3.52E-05 1.02E-05

U232 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 4.21E-05

U233 1.09E-02 0. 6.60E-04 0. 2.54E-03 5.32E-02 3.89E-05

U234 1.04E-02 0. 6.46E-04 0. 2.49E-03 5.22E-02 3.81E-05

U235 1.OOE-02 0. 6.07E-04 0. 2.34E-03 4.90E-02 4.84E-05

U236 1.OOE-02 0. 6.20E-04 0. 2.39E-03 5.OOE-02 3.57E-05

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

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

NP237 1.69E+00 1.47E-01 6.87E-02 0. 5.IOE-01 5.22E-02 4.92E-05

NP238 2.96E-07 8.OOE-09 4.61E-09 0. 2.72E-08 1.02E-05 2.13E-05

NP239 2.87E-08 2.82E-09 1.55E-09 0. 8.75E-09 4.70E-06 1.49E-05

PU238 2.74E+00 3.87E-01 6.90E-02 0. 2.96E-01 1.82E-01 4.52E-05

PU239 3.19E+00 4.31E-01 7.75E-02 0. 3.30E-01 1.72E-01 4.13E-05

PU240 3.18E+00 4.30E-01 7.73E-02 0. 3.29E-01 1.72E-01 4.21E-05

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

PU242 2.95E+00 4.15E-01 7.46E-02 0. 3.17E-01 1.65E-01 4.05E-05

PU244 3.45E+00 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05

AM241 1.O1E+00 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05

AM242M 1.02E+00 3.46E-01 6.73E-02 0. 5.01 E-01 244E-02 5.79E-05

AM243 1.O1E+00 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05

CM242 1.48E-02 1.51 E-02 9.84E-04 0. 4.48E-03 3.92E-02 4.91 E-05

CM243 7.86E-01 2.97E-01 4.61E-02 0. 2.15E-01 6.31E-02 4.84E-05

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

CM245 1.26E+00 3.59E-01 7.14E-02 0. 3.33E-01 5.85E-02 4.36E-05

CM246 1.25E+00 3.59E-01 7.13E-02 0. 3.33E-01 5.96E-02 4.29E-05

CM247 1.22E+00 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05

CM248 1.OIE+01 2.91E+00 5.79E-01 0. 2.70E+00 4.82E-01 9.09E-04

CF252 9.78E-01 0. 2.33E-02 0. 0. 1.99E-01 1.78E-04
Proc No ODCM

Attachment 6

Revision 25

Page 1 of 2

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND (DFG1

(mrem/hr per pCi/rn 2)

ELEMENT TOTAL BODY SKIN

H-3 0.0 0.0

C-14 0.0 0.0

Na-24 2.50E-08 2.90E-08

P-32 0.0 0.0

Cr-51 2.20E-10 2.60E-10

Mn-54 5.80E-09 6.80E-09

Mn-56 1.IOE-08 1.30E-08

Fe-55 0.0 0.0

Fe-59 8.OOE-09 9.40E-09

Co-58 7.OOE-09 8.20E-09

Co-60 1 .70E-08 2.OOE-08

Ni-63 0.0 0.0

Ni-65 3.70E-09 4.30E-09

Cu-64 1.50E-09 1.70E-09

Zn-65 4.OOE-09 4.60E-09

Zn-69 0.0 0.0

Br-83 6.40E-11 9.30E-11

Br-84 I .20E-08 I .40E-08

Br-85 0.0 0.0

Rb-86 6.30E-10 7.20E-10

Rb-88 3.50E-09 4.OOE-09

Rb-89 I .50E-08 I .80E-08

Sr-89 5.60E-13 6.50E-13

Sr-91 7.IOE-09 8.30E-09

Sr-92 9.OOE-09 I .OOE-08

Y-90 2.20E-12 2.60E-12

Y-91m 3.80E-09 4.40E-09

Y-91 2.40E-11 2.70E-11

Y-92 I .60E-09 I .90E-09

Y-93 5.70E-10 7.80E-l0

Zr-95 5.00E-09 5.80E-09

Zr-97 5.50E-09 6.40E-09

Nb-95 5.1OE-09 6.OOE-09

Mo-99 1 .90E-09 2.20E-09

Tc-99m 9.60E-10 1.1OE-09

Tc-101 2.70E-09 3.OOE-09
Proc No ODCM

Attachment 6

Revision 25

Page 2 of 2

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND CDFG1

(mremlhr per pCi/rn 2)

ELEMENT TOTAL BODY SKIN

Ru-I 03 3.60E-09 4.20E-09

Ru-105 4.50E-09 5.IOE-09

Ru-106 I.50E-09 1.80E-09

Ag-Ibm l.80E-08 2.1OE-08

Te-125m 3.50E-I1 4.80E-11

Te-127m 1.IOE-12 I.30E-12

Te-127 I.OOE-1I 1.1OE-l1

Te-129m 7.70E-I0 9.OOE-10

Te-129 7.IOE-I0 8.40E-b0

Te-131m 8.40E-09 9.90E-09

Te-131 2.20E-09 2.60E-06

Te-I32 1.70E-09 2.OOE-09

1-130 I.40E-08 I.70E-08

1-131 2.80E-09 3.40E-09

1-132 1.70E-08 2.OOE-08

1-133 3.70E-09 4.50E-09

1-134 I.60E-08 I.90E-08

1-135 1.20E-08 I.40E-08

Cs-134 l.20E-08 I.40E-08

Cs-136 I.50E-08 1.70E-08

Cs-I 37 4.20E-09 4.90E-09

Cs-138 2.1OE-08 2.40E-08

Ba-I 39 2.40E-09 2.70E-09

Ba-I40 2.IOE-09 2.40E-09

Ba-141 4.30E-09 4.90E-09

Ba-I 42 7.90E-09 9.OOE-09

La-I40 1.50E-08 1.70E-08

La-142 l.50E-08 1.80E-08

Ce-14I 5.50E-I0 6.20E-l0

Ce-I43 2.20E-09 2.50E-09

Ce-144 3.20E-10 3.70E-10

Pr-143 0.0 0.0

Pr-144 2.OOE-10 2.30E-bO

Nd-I47 1.OOE-09 1.20E-09

W-187 3.IOE-09 3.60E-09

Np-239 9.50E-b0 I.IOE-09
Proc No ODCM

Attachment 7

Revision 25

Page 1 of I

BIOACCUMULATION FACTORS

i.Cilpm per nCiImI

FRES HWATER

ELEMENT FISH

H 9.OE-O1

C 46E 03

NA 1.0E02

P 1.0E05

CR 2.OE 02

MN 4.OE 02

FE 1.0E02

CO 5.OE 01

NI 1.0E02

CU 5.OE 01

ZN 2.0E03

BR 4.2E 02

RB 2.OE 03

SR 3.OE 01

Y 2.5E 01

ZR 3.3E 00

NB 3.OE 04

MO 1.OEOI

TC 1.5E01

RU 1.OEO1

RH 1.OEOI

TE 4.0E02

I 1.5E01

CS 2.0E03

BA 4.OEOO

LA 2.5E01

CE 1.OEOO

PR 2.5E 01

ND 2.5E 01

W 1.2E03

NP 1.OEOI
Proc No ODCM

Attachment 8

Revision 25

Page 1 of 16

INGESTION DOSE COMMITMENT FACTORS

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl-LLI

H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07

BEIO 1.71E-05 2.49E-06 5.16E-07 0. 1.64E-06 0. 2.78E-05

C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06

N13 5.85E-08 5.85E-08 5.85E-08 5.835E-08 5.85E-08 5.85E-08 5.85E-08

F18 5.19E-06 0. 4.43E.07 0. 0. 0. 1.22E-06

NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05

NA24 1.O1E-05 1.QIE-05 1.OIE-05 1.OIE-05 1.OIE-05 1.O1E-05 1.OIE-05

P32 1.70E-03 1.OOE-04 6.59E-05 0. 0. 0. 2.30E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA41 3.74E-04 0. 4.08E-05 0. 0. 0. 1.91 E-07

SC46 3.75E-08 5.41 E-08 1.69E-08 0. 3.56E-08 0. 3.53E-05

CR51 0. 0. 1.41E-08 9.20E-09 2.O1E-09 1.79E-08 4.I1E-07

MN54 0. 1.99E-05 4.51E-06 0. 4.41E-06 0. 7.31E-06

MN56 0. 8.18E-07 1.41E-07 0. 7.03E-07 0. 7.43E-05

FE55 1.39E-05 8.98E-06 2.40E-06 0. 0. 4.39E-06 1.14E-06

FE59 3.08E-05 5.38E-05 2.12E-05 0. 0. 1.59E-05 2.57E-05

C057 0. 1.15E-06 1.87E-06 0. 0. 0. 3.92E-06

C058 0. 3.60E-06 8.98E-06 0. 0. 0. 8.97E-06

C060 0. 1.08E-05 2.55E-05 0. 0. 0. 2.57E-05

N159 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.16E-07

NI63 6.34E-04 3.92E-05 2.20E-05 0. 0. 0. 1.95E-06

N165 4.70E-06 5.32E-07 2.42E-07 0. 0. 0. 4.05E-05

CU64 0. 6.09E-07 2.82E-07 0. 1.03E-06 0. 1.25E-05

ZN65 1.84E-05 6.31E-05 2.91E-05 0. 3.06E-05 0. 5.33E-05

ZN69M 1.50E-06 3.06E-06 2.79E-07 0. 1.24E-06 0. 4.24E-05

ZN69 9.33E-08 1.68E-07 1.25E-08 0. 6.98E-08 0. 1.37E-05

SE79 0. 2.1OE-05 3.90E-06 0. 2.43E-05 0. 5.58E-07

BR82 0. 0. 1.27E-05 0. 0. 0. 0.

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

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

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

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

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

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

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

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

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

RB86 0. 1.70E-04 8.40E-05 0. 0. 0. 4.35E-06

RB87 0. 8.88E-05 3.52E-05 0. 0. 0. 5.98E-07

RB88 0. 4.98E-07 2.73E-07 0. 0. 0. 4.85E-07

RB89 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08

SR89 2.51E-03 0. 7.20E-05 0. 0. 0. 5.16E-05

SR9O 1.85E-02 0. 4.71 E-03 0. 0. 0. 2.31 E-04

SR91 5.OOE-05 0. 1.81E-06 0. 0. 0. 5.92E-05

SR92 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04
Proc No ODCM

Attachment 8

Revision 25

Page 2 of 16

INGESTION DOSE COMMITMENT FACTORS

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04

Y91M 8.1OE-1O 0. 2.76E-11 0. 0. 0. 2.70E-06

Y91 1.13E-06 0. 3.OIE-08 0. 0. 0. 8.1OE-05

Y92 7.65E-09 0. 2.15E-1O 0. 0. 0. 1.46E-04

Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04

ZR93 1.93E-07 9.18E-08 5.54E-08 0. 2.71E-07 0. 2.39E-05

ZR95 2.06E-07 5.02E-08 3.56E-08 0. 5.41 E-08 0. 2.50E-05

ZR97 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04

NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06

NB95 4.20E-08 1.73E-08 1.00E-08 0. 1.24E-08 0. 1.46E-05

NB97 4.59E-10 9.79E-11 3.53E-11 0. 7.65E-11 0. 3.09E-05

M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21E-06

M099 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05

TC99M 1.92E-09 3.96E-09 5.10E-08 0. 4.26E-08 2.07E-09 1.15E-06

TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31E-06

TCIOI 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07

RUIO3 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05

RUIO5 1.36E-07 0. 4.58E-08 0. 1.OOE-06 0. 5.41E-05

RU106 2.41E-05 0. 3.OIE-06 0. 2.85E-05 0. 1.83E-04

RH1O5 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05

PDIO7 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07

PD109 0. 1.50E-06 3.62E-07 0. 5.51E-06 0. 3.68E-05

AGIIOM 9.96E-07 7.27E-07 4.81E-07 0. 1.04E-06 0. 3.77E-05

AGIII 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E-05

CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05

CDII5M 0. 1.42E-05 4.93E-07 0. 7.41E-06 0. 8.09E-05

SN123 2.49E-04 3.89E-06 6.50E-06 3.91E-06 0. 0. 6.58E-05

SN125 7.41E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.IIE-04

SN126 5.53E-04 7.26E-06 1.80E-05 1.91E-06 0. 0. 2.52E-05

SB124 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.60E-05

SB125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05

SB126 8.06E-06 1.58E-07 2.91E-06 6.19E-08 0. 5.07E-06 8.35E-05

SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91E-05

TEI25M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.IIE-05

TE127M 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.36E-05

TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.1OE-05

TE129M 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05

TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05

TEI31M 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21E-05 0. 1.03E-04

TE131 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.1IE-06

TE132 2.08E-05 1.03E-05 9.61E-06 1.52E-05 6.44E-05 0. 3.81E-05

TEI33M 3.91E-07 1.79E-07 1.71E-07 3.45E-07 1.22E-06 0. 1.93E-05

TE134 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.06E-06

1129 2.86E-05 2.12E-05 1.55E-05 1.36E..02 2.51E-05 0. 4.24E-07

1130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06

1131 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 1.51E-06
Proc No ODCM

Attachment 8

Revision 25

Page 3 of 16

INGESTION DOSE COMMITMENT FACTORS

INFANT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06

1133 1.25E-05 1.82E-05 5.33E-06 3.31E-03 2.14E-05 0. 3.08E-06

1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06

1135 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06

XEI3IM 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

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

CSI34M 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07

CS134 3.77E-04 7.03E-04 7.1OE-05 0. 1.81E-04 7.42E-05 1.91E-06

CS135 1.33E-04 1.21E-04 6.30E-06 0. 3.44E-05 1.31E-05 4.37E-07

CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.IOE-05 2.05E-06

CS137 5.22E-04 6.IIE-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91E-06

CS138 4.81E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06

CS139 3.IOE-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08

BA139 8.81E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05

BAI4O 1.71E-04 1.71E-07 8.81E-06 0. 4.06E-08 1.05E-07 4.20E-05

BA141 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E-10 5.19E-06

BA142 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-11 9.26E-11 7.59E-07

LA14O 2.I1E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05

LAI4I 2.89E-09 8.38E-10 1.46E-1O 0. 0. 0. 9.61E-05

LA142 1.1OE-09 4.04E-1O 9.67E-11 0. 0. 0. 6.86E-05

CE14I 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05

CE143 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05

CE144 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.71E-04

PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05

PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-11 0. 4.93E-06

ND147 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05

PM147 3.88E-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06

PMI48M 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.443-05

PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05

PM149 1.38E-08 1.81E-09 7.90E-10 0. 2.20E-09 0. 4.86E-05

PM15I 6.18E-09 9.O1E-10 4.56E-1O 0. 1.07E-09 0. 4.17E-05

SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06

SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05

EU152 6.74E-07 1.79E-07 1.51E-07 0. 5.02E-07 0. 1.59E-05

EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05

EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05

EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05

TBI6O 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05

H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0.

W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07

W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05

W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05
Proc No ODCM

Attachment 8

Revision 25

Page4ofl6

INGESTION DOSE COMMITMENT FACTORS

INFANT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05

BI2IO 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.276-05

P0210 3.IOE-03 5.93E-03 7.41E-04 0. 1.26E-02 0. 6.61E-05

RN222 0. 0. 0. 0. 0. 0. 0.

RA223 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04

RA224 1.46E-02 3.296-05 2.91E-03 0. 6.OOE-04 0. 3.866-04

RA225 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04

RA226 6.20E-01 4.76E-05 5.14E-01 0. 8.71 E-04 0. 3.446-04

RA228 4.32E-01 2.58E-05 4.866-01 0. 4.73E-04 0. 5.866-05

AC225 3.92E-05 5.036-05 2.63E-06 0. 3.69E-06 0. 4.36E-04

AC227 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05

TH227 1.20E-04 2.OIE-06 3.45E-06 0. 7.41E-06 0. 5.70E-04

TH228 2.476-03 3.38E-05 8.366-05 0. 1.58E-04 0. 5.84E-04

Th229 1.486-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31 E-04

TH230 3.80E-03 1.90E-04 1.066-04 0. 9.12E-04 0. 6.246-05

TH232 4.24E-03 1.63E-04 1.65E-04 0. 7.79E-04 0. 5.31E-05

TH234 6.92E-07 3.77E-08 2.006-08 0. 1.39E-07 0. 1.19E-04

PA231 7.576-03 2.50E-04 3.02E-04 0. 1.346-03 0. 7.446-05

PA233 3.116-08 6.09E-09 5.436-09 0. 1.676-08 0. 1.466-05

U232 2.42E-02 0. 2.166-03 0. 2.37E-03 0. 7.04E-05

U233 5.086-03 0. 3.876-04 0. 1.08E-03 0. 6.51E-05

U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.376-05

U235 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.IOE-05

U236 4.67E-03 0. 3.64E-04 0. 1.OIE-03 0. 5.98E-05

U237 4.956-07 0. 1.326-07 0. 1.23E-06 0. 2.I1E-05

U238 4.476-03 0. 3.33E-04 0. 9.286-04 0. 5.716-05

NP237 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.236-05

NP238 1.246-07 3.126-09 1.92E-09 0. 6.81E-09 0. 4.17E-05

NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.986-09 0. 2.876-05

PU238 1.346-03 1.696-04 3.40E-05 0. 1.216-04 0. 7.576-05

PU239 1.456-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.916-05

PU240 1.45E-03 1.776-04 3.546-05 0. 1.28E-04 0. 7.04E-05

PU241 4.38E-05 1.906-06 8.826-07 0. 3.176-06 0. 1.456-06

PU242 1.356-03 1.706-04 3.41E-05 0. 1.236-04 0. 6.77E-05

PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41E-04 0. 1.O1E-04

AM241 1.53E-03 7.186-04 1.09E-04 0. 6.556-04 0. 7.70E-05

AM242M 1.586-03 7.026-04 1.13E-04 0. 6.64E-04 0. 9.696-05

AM243 1.51E-03 6.886-04 1.06E-04 0. 6.366-04 0. 9.03E-05

CM242 1.376-04 1.24E-04 9.1OE-06 0. 2.626-05 0. 8.236-05

CM243 1.45E-03 6.886-04 8.986-05 0. 3.276-04 0. 8.1OE-05

CM244 1.226-03 6.166-04 7.596-05 0. 2.71E-04 0. 7.84E-05

CM245 1.886-03 7.496-04 1.13E-04 0. 4.326-04 0. 7.306-05

CM246 1.876-03 7.49E-04 1.13E-04 0. 4.316-04 0. 7.17E-05

CM247 1.82E-03 7.36E-04 1.116-04 0. 4.246-04 0. 9.43E-05

CM248 1.51E-02 6.076-03 9.166-04 0. 3.506-03 0. 1.526-03

CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04
Proc No ODCM

Attachment 8

Revision 25

Page 5 of 16

INGESTION DOSE COMMITMENT FACTORS

CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

113 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07

BEIO 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05

C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06

N13 3.1OE-08 3.1OE-08 3.1OE-08 3.1OE-08 3.IOE-08 3.1OE-08 3.1OE-08

F18 2.49E-06 0. 2.47E-07 0. 0. 0. 6.74E-07

NA22 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05 5.88E-05

NA24 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06 5.80E-06

P32 8.25E-04 3.86E-05 3.18E-05 0. 0. 0. 2.28E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA4I 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07

SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05

CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07

MN54 0. 1.07E-05 2.85E-06 0. 3.OOE-06 0. 8.98E-06

MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 0. 4.84E-05

FE55 1.15E-05 6.IOE-06 1.89E-06 0. 0. 3.45E-06 1.13E-06

FE59 1.65E-05 2.67E-05 1.33E-05 0. 0. 7.74E-06 2.78E-05

C057 0. 4.93E-07 9.98E-07 0. 0. 0. 4.04E-06

C058 0. 1.80E-06 5.51E-06 0. 0. 0. 1.05E-05

C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.93E-05

N159 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.1OE-07

N163 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06

N165 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.56E-05

CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05

ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41 E-06

ZN69M 7.IOE-07 1.21E-06 1.43E-07 0. 7.03E-07 0. 3.94E-05

ZN69 4.38E-08 6.33E-08 5.85E-09 0. 3.84E-08 0. 3.99E-06

SE79 0. 8.43E-06 1.87E-06 0. 1.37E-05 0. 5.53E-07

BR82 0. 0. 7.55E-06 0. 0. 0. 0.

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

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

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

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

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

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

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

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

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

RB86 0. 6.70E-05 4.12E-05 0. 0. 0. 4.31E-06

RB87 0. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07

RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09

RB89 0. 1.17E-07 1.04E-07 0. 0. 0. 1.02E-09

SR89 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11E-05

SR9O 1.70E-02 0. 4.31E-03 0. 0. 0. 2.29E-04

SR91 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05

SR92 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71E-04
Proc No ODCM

Attachment 8

Revision 25

Page 6 of 16

INGESTION DOSE COMMITMENT FACTORS

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 4.1IE-08 0. 1.1OE-09 0. 0. 0. 1.17E-04

Y9IM 3.82E-10 0. 1.39E-11 0. 0. 0. 7.48E-07

Y91 6.02E-07 0. 1.61E-08 0. 0. 0. 8.02E-05

Y92 3.60E-09 0. 1.03E-10 0. 0. 0. 1.04E-04

Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04

ZR93 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05

ZR95 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05

ZR97 6.99E-09 1.O1E-09 5.96E-10 0. 1.45E-09 0. 1.53E-04

NB93M 1.05E-07 2.62E-08 8.61 E-09 0. 2.83E-08 0. 3.95E-06

NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05

NB97 2.17E-10 3.92E-11 1.83E-11 0. 4.35E-11 0. 1.21E-05

M093 0. 2.41E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06

M099 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.1OE-05

TC99M 9.23E-1O 1.81E-09 3.OOE-08 0. 2.63E-08 9.19E-10 1.03E-06

TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06

TC1OI 1.07E-09 1.12E-09 1.42E-08 0. 1.91E-08 5.92E-10 3.56E-09

RUIO3 7.31E-07 0. 2.81E-07 0. 1.84E-06 0. 1.89E-05

RU1O5 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21E-05

RUIO6 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04

RHIO5 5.14E-07 2.76E-07 2.36E-07 0. 1.1OE-06 0. 1.71E-05

PD1O7 0. 4.72E-07 4.OIE-08 0. 3.95E-06 0. 9.37E-07

PDIO9 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05

AG1IOM 5.39E-07 3.64E-07 2.91E-07 0. 6.78E-07 0. 4.33E-05

AGIII 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.75E-05

CD1I3M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05

CD1I5M 0. 5.89E-06 2.51E-07 0. 4.38E-06 0. 8.O1E-05

SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.52E-05

SN125 3.55E-05 5.35E-07 t59E-06 5.55E-07 0. 0. 1.1OE-04

SN126 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05

SB124 1.11E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05

SB125 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71E-05

SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.1OE-06 8.87E-05

SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05

TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.1OE-05

TE127M 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 2.34E-05

TE127 4.71E-07 1.27E-07 1.OIE-07 3.26E-07 1.34E-06 0. 1.84E-05

TE129M 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0. 5.94E-05

TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06

TE131M 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41E-05 0. 1.O1E-04

TEI3I 8.30E08 2.53E-08 2.47E-08 6.35E-08 2.51E-07 0. 4.36E-07

TE132 1.O1E-05 4.47E-06 5.40E-06 6.51E-06 4.15E-05 0. 4.50E-05

TE133M 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.77E-06

TE134 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.376-07 0. 5.89E-07

1129 1.396-05 8.53E-06 7.62E-06 5.586-03 1.44E-05 0. 4.29E-07

1130 2.926-06 5.906-06 3.04E-06 6.506-04 8.82E-06 0. 2.766-06

1131 1.726-05 1.73E-05 9.83E-06 5.726-03 2.84E-05 0. 1.54E-06
Proc No ODCM

Attachment 8

Revision 25

Page 7 of 16

INGESTION DOSE COMMITMENT FACTORS

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06

1133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06

1134 4.19E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07

1135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06

XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

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

CS134M 8.44E-08 1.25E-07 8.16E-08 0. 6.59E-08 1.09E-08 1.58E-07

CS134 2.34E-04 3.84E-04 8.IOE-05 0. 1.19E-04 4.27E-05 2.07E-06

CS135 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81E-06 4.33E-07

CS136 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06

CS137 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06

CS138 2.28E-07 3.17E-07 2.O1E-07 0. 2.23E-07 2.40E-08 1.46E-07

CS139 1.45E-07 1.61E-07 7.74E-08 0. 1.21E-07 1.22E-08 1.45E-11

BA139 4.14E-07 2.21E-10 1.20E-08 0. 1.93E-10 1.30E-1O 2.39E-05

BA14O 8.31E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21E-05

BAI4I 2.OOE-07 1.12E-1O 6.51E-09 0. 9.69E-11 6.58E-1O 1.14E-07

BA142 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09

LAI4O 1.O1E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05

LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05

LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05

CEI4I 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05

CE143 6.99E-09 3.79E-06 5.49E-1O 0. 1.59E-09 0. 5.55E-05

CE144 2.08E-06 6.52E-07 1.11E-07 0. 3.61E-07 0. 1.70E-04

PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39EO9 0. 4.24E-05

PR144 1.29E-1O 3.99E-11 6.49E-12 0. 2.I1E-11 0. 8.59E-08

ND147 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05

PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.O1E-08 0. 9.19E-06

PM148M 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05

PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05

PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05

PMI51 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05

SMI5I 2.56E-07 3.81E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06

SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05

EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05

EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81E-05

EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05

EU156 5.62E08 3.O1E-08 6.23E-09 0. 1.94E-08 0. 6.83E-05

TB16O 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05

H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0.

W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07

W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61E-05

W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05
Proc No ODCM

Attachment 8

Revision 25

Page 8 of 16

INGESTION DOSE COMMITMENT FACTORS

CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB2IO 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05

81210 1.97E-06 1.02E-05 1.69E-07 0. 1.15E-04 0. 5.17E-05

P0210 1.52E-03 2.43E-03 3.67E-04 0. 7.56E-03 0. 6.55E-05

RN222 0. 0. 0. 0. 0. 0. 0.

RA223 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04

RA224 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.78E-04

RA225 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21 E-04

RA226 5.75E-01 1.84E-05 4.72E-01 0. 4.88E-04 0. 3.41E-04

RA228 3.85E-01 9.99E-06 4.32E-01 0. 2.65E-04 0. 5.81 E-05

AC225 1.88E-05 1.94E-05 1.26E-06 0. 2.07E-06 0. 4.31E-04

AC227 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05

TH227 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04

TH228 2.07E-03 2.65E-05 7.OOE-05 0. 1.38E-04 0. 5.79E-04

TH229 1.38E-02 1.81E-04 6.80E-04 0. 8.84E-04 0. 5.27E-04

TH230 3.55E-03 1.78E-04 9.91E-05 0. 8.67E-04 0. 6.19E-05

TH232 3.96E-03 1.52E-04 3.O1E-04 0. 7.41E-04 0. 5.27E-05

TH234 3.42E-07 1.51E-08 9.88E-09 0. 8.OIE-08 0. 1.18E-04

PA231 7.07E-03 2.34E-04 2.81E-04 0. 1.28E-03 0. 7.37E-05

PA233 1.81E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05

U232 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05

U233 3.72E-03 0. 2.25E-04 0. 6.1OE-04 0. 6.45E-05

U234 3.57E-03 0. 2.21 E-04 0. 5.98E-04 0. 6.32E-05

U235 3.42E-03 0. 2.07E-04 0. 5.61 E-04 0. 8.03E-05

U236 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05

U237 2.36E-07 0. 6.27E-08 0. 6.81 E-07 0. 2.08E-05

U238 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05

NP237 2.36E-03 1.81E-04 9.79E-05 0. 6.05E-04 0. 8.16E-05

NP238 5.83E-08 1.18E-09 9.08E-10 0. 3.76E-09 0. 4.04E-05

NP239 5.25E-09 3.77E-10 2.65E-10 0. 1.09E-09 0. 2.79E-05

PU238 1.25E-03 1.56E-04 3.16E-05 0. 1.15E-04 0. 7.50E-05

PU239 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.85E-05

PU240 1.36E-03 1.65E-04 3.31E-05 0. 1.22E-04 0. 6.98E-05

PU241 4.OOE-05 1.72E-06 8.04E-07 0. 2.96E-06 0. 1.44E-06

PU242 1.26E-03 1.59E-04 3.19E-05 0. 1.17E-04 0. 6.71E-05

PU244 1.47E-03 1.82E-04 3.65E-05 0. 1.35E-04 0. 1.OOE-04

AM241 1.43E-03 6.40E-04 1.02E-04 0. 6.23E-04 0. 7.64E-05

AM242M 1.47E-03 6.25E-04 1.04E-04 0. 6.30E-04 0. 9.61E-05

AM243 1.41E-03 6.14E-04 9.83E-05 0. 6.06E-04 0. 8.95E-05

CM242 8.80E-05 6.73E-05 5.84E-06 0. 1.87E-05 0. 8.16E-05

CM243 1.33E-03 6.03E-04 8.24E-05 0. 3.08E-04 0. 8.03E-05

CM244 1.11E-03 5.36E-04 6.93E-05 0. 2.54E-04 0. 7.77E-05

CM245 1.76E-03 6.64E-04 1.05E-04 0. 4.11E-04 0. 7.24E-05

CM246 1.74E-03 6.64E-04 1.05E-04 0. 4.10E04 0. 7.1IE-05

CM247 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05

CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51E-03

CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04
Proc No ODCM

Attachment 8

Revision 25

Page 9 of 16

INGESTION DOSE COMMITMENT FACTORS

TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

H3 0. 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07 1.06E-07

BE1O 4.48E-06 6.94E-07 1.13E-07 0. 5.30E-07 0. 2.84E-05

C14 4.06E-06 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07 8.12E-07

N13 1.15E-08 1.15E-08 l.15E-08 l.15E-08 1.15E-08 l.15E-08 l.15E-08

F18 8.64E-07 0. 9.47E-08 0. 0. 0. 7.78E-08

NA22 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05 2.34E-05

NA24 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06 2.30E-06

P32 2.76E-04 1.71E-05 1.07E-05 0. 0. 0. 2.32E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA4I 1.97E-04 0. 2.13E-05 0. 0. 0. 1.95E-07

SC46 7.24E-09 1.41E-08 4.18E-09 0. 1.35E-08 0. 4.80E-05

CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.05E-07

MN54 0. 5.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-05

MN56 0. 1.58E-07 2.81E-08 0. 2.OOE-07 0. 1.04E-05

FE55 3.78E-06 2.68E-06 6.25E-07 0. 0. 1.70E-06 1.16E-06

FE59 5.87E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E-05

C057 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06

C058 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05

C060 0 2.81 E-06 6.33E-06 0. 0. 0. 3.66E-05

N159 1.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07

N163 1.77E-04 1.25E-05 6.OOE-06 0. 0. 0. 1.99E-06

N165 7.49E-07 9.57E-08 4.36E-08 0. 0. 0. 5.193-06

CU64 0. 1.15E-07 5.41E-08 0. 2.91E-07 0. 8.92E-06

ZN65 5.76E-06 2.OOE-05 9.33E-06 0. 1.28E-05 0. 8.47E-06

ZN69M 2.40E-07 5.66E-07 5.19E-08 0. 3.44E-07 0. 3.11E-05

ZN69 1.47E-08 2.80E-08 1.96E-09 0. 1.83E-08 0. 5.16E-08

SE79 0. 3.73E-06 6.27E-07 0. 6.50E-06 0. 5.70E-07

BR82 0. 0. 3.04E-06 0. 0. 0. 0.

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

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

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

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

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

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

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

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

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

RB86 0. 2.98E-05 1.40E-05 0. 0. 0. 4.41E-06

RB87 0. 1.75E-05 6.IIE-06 0. 0. 0. 6.IIE-07

RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15

RB89 0. 5.50E-08 3.89E-08 0. 0. 0. 8.43E-17

SR89 4.40E-04 0. 1.26E-05 0. 0. 0. 5.24E-05

SR9O 8.30E-03 0. 2.05E-03 0. 0. 0. 2.33E-04

SR9I 8.07E-06 0. 3.21 E-07 0. 0. 0. 3.66E-05

SR92 3.05E-06 0. 1.30E-07 0. 0. 0. 7.77E-05
Proc No ODCM

Attachment 8

Revision 25

Page 10 of 16

INGESTION DOSE COMMITMENT FACTORS

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM!50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 1.376-08 0. 3.696-10 0. 0. 0. 1.13E-04

Y9IM 1.29E-10 0. 4.93E-12 0. 0. 0. 6.09E-09

Y91 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05

Y92 1.21 E-09 0. 3.506-11 0. 0. 0. 3.326-05

Y93 3.836-09 0. 1.05E-10 0. 0. 0. 1.17E-04

ZR93 5.53E-08 2.736-08 1.49E-08 0. 9.656-08 0. 2.58E-05

ZR95 4.12E-08 1.30E-08 8.94E-09 0. 1.916-08 0. 3.OOE-05

ZR97 2.376-09 4.696-10 2.16E-10 0. 7.11E-10 0. 1.276-04

NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.07E-06

NB95 8.22E-09 4.56E-09 2.51E-09 0. 4.42E-09 0. 1.95E-05

NB97 7.37E-11 1.83E-11 6.686-12 0. 2.14E-11 0. 4.376-07

M093 0. 1.06E-05 2.90E-07 0. 3.046-06 0. 1.29E-06

M099 0. 6.036-06 1.156-06 0. 1.38E-05 0. 1.08E-05

TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.146-10 6.08E-07

TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.726-08 6.44E-06

TCIOI 3.60E-10 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.756-17

RUIO3 2.55E-07 0. 1.096-07 0. 8.996-07 0. 2.136-05

RUIO5 2.18E-08 0. 8.466-09 0. 2.75E-07 0. 1.76E-05

RUIO6 3.926-06 0. 4.94E-07 0. 7.56E-06 0. 1.886-04

RHIO5 1.736-07 1.256-07 8.20E-08 0. 5.31E-07 0. 1.596-05

PDIO7 0. 2.08E-07 1.346-08 0. 1.88E-06 0. 9.66E-07

PDIO9 0. 2.51E-07 5.70E-08 0. 1.45E-06 0. 2.53E-05

AGIIOM 2.05E-07 1.946-07 1.186-07 0. 3.706-07 0. 5.45E-05

AGIII 8.29E-08 3.44E-08 1.73E-08 0. 1.126-07 0. 4.80E-05

CDI13M 0. 4.516-06 1.456-07 0. 4.99E-06 0. 2.71E-05

CDII5M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05

SN123 4.44E-05 7.29E-07 1.08E-06 5.846-07 0. 0. 6.71E-05

SN125 1.196-05 2.376-07 5.37E-07 1.86E-07 0. 0. 1.12E-04

SN126 1.166-04 2.16E-06 3.306-06 5.69E-07 0. 0. 2.586-05

SB124 3.87E-06 7.13E-08 1.51E-06 8.786-09 0. 3.38E-06 7.80E-05

SB125 2.486-06 2.71E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05

SB126 1.59E-06 3.25E-08 5.716-07 8.996-09 0. 1.14E-06 9.416-05

SB127 3.636-07 7.766-09 1.376-07 4.086-09 0. 2.47E-07 6.16E-05

TE125M 3.83E-06 1.386-06 5.126-07 1.076-06 0. 0. 1.13E-05

TE127M 9.676-06 3.436-06 1.156-06 2.30E-06 3.92E-05 0. 2.41E-05

TE127 1.58E-07 5.606-08 3.406-08 1.096-07 6.406-07 0. 1.226-05

TE129M 1.636-05 6.05E-06 2.586-06 5.26E-06 6.82E-05 0. 6.12E-05

TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07

TE13IM 2.44E-06 1.176-06 9.76E-07 1.766-06 1.22E-05 0. 9.39E-05

TE13I 2.796-08 1.15E-08 8.726-09 2.15E-08 1.22E-07 0. 2.296-09

TE132 3.49E-06 2.216-06 2.086-06 2.336-06 2.126-05 0. 7.006-05

TE133M 6.44E-08 3.666-08 3.566-08 5.116-08 3.62E-07 0. 1.48E-07

TE134 4.47E-08 2.876-08 3.006-08 3.67E-08 2.746-07 0. 1.66E-09

1129 4.666-06 3.92E-06 6.54E-06 4.776-03 7.016-06 0. 4.576-07

1130 1.03E-06 2.986-06 1.196-06 2.43E-04 4.596-06 0. 2.296-06

1131 5.85E-06 8.196-06 4.40E-06 2.396-03 1.416-05 0. 1.626-06
Proc No ODCM

Attachment 8

Revision 25

Page 11 oflG

INGESTION DOSE COMMITMENT FACTORS

TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.18E-07

1133 2.O1E-06 3.41E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.58E-06

1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.1OE-07 0. 5.1OE-09

1135 6.IOE-07 1.57E-06 5.82E-07 1.OIE-04 2.48E-06 0. 1.74E-06

XEI3IM 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

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

CSI34M 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08

CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06

CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.46E-07

CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.72E-06

CS137 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06

CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.1OE-07 1.28E-08 6.76E-11

CS139 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23

BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06

BA14O 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05

BAI41 6.71E-08 5.OIE-11 2.24E-09 0. 4.65E-11 3.43E-11 1.43E-13

BA142 2.99E-08 2.99E-11 1.84E-09 0. 2.53E-11 1.99E-11 9.18E-20

LA14O 3.48E-09 1.71E-09 4.55E-10 0. 0. 0. 9.82E-05

LAI4I 4.55E-1O 1.40E-1O 2.31E-11 0. 0. 0. 2.48E-05

LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06

CEI41 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05

CE143 2.35E-09 1.71E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05

CE144 6.96E-07 2.88E-07 3.74E-08 0. 1.72E-07 0. 1.75E-04

PR143 1.31E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.31E-05

PR144 4.30E-11 1.76E-11 2.18E-12 0. 1.O1E-11 0. 4.74E-14

ND147 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05

PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06

PMI48M 4.14E-08 1.05E-08 8.21 E-09 0. 1.59E-08 0. 6.61 E-05

PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.OOE-09 0. 9.90E-05

PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05

PMI5I 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05

SM15I 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06

SM153 1.22E-09 1.O1E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05

EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05

EU154 7.91E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.39E-05

EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05

EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05

TB16O 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05

H0166M 3.57E-07 1.1OE-07 7.96E-08 0. 1.61E-07 0. 0.

W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07

W185 5.79E-07 1.91E-07 2.02E-08 0. 0. 0. 1.65E-05

W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 3.22E-05
Proc No ODCM

Attachment 8

Revision 25

Page 12 of 16

INGESTION DOSE COMMITMENT FACTORS

TEEN INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O 1.81E-02 5.44E-03 7.OIE-04 0. 1.72E-02 0. 5.74E-05

B1210 6.59E-07 4.51E-06 5.66E-08 0. 5.48E-05 0. 5.15E-05

P0210 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05

RN222 0. 0. 0. 0. 0. 0. 0.

RA223 7.1IE-03 1.08E-05 1.42E-03 0. 3.1OE-04 0. 3.43E-04

RA224 2.31E-03 5.52E-06 4.61E-04 0. 1.58E-04 0. 3.71E-04

RA225 9.37E-03 1.1OE-05 1.87E-03 0. 3.15E-04 0. 3.27E-04

RA226 3.22E-O1 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51E-04

RA228 1.37E-01 4.41E-06 1.51E-01 0. 1.26E-04 0. 5.98E-05

AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.36E-04

AC227 2.05E-03 3.03E-04 1.22E-04 0. 8.81 E-05 0. 8.68E-05

TH227 1.96E-05 3.52E-07 5.65E-07 0. 2.OIE-06 0. 5.75E-04

TH228 6.80E-04 1.14E-05 2.30E-05 0. 6.41E-05 0. 5.97E-04

TH229 8.39E-03 1.26E-04 4.I1E-04 0. 6.1OE-04 0. 5.43E-04

TH230 2.16E-03 1.23E-04 6.OOE-05 0. 5.99E-04 0. 6.38E-05

TH232 2.42E-03 1.05E-04 1.63E-04 0. 5.I1E-04 0. 5.43E-05

TH234 1.14E-07 6.68E-09 3.31E-09 0. 3.81E-08 0. 1.21E-04

PA231 4.31E-03 1.62E-04 1.68E-04 0. 9.1OE-04 0. 7.60E-05

PA233 7.33E-09 1.41E-09 1.26E-09 0. 5.32E-09 0. 1.61E-05

U232 5.89E-03 0. 4.21E-04 0. 6.38E-04 0. 7.19E-05

U233 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05

U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51E-05

U235 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05

U236 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.11E-05

U237 7.89E-08 0. 2.1OE-08 0. 3.24E-07 0. 2.09E-05

U238 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05

NP237 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41E-05

NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05

NP239 1.76E-09 1.66E-10 9.22E-11 0. 5.21E-10 0. 2.67E-05

PU238 7.21E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.73E-05

PU239 8.27E-04 1.12E-04 2.OIE-05 0. 8.57E-05 0. 7.06E-05

PU240 8.26E-04 1.12E-04 2.OIE-05 0. 8.56E-05 0. 7.19E-05

PU241 1.84E-05 9.42E-07 3.69E-07 0. 1.71E-06 0. 1.48E-06

PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.25E-05 0. 6.92E-05

PU244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 1.03E-04

AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31 E-04 0. 7.87E-05

AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05

AM243 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.23E-05

CM242 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05

CM243 6.91E-04 2.86E-04 4.09E-05 0. 1.91E-04 0. 8.28E-05

CM244 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.OOE-05

CM245 1.07E-03 3.33E-04 6.IOE-05 0. 2.85E-04 0. 7.46E-05

CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.33E-05

CM247 1.03E-03 3.27E-04 6.OOE-05 0. 2.80E-04 0. 9.63E-05

CM248 8.60E-03 2.69E-03 4.95E-04 0. 2.31E-03 0. 1.55E-03

CR252 3.51 E-04 0. 8.37E-06 0. 0. 0. 3.05E-04
Proc No ODCM

Attachment 8

Revision 25

Page 13 of 16

INGESTION DOSE COMMITMENT FACTORS

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1-13 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07

BE1O 3.18E-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05

C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07

N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09

F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08

NA22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05

NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06. 1.70E-06 1.70E-06 1.70E-06

P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA4I 1.83E-05 0. 2.OOE-05 0. 0. 0. 1.84E-07

SC46 5.51E-09 1.07E-08 3.IIE-09 0. 9.99E-09 0. 5.21E-05

CR51 0. 0. 2.66E-09 1.59E-09 5.86E-1O 3.53E-09 6.69E-07

MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05

MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06

FE55 2.75E-06 1.90E-06 4.43E-07 0. 0. 1.06E-06 1.09E-06

FE59 4.34E-06 1.02E-05 3.91E-06 0. 0. 2.85E-06 3.40E-05

C057 0. 1.75E-07 2.91 E-07 0. 0. 0. 4.44E-06

C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51E-05

C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05

NI59 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07

NI63 1.30E-04 9.O1E-06 4.36E-06 0. 0. 0. 1.88E-06

N165 5.28E-07 6.86E-08 3.13E-08 0. 0. 0. 1.74E-06

CU64 0. 8.33E-08 3.91E-08 0. 2.1OE-07 0. 7.1OE-06

ZN65 4.84E-06 1.54E-05 6.96E-06 0. 1.03E-05 0. 9.70E-06

ZN69M 1.70E-07 4.08E-07 3.73E-08 0. 2.47E-07 0. 2.49E-05

ZN69 1.03E-08 1.97E-08 1.37E-09 0. 1.28E-08 0. 2.96E-09

SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.38E-07

BR82 0. 0. 2.26E-06 0. 0. 0. 2.59E-06

BR83 0. 0. 4.02E-08 0. 0. 0. 5.79E-08

BR84 0. 0. 5.21E-08 0. 0. 0. 4.09E-13

BR85 0. 0. 2.14E-09 0. 0. 0. 0.

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

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

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

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

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

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

RB86 0. 2.11E-05 9.83E-06 0. 0. 0. 4.16E-06

RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07

RB88 0. 6.05E-08 3.21E-08 0. 0. 0. 8.36E-19

RB89 0. 4.01 E-08 2.82E-08 0. 0. 0. 2.33E-21

SR89 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05

SR9O 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04

SR91 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05

SR92 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05
Proc No ODCM

Attachment 8

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Page 14 of 16

INGESTION DOSE COMMITMENT FACTORS

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04

Y9IM 9.09E-11 0. 3.52E-12 0. 0. 0. 2.67E-10

Y91 1.41E-07 0. 3.77E-09 0. 0. 0. 7.76E-05

Y92 8.45E-1O 0. 2.47E-11 0. 0. 0. 1.48E-05

Y93 2.68E-09 0. 7.40E-11 0. 0. 0. 8.50E-05

ZR93 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06

ZR95 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.09E-05

ZR97 1.68E-09 3.39E-10 1.55E-1O 0. 5.12E-1O 0. 1.05E-04

NB93M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06

NB95 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.1OE-05

NB97 5.22E-11 1.32E-11 4.82E-12 0. 1.54E-11 0. 4.87E-08

M093 0. 7.51E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06

M099 0. 4.31 E-06 8.20E-07 0. 9.76E-06 0. 9.99E-06

TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.13E-07

TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.08E-06

TCIOI 2.54E-10 3.66E-1O 3.59E-09 0. 6.59E-09 1.87E-1O 1.1OE-21

RU1O3 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.16E-05

RUIO5 1.54E-08 0. 6.08E-09 0. 1.99E-07 0. 9.42E-06

RUIO6 2.75E-06 0. 3.48E-07 0. 5.31E-06 0. 1.78E-04

RHIO5 1.21E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41E-05

PDIO7 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.IIE-07

P0109 0. 1.77E-07 3.99E-08 0. 1.OIE-06 0. 1.96E-05

AGIIOM 1.60E-07 1.48E-07 8.79E-08 0. 2.91E-07 0. 6.04E-05

AG11I 5.81E-08 2.43E-08 1.21E-08 0. 7.84E-08 0. 4.46E-05

CDII3M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05

CDII5M 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E-05

SN123 3.IIE-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05

SN125 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04

SN126 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05

SB124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E05

SB125 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05

SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05

SB127 2.58E-07 5.65E-09 9.90E-08 3.IOE-09 0. 1.53E-07 5.90E-05

TE125M 2.68E-06 9.71E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05

TE125M 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05

TE127 1.IOE-07 3.95E-08 2.38E-08 8.ISE-08 4.48E07 0. 8.68E-06

TE129M 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05

TE129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.32E-07 0. 2.37E-08

TE13IM 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05

TE131 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09

TE132 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71E-05

TE133M 4.62E-08 2.70E-08 2.60E-08 3.91E-08 2.67E-07 0. 6.64E-08

TE134 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-11

1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06 0. 4.44E-07

1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0. 1.92E-06

1131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0. 1.57E-06
Proc No ODCM

Attachment 8

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INGESTION DOSE COMMITMENT FACTORS

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07

1133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06

1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-1O

1135 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31E-06

XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

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

CS134M 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.58E-08

CS134 6.22E-05 1.48E-04 1.21E-04 0. 4.79E-05 1.59E-05 2.59E-06

CS135 1.95E-05 1.80E-05 7.99E-06 0. 6.81E-06 2.04E-06 4.21E-07

CS136 6.51E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06

CS137 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.1IE-06

CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.O1E-08 7.91E-09 4.65E-13

CS139 3.41E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.IOE-30

BA139 9.70E-08 6.91E-11 2.84E-09 0. 6.46E-11 3.92E-11 1.72E-07

BAI4O 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05

BAI4I 4.71E-08 3.56E-11 1.59E-09 0. 3.31E-11 2.02E-11 2.22E-17

BA142 2.13E-08 2.19E-11 1.34E-09 0. 1.85E-11 1.24E-11 3.OOE-26

LAI4O 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05

LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05

LA142 1.28E-10 5.82E-11 1.45E-11 0. 0. 0. 4.25E-07

CEI4I 9.36E-09 6.33E-09 7.18E-1O 0. 2.94E-09 0. 2.42E-05

CE143 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05

CE144 4.88E-07 2.04E-07 2.62E-08 0. 1.21E-07 0. 1.65E-04

PR143 9.20E-09 3.69E-09 4.56E-10 0. 2.13E-09 0. 4.03E-05

PR144 3.O1E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18

ND147 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05

PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06

PM148M 3.07E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.74E-05

PM148 7.17E-09 1.19E-09 5.99E-10 0. 2.25E-09 0. 9.35E-05

PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05

PMI51 6.97E-10 1.17E-10 5.91E-11 0. 2.09E-10 0. 3.22E-05

SMI5I 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06

SM153 8.57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05

EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05

EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05

EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06

EU156 1.37E-08 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05

TB16O 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05

H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.

W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07

W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.56E-05

W187 1.03E-07 8.61E-08 3.OIE-08 0. 0. 0. 2.82E-05
Proc No ODCM

Attachment 8

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INGESTION DOSE COMMITMENT FACTORS

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB2IO 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05

BI21O 4.61E-07 3.18E-06 3.96E-08 0. 3.83E-05 0. 4.75E-05

P0210 3.56E-04 7.56E-04 8.59E-05 0. 2.52E-03 0. 6.36E-05

RN222 0. 0. 0. 0. 0. 0. 0.

RA223 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04

RA224 1.61E-03 3.90E-06 3.23E-04 0. 1.1OE-04 0. 3.40E-04

RA225 6.56E-03 7.78E-06 1.31E-03 0. 2.21E-04 0. 3.06E-04

RA226 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04

RA228 1.12E-01 3.12E-06 1.21E-01 0. 8.83E-05 0. 5.64E-05

AC225 4.40E-06 6.06E-06 2.96E-07 0. 6.90E-07 0. 4.07E-04

AC227 1.87E-03 2.48E-04 1.I1E-04 0. 8.OOE-05 0. 8.19E-05

TH227 1.37E-05 2.48E-07 3.95E-07 0. 1.41E-06 0. 5.40E-04

TH228 4.96E-04 8.40E-06 1.68E-05 0. 4.67E-05 0. 5.63E-04

TH229 7.98E-03 1.19E-04 3.91E-04 0. 5.75E-04 0. 5.12E-04

TH230 2.06E-03 1.17E-04 5.70E-05 0. 5.65E-04 0. 6.02E-05

TH232 2.30E-03 1.OOE-04 1.50E-04 0. 4.82E-04 0. 5.12E-05

TH234 8.OIE-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04

PA231 4.1OE-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05

PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05

U232 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05

U233 8.71 E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05

U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05

U235 8.O1E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05

U236 8.O1E-04 0. 4.96E-05 0. 1.91E-04 0. 5.76E-05

U237 5.52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05

U238 7.67E-04 0. 4.54E-05 0. 1.75E-04 0. 5.50E-05

NP237 1.37E-03 1.19E-04 5.54E-05 0. 4.12E-04 0. 7.94E-05

NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05

NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05

PU238 6.80E-04 9.58E-05 1.71E-05 0. 7.32E-05 0. 7.30E-05

PU239 7.87E-04 1.06E-04 1.91E-05 0. 8.1IE-05 0. 6.66E-05

PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.IOE-05 0. 6.78E-05

PU241 1.65E-05 8.44E-07 3.32E-07 0. 1.53E-06 0. 1.40E-06

PU242 7.29E-04 1.02E-04 1.84E-05 0. 7.81E-05 0. 6.53E-05

PU244 8.52E-04 1.17E-04 2.IIE-05 0. 8.95E-05 0. 9.73E-05

AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.07E-04 0. 7.42E-05

AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05

AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05

CM242 2.06E-05 2.IOE-05 1.37E-06 0. 6.22E-06 0. 7.92E-05

CM243 6.39E-04 2.41E-04 3.75E-05 0. 1.75E-04 0. 7.81E-05

CM244 4.83E-04 2.07E-04 2.87E-05 0. 1.34E-04 0. 7.55E-05

CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05

CM246 1.O1E-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05

CM247 9.84E-04 2.83E-04 5.67E-05 0. 2.64E-04 0. 9.09E-05

CM248 8.18E-03 2.33E-03 4.67E-04 0. 2.18E-03 0. 1.47E-03

CF252 2.64E-04 0. 6.29E-06 0. 0. 0. 2.88E-04
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

ODCM

Appendix A

Revision 16

Issued Date 5117111

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Process Applicability Exclusion 0

Joe Hager I 5117111

Procedure Sponsor Date

JJMiller I 5113/11

Technical Reviewer Date

JBBurnett I 6/3/10

User Reviewer Date

DHamilton

General Manager Plant Operations

I 5/13/11

Date
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 16

Page i

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

INTRODUCTION I

DEFINITIONS I

A. CHANNEL CALIBRATION I

B. CHANNEL CHECK I

C. CHANNEL FUNCTIONAL TEST 2

D. SOURCE CHECK 2

E. OFFSITE DOSE CALCULATION MANUAL 2

F. GASEOUS RADWASTE TREATMENT SYSTEM 2

G. MEMBERS OF THE PUBLIC 2

H. PROCESS CONTROL PROGRAM (PCP) 3

I. SITE BOUNDARY 3

J. UNRESTRICTED AREA 3

K. VENTILATION EXHAUST TREATMENT SYSTEM 3

III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 4

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING

INSTRUMENTATION 4

1. Requirement 4

2. Action 4

3. Surveillance Requirements 4

4. Bases 5

B. GASEOUS EFFLUENTS DOSE RATE 10

1. Requirement 10

2. Action 10

3. Surveillance Requirements 10

4. Bases 11

C. NOBLE GASES DOSE 12

1. Requirement 12

2. Action 12

3. Surveillance Requirements 12

4. Bases 13
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

D. 1-131, 1-133, TRITIUM, AND PARTICULATES 14

1. Requirement 14

2. Action 14

3. Surveillance Requirements 14

4. Bases 15

E. GASEOUS WASTE TREATMENT SYSTEM 18

1. Requirement 18

2. Action 18

3. Surveillance Requirements 18

4. Bases 19

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 19

1. Requirement 19

2. Action 20

3. Surveillance Requirements 20

4. Bases 20

G. LIQUID EFFLUENTS CONCENTRATION 25

1. Requirement 25

2. Action 25

3. Surveillance Requirements 25

4. Bases 26

H. LIQUID EFFLUENT DOSE 29

1. Requirement 29

2. Action 29

3. Surveillance Requirements 29

4. Bases 30

TOTAL DOSE 31

1. Requirement 31

2. Action 31

3. Surveillance Requirements 32

4. Bases 33
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

J. RADIOLOGICAL ENVIRONMENTAL MONITORING 34

1. Requirement 34

2. Action 34

3. Surveillance Requirements 35

4. Bases 36

K. SIRW OR TEMPORARY LIQUID STORAGE TANK 46

1. Requirement 46

2. Action 46

3. Surveillance Requirement 46

4. Bases 47

L. SURVEILLANCE REQUIREMENT TIME INTERVALS 47

1. Requirement 47

2. Action 47

3. Surveillance Requirements 48

4. Bases 48

M. SEALED SOURCE CONTAMINATION 48

1. Requirement 48

2. Action 48

3. Surveillance Requirements 49

4. Bases 49

IV. REPORTING REQUIREMENTS 50

A. RADIOLOGICAL EFFLUENT RELEASE REPORT 50

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 50

C. NONROUTINE REPORTS 51

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS 53

A. LICENSEE MODIFICATIONS 53

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 54

VI. ONSITE GROUND WATER MONITORING 55
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

TABLES

A-I Radioactive Gaseous Effluent Monitoring Instrumentation

A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance

Requirements

B-I Radioactive Gaseous Waste Sampling and Analysis Program

C-I Radioactive Liquid Effluent Monitoring Instrumentation

C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

D-1 Radioactive Liquid Waste Sampling and Analysis Program

E-1 Radiological Environmental Monitoring Program

E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples

E-3 Detection Capabilities for Environmental Sample Analysis

F-i Environmental Radiological Monitoring Program Summary
PALISADES NUCLEAR PLANT ODCM

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Page 1 of 55

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

INTRODUCTION

The NRC, through 1OCFR5O.36a, requires implementation of Technical

Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01,

dated January 31, 1989, allowed relocation of the existing procedural

requirements from the Technical Specifications (implemented in Amendment 85,

November 9, 1984). The relocated procedural requirements related to gaseous and

liquid effluents, total dose, environmental monitoring program, and associated

procedural reporting requirements follow below. Programmatic controls are retained

in the Administrative Controls section of the Technical Specification to satisfy the

regulatory requirements of I OCFR5O.36a. The Technical Specifications

programmatic controls include requirements for the establishment, implementation,

maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well

as record retention and reporting requirements.

DEFINITIONS

A. CHANNEL CALIBRATION

- a Channel Calibration shall be the adjustment, as necessary, of the channel

output such that it responds with the necessary range and accuracy to known

values of the parameter which the channel monitors. The Channel

Calibration shall encompass the entire channel including the sensor and

alarm and/or trip functions, and shall include the Channel Function Test.

The Channel Calibration may be performed by any series of sequential,

overlapping, or total channel steps such that the entire channel is calibrated.

B. CHANNEL CHECK

- a Channel Check shall be the qualitative assessment of channel behavior

during operation by observation. This determination shall include, where

possible, comparison of the channel indication and/or status with other

indications and/or status derived from independent instrumentation channels

measuring the same parameter.
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Page 2 of 55

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. CHANNEL FUNCTIONAL TEST

- a Channel Functional Test shall be:

1. Analog channels - the injection of a simulated signal into the channel

as close to the sensor as practicable to verify operability including

alarm and/or trip functions.

2. Bistable channels - the injection of a simulated signal into the sensor to

verify operability including alarm and/or trip functions.

D. SOURCE CHECK

- a source check shall be the qualitative assessment of channel response

when the channel sensor is exposed to a radioactive source.

E. OFFSITE DOSE CALCULATION MANUAL

- (per Plant Technical Specifications) - the Offsite Dose Calculation Manual

(ODCM) shall contain the methodology and parameters used in the

calculation of offsite doses resulting from radioactive gaseous and liquid

effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip

setpoints, and in the conduct of the Radiological Environmental Monitoring

Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls

and Radiological Environmental Monitoring Programs required by the

Technical Specifications, and 2) descriptions of the information that should be

included in the Annual Radiological Environmental Operating and Radioactive

Effluent Release Reports required by the Technical Specifications.

F. GASEOUS RADWASTE TREATMENT SYSTEM

- any system designed and installed to reduce radioactive gaseous effluents

by collecting primary coolant system off gases from the primary system and

providing for delay or holdup for the purpose of reducing the total radioactivity

prior to release to the environment.

G. MEMBERS OF THE PUBLIC

- all persons who are not occupationally associated with the Plant. This

category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service

equipment or to make deliveries.
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. PROCESS CONTROL PROGRAM (PCP)

-shall contain the current formula, sampling, analyses, tests, and

determinations to be made to ensure that the processing and packaging of

solid radioactive wastes based on demonstrated processing of actual or

simulated wet solid wastes will be accomplished in such a way as to assure

compliance with 1OCFR Part 20, IOCFR Part 71 and Federal and State

regulations and other requirements governing the disposal of the radioactive

waste.

SITE BOUNDARY

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

the licensee.

J. UNRESTRICTED AREA

- any area at or beyond the Site Boundary access which is not controlled by

the licensee for purposes of protection of individuals from exposure to

radiation and radioactive materials or, any area within the Site Boundary used

for residential quarters or for industrial, commercial, institutional, and/or

recreational purposes.

K. VENTILATION EXHAUST TREATMENT SYSTEM

- any system designed and installed to reduce gaseous radioiodine or

radioactive material in particulate form in effluents by passing ventilation or

vent exhaust gases through charcoal absorbers and/or HEPA filters for the

purpose of removing iodines or particulates from the gaseous exhaust stream

prior to the release to the environment. Such a system is not considered to

have any effect on noble gas effluents. Engineered Safety Feature (ESF)

atmospheric cleanup systems are not considered to be ventilation exhaust

treatment system components.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Ill. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

Requirement

The radioactive gaseous effluent monitoring instrumentation channels

shown in Table A-I shall be operable with their alarm/trip setpoints set

to ensure that the limits of requirement lll.B.1 are not exceeded. The

alarm/trip setpoints of these channels shall be determined and

adjusted in accordance with the methodology and parameters in the

ODCM.

2. Action

a. With a radioactive gaseous effluent monitoring instrumentation

channel alarm/trip setpoint less conservative than required by

the above requirement, without delay, suspend the release of

radioactive gaseous effluents monitored by the affected channel

or declare the channel inoperable or change the setpoint so it is

acceptably conservative.

b. With less than the minimum number of radioactive gaseous

effluent monitoring instrumentation channels operable, take the

action shown in Table A-I. Exert best efforts to return the

instruments to operable status within 30 days and, if

unsuccessful, explain in the next Radioactive Effluent Release

Report why the inoperability was not corrected in a timely

manner.

3. Surveillance Requirements

Each radioactive gaseous effluent monitoring instrumentation channel

shall be demonstrated operable by performance of the Channel Check,

Source Check, Channel Calibration, and Channel Functional Test

operations at the frequencies shown in Table A-2.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

The radioactive gaseous effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

gaseous effluents during actual or potential releases of gaseous

effluents. The alarm/trip setpoints for these instruments shall be

calculated and adjusted in accordance with the methodology and

parameters in the ODCM to ensure that the alarm/trip will occur prior to

exceeding the limits of 1OCFR 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 1OCFR Part 50.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I

Radioactive Gaseous Effluent Monitoring Instrumentation

ODCM

Appendix A

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Page 6 of 55

Minimum

Instrument Operable Applicability Action

Channels

WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) Providing

Alarm and Automatic Termination of Release (1) At All Times 1

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1) Above 210°F 3

Modes 1,2,3,4

Above 210°F

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

3. STACK GAS EFFLUENT SYSTEM

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

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

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

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

Modes 1,2,3,4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

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

Modes 1,2,3,4

5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE

a. Gross Gamma Activity Monitor* I per Main Above 325°F 4

(RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** I per Room Above 210°F 5

(RlAl8lOandI8ll) Modesl,2,3,4

*

Setpoints for these instruments are exempted from III.B.1 limfts, but are governed by

Emergency Implementing Procedures or Operating procedures.

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

Documentation of operability not required.
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I (Cont’d)

TABLE NOTATION - ACTION STATEMENTS

ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels

requirements, the contents of the tank(s) may be released to the environment provided that

prior to initiating the release:

a. At least two independent samples of the 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.

ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels

requirement, effluent releases via this pathway may continue provided the flow rate is

estimated at least once per 24 hours.

ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels

requirement, effluent releases via this pathway may continue provided grab samples are

taken at least once per 12 hours and these samples are analyzed for gross activity within

24 hours.

ACTION 4 - With the number of operable channels less than required by the Minimum Operable Channels

requirements, initiate the preplanned alternate method of monitoring the appropriate

parameter(s), within 72 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.

ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with

that channel shall be closed immediately and action shall be taken to have the affected

channel repaired. The dampers associated with the channel shall not be opened until the

affected channel has been declared operable.

(Reference Technical Specifications LCO 3.3.10.)
PALISADES NUCLEAR PLANT 

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 Requiremen

fL. • , Channel 

Instrument anne. ource Functional 

....ecn v.,iiecn 4.aIIIJraLlon Test 

WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and D(4)

i R(3) Q(1 )(2) 

Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

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

c. Evacuation Flow Indicator (Fl-0631)

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

b. Iodine Particulate Sampler/Monitor

w M** R(3)** NA 

c. Sampler Flow Rate Monitor

D NA

R NA 

d. Hi Range Noble Gas

D

M R(3) Q(2) 

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE 

D

M R(3) Q(2) 

a. Gross_Gamma_Activity_Monitor

6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours 31 days 18 months (3) 31 days(1)(2) 

(Technical Specifications SR 3.3.10 and 

SR_3.7.13.1) * At all times other than when the line is valved out and locked.

** Sampler not applicable

This type of Flowmeter doesn’t have any surveillance requirements.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-2 (Cont’d)

Table Notation

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if i

measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if ei

conditions exists.

a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Ran

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceab

Institute of Standards and Technology or using standards that have been obtained from suppliers 

measurement assurance activities with NIST. These standards shall permit calibrating the system 

range of energy and measurement range.

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

(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch releas

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
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. GASEOUS EFFLUENTS DOSE RATE

Requirement

The dose rate due to radioactive materials released in gaseous

effluents from the site to areas at and beyond the Site Boundary

(see Figure 2-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the

total body and less than or equal to 3000 mrems/yr to the skin,

and

b. For Iodine-i 31, for Iodine-I 33, for tritium, and for all

radionuclides in particulate form with half-lives greater than

8 days: Less than or equal to 1500 mrems/yr to any organ.

2. Action

With the dose rate(s) averaged over a period of one hour exceeding

the above limits, without delay, restore the release rate to within the

above limit(s).

3. Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be

determined to be within the limits of B.1 .a in accordance with

the methodology and parameters in the ODCM.

b. The dose rate due to lodine-131, Iodine-I 33, tritium, and all

radionuclides in particulate form with half-lives greater than

8 days in gaseous effluents shall be determined to be within the

limits of B.1 .b in accordance with the methodology and

parameters in the ODCM by obtaining representative samples

and performing analyses in accordance with the sampling and

analysis program specified in Table B-i.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This is provided to ensure that the dose at any time at and beyond the

Site Boundary from gaseous effluents from all units on the site will be

within 10 times the annual dose limits of IOCFR Part 20 to Unrestricted

Areas. The annual dose limits are the doses associated with the

concentrations of 10 times 1OCFR 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 1OCFR 50, Appendix I, Section ll.B.1. For

Members of the Public who may at times be within the Site Boundary,

the occupancy of the Member of the Public will usually be sufficiently

low to compensate for any increase in the atmospheric diffusion factor

above that for the Site Boundary. Examples of calculations for such

Members of the Public, with the appropriate occupancy factors, shall

be given in the ODCM. The specified release rate limits restrict, at all

times, the corresponding dose rate above background to a Member of

the Public at or beyond the Site Boundary to less than or equal to

500 mrems/yr to the total body.

The required detection capabilities for radioactive materials in gaseous

waste samples are tabulated in terms of the lower limits of detection

(LLD5). Detailed discussion of the LLD and other detection limits can

be found in HASL Procedures Manual, HASL-300, Currie, L A, “Limits

for Qualitative Detection and Quantitative Determination -Application

to Radiochemistry,” Anal Chem 40, 586-93 (1968), and Hartwell, JK,

“Detection Limits for Radioanalytical Counting Techniques,” Atlantic

Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. NOBLE GASES DOSE

Requirement

The air dose due to noble gases released in gaseous effluents to areas

at and beyond the Site Boundary (see Figure 2-1) shall be limited to

the following:

a. During any calendar quarter: Less than or equal to 5 mrads for

gamma radiation and less than or equal to 10 mrads for beta

radiation, and

b. During any calendar year: Less than or equal to 10 mrads for

gamma radiation and less than or equal to 20 mrads for beta

radiation.

2. Action

With the calculated air dose from radioactive noble gases in gaseous

effluents exceeding any of the above limits, prepare and submit to the

NRC within 30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for noble gases shall be determined in

accordance with the methodology and parameters in the ODCM at

least once per 31 days.
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OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This requirement is provided to implement the requirements of

Sections ll.B, lll.A, and IV.A of Appendix I, IOCFR Part 50. The

limiting Condition for Operation implements the guides set forth in

Section II.B of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in gaseous effluents to Unrestricted Areas will be

kept “as low as is reasonably achievable.” The Surveillance

Requirements implement the requirements in Section lll.A of

Appendix I that conformance with the guides of Appendix I be shown

by calculational procedures based on models and data such that the

actual exposure of a Member of the Public through appropriate

pathways is unlikely to be substantially underestimated. The dose

calculation methodology and parameters established in the ODCM for

calculating the doses due to the actual release rates of radioactive

noble gases in gaseous effluents are consistent with the methodology

provided in Regulatory Guide 1.109, “Calculation of Annual Doses to

Man from Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with 1OCFR Part 50, Appendix I,” Revision 1,

October 1977 and Regulatory Guide 1.111, “Methods for Estimating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases from Light-Water-Cooled Reactors,” Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and

beyond the Site Boundary are based upon the historical average

atmospheric conditions.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

D. 1-131, 1-133, TRITIUM, AND PARTICULATES

Requirement

The dose to a Member of the Public from Iodine-i 31, Iodine-i 33,

tritium, and all radionuclides in particulate form with half-lives greater

than 8 days in gaseous effluents released, from each reactor unit, to

areas at and beyond the Site Boundary (see Figure 2-1) shall be

limited to the following:

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

to any organ, and

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

any organ.

2. Action

With the calculated dose from the release of lodine-131, Iodine-i 33,

tritium, and radionuclides in particulate form with half-lives greater than

8 days, in gaseous effluents exceeding any of the above limits, prepare

and submit to the NRC within 30 days a Special Report that identifies

the cause(s) for exceeding the limit and define(s) the corrective actions

that have been taken to reduce the releases and the proposed

corrective actions to be taken to assure that subsequent releases will

be in compliance with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for Iodine-i 31, Iodine-i 33, tritium, and

radionuclides in particulate form with half-lives greater than 8 days

shall be determined in accordance with the methodology and

parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This requirement is provided to implement the requirements of

Sections ll.C, lll.A, and IV.A of Appendix I, IOCFR Part 50. The

requirements are the guides set forth in Section ll.C of Appendix I.

The Action statements provide the required operating flexibility and at

the same time implement the guides set forth in Section IV.A of

Appendix I to assure that the releases of radioactive materials in

gaseous effluents to Unrestricted Areas will be kept “as low as is

reasonably achievable.” The ODCM calculational methods specified in

the Surveillance Requirements implement the requirements in

Section ll.A of Appendix I that conformance with the guides of

Appendix I be shown by calculational procedures based on models

and data, such that the actual exposure of a Member of the Public

through appropriate pathways is unlikely to be substantially

underestimated. The ODCM calculational methodology and

parameters for calculating the doses due to the actual release rates

of the subject materials are consistent with the methodology provided

in Regulatory Guide 1.109, “Calculation of Annual Doses to Man

From Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with IOCFR Part 50, Appendix I,” Revision 1,

October 1977 and Regulatory Guide 1.111, “Methods for Estimating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases From Light-Water-Cooled Reactors,” Revision 1, July 1977.

These equations also provide for determining the actual doses based

upon the historical average atmospheric conditions. The release rate

requirements for lodine-131, lodine-133, tritium, and radionuclides in

particulate form with half-lives greater than 8 days are dependent upon

the existing radionuclide pathways to man, in areas at and beyond the

Site Boundary. The pathways that were examined in the development

of these calculations were: 1) individual inhalation of airborne

radionuclides, 2) deposition of radionuclides onto green leafy

vegetation with subsequent consumption by man, 3) deposition onto

grassy areas where milk animals and meat producing animals graze

with consumption of the milk and meat by man, and 4) deposition on

the ground with subsequent exposure of man.
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OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

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Table B-I

Radioactive Gaseous Waste Sampling and Analysis Program

Gaseous Release Type Sampling Minimum Type of 

Frequency Analysis Activity Analysis 

Frequency 

A. Waste Gas Storage Tank

P

Each Tank

P

Grab Sample Each Tank Principal Gamma Emitters’ 

B. Containment PURGE

P

Each PURGE

P

Grab Sample Each PURGE Principal Gamma Emittersb 

C. Stack Gas Effluent

ContinuousC Charcoal 1-131, 1-133 

Sample

W

Continuousc Particulate Principal Gamma Emittersb 

Sample (1-131, Others)

Q

Continuousc Composite Sr-89, Sr-90, and 

Particulate Gross Alpha

Sample

Noble Gas Noble Gases 

ContinuousC Monitor Gross Beta or Gamma
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table B-I (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-i 35, and Xe-i 38 for

gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo99*, Cs-i 34,

Cs-i 37, Ce-141, and Cei44* for particulate emissions. This list does not mean that

only these nuclides are to be considered. Other gamma peaks that are identifiable,

together with those of the above nuclides, shall also be analyzed and reported in the

Radioactive Effluent Release Report.

*Ten times the LLD because of low gamma yields.

c The ratio of the sample flow rate to the sample stream flow rate shall be known for

the time period covered by each dose or dose rate calculation made in accordance

with requirements lll.B.i, lll.C.1, and lll.D.i.

d Samples shall be changed at least once per 7 days and analyses shall be completed

within 48 hours after changing or after removal from sampler.

e With channels operable on iodine monitor RIA 2325 less than required per lll.A.i,

sampling shall also be performed at least once per 24 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.
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

E. GASEOUS WASTE TREATMENT SYSTEM

Requirement

When gaseous waste exceeds a Xe-I 33 concentration of

I E-05 pCi/cc, the Waste Gas Decay Tank System shall be used to

reduce radioactive gaseous effluents by holding gaseous waste

collected by the system for a minimum of 15 days.

2. Action

a. If a waste gas decay tank is required to be released with less

than 15 days holdup time, the system waste gas tank contents

shall be evaluated and the waste gas decay tank with the lowest

Xe-i 33 content shall be released.

b. Gaseous waste may be discharged directly from the waste gas

surge tank through a high-efficiency filter or from a waste gas

decay tank with less than 15 days of holdup directly to the

stack for a period not to exceed 7 days if the holdup system

equipment is not available and the release rates meet

requirements lll.B, C, and D.

3. Surveillance Requirements

Not Applicable.
PALISADES NUCLEAR PLANT ODCM

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NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

The requirement that the appropriate portions of these systems be

used, when specified, provides reasonable assurance that the releases

of radioactive materials in gaseous effluents will be kept “as low as is

reasonably achievable” by meeting the design objectives given in

Section Il.D of Appendix Ito IOCFR5O.

It is expected that releases of radioactive materials in effluents shall be

kept at small fractions of the limits specified in 20.1302 of 1OCFR2O.

At the same time the licensee is permitted the flexibility of operation,

compatible with considerations of health and safety, to assure that the

public is provided a dependable source of power even under unusual

operating conditions which may temporarily result in releases higher

than such small fractions, but still within the limits specified in lll.B, C,

and D.

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

Requirement

The radioactive liquid effluent monitoring instrumentation channels

shown in Table C-I shall be operable with their alarm/trip setpoints

set to ensure that the limits of lll.G are not exceeded. The alarm/trip

setpoints of these channels shall be determined and adjusted in

accordance with the methodology and parameters in the Offsite Dose

Calculation Manual (ODCM).
PALISADES NUCLEAR PLANT ODCM

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NRC GENERIC LETTER 89-01 (TAC NO 75060)

2. Action

a. With a radioactive liquid effluent monitoring instrumentation

channel alarm/trip setpoint less conservative than required by

the above specification, without delay suspend the release of

radioactive liquid effluents monitored by the affected channel or

declare the channel inoperable, or change the setpoint so it is

acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent

monitoring instrumentation channels Operable, take the Action

shown in Table C-i. Exert best efforts to return the instruments

to Operable status within 30 days and, if unsuccessful, explain

in the next Radioactive Effluent Release Report why the

inoperability was not corrected in a timely manner.

3. Surveillance Requirements

Each radioactive liquid effluent monitoring instrumentation channel

shall be demonstrated Operable by performance of the Channel

Check, Source Check, Channel Calibration, and Channel Functional

Test operations at the frequencies shown in Table C-2.

4. Bases

The radioactive liquid effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and

adjusted in accordance with the methodology and parameters in the

ODCM to ensure that the alarm/trip will occur prior to exceeding

10 times the limits of I OCFR Part 20. The Operability and use of this

instrumentation is consistent with the requirements of General Design

Criteria 60, 63, and 64 of Appendix A to I OCFR Part 50.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

ODCM

Appendix A

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Table C-I

Radioactive Liquid Effluent Monitoring Instrumentation

Minimum

Instrument Operable Applicability Action

Channels

GROSS RADIOACTIVITY MONITORS PROVIDING

ALARM AND AUTOMATIC TERMINATION OF

RELEASE

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

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

(RIA_0707)

2. GROSS BETA OR GAMMA RADIOACTIVE

MONITORS PROVIDING ALARM BUT NOT

PROVIDING AUTOMATIC TERMINATION OF

RELEASE

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

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

Line_(RIA_5211)

3. FLOW RATE MEASUREMENT DEVICES

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

1050)

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip

Setpoints are not applicable)

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

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

c. Steam Generator Blowdown Effluent (1) For Effluent Releases 3
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Table C-I (Cont’d)

TABLE NOTATION

ACTION I - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases may continue provided that

prior to initiating a release:

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

requirements and

b. At least two technically qualified members of the Facility Staff

independently verify the release rate calculations and discharge line

valving;

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided grab samples are analyzed for radioactivity at a lower limit

of detection as specified in Table D-1 for principle gamma emitters and 1-131

at least once per 12 hours.

NOTES The Steam Generator blowdown monitor is normally used in a clean up closed

loop system instead of as an effluent monitor. The action statement only applies

when the monitor is used as an effluent monitor.

ACTION 3 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided that, at least once per 24 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.

ACTION 4 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided the flow rate is estimated at least once per 4 hours during

actual releases. Pump performance curves or tank levels may be used to

estimate flow.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-2

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirement

Channel Source Ch

Instrument 

Check Check Cal

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND

AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RIA 1049)

P

P 

b. Steam Generator Blowdown Effluent Line (RIA 0707)

D

M 

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 

b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211)

D

M 

3. FLOW RATE MEASUREMENT DEVICES (5)

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

4. TURBINE SUMP EFFLUENT COMPOSITER D(4) NA 

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

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

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table C-2 (Cont’d)

TABLE NOTATION

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if in

measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if eit

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 traceabl

Institute of Standards and Technology or using standards that have been obtained from suppliers t

measurement assurance activities with

N 1ST. These standards shall permit calibrating the system 

range of energy and measurement range.

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

(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check s

least once per 24 hours on days on which continuous or batch releases are made.

(5) Turbine Sump Discharge Flow Meter FQI-5210 was calibrated at factory and doesn’t require recafibratio

TABLE FREQUENCY NOTATION

D At least once per 24 hours

Q At least once per 92 days

M At least once per 31 days

R At least once per 18 months

P Prior to radioactive batch release

W At least once per week
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NRC GENERIC LETTER 89-01 (TAC NO 75060)

G. LIQUID EFFLUENTS CONCENTRATION

Requirement

The concentration of radioactive material released in liquid effluents to

Unrestricted Areas shall be limited to 10 times the concentrations

specified in IOCFR Part 20, Appendix B, Table 2, Column 2 for

radionuclides other than dissolved or entrained noble gases. For

dissolved or entrained noble gases, the concentration shall be limited

to 2 x i0 microcuries/mI total activity.

2. Action

With the concentration of radioactive material released in liquid

effluents to Unrestricted Areas exceeding the above limits, without

delay, restore the concentration to within the above limits.

3. Surveillance Requirements

a. Radioactive liquid wastes shall be sampled and analyzed

according to the sampling and analysis program of Table D-1.

b. The results of the radioactivity analysis shall be used in

accordance with the methodology and parameters in the ODCM

to assure that the concentrations at the point of release are

maintained within the limits of G.1 above.
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4. Bases

This requirement is provided to ensure that the concentration of

radioactive materials released in liquid waste effluents to Unrestricted

Areas will be less than 10 times the concentration levels specified in

1OCFR Part 20, Appendix B, Table 2, Column 2. This limitation

provides additional assurance that the levels of radioactive materials in

bodies of water in Unrestricted Areas will result in exposures within the

Section ll.A design objectives of Appendix I, IOCFR Part 50, to a

Member of the Public. The concentration limit for dissolved or

entrained noble gases is based upon the assumption that Xe-i 35 is

the controlling radioisotope and 10 times the effluent concentration in

air (submersion) was converted to an equivalent concentration in water

using the methods described in International Commission on

Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid

waste samples are tabulated in terms of the lower limits of detection

(LLDs). Detailed discussion of the LLD and other detection limits can

be found in HASL Procedures Manual, HASL-300, Currie, LA, “Limits

for Qualitative Detection and Quantitative Determination -Application

to Radiochemistry,” Anal Chem 40, 586-93 (1968), and Hartwell, JK,

“Detection Limits for Radioanalytical Counting Techniques,” Atlantic

Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

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Table D-1

Radioactive Liciuid Waste SamDlinq and Analysis Proqram

Liquid Release Type Sampling Minimum Analysis Type of Activity Analysis 

Frequency Frequency 

A. Batch Waste Release Tanksb

P

P Principal Gamma Emittersc 

Each Batch Each Batch 1-131 

P

M Dissolved and Entrained Gases 

One Batch/M (Gamma Emitters)

Each

P

Batch Composited M H-3 

Gross Alpha 

P

Q Sr-89, Sr-90 

Each Batch Compositec

B. Continuous Releasese Continuous t

W Principal Gamma Emittersc 

(Turbine Sump, Steam Generator Composite t 1-131 

Blowdown, and Service Water)

M

M Dissolved and Entrained Gases

Grab Sample (Gamma Emitters) 

Continuous t

M H-3 

Composite t Gross Alpha 

Continuous’

Q Sr-89, Sr-90 

Composite

Frequency Notation

P Prior to batch release

M Calendar monthQ Calendar quarter

W Calendar week
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Table D-1 (Cont’d)

TABLE NOTATION

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

b A batch release is the discharge of liquid wastes of a discrete volume. Prior to

sampling for analyses, each batch shall be isolated and then thoroughly mixed to

assure representative sampling.

c The principal gamma emitters for which the LLD specification applies exclusively are

the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo99*, Cs-i 34,

Cs-i 37, Ce-i41, and Ce144*. This list does not mean that only these nuclides are

to be considered. Other gamma peaks that are identifiable, together with those of

the above nuclides, shall also be analyzed and reported in the Radioactive Effluent

Release Report.

*LLD - 5E-06 because of low gamma yields.

d A composite sample is one in which the quantity of liquid sampled is proportional to

the quantity of liquid waste discharged and in which the method of sampling

employed results in a specimen that is representative of the liquids released.

e A continuous release is the discharge of liquid wastes of a nondiscrete volume;

eg, from a volume of a system that has an input flow during the continuous release.

f To be representative of the quantities and concentrations of radioactive materials in

liquid effluents, samples shall be collected in a series of aliquots of constant volume

collected at regular time intervals and combined to form a single sample. Prior to

analyses, all samples taken for the composite shall be thoroughly mixed in order for

the composite sample to be representative of the effluent release.
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H. LIQUID EFFLUENT DOSE

Requirement

The dose or dose commitment to a Member of the Public from

radioactive materials in liquid effluents released from each reactor unit

to Unrestricted Areas shall be limited:

a. During any calendar quarter to less than or equal to 1 .5 mrems

to the total body and to less than or equal to 5 mrems to any

organ, and

b. During any calendar year to less than or equal to 3 mrems to

the total body and to less than or equal to 10 mrems to any

organ.

2. Action

With the calculated dose from the release of radioactive materials in

liquid effluents exceeding any of the above limits, prepare and submit

to the NRC within 30 days a Special Report that identifies the cause(s)

for exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits. This Special Report shall also include the results

of radiological analyses of the drinking water source.

3. Surveillance Requirements

Cumulative dose contributions from liquid effluents for the current

calendar quarter and the current calendar year shall be determined in

accordance with the methodology and parameters in the ODCM at

least once every 31 days.
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4. Bases

This requirement is provided to implement the requirements of

Sections ll.A, Ill.A, and IV.A of Appendix I, 1OCFR Part 50. The

Limiting Condition for Operation implements the guides set forth in

Section ll.A of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in liquid effluents to Unrestricted Areas will be kept

“as low as is reasonably achievable.” Also, for freshwater sites with

drinking water supplies that can be potentially affected by Plant

operations, there is reasonable assurance that the operation of the

facility will not result in radionuclide concentrations in the finished

drinking water that are in excess of the requirements of 4OCFR

Part 141. The dose calculation methodology and parameters in the

ODCM implement the requirements in Section lll.A of Appendix I that

conformance with the guides of Appendix I be shown by calculational

procedures based on models and data, such that the actual exposure

of a Member of the Public through appropriate pathways is unlikely

to be substantially underestimated. The equations specified in the

ODCM for calculating the doses due to the actual release rates of

radioactive materials in liquid effluents are consistent with the

methodology provided in Regulatory Guide 1.109, “Calculation of

Annual Doses to Man From Routine Releases of Reactor Effluents

for the Purpose of Evaluating Compliance with 1 OCFR Part 50,

Appendix I,” Revision 1, October 1977 and Regulatory Guide 1.113,

“Estimating Aquatic Dispersion of Effluents From Accidental and

Routine Reactor Releases for the Purpose of Implementing

Appendix I,” April 1977.
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TOTAL DOSE

Requirement

The annual (calendar year) dose or dose commitment to any Member

of the Public due to releases of radioactivity and to radiation from

uranium fuel cycle sources shall be limited to less than or equal to

25 mrems to the total body or any organ, except the thyroid, which

shall be limited to less than or equal to 75 mrems.

2. Action

With the calculated doses from the release of radioactive materials in

liquid or gaseous effluents exceeding twice the limits of lll.C.1 .a,

lll.C.1.b, lll.D.1.a, lll.D.1.b, lll.H.1.a, or III.H.1.b, calculations should be

made including direct radiation contributions from the reactor units and

from outside storage tanks to determine whether the above limits of

111.1.1 have been exceeded. If such is the case, prepare and submit to

the NRC within 30 days a Special Report that defines the corrective

action to be taken to reduce subsequent releases to prevent

recurrence of exceeding the above limits and includes the schedule for

achieving conformance with the above limits. This Special Report, as

defined in 1OCFR Part 20.2203, shall include an analysis that

estimates the radiation exposure (dose) to a Member of the Public

from uranium fuel cycle sources, including all effluent pathways and

direct radiation, for the calendar year that includes the release(s)

covered by this report. It shall also describe levels of radiation and

concentrations of radioactive material involved and the cause of the

exposure levels or concentrations. If the estimated dose(s) exceeds

the above limits, and if the release condition resulting in violation of

400FR Part 190 has not already been corrected, the Special Report

shall include a request for a variance in accordance with the provisions

of 4OCFR Part 190. Submittal of the report is considered a timely

request and a variance is granted until staff action on the request is

complete.
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3. Surveillance Requirements

a. Cumulative dose contributions from liquid and gaseous effluents

shall be determined in accordance with Ill.C.1, lIl.D.1, and

lll.H.1 and in accordance with the methodology and parameters

in the ODCM.

b. Cumulative dose contributions from direct radiation from the

reactor units and from radwaste storage tanks shall be

determined in accordance with the methodology and

parameters in the ODCM. This requirement is applicable only

under conditions set forth in Action 1.2 above.
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4. Bases

This requirement is provided to meet the dose limitations of

4OCFR Part 190 that have been incorporated into 1OCFR Part 20 by

46 FR 18525. It also requires the preparation and submittal of a

Special Report whenever the calculated doses from Plant generated

radioactive effluents and direct radiation exceed 25 mrems to the total

body or any organ, except for thyroid, which shall be limited to less

than or equal to 75 mrems. For sites containing up to 4 reactors, it is

highly unlikely that the resultant dose to a Member of the Public will

exceed the dose limits of 4OCFR Part 190 if the individual reactors

remain within twice the dose design objectives of Appendix I and if

direct radiation doses from the reactor units and outside storage tanks

are kept small. The Special Report will describe a course of action that

should result in the limitation of the annual dose to a Member of the

Public to within the 4OCFR Part 190 limits. For the purposes of the

Special Report, it may be assumed that the dose commitment to the

Member of the Public from other uranium fuel cycle sources is

negligible, with the exception that dose contributions from other

nuclear fuel cycle facilities at the same site or within a radius of 8 km

must be considered. If the dose to any Member of the Public is

estimated to exceed the requirements of 4OCFR Part 190, the Special

Report with a request for a variance (provided the release conditions

resulting in violation of 4OCFR Part 190 have not already been

corrected), in accordance with the provisions of 4OCFR Part 190.11

and IOCFR Part 20.2203, is considered to be a timely request and

fulfills the requirements of 4OCFR Part 190 until NRC staff action is

completed. The variance only relates to the limits of 4OCFR Part 190

and does not apply in any way to the other requirements for dose

limitation of IOCFR Part 20. An individual is not considered a Member

of the Public during any period in which he/she is engaged in carrying

out any operation that is part of the nuclear fuel cycle.
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NRC GENERIC LETTER 89-01 (TAC NO 75060)

J. RADIOLOGICAL ENVIRONMENTAL MONITORING

Requirement

The radiological environmental monitoring program shall be conducted

as specified in Table E-1.

2. Action

a. With the radiological environmental monitoring program not

being conducted as specified in Table E-1, prepare and submit

to the NRC, in the Annual Radiological Environmental Operating

Report a description of the reasons for not conducting the

program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of Plant effluents in

an environmental sampling medium at a specified location

exceeding the reporting levels of Table E-2 when averaged over

any calendar quarter, prepare and submit to the NRC within

30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions to be

taken to reduce radioactive effluents. When more than one of

the radionuclides in Table E-2 are detected in the sampling

medium, this report shall be submitted if:

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

Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table E-2 are detected

and are the result of Plant effluents, this report shall be

submitted if the potential annual dose to a Member of the Public

is equal to or greater than the calendar year limits of Ill.C.1,

lll.D.1, and lll.H.1. This report is not required if the measured

level of radioactivity was not the result of Plant effluents;

however, in such an event, the condition shall be reported and

described in the Annual Radiological Environmental Operating

Report.
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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 ft2)

producing broad leaf vegetation.

c. The land use census shall be conducted during the growing

season at least once per 12 months using that information that

will provide the best results, such as by a door-to-door survey,

aerial survey, or by consulting local agriculture authorities. The

results of the land use census shall be included in the Annual

Radiological Environmental Operating Report and shall be

included in a revision of the ODCM for use in the following

calendar year.

d. Analyses shall be performed on radioactive materials supplied

as part of an Interlaboratory Comparison Program that has been

approved by the NRC.
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e. A summary of the results obtained as part of the above required

Interlaboratory Comparison Program shall be included in the

Annual Radiological Environmental Operating Report.

f. The environmental air samplers shall be operationally checked

monthly and airflow verified annually.

4. Bases

a. Monitoring Program

The radiological environmental monitoring program provides

representative measurements of radiation and of radioactive

materials in those exposure pathways and for those

radionuclides that lead to the highest potential radiation

exposures of Members of the Public resulting from the station

operation. This monitoring program implements Section lV.B.2

of Appendix Ito 1OCFR 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).
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b. Land Use Census:

This requirement is provided to ensure that changes in the use

of areas at and beyond the site boundary are identified and that

modifications to the radiological environmental monitoring

program are made if required by results of this census. The

best information from the door-to-door survey, from aerial

survey or from consulting with local agricultural authorities shall

be used. This census satisfies the requirements of

Section IV.B.3 of Appendix Ito IOCFR Part 50. Restricting the

census to gardens of greater than 50 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 kglm 2.

c. Interlaboratory Comparison Program:

The requirement for participation in an approved Interlaboratory

Comparison Program is provided to ensure that independent

checks on the precision and accuracy of the measurements of

radioactive material in environmental sample matrices are

performed as part of the quality assurance program for

environmental monitoring in order to demonstrate that the

results are valid for the purposes of Section IV.B.2 of Appendix I

to IOCFR Part 50.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

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Table E-1

Radiological Environmental Monitoring Program

Exposure Pathway Number of Representative Sampling and Type an

and/or Sample Samples and Sample Locationsa Collection Frequency of 

1. DIRECT RADIATIONb 21 routine monitoring stations either with two or Quarterly Gamma 

more dosimeters or with one instrument for

measuring and recording dose rate continuously,

placed as follows:

An inner ring of stations, one in each overland

meteorological sector (9) in the general area of

the Site Boundary.

An outer ring of stations, one in each overland

meteorological sector (9) within the 12 km range

from the site.

The balance of the stations (3) to be placed to

serve as control stations.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAG NO 75060)

Exposure Pathway Number of Representative Sampling and Type a

and/or Sample Samples and Sample Locationsa Collection Frequency of 

2. AIRBORNE

Radioiodine and Samples from 5 locations. Continuous sample RadioiodinParticulates operation with sample 1-131 analy

3 samples from within 6 km of the Site Boundary collection weekly or more each filter 

in different sectors (2.4 km-SSW, 5.6 km-ESE, frequently if required by

and 1.6 km-N). dust loading. Particulate 

Gross beta 

1 sample from the vicinity of a community having analysis fo

the highest calculated annual average ground changed. G

level DIQ (Covert-5.6 km-SE). analysise if 

>1.0 pCi/m 3.

I sample from a control location in the least

prevalent wind directionc (Grand Rapids89 km-NNE).

3. WATERBORNE

a. Lake (surface) Plant lake water inlet. Composite sample over Gross beta 

1-month period t, requires ga

monthly.

b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gross beta 

1-month period t, requires ga

monthly.

1 sample from a control location (Ludington Composite sample over Gross beta 

Pumped Storage 201 km N) 1-month period t requires ga

monthly.

c. Well (drinking) 1 grab sample per month when Palisades Park 1 grab sample per month Gross beta 

community drinking water well is in operation (Park when operational requires gam

is seasonal in operations and is only open for the per month w

summer months) operational
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OFFSITE DOSE CALCULATION MANUAL 

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Exposure Pathway Number of Representative Sampling and Type an

andlor Sample Samples and Sample Locationsa Collection Frequency of 

d. Sediment from shoreline I sample from between north boundary and Van Semiannually Gamma iso

Buren State Park beach, approximately

% mile semiannual

north of the Plant discharge.

4. INGESTION

a. Milk Samples from milking animals in 3 locations Monthly Gamma iso

between 5-8 km distance. analysis mo

1 sample from milking animals at a control location, Monthly Gamma iso

15-30 km distance. analysis mo

b. Broad leaf Samples of 3 different kinds of broad leaf vegetation Monthly during growing Gamma iso

vegetation grown nearest each of two different offsite locations season analysis of highest predicted annual average ground level

D/Q if milk sample is not performed. (SE or SSE

sectors near site.)

I sample of each of the similar broad leaf vegetation Monthly during growing Gamma isot

grown 1 5-30 km distance in the least prevalent wind season analysis direction if milk sampling is not performed. (NNE or

NE sectors.)

c. Fish Sample 2 species of commercially and/or Sample in season or Gamma iSot

recreationally important species in vicinity of Plant semiannually if they are analysis.

discharge area. 1 sample of same species in areas not seasonal.not influenced by Plant discharge.

d. Food Products I sample each of two principal fruit crops At time of harvest 9 Gamma Iso

(blueberries and apples). analysis.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-1 (Cont’d)

Table Notation

a Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal 

malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipm

every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the samplin

documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or probtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locati

the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring pr

b One or more instwments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in p

integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two 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 

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 a

decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic 

performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the 

facility.

A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in 

sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composi

criteria are acceptable).

g If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-2

Reporting Levels for Radioactivity Concentrations in Environmental Samples

Reporting Levels

Analysis. Water Airborne Particulates Fish Milk Food 

(pCill) or Gases (pCi/rn 3) (pCi/kg, Wet) (pCiII) (pC

H-3 20,000*

Mn-54 1,000 30,000

Fe-59 400 10,000

Co-58 1,000 30,000

Co-60 300 10,000

Zn-65 300 20,000

Zr-Nb-95 400

1-131

2 0.9 3 

Cs-134 30 10 1,000 60 

Cs-I 37 50 20 2,000 70 

Ba-La-140 200 300

* For drinking water samples. This is 4OCFR Part 141 value. If no drinking water pathway exists,

a value 

be used.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-3

Detection Capabilities for Environmental Sample Analysisa

Lower Limit of Detection (LLD)’

• Water Airborne Particulates Fish Milk Food Products 

Analysis . 3) (pCill) or Gases (pCi/rn (pCi/kg, Wet) (pCi/I) (pCi/kg, Wet) 

Gross Beta

4 0.01

H-3 2,000*

Mn-54 15 130

Fe-59 30 260

Co-58, 60 15 130

Zn-65 30 260

Zr-Nb-95 15

1-131

1d 0.07 1 60

Cs-134 15 0.05 130 15 60 

Cs-I 37 18 0.06 150 18 80 

Ba-La-140 15 15

* If no drinking water pathway exists,

a value of 3,000 pCi/I 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-3 (Cont’d)

TABLE NOTATION

a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the a

be analyzed and reported in the Annual Radiological Environmental Operating Report.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory G

C The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system backg

detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a ‘real” signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66

b

E

V 2.22

Y Exp (-l..At)

Where:

LLD is the “a priori” lower limit of detection as defined above, as picocuries per unit mass or volume.

Sb iS the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per 

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.

tfor environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of cou

Typical values of E, V, Y, and

tshould 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

It should be recognized that the LLD is defined as an ‘a priori” (before the fact) limit representing the capability of a measurement system 

“a posteriori” (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will b

conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontr

render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Env

Report.

d

LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
PALISADES NUCLEAR PLANT 00CM

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NRC GENERIC LETTER 89-01 (TAC NO 75060)

K. SIRW OR TEMPORARY LIQUID STORAGE TANK

Requirement

The concentration of radioactive material contained in the SIRW tank

or any unprotected outside temporary tank* shall be limited such that

the mixture radionuclides do not exceed 1,000 times the effluent

concentration (EC) as listed in 1OCFR Part 20, Appendix B, Table 2,

Column 2.

+ k•.•Qi = <1000

ECa ECb EC1

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.

or

A calculational methodology performed prior to the material being

transferred may be used to show compliance with the requirement of

this section if a representative sample cannot be obtained at least once

per seven days. A representative sample of the radioactive material to

be added to the SIRW or Temporary Liquid Storage Tank shall be

analyzed and a calculation performed to show compliance with the

1000 EC limit.
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4. Bases

This requirement will provide reasonable assurance that in the event

of an uncontrolled release of the tanks’ contents, the resulting

concentrations would be less than the limits of 1OCFR Part 20,

Appendix B, Table 2, Column 2, at the nearest potable water

supply and the nearest surface water supply in an Unrestricted Area.

(The dilution between Palisades and the South Haven drinking water

supply has been established as 1000.)

*Tanks included in this specification are those outdoor tanks that are not

surrounded by liners, dikes, or walls capable of holding the tank contents and

that do not have tank overflows and surrounding area drains connected to the

liquid radwaste treatment system.

NOTES The limit for the SIRW Tank may be exceeded for operational flexibility if the

conditions of this section are met.

L. SURVEILLANCE REQUIREMENT TIME INTERVALS

Requirement

Each Surveillance Requirement shall be performed within the specified

surveillance interval with a maximum allowable extension not to

exceed 25 percent of the specified surveillance interval.

2. Action

Failure to perform a Surveillance Requirement within the allowed

surveillance interval shall constitute noncompliance with the operability

requirements. The time limits of the action requirements are applicable

at the time it is identified that a Surveillance Requirement has not been

performed. The action requirements may be delayed for up to

24 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.
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3. Surveillance Requirements

The applicable surveillance interval frequencies are specified in

Tables A-2 and C-2. The applicable sampling and/or analysis

frequencies are specified in Tables A-i, B-I, C-I, D-1, and E-1.

Extendable surveillance requirements are limited to Channel Checks,

Source Checks, Channel Calibrations, Channel Functional Checks,

sampling frequencies and/or analysis frequencies.

4. Bases

The maximum allowable extension for a surveillance interval is

consistent with the surveillance requirements specified in the Technical

Specifications, Section 4.0. Until relocated in the ODCM, all of the

effluent surveillances were subject to these same requirements.

M. SEALED SOURCE CONTAMINATION

1. Requirement

Each sealed source containing radioactive material either in excess

of 100 microcuries of beta and/or gamma emitting material or

5 microcuries of alpha emitting material shall be free of greater than

or equal to 0.005 microcuries of removable contamination.

2. Action

a. With a sealed source having removable contamination in excess

of 0.005 microcuries, immediately withdraw the sealed source

from use and either:

(1) Decontaminate and repair the sealed source, or

(2) Dispose of the sealed source in accordance with

applicable regulations.

b. A report shall be prepared and submitted to the Commission on

an annual basis if sealed source leakage tests reveal the

presence of greater than or equal to 0.005 microcuries of

removable contamination.
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3. Surveillance Requirements

a. Each category of sealed sources as described in the

requirement with a half-life greater than 30 days (excluding

Hydrogen-3), and in any other form than gas, shall be tested for

leakage and/or contamination at intervals not to exceed

6 months.

b. The test shall be performed by the licensee or by other persons

specifically authorized by the Commission or an Agreement

State. The test method shall have a detection sensitivity of at

least 0.005 microcuries per test sample.

c. The test sample shall be taken from the sealed source or, in the

case of permanently mounted sources, from the surfaces of the

mounting device on which contamination would be expected to

accumulate.

d. The periodic leak test does not apply to sealed sources that are

stored and not being used. These sources shall be tested prior

to use or transfer to another licensee, unless tested within the

previous 6 months. Sealed sources which are continuously

enclosed within a shielded mechanism (ie, sealed sources

within radiation monitoring or boron measuring devices) are

considered to be stored and need not be tested unless they are

removed from the shielded mechanism.

e. Sealed sources transferred without a certificate indicating the

last test date shall be tested prior to being placed in use.

4. Bases

The requirement, actions, and surveillance requirements are the same

as contained in the Technical Specifications 6.21 prior to relocation to

the ODCM and will provide assurance that sealed sources are tested

to demonstrate that source integrity is being maintained.
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

IV. REPORTING REQUIREMENTS

A. RADIOLOGICAL EFFLUENT RELEASE REPORT

The Radioactive Effluent Release Report shall be submitted in accordance

with IOCFR 50.36a prior to May 1 of each year. The report shall follow the

guidance contained in Regulatory Guide 1.21 Revision 2, Section 8, Format

and Content of the Annual Radioactive Effluent release Report.

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Radiological Environmental Operating Report covering the operation of

the unit during the previous calendar year shall be submitted prior to May 15

of each year. The report shall include summaries, interpretations, and

analysis of trends of the results of the Radiological Environmental Monitoring

Program for the reporting period. The material provided shall be consistent

with the objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, lV.B.3,

and IV.C of Appendix Ito IOCFR5O.

The Annual Radiological Environmental Operating Reports shall include

summaries, interpretation and statistical evaluation of the results of the

radiological environmental surveillance activities for the report period,

including a comparison with preoperational studies, operational controls

(as appropriate), and previous environmental surveillance reports and an

assessment of the observed impacts of the Plant operation on the

environment. The reports shall also include the results of land use census

pursuant to Ill.J.3.c.

The Annual Radiological Environmental Operating Reports shall include

summarized and tabulated results in the format of Table F-I of all radiological

environmental samples taken during the report period. In the event that some

results are not available for inclusion with the report, the report shall be

submitted noting and explaining the reasons for the missing results. The

missing data shall be submitted as soon as possible in a supplementary

report.

The reports shall also include the following; a summary description of the

radiological environmental monitoring program, including sampling methods

for each sample type, a map of all sampling locations keyed to a table giving

distances and directions from the reactor and the results of land use census

required by IlI.J.3.c and results of the Interlaboratory Comparison Program

required by III.J.3.e.
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C. NONROUTINE REPORTS

A report shall be submitted to the NRC in the event that: 1) the Radiological

Environmental Monitoring Programs are not substantially conducted as

described in Section Ill.J, or 2) an unusual or important event occurs from

Plant operation that causes a significant environmental impact or affects a

potential environmental impact. Reports shall be submitted within 30 days.
PALISADES NUCLEAR PLANT O

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table F-I

Environmental Radiological Monitoring Program Summary

A

R

P

Name of Facility

Location of Facility

(County, Stat&)

Docket No

Reporting Period___

4

Medium or Pathway Type/Total Lower Limit All Indicator

Number of of Locations Name Mean (f)b Control Lo

Sampled

(Unit of Measure)

Analyses Detectiona Mean (f)b Distance

& Direction Rangeb Mean(

Performed (LLD) Ranges Rang&

Air Particulates Gross R 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/

(pCi/rn 3) (200/312) 5 miles 3400 (0.08-2.0) (0.05-1

v-Spec 32 (0.05-2.0)

Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 

(0.03-0.13) 2.5 miles 160° (0.03-0.13)

Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (

(0.01 -0.08) 4 miles 270° (0.01-0.08)

Sr-89 40 0.002 <LLD --

-- <LLD 

Sr-90 40 0.0003 <LLD --

-- <LLD 

Fish v-Spec 8

pCi/kg (dry weight) <LLD

Cs-137 80

-- <LLD 90(1/

<LLD

Cs-134 80

— <LLD <LLD 

120 (3/4)

Co-60 80 (90-200) River Mile 35 See <LLD 

Podunk River Column 4

a

b

NOTE: The example data are provided for illustrative purposes only.

Nominal Lower Limit of Detection (LLD) as defined in table notation c of Table E-3.

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is i
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NRC GENERIC LETTER 89-01 (TAC NO 75060)

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS

A. LICENSEE MODIFICATIONS

Licensee initiated major modifications to the radioactive liquid and gaseous

waste systems.

1. Shall be reported to the NRC pursuant to IOCFR 50.59. The

discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that

the modification could be made in accordance with

IOCFR Part 50.59.

b. A description of the equipment, components and processes

involved, and the interfaces with other Plant systems.

c. Documentation of the fact that the modification was reviewed

and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the General

Manager Plant Operations.
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B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION

1. Purpose:

The purpose of this definition is to assure that this requirement will be

satisfied under clearly identifiable circumstances, and with the

objective that current radwaste system capabilities are not jeopardized.

2. Definition:

A major radwaste system modification is a modification which would

remove (either by bypassing for greater than 7 days or physical

removal) or replace with less efficient equipment, any components of

the radwaste system:

a. Letdown filters or demineralizers.

b. Vacuum degassifier (not applicable when the reactor is in cold

shutdown and depressurized).

c. Miscellaneous or clean waste evaporators.

d. The present waste gas compressor/decay tank system.

e. Fuel Pool filters/demineralizers.

f. Radwaste polishing demineralizers.

g. Radwaste Solidification system.

Improvements or additions to improve efficiency will not be

considered major modifications unless a complete substitution

of equipment or systems is made with equipment of unrelated

design. Examples would be: 1) replacement of mechanical

degassifier with steam, jet degassifier, 2) replacement of waste

gas system with cryogenic system, 3) replacement of asphalt

solidification with cement system, and 4) change from deep

bead resins to Powdex, etc.
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VI. ONSITE GROUND WATER MONITORING

Palisades installed 5 ground water monitoring wells in 2007 and added an additional

9 wells in 2008. These wells were installed in response to NEI 07-07, Industry

Ground Water Protection Initiative — Final Guidance Document. These wells are

strategically placed within the Owner Controlled Area, both inside and outside the

Protected Area to allow detection of radioactive contamination of ground water due

to leaks or spills from plant systems.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

ODCM

Appendix A

Revision 17

Issued Date 12129111

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Process Applicability Exclusion

DWFoster for JHager I 12I28/11

Procedure Sponsor Date

JJMiller / 12/15111

Technical Reviewer Date

JHager I 12/15/11

User Reviewer Date

DHamilton

General Manager Plant Operations

12l19I11

Date

I
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Table of Contents

INTRODUCTION I

DEFINITIONS I

A. CHANNEL CALIBRATION I

B. CHANNEL CHECK I

C. CHANNEL FUNCTIONAL TEST 2

0. SOURCE CHECK 2

E. OFFSITE DOSE CALCULATION MANUAL 2

F. GASEOUS RADWASTE TREATMENT SYSTEM 2

G. MEMBERS OF THE PUBLIC 2

H. PROCESS CONTROL PROGRAM (PCP) 3

I. SITE BOUNDARY 3

J. UNRESTRICTED AREA 3

K. VENTILATION EXHAUST TREATMENT SYSTEM 3

III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES 4

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING

INSTRUMENTATION 4

1. Requirement 4

2. Action 4

3. Surveillance Requirements 4

4. Bases 5

B. GASEOUS EFFLUENTS DOSE RATE 10

1. Requirement 10

2. Action 10

3. Surveillance Requirements 10

4. Bases 11

C. NOBLE GASES DOSE 12

1. Requirement 12

2. Action 12

3. Surveillance Requirements 12

4. Bases 13
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Table of Contents

D. 1-131, 1-133, TRITIUM, AND PARTICULATES 14

1. Requirement 14

2. Action 14

3. Surveillance Requirements 14

4. Bases 15

E. GASEOUS WASTE TREATMENT SYSTEM 19

1. Requirement 19

2. Action 19

3. Surveillance Requirements 19

4. Bases 20

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 20

1. Requirement 20

2. Action 21

3. Surveillance Requirements 21

4. Bases 21

G. LIQUID EFFLUENTS CONCENTRATION 26

1. Requirement 26

2. Action 26

3. Surveillance Requirements 26

4. Bases 27

H. LIQUID EFFLUENT DOSE 30

1. Requirement 30

2. Action 30

3. Surveillance Requirements 30

4. Bases 31

TOTAL DOSE 32

1. Requirement 32

2. Action 32

3. Surveillance Requirements 33

4. Bases 34
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Table of Contents

J. RADIOLOGICAL ENVIRONMENTAL MONITORING 35

1. Requirement 35

2. Action 35

3. Surveillance Requirements 36

4. Bases 37

K. SIRW OR TEMPORARY LIQUID STORAGE TANK 51

1. Requirement 51

2. Action 51

3. Surveillance Requirement 51

4. Bases 52

L. SURVEILLANCE REQUIREMENT TIME INTERVALS 52

1. Requirement 52

2. Action 52

3. Surveillance Requirements 53

4. Bases 53

M. SEALED SOURCE CONTAMINATION 53

1. Requirement 53

2. Action 53

3. Surveillance Requirements 54

4. Bases 54

IV. REPORTING REQUIREMENTS 55

A. RADIOLOGICAL EFFLUENT RELEASE REPORT 55

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 56

C. NONROUTINE REPORTS 56

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS 58

A. LICENSEE MODIFICATIONS 58

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION 59

VI. ONSITE GROUND WATER MONITORING 60
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Table of Contents

TABLES

A-I Radioactive Gaseous Effluent Monitoring Instrumentation

A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance

Requirements

B-I Radioactive Gaseous Waste Sampling and Analysis Program

C-i Radioactive Liquid Effluent Monitoring Instrumentation

C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

D-1 Radioactive Liquid Waste Sampling and Analysis Program

E-I Radiological Environmental Monitoring Program

E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples

E-3 Detection Capabilities for Environmental Sample Analysis

E-4 Radiological Environmental Monitoring Program Locations

F-I Environmental Radiological Monitoring Program Summary
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

INTRODUCTION

The NRC, through 1OCFR5O.36a, requires implementation of Technical

Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01,

dated January 31, 1989, allowed relocation of the existing procedural

requirements from the Technical Specifications (implemented in Amendment 85,

November 9, 1984). The relocated procedural requirements related to gaseous and

liquid effluents, total dose, environmental monitoring program, and associated

procedural reporting requirements follow below. Programmatic controls are retained

in the Administrative Controls section of the Technical Specification to satisfy the

regulatory requirements of 1OCFR5O.36a. The Technical Specifications

programmatic controls include requirements for the establishment, implementation,

maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well

as record retention and reporting requirements.

DEFINITIONS

A. CHANNEL CALIBRATION

- a Channel Calibration shall be the adjustment, as necessary, of the channel

output such that it responds with the necessary range and accuracy to known

values of the parameter which the channel monitors. The Channel

Calibration shall encompass the entire channel including the sensor and

alarm and/or trip functions, and shall include the Channel Function Test.

The Channel Calibration may be performed by any series of sequential,

overlapping, or total channel steps such that the entire channel is calibrated.

B. CHANNEL CHECK

- a Channel Check shall be the qualitative assessment of channel behavior

during operation by observation. This determination shall include, where

possible, comparison of the channel indication and/or status with other

indications and/or status derived from independent instrumentation channels

measuring the same parameter.
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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. CHANNEL FUNCTIONAL TEST

- a Channel Functional Test shall be:

1. Analog channels - the injection of a simulated signal into the channel

as close to the sensor as practicable to verify operability including

alarm and/or trip functions.

2. Bistable channels - the injection of a simulated signal into the sensor to

verify operability including alarm and/or trip functions.

D. SOURCE CHECK

- a source check shall be the qualitative assessment of channel response

when the channel sensor is exposed to a radioactive source.

E. OFFSITE DOSE CALCULATION MANUAL

- (per Plant Technical Specifications) - the Offsite Dose Calculation Manual

(ODCM) shall contain the methodology and parameters used in the

calculation of offsite doses resulting from radioactive gaseous and liquid

effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip

setpoints, and in the conduct of the Radiological Environmental Monitoring

Program. The ODCM shall also contain: 1)the Radioactive Effluent Controls

and Radiological Environmental Monitoring Programs required by the

Technical Specifications, and 2) descriptions of the information that should be

included in the Annual Radiological Environmental Operating and Radioactive

Effluent Release Reports required by the Technical Specifications.

F. GASEOUS RADWASTE TREATMENT SYSTEM

- any system designed and installed to reduce radioactive gaseous effluents

by collecting primary coolant system off gases from the primary system and

providing for delay or holdup for the purpose of reducing the total radioactivity

prior to release to the environment.

G. MEMBERS OF THE PUBLIC

- all persons who are not occupationally associated with the Plant. This

category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service

equipment or to make deliveries.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. PROCESS CONTROL PROGRAM (PCP)

-shall contain the current formula, sampling, analyses, tests, and

determinations to be made to ensure that the processing and packaging of

solid radioactive wastes based on demonstrated processing of actual or

simulated wet solid wastes will be accomplished in such a way as to assure

compliance with IOCFR Part 20, IOCFR Part 71 and Federal and State

regulations and other requirements governing the disposal of the radioactive

waste.

SITE BOUNDARY

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

the licensee.

J. UNRESTRICTED AREA

- any area at or beyond the Site Boundary access which is not controlled by

the licensee for purposes of protection of individuals from exposure to

radiation and radioactive materials or, any area within the Site Boundary used

for residential quarters or for industrial, commercial, institutional, and/or

recreational purposes.

K. VENTILATION EXHAUST TREATMENT SYSTEM

- any system designed and installed to reduce gaseous radioiodine or

radioactive material in particulate form in effluents by passing ventilation or

vent exhaust gases through charcoal absorbers and/or HEPA filters for the

purpose of removing iodines or particulates from the gaseous exhaust stream

prior to the release to the environment. Such a system is not considered to

have any effect on noble gas effluents. Engineered Safety Feature (ESF)

atmospheric cleanup systems are not considered to be ventilation exhaust

treatment system components.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

Requirement

The radioactive gaseous effluent monitoring instrumentation channels

shown in Table A-i shall be operable with their alarm/trip setpoints set

to ensure that the limits of requirement lll.B.1 are not exceeded. The

alarm/trip setpoints of these channels shall be determined and

adjusted in accordance with the methodology and parameters in the

ODCM.

2. Action

a. With a radioactive gaseous effluent monitoring instrumentation

channel alarm/trip setpoint less conservative than required by

the above requirement, without delay, suspend the release of

radioactive gaseous effluents monitored by the affected channel

or declare the channel inoperable or change the setpoint so it is

acceptably conservative.

b. With less than the minimum number of radioactive gaseous

effluent monitoring instrumentation channels operable, take the

action shown in Table A-i. Exert best efforts to return the

instruments to operable status within 30 days and, if

unsuccessful, explain in the next Radioactive Effluent Release

Report why the inoperability was not corrected in a timely

manner.

3. Surveillance Requirements

Each radioactive gaseous effluent monitoring instrumentation channel

shall be demonstrated operable by performance of the Channel Check,

Source Check, Channel Calibration, and Channel Functional Test

operations at the frequencies shown in Table A-2.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

The radioactive gaseous effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

gaseous effluents during actual or potential releases of gaseous

effluents. The alarm/trip setpoints for these instruments shall be

calculated and adjusted in accordance with the methodology and

parameters in the ODCM to ensure that the alarm/trip will occur prior to

exceeding the limits of 1OCFR Part 20.

The operability and use of this instrumentation is consistent with the

requirements of General Design Criteria 60, 63, and 64 of Appendix A

to IOCFR Part 50.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I

Radioactive Gaseous Effluent Monitoring Instrumentation

ODCM

Appendix A

Revision 17

Page 6 of 60

Minimum

Instrument Operable Applicability Action

Channels

WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) Providing

Alarm and Automatic Termination of Release (1) At All Times I

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1) Above 210°F 3

Modes 1, 2, 3, 4

Above 21 0°F

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

3. STACK GAS EFFLUENT SYSTEM

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

b. Iodine/Particulate/Sampler/Monitor (RIA 2325) (1) At All Times 6

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

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

Modes 1, 2, 3, 4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

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

Modes 1,2,3,4

5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE

a. Gross Gamma Activity Monitor* 1 per Main Above 325°F 4

(RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** I per Room Above 210°F 5

(RIA 1810 and 1811) Modes 1,2,3,4

Setpoints for these instruments are exempted from llI.B.1 limits, bit are governed by

Emergency Implementing Procedures or Operating procedures.

** Setpoints for these instruments are exempted from lII.B.1 limits, but are governed by

Technical Specifications SR 3.3.10.3.

*

Documentation of operability not required.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-I (Cont’d)

TABLE NOTATION - ACTION STATEMENTS

ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels

requirements, the contents of the tank(s) may be released to the environment provided that

prior to initiating the release:

a. At least two independent samples of the 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.

ACTION 2 - With the number of channels operable less than required by the Minimum Operable Channels

requirement, effluent releases via this pathway may continue provided the flow rate is

estimated at least once per 24 hours.

ACTION 3 - With the number of channels operable less than required by the Minimum Operable Channels

requirement, effluent releases via this pathway may continue provided grab samples are

taken at least once per 12 hours and these samples are analyzed for gross activity within

24 hours.

ACTION 4 - With the number of operable channels less than required by the Minimum Operable Channels

requirements, initiate the preplanned alternate method of monitoring the appropriate

parameter(s), within 72 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.

ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with

that channel shall be closed immediately and action shall be taken to have the affected

channel repaired. The dampers associated with the channel shallr be opened until the

affected channel has been declared operable.

(Reference Technical Specifications LCO 3.3.10.)

ACTION 6 - 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-i.
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 Requiremen

Channel Channel 

Source Channel Instrument Check Functional 

Check Calibration Test 

WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and D(4)

p R(3) Q(1 )(2) 

Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

b. Evacuation Flow Indicator (FI-0632) or *** *** *** c. Evacuation Flow Indicator (Fl-0631)

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

b. Iodine Particulate Sampler/Monitor

w M** R(3)** NA 

c. Sampler Flow Rate Monitor

D NA

R NA 

d. Hi Range Noble Gas

D

M R(3) Q(2) 

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor

D

M R(3) Q(2) 

5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE 

D

M R(3) Q(2) 

a. Gross_Gamma_Activity_Monitor

6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours 31 days 18 months (3) 31 days(1)(2) 

(Technical Specifications SR 3.3.10 and 

SR_3.7.13.1) * At all times other than when the line is valved out and locked.

** Sampler not applicable

This type of Flowmeter doesn’t have any surveillance requirements.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table A-2 (Cont’d)

Table Notation

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if in

measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if eit

conditions exists.

a. Instrument indicates measured levels above the alarm setpoint (not applicable for Item 3.d, Hi Ran

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceab

Institute of Standards and Technology or using standards that have been obtained from suppliers 

measurement assurance activities with

N 1ST. These standards shall permit calibrating the system 

range of energy and measurement range.

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

(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch release

TABLE FREQUENCY NOTATION

S At least once per 12 hours

D At least once per 24 hours

M At least once per 31 daysP Prior to radioactive batch release

Q At least once per 92 days

R At least once per 18 months

W At least once per week
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. GASEOUS EFFLUENTS DOSE RATE

Requirement

The dose rate due to radioactive materials released in gaseous

effluents from the site to areas at and beyond the Site Boundary

(see Figure 2-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the

total body and less than or equal to 3000 mrems/yr to the skin,

and

b. For Iodine-I 31, for Iodine-I 33, for tritium, and for all

radionuclides in particulate form with half-lives greater than

8 days: Less than or equal to 1500 mrems/yr to any organ.

2. Action

With the dose rate(s) averaged over a period of one hour exceeding

the above limits, without delay, restore the release rate to within the

above limit(s).

3. Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be

determined to be within the limits of B.I .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 B.1 .b in accordance with the methodology and

parameters in the ODCM by obtaining representative samples

and performing analyses in accordance with the sampling and

analysis program specified in Table B-i.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This is provided to ensure that the dose at any time at and beyond the

Site Boundary from gaseous effluents from all units on the site will be

within 10 times the annual dose limits of 1OCFR Part 20 to Unrestricted

Areas. The annual dose limits are the doses associated with the

concentrations of 10 times IOCFR 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 IOCFR 50, Appendix I, Section ll.B.1. For

Members of the Public who may at times be within the Site Boundary,

the occupancy of the Member of the Public will usually be sufficiently

low to compensate for any increase in the atmospheric diffusion factor

above that for the Site Boundary. Examples of calculations for such

Members of the Public, with the appropriate occupancy factors, shall

be given in the ODCM. The specified release rate limits restrict, at all

times, the corresponding dose rate above background to a Member of

the Public at or beyond the Site Boundary to less than or equal to

500 mrems/yr to the total body.

The required detection capabilities for radioactive materials in gaseous

waste samples are tabulated in terms of the lower limits of detection

(LLDs). Detailed discussion of the LLD and other detection limits can

be found in HASL Procedures Manual, HASL-300, Currie, L A, “Limits

for Qualitative Detection and Quantitative Determination -Application

to Radiochemistry,” Anal Chem 40, 586-93 (1968), and Hartwell, JK,

“Detection Limits for Radioanalytical Counting Techniques,” Atlantic

Richfield Hanford Company Report ARH-SA-215 (June 1975).
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

C. NOBLE GASES DOSE

Requirement

The air dose due to noble gases released in gaseous effluents to areas

at and beyond the Site Boundary (see Figure 2-1) shall be limited to

the following:

a. During any calendar quarter: Less than or equal to 5 mrads for

gamma radiation and less than or equal to 10 mrads for beta

radiation, and

b. During any calendar year: Less than or equal to 10 mrads for

gamma radiation and less than or equal to 20 mrads for beta

radiation.

2. Action

With the calculated air dose from radioactive noble gases in gaseous

effluents exceeding any of the above limits, prepare and submit to the

NRC within 30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for noble gases shall be determined in

accordance with the methodology and parameters in the ODCM at

least once per 31 days.
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OFFSITE DOSE CALCULATION MANUAL Appendix A

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This requirement is provided to implement the requirements of

Sections ll.B, llI.A, and IV.A of Appendix I, IOCFR Part 50. The

limiting Condition for Operation implements the guides set forth in

Section Il.B of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in gaseous effluents to Unrestricted Areas will be

kept “as low as is reasonably achievable.” The Surveillance

Requirements implement the requirements in Section lll.A of

Appendix I that conformance with the guides of Appendix I be shown

by calculational procedures based on models and data such that the

actual exposure of a Member of the Public through appropriate

pathways is unlikely to be substantially underestimated. The dose

calculation methodology and parameters established in the ODCM for

calculating the doses due to the actual release rates of radioactive

noble gases in gaseous effluents are consistent with the methodology

provided in Regulatory Guide 1.109, “Calculation of Annual Doses to

Man from Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with 1OCFR Part 50, Appendix I,” Revision 1,

October 1977 and Regulatory Guide 1.111, “Methods for Estimating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases from Light-Water-Cooled Reactors,” Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and

beyond the Site Boundary are based upon the historical average

atmospheric conditions.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

0. 1-131, 1-133, TRITIUM, AND PARTICULATES

Requirement

The dose to a Member of the Public from Iodine-131, Iodine-I 33,

tritium, and all radionuclides in particulate form with half-lives greater

than 8 days in gaseous effluents released, from each reactor unit, to

areas at and beyond the Site Boundary (see Figure 2-1) shall be

limited to the following:

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

to any organ, and

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

any organ.

2. Action

With the calculated dose from the release of lodine-131, Iodine-i 33,

tritium, and radionuclides in particulate form with half-lives greater than

8 days, in gaseous effluents exceeding any of the above limits, prepare

and submit to the NRC within 30 days a Special Report that identifies

the cause(s) for exceeding the limit and define(s) the corrective actions

that have been taken to reduce the releases and the proposed

corrective actions to be taken to assure that subsequent releases will

be in compliance with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for lodine-131, Iodine-i 33, tritium, and

radionuclides in particulate form with half-lives greater than 8 days

shall be determined in accordance with the methodology and

parameters in the ODCM at least once per 31 days.
PALISADES NUCLEAR PLANT ODCM

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Page 15 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This requirement is provided to implement the requirements of

Sections Il.C, lIl.A, and IV.A of Appendix I, 1OCFR Part 50. The

requirements are the guides set forth in Section ll.C of Appendix I.

The Action statements provide the required operating flexibility and at

the same time implement the guides set forth in Section IV.A of

Appendix I to assure that the releases of radioactive materials in

gaseous effluents to Unrestricted Areas will be kept “as low as is

reasonably achievable.” The ODCM calculational methods specified in

the Surveillance Requirements implement the requirements in

Section ll.A of Appendix I that conformance with the guides of

Appendix I be shown by calculational procedures based on models

and data, such that the actual exposure of a Member of the Public

through appropriate pathways is unlikely to be substantially

underestimated. The ODCM calculational methodology and

parameters for calculating the doses due to the actual release rates

of the subject materials are consistent with the methodology provided

in Regulatory Guide 1.109, “Calculation of Annual Doses to Man

From Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with 1OCFR Part 50, Appendix I,” Revision 1,

October 1977 and Regulatory Guide 1.111, “Methods for Estimating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases From Light-Water-Cooled Reactors,” Revision 1, July 1977.

These equations also provide for determining the actual doses based

upon the historical average atmospheric conditions. The release rate

requirements for lodine-131, lodine-133, tritium, and radionuclides in

particulate form with half-lives greater than 8 days are dependent upon

the existing radionuclide pathways to man, in areas at and beyond the

Site Boundary. The pathways that were examined in the development

of these calculations were: 1) individual inhalation of airborne

radionuclides, 2) deposition of radionuclides onto green leafy

vegetation with subsequent consumption by man, 3) deposition onto

grassy areas where milk animals and meat producing animals graze

with consumption of the milk and meat by man, and 4) deposition on

the ground with subsequent exposure of man.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table B-I

Radioactive Gaseous Waste Sampling and Analysis Program

Gaseous Release Type Sampling Minimum Type of 

Frequency Analysis Activity Analysis 

Frequency 

A. Waste Gas Storage Tank

P

Each Tank

P

Grab Sample Each Tank Principal Gamma Emittersb 

B. Containment PURGE

P

Each PURGE

P

Grab Sample Each PURGE Principal Gamma Emittersb 

C. Stack Gas Effluent

Continuousc Charcoal 1-131, 1-133 

Sample

W

ContinuousC Particulate Principal Gamma Emitters 1’ 

Sample

Q

ContinuousC Composite Sr-89, Sr-90, and 

Particulate Gross Alpha

Sample

Noble Gas Noble Gases 

ContinuousC Monitor Gross Beta or Gamma
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Gaseous Release Type Sampling Minimum Type of 

Frequency Analysis Activity Analysis 

Frequency 

D. Condenser Evacuation

System Continuous Noble Gas Noble Gases 

Monitor

w b 

Grab

W Principal Gamma Emitters 
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NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table B-I (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-i 33, Xe-i 33m, Xe-i 35, and Xe-I 38 for

gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-i 34,

Cs-I 37, 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 III.B.1, III.C.1, and III.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 IlI.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, I) 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.
PALISADES NUCLEAR PLANT ODCM

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

E. GASEOUS WASTE TREATMENT SYSTEM

Requirement

When gaseous waste exceeds a Xe-I 33 concentration of

1 E-05 pCi/cc, the Waste Gas Decay Tank System shall be used to

reduce radioactive gaseous effluents by holding gaseous waste

collected by the system for a minimum of 15 days.

2. Action

a. If a waste gas decay tank is required to be released with less

than 15 days holdup time, the system waste gas tank contents

shall be evaluated and the waste gas decay tank with the lowest

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 lll.B, C, and D.

3. Surveillance Requirements

Not Applicable.
PALISADES NUCLEAR PLANT ODCM

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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 lI.D of Appendix Ito IOCFR5O.

It is expected that releases of radioactive materials in effluents shall be

kept at small fractions of the limits specified in 20.1302 of IOCFR2O.

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 III.B, C,

and D.

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

1. Requirement

The radioactive liquid effluent monitoring instrumentation channels

shown in Table C-i shall be operable with their alarm/trip setpoints

set to ensure that the limits of llI.G are not exceeded. The alarm/trip

setpoints of these channels shall be determined and adjusted in

accordance with the methodology and parameters in the Offsite Dose

Calculation Manual (ODCM).
PALISADES NUCLEAR PLANT ODCM

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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-i. Exert best efforts to return the instruments

to Operable status within 30 days and, if unsuccessful, explain

in the next Radioactive Effluent Release Report why the

inoperability was not corrected in a timely manner.

3. Surveillance Requirements

Each radioactive liquid effluent monitoring instrumentation channel

shall be demonstrated Operable by performance of the Channel

Check, Source Check, Channel Calibration, and Channel Functional

Test operations at the frequencies shown in Table C-2.

4. Bases

The radioactive liquid effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and

adjusted in accordance with the methodology and parameters in the

ODCM to ensure that the alarm/trip will occur prior to exceeding

10 times the limits of I OCFR Part 20. The Operability and use of this

instrumentation is consistent with the requirements of General Design

Criteria 60, 63, and 64 of Appendix A to 1 OCFR Part 50.
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Table C-I

Radioactive Liquid Effluent Monitorinq Instrumentation

Minimum

Instrument Operable Applicability Action

Channels

GROSS RADIOACTIVITY MONITORS PROVIDING

ALARM AND AUTOMATIC TERMINATION OF

RELEASE

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

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

(RIA 0707)

2. GROSS BETA OR GAMMA RADIOACTIVE

MONITORS PROVIDING ALARM BUT NOT

PROVIDING AUTOMATIC TERMINATION OF

RELEASE

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

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

Line_(RIA_5211)

3. FLOW RATE MEASUREMENT DEVICES

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

1050)

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip

Setpoints are not applicable)

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

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

c. Steam Generator Blowdown Effluent (1) For Effluent Releases 3
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Table C-I (Cont’d)

TABLE NOTATION

ACTION I - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases may continue provided that

prior to initiating a release:

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

requirements and

b. At least two technically qualified members of the Facility Staff

independently verify the release rate calculations and discharge line

valving;

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided grab samples are analyzed for radioactivity at a lower limit

of detection as specified in Table D-1 for principle gamma emitters and 1-131

at least once per 12 hours.

NOTES The Steam Generator blowdown monitor is normally used in a clean up closed

loop system instead of as an effluent monitor. The action statement only applies

when the monitor is used as an effluent monitor.

ACTION 3 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided that, at least once per 24 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.

ACTION 4 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided the flow rate is estimated at least once per 4 hours during

actual releases. Pump performance curves or tank levels may be used to

estimate flow.
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OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

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Table C-2

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirement

Channel Source Ch

Instrument . 

Check Check Cali

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND

AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line (RIA 1049)

P

P R

b. Steam Generator Blowdown Effluent Line (RIA 0707)

D

M R

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

b. Turbine Building (Floor Drains) Sumps Effluent Line (RIA 5211)

D

M R

3. FLOW RATE MEASUREMENT DEVICES (5)

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

4. TURBINE SUMP EFFLUENT COMPOSITER D(4) NA 

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

6. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER D(4) NA 
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OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

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Table C-2 (Cont’d)

TABLE NOTATION

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if in

measured levels above the alarm/trip setpoint.

(2) The Channel Functional Test shall also demonstrate that Control Room alarm annunciation occurs if eit

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 traceabl

Institute of Standards and Technology or using standards that have been obtained from suppliers t

measurement assurance activities with NIST. These standards shall permit calibrating the system 

range of energy and measurement range.

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

(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check sh

least once per 24 hours on days on which continuous or batch releases are made.

(5) Turbine Sump Discharge Flow Meter FQI-5210 was calibrated at factory and doesn’t require recalibratio

TABLE FREQUENCY NOTATION

D At least once per 24 hours

Q At least once per 92 days

M At least once per 31 days

R At least once per 18 months

P Prior to radioactive batch release

W At least once per week
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G. LIQUID EFFLUENTS CONCENTRATION

Requirement

The concentration of radioactive material released in liquid effluents to

Unrestricted Areas shall be limited to 10 times the concentrations

specified in IOCFR Part 20, Appendix B, Table 2, Column 2 for

radionuclides other than dissolved or entrained noble gases. For

dissolved or entrained noble gases, the concentration shall be limited

to 2 x 1 0 microcuries/mI total activity.

2. Action

With the concentration of radioactive material released in liquid

effluents to Unrestricted Areas exceeding the above limits, without

delay, restore the concentration to within the above limits.

3. Surveillance Requirements

a. Radioactive liquid wastes shall be sampled and analyzed

according to the sampling and analysis program of Table D-1.

b. The results of the radioactivity analysis shall be used in

accordance with the methodology and parameters in the ODCM

to assure that the concentrations at the point of release are

maintained within the limits of G.1 above.
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4. Bases

This requirement is provided to ensure that the concentration of

radioactive materials released in liquid waste effluents to Unrestricted

Areas will be less than 10 times the concentration levels specified in

1OCFR Part 20, Appendix B, Table 2, Column 2. This limitation

provides additional assurance that the levels of radioactive materials in

bodies of water in Unrestricted Areas will result in exposures within the

Section ll.A design objectives of Appendix I, IOCFR Part 50, to a

Member of the Public. The concentration limit for dissolved or

entrained noble gases is based upon the assumption that Xe-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).
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Table 0-1

Radioactive Liquid Waste Sampling and Analysis Program

Frequency Notation

P Prior to batch release

M Calendar month

Q Calendar quarter

W Calendar week

‘ Liquid Release Type Sampling Minimum Analysis Type of Activity Analysis 

Frequency Frequency 

A. Batch Waste Release Tanksb

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 

B. Continuous Releasese Continuous t

W Principal Gamma Emittersc 

(Turbine Sump, Steam Generator Composite t 1-131 

Blowdown, and Service Water)

M

M Dissolved and Entrained Gases

Grab Sample (Gamma Emitters) 

Continuous t

M H-3 

Composite t Gross Alpha 

Continuous t

Q Sr-89, Sr-90 

Composite t
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Table D-1 (Cont’d)

TABLE NOTATION

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

b A batch release is the discharge of liquid wastes of a discrete volume. Prior to

sampling for analyses, each batch shall be isolated and then thoroughly mixed to

assure representative sampling.

c The principal gamma emitters for which the LLD specification applies exclusively are

the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-i 34,

Cs-I 37, Ce-141, and CeI44*. 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.
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H. LIQUID EFFLUENT DOSE

Requirement

The dose or dose commitment to a Member of the Public from

radioactive materials in liquid effluents released from each reactor unit

to Unrestricted Areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems

to the total body and to less than or equal to 5 mrems to any

organ, and

b. During any calendar year to less than or equal to 3 mrems to

the total body and to less than or equal to 10 mrems to any

organ.

2. Action

With the calculated dose from the release of radioactive materials in

liquid effluents exceeding any of the above limits, prepare and submit

to the NRC within 30 days a Special Report that identifies the cause(s)

for exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits. This Special Report shall also include the results

of radiological analyses of the drinking water source.

3. Surveillance Requirements

Cumulative dose contributions from liquid effluents for the current

calendar quarter and the current calendar year shall be determined in

accordance with the methodology and parameters in the ODCM at

least once every 31 days.
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4. Bases

This requirement is provided to implement the requirements of

Sections lI.A, III.A, and IV.A of Appendix I, IOCFR Part 50. The

Limiting Condition for Operation implements the guides set forth in

Section Il.A of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in liquid effluents to Unrestricted Areas will be kept

“as low as is reasonably achievable.” Also, for freshwater sites with

drinking water supplies that can be potentially affected by Plant

operations, there is reasonable assurance that the operation of the

facility will not result in radionuclide concentrations in the finished

drinking water that are in excess of the requirements of 4OCFR

Part 141. The dose calculation methodology and parameters in the

ODCM implement the requirements in Section lll.A of Appendix I that

conformance with the guides of Appendix I be shown by calculational

procedures based on models and data, such that the actual exposure

of a Member of the Public through appropriate pathways is unlikely

to be substantially underestimated. The equations specified in the

ODCM for calculating the doses due to the actual release rates of

radioactive materials in liquid effluents are consistent with the

methodology provided in Regulatory Guide 1.109, “Calculation of

Annual Doses to Man From Routine Releases of Reactor Effluents

for the Purpose of Evaluating Compliance with I 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.
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TOTAL DOSE

Requirement

The annual (calendar year) dose or dose commitment to any Member

of the Public due to releases of radioactivity and to radiation from

uranium fuel cycle sources shall be limited to less than or equal to

25 mrems to the total body or any organ, except the thyroid, which

shall be limited to less than or equal to 75 mrems.

2. Action

With the calculated doses from the release of radioactive materials in

liquid or gaseous effluents exceeding twice the limits of lll.C.1 .a,

lII.C.1.b, III.D.1.a, lIl.D.1.b, Ill.H.1.a, or III.H.1.b, calculations should be

made including direct radiation contributions from the reactor units and

from outside storage tanks to determine whether the above limits of

111.1.1 have been exceeded. If such is the case, prepare and submit to

the NRC within 30 days a Special Report that defines the corrective

action to be taken to reduce subsequent releases to prevent

recurrence of exceeding the above limits and includes the schedule for

achieving conformance with the above limits. This Special Report, as

defined in IOCFR 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

4OCFR Part 190 has not already been corrected, the Special Report

shall include a request for a variance in accordance with the provisions

of 4OCFR Part 190. Submittal of the report is considered a timely

request and a variance is granted until staff action on the request is

complete.
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3. Surveillance Requirements

a. Cumulative dose contributions from liquid and gaseous effluents

shall be determined in accordance with lll.C.1, lll.D.1, and

lll.H.1 and in accordance with the methodology and parameters

in the ODCM.

b. Cumulative dose contributions from direct radiation from the

reactor units and from radwaste storage tanks shall be

determined in accordance with the methodology and

parameters in the ODCM. This requirement is applicable only

under conditions set forth in Action 1.2 above.
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4. Bases

This requirement is provided to meet the dose limitations of

4OCFR Part 190 that have been incorporated into 1OCFR Part 20 by

46 FR 18525. It also requires the preparation and submittal of a

Special Report whenever the calculated doses from Plant generated

radioactive effluents and direct radiation exceed 25 mrems to the total

body or any organ, except for thyroid, which shall be limited to less

than or equal to 75 mrems. For sites containing up to 4 reactors, it is

highly unlikely that the resultant dose to a Member of the Public will

exceed the dose limits of 4OCFR Part 190 if the individual reactors

remain within twice the dose design objectives of Appendix I and if

direct radiation doses from the reactor units and outside storage tanks

are kept small. The Special Report will describe a course of action that

should result in the limitation of the annual dose to a Member of the

Public to within the 4OCFR Part 190 limits. For the purposes of the

Special Report, it may be assumed that the dose commitment to the

Member of the Public from other uranium fuel cycle sources is

negligible, with the exception that dose contributions from other

nuclear fuel cycle facilities at the same site or within a radius of 8 km

must be considered. If the dose to any Member of the Public is

estimated to exceed the requirements of 4OCFR Part 190, the Special

Report with a request for a variance (provided the release conditions

resulting in violation of 4OCFR Part 190 have not already been

corrected), in accordance with the provisions of 4OCFR Part 190.11

and IOCFR Part 20.2203, is considered to be a timely request and

fulfills the requirements of 4OCFR Part 190 until NRC staff action is

completed. The variance only relates to the limits of 4OCFR Part 190

and does not apply in any way to the other requirements for dose

limitation of 1OCFR 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.
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J. RADIOLOGICAL ENVIRONMENTAL MONITORING

Requirement

The radiological environmental monitoring program shall be conducted

as specified in Table E-1.

2. Action

a. With the radiological environmental monitoring program not

being conducted as specified in Table E-1, prepare and submit

to the NRC, in the Annual Radiological Environmental Operating

Report a description of the reasons for not conducting the

program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of Plant effluents in

an environmental sampling medium at a specified location

exceeding the reporting levels of Table E-2 when averaged over

any calendar quarter, prepare and submit to the NRC within

30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions to be

taken to reduce radioactive effluents. When more than one of

the radionuclides in Table E-2 are detected in the sampling

medium, this report shall be submitted if:

Concentration (1) + Concentration (2) + ....> 1 .0

Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table E-2 are detected

and are the result of Plant effluents, this report shall be

submitted if the potential annual dose to a Member of the Public

is equal to or greater than the calendar year limits of lll.C.1,

lll.D.1, and lll.H.1. This report is not required if the measured

level of radioactivity was not the result of Plant effluents;

however, in such an event, the condition shall be reported and

described in the Annual Radiological Environmental Operating

Report.
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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 ft2)

producing broad leaf vegetation.

c. The land use census shall be conducted during the growing

season at least once per 12 months using that information that

will provide the best results, such as by a door-to-door survey,

aerial survey, or by consulting local agriculture authorities. The

results of the land use census shall be included in the Annual

Radiological Environmental Operating Report and shall be

included in a revision of the ODCM for use in the following

calendar year.

d. Analyses shall be performed on radioactive materials supplied

as part of an Interlaboratory Comparison Program that has been

approved by the NRC.
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e. A summary of the results obtained as part of the above required

Interlaboratory Comparison Program shall be included in the

Annual Radiological Environmental Operating Report.

f. The environmental air samplers shall be operationally checked

monthly and airflow verified annually.

4. Bases

a. Monitoring Program

The radiological environmental monitoring program provides

representative measurements of radiation and of radioactive

materials in those exposure pathways and for those

radionuclides that lead to the highest potential radiation

exposures of Members of the Public resulting from the station

operation. This monitoring program implements Section lV.B.2

of Appendix I to I 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).
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b. Land Use Census:

This requirement is provided to ensure that changes in the use

of areas at and beyond the site boundary are identified and that

modifications to the radiological environmental monitoring

program are made if required by results of this census. The

best information from the door-to-door survey, from aerial

survey or from consulting with local agricultural authorities shall

be used. This census satisfies the requirements of

Section IV.B.3 of Appendix Ito 1OCFR 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 kglm 2.

c. I nterlaboratory 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 lV.B.2 of Appendix I

to IOCFR Part 50.
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__

Table E-1

Radiological Environmental Monitoring Program

Exposure Pathway Number of Representative Sampling and Type an

andlor Sample Samples and Sample Locationsa Collection Frequency of 

1. DIRECT RADIATIONb 21 routine monitoring stations either with two or Quarterly Gamma 

more dosimeters or with one instrument for

measuring and recording dose rate continuously,

placed as follows:

An inner ring of stations, one in each overland

meteorological sector (9) in the general area of

the Site Boundary.

An outer ring of stations, one in each overland

meteorological sector (9) within the 12 km range

from the site.

The balance of the stations (3) to be placed to

serve as control stations.
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Exposure Pathway Number of Representative Sampling and Type an

and/or Sample Samples and Sample Locationsa Collection Frequency of 

2. AIRBORNE

Radioiodine and Samples from 5 locations. Continuous sample Radioiodine 

Particulates operation with sample 1-131 analy

3 samples from within 6 km of the Site Boundary collection weekly or more each filter c

in different sectors (2.4 km-SSW, 5.6 km-ESE, frequently if required by and 1.6 km-N). dust loading. Particulate 

Gross beta 

I sample from the vicinity of a community having analysis fol

the highest calculated annual average ground changed. G

level DIQ (Covert-5.6 km-SE). analysis on 

composite

I sample from a control location in the least

prevalent wind directionc (Grand Rapids

89 km-NNE) h

3. WATERBORNE

a. Lake (surface) Plant lake water inlet. Composite sample over Gamma iso

I -month period t, analyses m

b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gamma iSo

1-month perio&. beta, and tr

monthly.

1 sample from a control location (Ludington Composite sample over Gamma iso

Pumped Storage 201 km N) 1-month period t, beta, and tr

monthly.

c. Well (drinking) I grab sample per month when Palisades Park 1 grab sample per month Gamma iso

community drinking water well is in operation when operational analyses m

(Park is seasonal in operations and is only open Park is oper

for the summer months)
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL.

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Exposure Pathway Number of Representative Sampling and Type an

and!or Sample Samples and Sample Locationsa Collection Frequency of 

d. Sediment from I sample from between north boundary and Van Semiannually Gamma IsO

shoreline Buren State Park beach, approximately 1/2 mile semiannual

north of the Plant discharge.

4. INGESTION

a. Milk Samples from milking animals in 3 locations Monthly Gamma iso

between 5-8 km distance. analyses m

1 sample from milking animals at a control location, Monthly Gamma iSo15-30 km distance. analyses m

b. Broad leaf Samples of 3 different kinds of broad leaf vegetation Monthly during growing Gamma iso

vegetation grown nearest each of two different offsite locations season analyses of highest predicted annual average ground level

DIQ if milk sample is not performed. (SE or SSE

sectors near site.)

I sample of each of the similar broad leaf vegetation Monthly during growing Gamma So

grown 1 5-30 km distance in the least prevalent wind season analyses direction if milk sampling is not performed. (NNE or

NE sectors.)

c. Fish Sample 2 species of commercially and/or Sample in season or Gamma iSo

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.

d. Food Products 1 sample each of two principal fruit crops At time of harvest 9 Gamma isot

(blueberries and apples). analyses.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-1 (Cont’d)

Table Notation

a Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasona

malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipm

every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the samplin

documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or p

obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locati

the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring p

b One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in 

integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two 

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 

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 a

decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic 

performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to 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 

sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composi

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.
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table E-2

Reporting Levels for Radioactivity Concentrations in Environmental Samples

Reporting Levels

Analysis. Water Airborne Particulates Fish Milk Food 

(pCill) or Gases (pCiIm 3) (pCilkg, Wet) (pCiIl) (pC

H-3 20,000*

Mn-54 1,000 30,000

Fe-59 400 10,000

Co-58 1,000 30,000

Co-60 300 10,000

Zn-65 300 20,000

Zr-Nb-95 400

1-131

2 0.9 3 

Cs-134 30 10 1,000 60 

Cs-I 37 50 20 2,000 70 

Ba-La-140 200 300

* For drinking water samples. This is 4OCFR Part 141 value. If no drinking water pathway exists,

a value 

be used.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

• Water Airborne Particulates Fish Milk Food Products 

Analysis (pCiII) or Gases (pCiIm 3 (pCilkg, Wet) (pCiII) (pCi/kg, Wet) 

Gross Beta

4 0.01

H-3 2,000*

Mn-54 15 130

Fe-59 30 260

Co-58 15 130

Co-60 15 130

Zn-65 30 260

Zr-95 30

Nb-95 15

1-131 0.07 1 60

Cs-134 15 0.05 130 15 60 

Cs-137 18 0.06 150 18 80 

Ba-140 60 60

La-140 15 15

Table E-3

Detection Capabilities for Environmental Sample Analysisa

Lower Limit of Detection (LLD)bC
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

* If no drinking water pathway exists,

a value of 3,000 pCi/I may be used.

Table E-3 (Cont’d)

TABLE NOTATION

a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the a

be analyzed and reported in the Annual Radiological Environmental Operating Report.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory G

C The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system backg

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:

LLDr 4.66xsb

E x V x 2.22 x Y x Exp(—2At)

Where:

LLD is the ‘a priori” lower limit of detection as defined above, as picocuries per unit mass or volume.

sis the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per 

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.

tfor environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of cou
PALISADES NUCLEAR PLANT 

OFFSITE DOSE CALCULATION MANUAL 

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Typical values of E, V, Y, and tt should be used in the calculation.

Table E-3 (Cont’d)

Table Notation

It should be recognized that the LLD is defined as an a priori” (before the fact) limit representing the capability of a measurement system 

‘a posteriori” (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will b

conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontr

render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Env

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)

ODCM

Appendix A

Revision 17

Page 47 of 60

RADIOLOGICAL

Table E-4

ENVIRONMENTAL MONITORING PROGRAM LOCATIONS

WNW

w

wsW

NW

Seven Mile Map

N

I

SW
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

ODCM

Appendix A

Revision 17

Page 48 of 60

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS

Four Mile Map
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

ODCM

Appendix A

Revision 17

Page 49 of 60

TLDs

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS

Location Coordinates Distance (miles) Degrees Sector

Stack N42 1923.5

W86 1851.6

1 N 42 19 20.7 0.507 96.09 E

W 86 18 36.1

Inner Ring

13 N 42 19 47.2 0.518 28.62 NNE

W 86 18 34.1

8 N42 1946.8 0.594 41.21 NE

W 86 18 24.0

14 N42 1941.1 0.548 51.93 NE

W86 1821.2

15 N42 1942.3 0.838 64.94 ENE

W86 1758.1

16 N 42 19 28.0 0.814 83.9 E

W 86 17 54.6

17 N 42 19 10.5 0.590 114.98 ESE

W 86 18 13.9

18 N 42 19 4.2 0.491 138.96 SE

W 86 18 28.9

19 N 42 19 0.9 0.465 158.69 SSE

W 86 18 39.7

20 N42 191.1 0.432 174.42 S

W 86 18 48.8

21 N42 193.4 0.397 194.02 SSW

W 86 18 58.4

Outer Ring -Displayed on 7 mile map

7 N422240.8 4.102 22.6 NNE

W 86 17 0.4

6 N4222 30.6 5.309 47.42 NE

W 86 14 15.9

23 N 42 20 44.7 3.191 60.75 ENE

W 86 15 35.3

24 N42 1959.4 6.029 83.4 E

W 8611 49.4

5 N 42 18 27.6 3.491 107.87 ESE

W 86 14 57.5

4 N42 17 10.8 3.690 133.63 SE

W86 1543.5

3 N42 1438.0 5.704 163.82 SSE

W 86 16 59.7
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

ODCM

Appendix A

Revision 17

Page 50 of 60

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM LOCATIONS

TLDs

Location Coordinates Distance (miles) Degrees Sector

2 N42 1433.4 5.578 183.62 S

W 86 19 16.4

9 N42 181.6 1.686 201.22 SSW

W 86 19 34.6

Control TLDs

10 N 42 53 16.5 50.727 39.51 NE

W 8540 36.1

11 N42 1524.4 39.749 96.42 E

W 85 32 49.4

12 N 41 56 54.3 27.989 157.61 SSE

W 86 6 24.5

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 ot 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 58399 Wilbur Road, Dowagiac, Mi.

Air SamDle Stations

Location Coordinates Distance (miles) Degrees Sector

A8 (State Park) N 42 19 46.8 0.587 40.38 NE

W 86 18 24.8

A9 (Township N 42 18 4.6 1.539 190.40 S

Park) W861911.2

A4(Covert) N4217 12.1 3.903 130.22 SE

W86 1521.7

A5(Rood) N42 1830.5 5.804 106.36 ESE

W 86 14 47.8

AlO (Grand N4253 16.5 50.727 39.51 NE

Rapids) W 85 40 36.1

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 obtained from the Consumers Energy Pump Storage

Facility located in Ludington, Mi
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 51 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

K. SIRW OR TEMPORARY LIQUID STORAGE TANK

Requirement

The concentration of radioactive material (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

IOCFR Part 20, Appendix B, Table 2, Column 2.

+ = <1000

ECa ECb EC1

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.

or

A calculational methodology performed prior to the material being

transferred may be used to show compliance with the requirement of

this section if a representative sample cannot be obtained at least once

per seven days. A representative sample of the radioactive material to

be added to the SIRW or Temporary Liquid Storage Tank shall be

analyzed and a calculation performed to show compliance with the

1000 EC limit.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 52 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

4. Bases

This requirement will provide reasonable assurance that in the event

of an uncontrolled release of the tanks’ contents, the resulting

concentrations would be less than the limits of 100FR 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

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 ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 53 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

3. Surveillance Requirements

The applicable surveillance interval frequencies are specified in

Tables A-2 and C-2. The applicable sampling and/or analysis

frequencies are specified in Tables A-i, B-I, C-I, D-1, and E-I.

Extendable surveillance requirements are limited to Channel Checks,

Source Checks, Channel Calibrations, Channel Functional Checks,

sampling frequencies and/or analysis frequencies.

4. Bases

The maximum allowable extension for a surveillance interval is

consistent with the surveillance requirements specified in the Technical

Specifications, Section 4.0. Until relocated in the ODCM, all of the

effluent surveillances were subject to these same requirements.

M. SEALED SOURCE CONTAMINATION

1. Requirement

Each sealed source containing radioactive material either in excess

of 100 microcuries of beta and/or gamma emitting material or

5 microcuries of alpha emitting material shall be free of greater than

or equal to 0.005 microcuries of removable contamination.

2. Action

a. With a sealed source having removable contamination in excess

of 0.005 microcuries, immediately withdraw the sealed source

from use and either:

(1) Decontaminate and repair the sealed source, or

(2) Dispose of the sealed source in accordance with

applicable regulations.

b. A report shall be prepared and submitted to the Commission on

an annual basis if sealed source leakage tests reveal the

presence of greater than or equal to 0.005 microcuries of

removable contamination.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 54 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

3. Surveillance Requirements

a. Each category of sealed sources as described in the

requirement with a half-life greater than 30 days (excluding

Hydrogen-3), and in any other form than gas, shall be tested for

leakage and/or contamination at intervals not to exceed

6 months.

b. The test shall be performed by the licensee or by other persons

specifically authorized by the Commission or an Agreement

State. The test method shall have a detection sensitivity of at

least 0.005 microcuries per test sample.

c. The test sample shall be taken from the sealed source or, in the

case of permanently mounted sources, from the surfaces of the

mounting device on which contamination would be expected to

accumulate.

d. The periodic leak test does not apply to sealed sources that are

stored and not being used. These sources shall be tested prior

to use or transfer to another licensee, unless tested within the

previous 6 months. Sealed sources which are continuously

enclosed within a shielded mechanism (ie, sealed sources

within radiation monitoring or boron measuring devices) are

considered to be stored and need not be tested unless they are

removed from the shielded mechanism.

e. Sealed sources transferred without a certificate indicating the

last test date shall be tested prior to being placed in use.

4. Bases

The requirement, actions, and surveillance requirements are the same

as contained in the Technical Specifications 6.21 prior to relocation to

the ODCM and will provide assurance that sealed sources are tested

to demonstrate that source integrity is being maintained.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 55 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

IV. REPORTING REQUIREMENTS

A. RADIOLOGICAL EFFLUENT RELEASE REPORT

The Radioactive Effluent Release Report (RERR) shall be submitted in

accordance with I 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, RI, 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 radionuctides in each category

• Disposition of waste shipments and irradiated fuel shipments (identify

number of shipments mode of transport and destination)
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 56 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Radiological Environmental Operating Report covering the operation of

the unit during the previous calendar year shall be submitted prior to May 15

of each year. The report shall include summaries, interpretations, and

analysis of trends of the results of the Radiological Environmental Monitoring

Program for the reporting period. The material provided shall be consistent

with the objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, lV.B.3,

and IV.C of Appendix Ito IOCFR5O.

The Annual Radiological Environmental Operating Reports shall include

summaries, interpretation and statistical evaluation of the results of the

radiological environmental surveillance activities for the report period,

including a comparison with preoperational studies, operational controls

(as appropriate), and previous environmental surveillance reports and an

assessment of the observed impacts of the Plant operation on the

environment. The reports shall also include the results of land use census

pursuant to lll.J.3.c.

The Annual Radiological Environmental Operating Reports shall include

summarized and tabulated results in the format of Table F-I of all radiological

environmental samples taken during the report period. In the event that some

results are not available for inclusion with the report, the report shall be

submitted noting and explaining the reasons for the missing results. The

missing data shall be submitted as soon as possible in a supplementary

report.

The reports shall also include the following; a summary description of the

radiological environmental monitoring program, including sampling methods

for each sample type, a map of all sampling locations keyed to a table giving

distances and directions from the reactor and the results of land use census

required by lll.J.3.c and results of the Interlaboratory Comparison Program

required by III.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 lll.J, or 2) an unusual or important event occurs from

Plant operation that causes a significant environmental impact or affects a

potential environmental impact. Reports shall be submitted within 30 days.
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table F-I

Environmental Radiological Monitoring Program Summary

O

A

R

P

Name of Facility

Location of Facility(County, State’

Docket No

Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is i

Reporting Period

Medium TypelTotal Lower Limit All Indicator or Pathway Number of of Locations Name Mean (b Control Lo

Sampled

(Unit of Measure) Analyses Detectiona Mean (f)b Distance

& Direction Rangeb Mean

Performed (LLD) Rangeb Rang

Air Particulates Gross (, 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/

(pCi/m 3) (200/312) 5 miles 3400 (0.08-2.0) (0.05-1

v-Spec 32 (0.05-2.0)

Cs-i 37 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LL

(0.03-0.13) 2.5 miles 160° (0.03-0.13)

Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (

(0.01-0.08) 4 miles 270° (0.0 1-0.08)

Sr-89 40 0.002 <LLD --

— <LL

Sr-90 40 0.0003 <LLD --

-- <LLD 

Fish v-Spec 8

pCi/kg (dry weight) <LCD

Cs-137 80

— <LLD 90(1/

<LLD

Cs-134 80

— <LLD <LLD 

120 (3/4)

Co-60 80 (90-200) River Mile 35 See <LLD 

Podunk River Column 4

a

b

Nominal Lower Limit of Detection (LLD) as defined in table notation c of Table E-3.

NOTE: The example data are provided for illustrative purposes only.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 58 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS

A. LICENSEE MODIFICATIONS

Licensee initiated major modifications to the radioactive liquid and gaseous

waste systems.

1. Shall be reported to the NRC pursuant to 100FR 50.59. The

discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that

the modification could be made in accordance with

IOCFR Part 50.59.

b. A description of the equipment, components and processes

involved, and the interfaces with other Plant systems.

c. Documentation of the fact that the modification was reviewed

and found acceptable by the PRO.

2. Shall become effective upon review and acceptance by the General

Manager Plant Operations.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 59 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION

1. Purpose:

The purpose of this definition is to assure that this requirement will be

satisfied under clearly identifiable circumstances, and with the

objective that current radwaste system capabilities are not jeopardized.

2. Definition:

A major radwaste system modification is a modification which would

remove (either by bypassing for greater than 7 days or physical

removal) or replace with less efficient equipment, any components of

the radwaste system:

a. Letdown filters or demineralizers.

b. Vacuum degassifier (not applicable when the reactor is in cold

shutdown and depressurized).

c. Miscellaneous or clean waste evaporators.

d. The present waste gas compressor/decay tank system.

e. Fuel Pool filters/demineralizers.

f. Radwaste polishing demineralizers.

g. Radwaste Solidification system.

Improvements or additions to improve efficiency will not be

considered major modifications unless a complete substitution

of equipment or systems is made with equipment of unrelated

design. Examples would be: 1) replacement of mechanical

degassifier with steam, jet degassifier, 2) replacement of waste

gas system with cryogenic system, 3) replacement of asphalt

solidification with cement system, and 4) change from deep

bead resins to Powdex, etc.
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 17

Page 60 of 60

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

VI. ONSITE GROUND WATER MONITORING

Palisades installed 5 ground water monitoring wells in 2007 and added an additional

9 wells in 2008. These wells were installed in response to NEI 07-07, Industry

Ground Water Protection Initiative — Final Guidance Document. These wells are

strategically placed within the Owner Controlled Area, both inside and outside the

Protected Area to allow detection of radioactive contamination of ground water due

to leaks or spills from plant systems.
ENCLOSURE 2

PALISADES NUCLEAR PLANT

JOINT FREQUENCY TABLES -MET DATA

32 Pages Follow
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/11 -3/31/11

Stability Class: A

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 2 3 1 6

NNE 2 3 5

NE 6 1 7

ENE 3 1 4

E 2 2

ESE 2 1 3

SE 2 2 4

SSE 5 6 11

S 2 3 5

SSW 3 2 1 6

SW 2 8 10

WSW 6 3 9

W 2 2

WNW 3 5 8

NW 6 15 21

NNW 1 35 9 45

Total 45 89 13 1 148

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/11 -3/31/11

Stability Class: B

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 2 1 3

NNE 1 2 2 5

NE 1 1 2

ENE 1 1 2

E 0

ESE 1 1 2

SE 4 4

SSE 2 1 2 5

S 1 1 2

SSW 0

SW 2 4 6

WSW 8 2 1 11

W 1 1

WNW 3 2 5

NW 6 6

NNW 1 14 5 20

Total 1 22 41 10 74

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/11 - 3/31/11

Stability Class: C

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 3 8 3 14

NNE 1 1

NE 1 2 3

ENE 1 1

E 1 3 1 5

ESE 1 3 1 5

SE 2 6 1 3 12

SSE 3 6 2 11

S 7 7

SSW 2 3 5

SW 5 3 3 11

WSW 2 4 1 7

W 2 3 1 6

WNW 3 2 5

NW 5 5 10

NNW 5 6 11

Total 42 53 15 4 114

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/11 -3/31/11

Stability Class: D

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 5 38 73 9 125

NNE 3 22 24 49

NE 2 21 17 5 1 46

ENE 4 13 26 10 4 57

E 6 8 20 4 38

ESE 2 8 25 18 6 59

SE 5 18 37 37 4 101

SSE 7 52 28 29 116

S 14 58 16 88

SSW 6 25 6 37

SW 26 38 5 69

WSW 10 35 13 58

W 1 20 67 21 109

WNW 4 22 61 10 97

NW 6 26 66 37 135

NNW 1 24 35 43 103

Total -- 66 391 574 241 15 1287

Periods of Calm (hours): 2

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/1 1 - 3/31/11

Stability Class: E

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 12 2 15

NNE 1 27 28

NE 1 28 29

ENE 2 28 15 45

E 4 7 4 15

ESE 1 6 9 16

SE 5 5 23 4 37

SSE 5 22 13 1 41

5 3 24 19 46

SSW 2 13 10 1 26

SW 7 10 6 23

WSW 2 7 5 14

W 2 6 6 6 1 21

WNW 3 6 7 1 17

NW 2 2 4 8

NNW 2 10 1 13

Total 34 205 130 24 1 394

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/1 1 - 3/31/11

Stability Class: F

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 1 2

NNE 1 4 5

NE 5 5

ENE 6 1 7

E 1 7 8

ESE 1 4 2 7

SE 2 7 2 11

SSE 20 20

5 7 7

SSW 0

SW 0

WSW 1 1

W 2 1 3

WNW 5 5

NW 2 2

NNW 1 1

Total 6 64 12 2 84

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 1/1/11 - 3/31/1 1

Stability Class: G

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 0

NNE 0

NE 2 2

ENE 2 2

E 2 2

ESE 0

SE 0

SSE 6 6

5 4 1 5

SSW 0

SW 0

WSW 0

W 0

WNW 0

NW 0

NNW 1 1

Total 17 1 18

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Periodof Record: 1/1/11 -3/31/11

Stability Class: All

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 7 56 88 14 165

NNE 6 57 30 93

NE 3 64 21 5 1 94

ENE 6 54 44 10 4 118

E 11 27 27 5 70

ESE 4 19 37 24 8 92

SE 12 34 74 42 7 169

SSE 12 110 54 34 210

S 17 103 40 160

SSW 8 43 21 2 74

SW 42 63 14 119

WSW 28 51 21 100

W 3 30 79 29 1 142

WNW 7 37 82 11 137

NW 8 39 98 37 182

NNW 3 43 91 57 194

Total 107 786 900 305 21 2119

Periods of Calm (hours): 2

Variable direction: 0

Hours of Missing Data: 39

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 - 6/30/11

Stability Class: A

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 1

NNE 1 1 1 3

NE 3 8 2 13

ENE 1 3 4

E 1 2 3 1 7

ESE 1 2 3 6

SE 5 8 7 2 22

SSE 7 6 1 14

S 6 10 1 17

SSW 1 2 3

SW 10 15 1 26

WSW 7 13 20

W 2 22 2 1 27

WNW 4 29 9 42

NW 4 20 12 36

NNW 20 29 5 54

Total 14 135 125 19 2 295

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 3
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 -6/30/11

Stability Class: B

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 1 2

NNE 1 1

NE 3 2 5

ENE 2 1 3

E 3 2 5

ESE 3 5 3 11

SE 1 5 5 1 12

SSE 1 5 2 8

S 1 1 2

SSW 1 1 2

SW 5 4 1 10

WSW 2 3 5

W 6 4 1 11

WNW 2 4 6 12

NW 6 1 7

NNW 1 5 9 15

Total 3 44 51 12 1 111

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 3
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 - 6/30/11

Stability Class: C

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 2 3

NNE 2 2 4

NE 2 3 5

ENE 1 2 3

E 1 2 3

ESE 1 10 3 14

SE 2 4 6 1 13

SSE 2 3 1 2 8

S 2 1 3

SSW 2 2

SW 3 8 11

WSW 2 10 12

W 1 4 3 2 10

WNW 4 4 2 10

NW 2 5 7

NNW 6 6 12

Total 7 38 60 9 6 120

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 3
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 -6/30/11

Stability Class: D

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 5 21 10 36

NNE 1 10 11 22

NE 2 15 20 37

ENE 2 12 15 3 32

E 1 24 26 15 1 67

ESE 3 8 39 45 16 111

SE 2 17 44 51 8 122

SSE 3 21 17 7 1 49

5 3 10 8 1 22

SSW 14 2 2 18

SW 1 24 32 4 61

WSW 6 9 16 31

W 8 47 15 14 84

WNW 10 25 11 1 47

NW 5 18 16 2 41

NNW 3 32 23 2 60

Total 55 307 305 147 26 840

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 3
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 - 6/30/11

Stability Class: E

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 5 22 5 2 34

NNE 3 16 19

NE 1 15 2 18

ENE 3 12 1 16

E 1 10 4 15

ESE 2 11 16 2 31

SE 3 27 28 2 60

SSE 1 25 24 7 57

S 2 27 4 33

SSW 3 20 2 1 26

SW 3 8 20 3 34

WSW 6 11 16 33

W 5 10 9 24

WNW 7 10 5 22

NW 5 7 3 15

NNW 10 22 4 2 38

Total 60 253 143 19 475

Periods of Calm (hours): 5

Variable direction: 0

Hours of Missing Data: 3
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 - 6/30/11

Stability Class: F

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 2 6 1 9

NNE 6 6

NE 3 11 14

ENE 2 6 1 9

E 1 6 7

ESE 6 14 1 21

SE 3 19 1 23

SSE 1 7 3 11

S 2 11 1 14

SSW 4 3 7

SW 3 2 1 6

WSW 2 2

W 2 2 3 7

WNW 7 6 13

NW 4 5 1 10

NNW 6 8 14

Total 46 112 14 1 173

Periods of Calm (hours): 1

Variable direction: 0

Hours of Missing Data: 3
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 -6/30/11

Stability Class: G

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 6 7

NNE 3 3 6

NE 3 3 6

ENE 5 5

E 5 13 18

ESE 1 15 16

SE 2 19 2 23

SSE 6 15 1 22

S 3 17 20

SSW 2 4 1 7

SW 0

WSW 1 1

W 4 1 5

WNW 5 1 6

NW 9 1 10

NNW 7 1 8

Total 52 104 4 160

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 3
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 4/1/11 - 6/30/11

Stability Class: All

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 13 57 20 2 92

NNE 8 38 15 61

NE 9 52 35 2 98

ENE 8 38 23 3 72

E 9 59 37 16 1 122

ESE 13 54 74 50 19 210

SE 10 90 92 71 12 275

SSE 11 78 59 18 3 169

S 10 74 24 3 111

SSW 9 43 10 3 65

SW 7 52 80 9 148

WSW 13 31 60 104

W 22 92 36 18 168

WNW 39 79 33 1 152

NW 29 62 33 2 126

NNW 27 94 71 9 201

Total 237 993 703 207 35 2175

Periods of Calm (hours): 6

Variable direction: 0

Hours of Missing Data: 3
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 - 9/30/11

Stability Class: A

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 4 5 10

NNE 1 1 2

NE 6 6

ENE 5 5

E 1 1

ESE 2 2 2 6

SE 1 5 4 10

SSE 1 8 4 13

5 3 1 4

SSW 1 1 2

SW 5 2 7

WSW 7 1 8

W 3 9 12

WNW 1 21 1 23

NW 4 40 3 2 49

NNW 1 29 48 1 79

Total 17 146 70 2 2 237

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 -9/30/11

Stability Class: B

Elevation: Speed: SP1OM Direction: DR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 6 7

NNE 0

NE 4 4

ENE 3 3

E 1 1

ESE 1 3 1 5

SE 1 2 2 5

SSE 1 4 2 1 8

S 1 1

SSW 2 2

SW 3 5 2 10

WSW 1 9 1 11

W 2 3 1 6

WNW 6 6

NW 16 1 17

NNW 1 7 14 22

Total 10 62 32 4 108

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 - 9/30/11

Stability Class: C

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 2 4 7

NNE 4 1 1 6

NE 2 2 4

ENE 2 2 4

E 4 4

ESE 1 2 3 1 7

SE 1 3 6 10

SSE 1 1 4 1 7

S 2 1 3

SSW 2 1 3

SW 1 8 7 16

WSW 2 6 1 9

W 4 6 1 11

WNW 2 8 1 11

NW 5 11 1 17

NNW 2 12 6 1 1 22

Total 30 71 35 3 2 141

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 - 9/30/11

Stability Class: D

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 8 18 10 3 39

NNE 5 10 1 16

NE 3 5 8

ENE 1 8 9

E 1 7 2 10

ESE 5 16 5 3 29

SE 1 8 21 2 32

SSE 3 16 9 28

S 1 4 2 7

SSW 6 13 19

SW 9 38 19 66

WSW 7 20 5 32

W 10 19 3 1 33

WNW 14 13 27

NW 18 35 10 1 64

NNW 11 34 26 4 9 2 86

Total 103 264 113 13 10 2 505

Periods of Calm (hours): 1

Variable direction: 0

Hours of Missing Data: 0
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 - 9/30/11

Stability Class: E

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 10 43 10 1 64

NNE 2 23 3 28

NE 8 16 24

ENE 7 11 1 19

E 6 8 14

ESE 6 24 13 43

SE 2 26 17 1 46

SSE 8 38 9 55

S 8 21 29

SSW 10 11 1 22

SW 11 33 23 67

WSW 6 21 2 29

W 4 17 3 1 25

WNW 18 16 4 38

NW 17 15 5 37

NNW 17 42 17 76

Total 140 365 108 3 616

Periods of Calm (hours): 2

Variable direction: 0

Hours of Missing Data: 0
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 -9/30/11

Stability Class: F

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 7 12 19

NNE 6 9 15

NE 8 11 19

ENE 14 14 28

E 5 9 14

ESE 5 15 6 26

SE 8 26 8 42

SSE 10 32 2 44

5 19 21 40

SSW 9 16 25

SW 6 7 13

WSW 2 2

W 9 9

WNW 4 4 1 9

NW 2 2

NNW 10 6 16

Total 124 182 17 323

Periods of Calm (hours): 6

Variable direction: 0

Hours of Missing Data: 0
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 -9/30/11

Stability Class: G

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 3 3

NNE 1 2 3

NE 3 6 9

ENE 4 19 1 24

E 8 13 21

ESE 3 5 8

SE 9 10 1 20

SSE 10 60 70

S 6 73 79

SSW 7 13 20

SW 2 2

WSW 3 3

W 1 1

WNW 0

NW 0

NNW 4 4

Total 57 208 2 267

Periods of Calm (hours): 1

Variable direction: 0

Hours of Missing Data: 0
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 7/1/11 -9/30/11

Stability Class: All

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 27 83 35 4 149

NNE 19 46 6 71

NE 24 50 74

ENE 28 62 2 92

E 22 41 2 65

ESE 22 65 32 5 124

SE 23 78 59 5 165

SSE 34 159 30 2 225

S 34 125 4 163

SSW 35 57 1 93

SW 32 96 53 181

WSW 21 63 10 94

W 33 54 8 2 97

WNW 39 68 5 1 1 114

NW 46 117 20 3 186

NNW 42 134 111 6 10 2 305

Total 481 1298 378 25 14 2 2198

Periods of Calm (hours): 10

Variable direction: 0

Hours of Missing Data: 0
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: A

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 10 3 13

NNE 3 1 2 6

NE 0

ENE 2 2

E 1 1

ESE 0

SE 3 2 5

SSE 1 10 12 23

S 16 18 1 35

SSW 4 5 1 10

SW 2 7 9

WSW 4 4

W 2 4 9 1 16

WNW 1 8 4 3 3 19

NW 1 12 4 5 1 23

NNW 6 5 3 9 23

Total 7 80 70 19 13 189

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: B

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 3 5 2 10

NNE 1 1

NE 0

ENE 1 1

E 1 1

ESE 2 2

SE 3 3

SSE 6 4 10

S 4 4 1 9

SSW 3 1 4

SW 9 2 11

WSW 2 1 3

W 1 1 4 6

WNW 1 3 6 10

NW 4 3 7

NNW 1 1 1 3

Total 1 37 30 10 3 81

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: C

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 1 6 4 12

NNE 1 1

NE 1 1 2

ENE 1 1

E 1 1

ESE 0

SE 2 3 5

SSE 1 4 1 6

S 4 6 1 11

SSW 3 5 1 9

SW 1 9 4 14

WSW 3 3 6

W 3 2 5 1 11

WNW 2 4 5 1 12

NW 2 6 2 1 11

NNW 2 2 4

Total 9 41 46 10 106

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: D

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 23 22 10 55

NNE 2 33 31 5 71

NE 5 56 19 80

ENE 1 10 10 2 23

E 2 6 2 6 1 17

ESE 2 4 5 11

SE 4 9 23 4 40

SSE 4 43 24 20 91

5 5 46 43 5 99

SSW 4 33 41 2 80

SW 4 22 42 3 71

WSW 8 15 17 2 42

W 3 23 59 20 1 106

WNW 4 26 85 39 1 155

NW 1 29 53 22 105

NNW 1 19 16 18 10 64

Total 50 397 492 158 13 1110

Periods of Calm (hours): 3

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: E

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 7 6 14

NNE 1 5 6

NE 2 12 14

ENE 1 4 12 17

E 5 3 4 3 15

ESE 3 12 2 1 18

SE 4 14 15 4 37

SSE 5 33 40 6 84

S 3 98 13 114

SSW 4 16 5 25

SW 5 8 11 2 26

WSW 6 1 2 9

W 2 4 3 9

WNW 6 2 8

NW 4 1 1 6

NNW 3 8 4 15

Total 39 240 119 19 417

Periods of Calm (hours): 2

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: F

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 3 1 4

NNE 7 7

NE 1 2 3

ENE 1 4 5

E 0

ESE 7 3 10

SE 4 25 2 31

SSE 2 31 11 44

S 2 25 27

SSW 1 1 2

SW 1 1 2

WSW 0

W 1 1

WNW 4 4

NW 2 1 3

NNW 2 2

Total 23 105 17 145

Periods of Calm (hours): 1

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SITE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: G

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 1 1 2

NNE 2 2 4

NE 2 2

ENE 2 4 6

E 3 4 7

ESE 3 6 9

SE 18 18

SSE 4 62 66

S 1 37 38

SSW 1 1

SW 0

WSW 0

W 0

WNW 0

NW 0

NNW 1 1

Total 19 135 154

Periods of Calm (hours): 0

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
SiTE: Palisades

Hours at each Wind Speed and Direction

Period of Record: 10/1/11 - 12/31/11

Stability Class: All

Elevation: Speed: SP1OM Direction: DIR1OM Lapse:DT5OM

Wind Speed (MPH)

Wind

Direction 1-3 4-7 8-12 13-18 19-24 >24 Total

N 6 33 47 22 2 110

NNE 5 52 32 7 96

NE 10 71 20 101

ENE 5 25 23 2 55

E 10 16 6 9 1 42

ESE 8 31 10 1 50

SE 12 71 48 8 139

SSE 16 186 95 27 324

5 11 230 84 8 333

SSW 8 61 58 4 131

SW 13 56 59 5 133

WSW 8 30 22 4 64

W 11 34 77 26 1 149

WNW 12 47 102 43 4 208

NW 6 56 63 29 1 155

NNW 7 36 28 21 20 112

Total 148 1035 774 216 29 2202

Periods of Calm (hours): 6

Variable direction: 0

Hours of Missing Data: 0

Hours are not adjusted for Daylight Savings Time.
ATTACHMENT 2

BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION

2011 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 2011. 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 2011.

2011 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-6, was

transferred to Entergy Nuclear Operations, Inc.

During 2011, normal independent spent fuel 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 iodines 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

2011. 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 2011.

C. Radioactive Effluent Monitoring Instrumentation

All plant-installed liquid and gaseous radioactive effluent monitoring

instrument channels have been permanently removed and dismantled.

2. Gaseous Effluents

Although there were no gaseous effluents released during 2011, Table 1

provides a summary of all gaseous radioactive effluent monitoring conducted during

the reporting period as required by the ODCM.

Letter from the USNRC dated January 8, 2007, “Release of Land from Part 50 License for Unrestricted Use”

Page 1 of 7
3. Liquid Effluents

There were no liquid effluent batch releases during 2011. Table 2 lists and

summarizes liquid effluent releases in accordance with the ODCM.

4. Solid Waste

There was no solid radioactive waste generated or shipped during 2011.

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 2011, 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 2011.

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 2011.

Page 2 of 7
TABLE 1

Big Rock Point

Gaseous Effluent Releases

January 1, 2011 to December 31, 2011

1ST 2ND - 3RD

A. FISSION AND ACTIVATION GASES Units QTR QTR QTR

4TH

QTR

Est Total

Error %

1. Total release Ci N/A N/A N/A N/A

2. Average release rate for period .jCi/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A

B._IODINES

1. Totaliodine Ci N/A N/A N/A N/A

2. Average release rate for period iiCilsec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A

C._PARTICULATES

1. P articulates with half-life >8 day Ci N/A N/A N/A N/A

2. Average release rate for period .‘ Cl/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A

4. Gross alpha radioactivity Ci N/A N/A N/A N/A

D. TRITIUM

1. Total Release Ci N/A N/A N/A N/A

2. Average release rate for period .Ci/sec N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A N/A N/A

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 N/A N/A N/A N/A

2. Percent limit % N/A N/A N/A N/A

3. Gamma Air dose at Site Boundary due to Noble

Gas (ODCM Section 1, 1.3.2 a (1) (2)) mrads N/A N/A N/A N/A

4. Percent limit % N/A N/A N/A N/A

F. ORGAN DOSE (00CM Section 1, 1.3.2b (1) (2))

1. Maximum organ dose to pubic based on Critical

Receptors (child bone) mrem N/A N/A N/A N/A

2. Percent of limit (7.5 mrem/guarter) N/A N/A N/A N/A

Page 3 of 7
TABLE 1

Big Rock Point

Gaseous Effluent Releases

January 1,2011 to December31, 2011

1. FISSIONGASES Units 1STQTR 2NDQTR 3RDQTR 4THQTR

Krypton-85m Ci N/A N/A N/A N/A

Krypton-87 Ci N/A N/A N/A N/A

Krypton-88 Ci N/A N/A N/A N/A

Xenon-i33 Ci N/A N/A N/A N/A

Xenon-133m Ci N/A N/A N/A N/A

Xenon-135 Ci N/A N/A N/A N/A

Xenon-135m Ci N/A N/A N/A N/A

Xenon-138 Ci N/A N/A N/A N/A

Total for Period Ci N/A N/A N/A N/A

2. IODINES

lodine-13i Ci N/A N/A N/A N/A

lodine-132 Ci N/A N/A N/A N/A

lodine-133 Ci N/A N/A N/A N/A

Iodine-i 34 Ci N/A N/A N/A N/A

Iodine-i35 Ci N/A N/A N/A N/A

Total for Period Ci N/A N/A N/A N/A

Page 4 of 7
TABLE 1

Big Rock Point

Gaseous Effluent Releases

January 1, 2011 to December 31, 2011

3. PARTICUL.ATES Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR

Chromium-51 Ci N/A N/A N/A N/A

Manganese-54 Ci N/A N/A N/A N/A

Cobalt-58 Ci N/A N/A N/A N/A

Iron-59 Ci N/A N/A N/A N/A

Cobalt-60 Ci N/A N/A N/A N/A

Zinc-65 Ci N/A N/A N/A N/A

Silver-hOrn Ci N/A N/A N/A N/A

Cesium-i 34 Ci N/A N/A N/A N/A

Cesium-i 37 Ci N/A N/A N/A N/A

Barium-i40 Ci N/A N/A N/A N/A

Europium-i 52 Ci N/A N/A N/A N/A

Strontium-89 Ci N/A N/A N/A N/A

Strontium-90 Ci N/A N/A N/A N/A

Net unidentified beta Ci N/A N/A N/A N/A

*

Total Ci N/A N/A N/A N/A

Particulates with half-life >8 days

Page 5 of 7
TABLE 2

Big Rock Point

Liquid Effluent Releases

January 1, 2011 to December 31, 2011

D. GROSS ALPHA RADIOACTIVITY Ci N/A N/A N/A N/A

E. VOLUME OF WASTE RELEASED

(Prior to dilution)

F. VOLUME OF DILUTION WATER USED DURING

PERIOD

G. MAXIMUM DOSE COMMITMENT WHOLEBODY

Percent of ODCM Section 1 2.3.2 a (1.5 mrem)

Liters

Liters

mrem

%

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

H. MAXIMUM DOSE COMMITMENT -ORGAN Mrem N/A N/A N/A N/A

Percent of ODCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A N/A N/A

A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2NDQTR 3RDQTR 4TH QTR

Est Total

Error %

1. Total release (not including tritium, gases, alpha) Ci N/A N/A N/A N/A

N/A

2. Average diluted concentration during period pCi/mI N/A N/A N/A N/A

3. Percent of EC % N/A N/A N/A N/A

B. TRITIUM

1. Total release Ci N/A N/A N/A N/A

N/A

2. Average diluted concentration during period pCi/mI N/A N/A N/A

3. PercentofEC N/A J N/A N/A N/A

C. DISSOLVED AND ENTRAINED GASES

1. Total release Ci N/A N/A N/A N/A

N/A

2. Average diluted concentration during period pCi/mI N/A N/A N/A N/A

3. Percent of EC N/A N/A N/A N/A

Page 6 of 7
TABLE 2

Big Rock Point

Liquid Effluent Releases

January 1, 2011 to December 31, 2011

1. NUCLIDES

RELEASED Units 1STQTR 2NDQTR 3RDQTR 4THQTR

Chromium-5i Ci -. -- -- --

Manganese 54 Ci -. -- -- -.

Cobalt-58 Ci -- -- -- -.

Iron-59 Ci -- -- -- --

Cobalt-60 Ci -- -- -- -.

Zinc-65 Ci -- -- -- --

Strontium-89 Ci -- — -- --

Strontium-90 Ci -- -- -- --

Molybdenum-99 Ci — -. -- —

Silver-hOrn Ci -- -- -- --

Iodine-i 31 Ci -- -. -- --

Cesium-134 Ci -- -- -- --

Cesium-i 37 Ci -- -- --

Antimony-i 25 Ci -- -- — --

Tin-ii3 Ci -- -. -- --

Net Unidentified Beta Ci — -- -- —

Fission & Activation

Product Total Ci -- -- -- --

Xenon-133 Ci -- -- -- --

Tritium Ci -- -- -- -

Grand Total Ci -• -- -- --

Page 7 of 7