Entergy

Entergy Nuclear Operations, Inc.

Palisades Nuclear Plant

27780 Blue Star Memorial Highway

Covert, MI 49043

Tel 269 764 2000

April 29, 2009 10 CFR 50.36a

U. S. Nuclear Regulatory Commission

ATTN: Document Control Desk

Washington, DC 20555-0001

Subject: 2008 Annual Radioactive Effluent Release and Waste Disposal Report

Palisades Nuclear Plant

Docket 50-255

License No. DPR-20

Big Rock Point

Dockets 50-155 and 72-043

License No. DPR-6

Dear Sir or Madam:

Enclosed is the Entergy Nuclear Operations, Inc. 2008 Annual Radioactive Effluent

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

Point Plant (BRP). This report is submitted in accordance with 10 CFR 50.36a(a)(2).

Enclosure 1 contains the report for PNP. Enclosure 2 contains the report for BRP.

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, 2008, through December 31, 2008.

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

Sincerely,

Terry A. Davis

Licensing Manager

Palisades Nuclear Plant

tad/bed

Enclosures (2)

CC Administrator, Region III, USNRC

Project Manager, Palisades, USNRC

Resident Inspector, Palisades, USNRC

NRC NMSS Project Manager

VZC/'2 6 /0
ENCLOSURE 1

PALISADES RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF RELEASES

JANUARY - DECEMBER 2008

2008 Plant Operating History

Palisades Nuclear Plant (PNP) was on line on January 1, 2008. PNP was taken off line

on January 13, 2008, due to a main feedwater pump trip. The plant was returned to

service on January 14, 2008. PNP was taken off line on May 23, 2008, due to an

apparent loss of load and was returned to service on May 25, 2008. PNP was taken off

line on August 5, 2008, due to excessive control rod drive mechanism leakage and

returned to service on August 10, 2008. PNP remained on line for the remainder of

2008.

1. Supplemental Information

a. Batch Releases

Information relating to batch release of gaseous and liquid effluents is

provided in Attachment 1, "Batch Releases."

b. Abnormal Releases

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

34,500 pCi/L. Monitoring performed during 2008, showed tritium levels

range from 639 pCi/L to 42,900 pCi/L. No radionuclides other than tritium

have been detected. Repairs have been completed on buried piping and a

storage tank, however, troubleshooting and additional repairs are necessary.

Tritium is still being released to the environment via an unmonitored pathway

as evidenced by the continued detection of monitoring well sample activity.

A definitive release rate or total activity released cannot be determined.

Conservatively, the same 1% estimate of total tritium activity released via

batch releases that was used in 2007 will be used for 2008 effluent

calculations. The result is 6.18 curies.

2. Gaseous Effluents

Attachment 2, "Gaseous Effluents - Summation of Releases," lists and summarizes

all gaseous radioactive effluents released during the reporting period.

3. Liquid Effluents

Attachment 3, "Liquid Effluents - Summation of Releases," lists and summarizes all

liquid radioactive effluents released during the reporting period.

Page 1 of 3
4. Radioloaical Impact on Man

Doses to individuals and populations were calculated using LADTAP and GASPAR

computer programs.

a. Total body and organ doses to an individual in unrestricted areas from

receiving water-related exposure pathways were 1.98E-3 mrem and 2.29E-3

mrem respectively. (Teen whole body and teen gastrointestinal-lower large

intestine - organ)

b. The maximum offsite air doses due to beta and gamma radiations at

locations near ground level from gaseous effluents occurred at the site

boundary (0.48 miles south-south east (SSE)). The air doses were 1.04E-3

millirad beta and 3.71 E-4 millirem gamma.

c. Organ doses to individuals in unrestricted areas from radioactive iodine and

radioactive material in gaseous particulate form from the major pathways of

exposure were 5.44E-3 millirem. (Child thyroid)

d. Total body dose to the population and average dose to individuals in the

population from receiving water-related pathways to a distance of 50 miles

from the site were 4.22E-3 rem and 3.19E-6 millirem, respectively.

e. Total body doses to the population and average doses to individuals from

gaseous effluents to a distance of 50 miles from the site were 3.25E-2 rem

and 2.46E-5 millirem respectively.

5. ODCM Changes

The ODCM with changes annotated is included as Attachment 7. Locations for

dose calculations based on the latest Land Use Census are as follows:

Location Direction Miles from Plant

Site Boundary SSE 0.48

Residence SSW 0.49

Garden SE 1.49

Beef Cattle SE 4.3

Attachment 7 contains the ODCM, Revision 20, per the requirements of Technical

Specification 5.5.1 .c.3.

Page 2 of 3
6. Additional Information

a. Estimate of Uncertainty

Both the Gaseous and Liquid Summation of Release data sheets includeestimates of the uncertainty associated with the measurement of radioactive

effluents. These estimates are based on statistical analyses of a series of

sample results as described in the ODCM, Appendix A. These results are

listed in the "Est Error %" columns on the Gaseous and Liquid Summation

Reports.

b. Solid Waste

Attachment 4, "Solid Waste," summarizes all solid radioactive waste shipped

for burial in 2008, including the waste classification, sources, volume

shipped, activity (curies), and principal nuclide content. Radwaste

shipments were made either to Barnwell Waste Management Facility, or to

Envirocare of Utah, Inc.

c. Process Control Program

No changes were made to the process control program.

d. Lower Limits of Detection

The lower limits of detection (LLDs) required by the Offsite Dose Calculation

Manual (ODCM) for gaseous and liquid effluents are provided in

Attachment 5, "Lower Limits of Detection for Palisades Effluents."

e. Cross Check Program

Results of the 2008 Radiochemistry Cross Check Program with Analytics are

shown in Attachment 6. Results were in agreement for all isotopes on all

three detectors.

f. Radioactive Effluent Monitoring Instrumentation

RIA-1 113, waste gas discharge monitor, was out of service at the beginning

of 2008, placed back in service on January 17, 2008, taken out again on

January 23, 2008, and returned to service on January 31, 2008. All other

effluent monitors required to be in service per the ODCM were in service for

the duration of 2008.

Page 3 of 3
ATTACHMENT 1

PALISADES NUCLEAR PLANT

RADIOACTIVE EFFLUENT RELEASE REPORT

BATCH RELEASES

JANUARY - DECEMBER 2008

TABLE HP 10.5-1

GASEOUS Units 1St Qtr 2 nd Qtr 3 rd Qtr 4 th Qtr

Number of Releases N/A 4 2 7 5

Total Release Time Minutes 441 137 653 579

Maximum Release Minutes 139 75 125 163

Time

Average Release Time Minutes 110 68.5 93.3 115.8

Minimum Release Minutes 67 62 63 69

Time

Page 1 of 1
ATTACHMENT 2

RADIOACTIVE EFFLUENT RELEASE REPORT

GASEOUS EFFLUENTS - SUMMATION OF RELEASES

Est

Fission and Activation Error

A. Gases Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year %

1. Quarterly sum of total curies Ci 3.74E-01 8.29E-01 9.91 E+00 9.86E-01 1.21 E+01 4.0

2. Average release rate pCi/sec 4.75E-02 1.05E-01 1.25E+00 1.24E-01

3. Percent of limit % 2.33E-05 4.78E-05 6.17E-04 5,64E-05

Ar-41 Ci < LLD < LLD < LLD < LLD

Kr-85 Ci 4.16E-02 4.29E-03 6.95E-03 < LLD

Kr-85m Ci < LLD < LLD 7.08E-03 < LLD

Kr-87 Ci 1.19E-03 < LLD < LLD < LLD

Kr-88 Ci < LLD < LLD < LLD < LLD

4. Xe-131m Ci 5.40E-04 1.52E-04 6.27E-03 1.1OE-03

Xe-133 Ci 3.26E-01 8.19E-01 9.57E+00 9.78E-01

Xe-133m Ci < LLD < LLD 6.26E-02 < LLD

Xe-135 Ci 1.99E-03 2.15E-03 2.51E-01 2.27E-03

Xe-135m Ci 2.52E-03 3.61E-03 5.73E-03 4.66E-03

Xe-138 Ci < LLD < LLD < LLD < LLD

B. lodines

1. Total Iodine Ci 2.15E-04 3.04E-04 4.87E-04 3.96E-04 1.40E-03 7.5

2. Average release rate -pCi/sec 2.73E-05 3.86E-05 6.13E-05 4.98E-05

3. % of limit for Iodine 131/133 % 1.24E-05 1.70E-05 2.90E-05 1.85E-05

1-131 Ci 6.08E-05 8.15E-05 1.49E-04 7.38E-05

4. 1-133 Ci 1.54E-04 2.22E-04 3.38E-04 3.22E-04

1-135 Ci < LLD < LLD < LLD < LLD

C. Particulates half-life > 8 days

1. Total Release Ci 9.86E-06 8.74E-06 7.66E-06 1.13E-05 3.76E-05 31.0

Average release rate for

2. Deriod uCi/sec 1.25E-06 1.11E-06 9.64E-07 1.42E-06

3. % of limit % 4.15E-05 3.94E-05 3.42E-05 5.04E-05

Mn-54 Ci < LLD < LLD < LLD < LLD

Co-58 Ci 6.72E-07 < LLD < LLD < LLD

Fe-59 Ci <LLD <LLD <LLD <LLD

Co-60 Ci < LLD < LLD < LLD < LLD

Zn-65 Ci < LLD < LLD < LLD < LLD

Y-88 Ci < LLD < LLD < LLD < LLD

4. Nb-95 Ci < LLD < LLD < LLD < LLD

Sr-89 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Sr-90 Ci 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

Cs-134 Ci < LLD < LLD < LLD < LLD

Cs-137 Ci < LLD < LLD < LLD < LLD

Ce-141 Ci < LLD < LLD < LLD < LLD

Ce-144 Ci <LLD <LLD <LLD <LLD

Total For Period Ci 6.72E-07 0.OOE+00 0.OOE+00 0.OOE+00

5. Gross alpha radioactivity Ci 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00

Page 1 of 2
ATTACHMENT 2

RADIOACTIVE EFFLUENT RELEASE REPORT

GASEOUS EFFLUENTS - SUMMATION OF RELEASES

D. Tritium 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year

1. Total Release Ci 1.19E+01 1.01E+01 - 7.71E+00 8.32E+00

2. Average release rate for

period pCi/sec 1.51 E+00 1.28E+00 9.70E-01 1.05E+00

3. Percent of limit % 3.22E-03 2.73E-03 2.06E-03 2.23E-03

E. Whole Body Dose

1. Beta Airdose at site

boundary due

to noble gases (ODCM App A

lll.C) mrads 3.50E-05 6.95E-05 8.56E-04 8.22E-05

2. Percent limit % 3.50E-04 6.95E-04 8.56E-03 8.22E-04

3. Gamma Airdose at Site

boundary due to noble gasses

(ODCM App A 11I.C) mrads 1.03E-05 2.37E-05 3.09E-04 2.83E-05

4. Percent Limit % 2,06E-04 4.74E-04 6.18E-03 5.66E-04

F. Organ Dose .

1. Maximum organ dose to

public based on critical

receptors (ODCM App A 111.D) mrem 1.09E-03 1.26E-03 1.97E-03 1.12E-03 2. Percent of Limit % 1.45E-02 1.68E-02 2.62E-02 1.50E-02

ITritium ICi I1.19E+01 I 1.01E+01 1 7.71 E+00 I 8.32E+001 Total Ci 2.53E+01 2.15E+01 1.64E+01 1.77E+01

Net Unidentified beta Ci 9.19E-06 8.74E-06 7.66E-06 1.13E-05

I Un ID Beta % of Release I _ 3.05E-04 I

Note: All gaseous releases from PNP are considered to be ground-level releases.

Page 2 of 2
ATTACHMENT 3

RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF RELEASES

Est

Mixed Fission and Activation Total

A. Products Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year Error %

Total Release (not including

1. tritium, gasses or alpha) Ci 1.67E-03 9.20E-04 6.80E-03 8.19E-03 1.76E-02 20.2

Average concentration for

2. quarter pCi/ml 4.24E-11 3.20E-11 1.74E-10 2.11E-10

3. Percent of limit % 8.00E-04 4.43E-04 1.59E-03 2.19E-03

Cr-51 Ci < LLD 3.63E-04 < LLD < LLD

Mn-54 Ci 1.13E-04 3.91E-05 1.89E-04 8.40E-04

Co-57 Ci < LLD < LLD < LLD < LLD

Co-58 Ci 7.65E-04 1.79E-04 5.43E-03 5.58E-03

Fe-59 Ci < LLD 1.45E-05 9.64E-05 1.91 E-04

Co-60 Ci 7.OOE-04 2.60E-04 9.41 E-04 1.41 E-03

Zn-65 Ci < LLD < LLD < LLD < LLD

Sr-89 Ci 7.96E-06 0.OOE+00 8.15E-05 6.85E-05

Sr-90 Ci 7.47E-06 0.00E+00 5.15E-06 1.41E-05

Nb-95 Ci < LLD 7.74E-06 4.34E-05 < LLD

Zr-95 Ci 5.12E-06 < LLD 3.48E-05 < LLD.

Ag-11 Om Ci 6.11 E-05 3.36E-05 <LLD 8.94E-05

Sb-125 Ci < LLD < LLD < LLD < LLD

1-131 Ci < LLD 6.39E-06 < LLD .< LLD

Cs-134 Ci < LLD < LLD < LLD < LLD

Cs-137 Ci 1.38E-05 1.62E-05 < LLD 4.62E-07

Ce-141 Ci <LLD < LLD < LLD < LLD

Ce-144 Ci < LLD < LLD < LLD < LLD

B. Tritium

1. Total release Ci 5.39E+01 1.43E+02 2.-87E+02 2.54E+02 7.38E+02 4.0 1

Average concentration for

2. quarter POCi/mI 1.37E-06 4.97E-06 7.35E-06 6.55E-06

3. Percent of limit % 1.37E-01 4.97E-01 7.35E-01 6.55E-01

Dissolved and Entrained

SGasses

1. Total release Ci .OOE+00 0.OOE+00 1.87E-04 0.OOE+00 1.87E-04 28.0

Average diluted concentration

2. during period ,pCi/ml 0.OOE+00 0.00E+00 4.79E-12 0.OOE+00

3. Percent of limit % 0.OOE+00 0.OOE+00 2.40E-06 0.OOE+00

4. Xe-133 Ci < LLD < LLD 1.87E-04 <LLD

Xe-135 Ci < LLD < LLD < LLD < LLD

D. Gross Alpha Radioactivity I

1. Total Release Ci < LLD < LLD < LLD 1.20E-05 I 1.20E-05

Page 1 of 2
ATTACHMENT 3

RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF RELEASES

E. Volumes Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr Year

Volume of liquid effluent released

1. prior to dilution liters 3.73E+05 3.72E+05 5.03E+05 6.63E+05 1.91 E+06

Volume of dilution water used during

2. period liters 3.95E+10 2.88E+10 3.90E+10 3.88E+10 1.46E+11

Radiological Impact on Man

F. Total Body Dose

F. Maximum Dose Commitment -

1, Whole Body mrem 3.28E-04 2.75E-04 5.88E-04 7.86E-04

2, Percent of ODCM App A INA.H limit % 2.19E-02 1.83E-02 3.92E-02 5.24E-02

G. Organ Dose

G. Maximum Dose Commitment -

1. Organ mrem 3.46E-04 3.08E-04 7.98E-04 8.52E-04

2. Percent of ODCM App A lII.H limit % 6.92E-03 6.16E-03 1.60E-02 1.70E-02

* Particulates with half-lives > 8 days

Page 2 of 2
ATTACHMENT 4

PALISADES NUCLEAR PLANT

RADIOACTIVE EFFLUENT RELEASE REPORT

SOLID WASTE

JANUARY - DECEMBER 2008

Waste Source Container Volume *Total

Class of Waste Type (m) Curies ** Principal Radionuclides

H-3, Mn-54, Fe-55, Co-57 Co-58, Co-60,

Ni-59, Ni-63, Zn-65, Sr-90, Nb-95, Nb-97,

High Ag-110m, Sb-125, Cs-137, La-140, CeResin Integrity 144, Pu-238, Pu-239, Pu-241, Am-242,

AS Charcoal Container 3.6 12 Cm-242, Cm-243

H-3, Cr-51, Mn-54, Fe-59, Co-58, Co-60,

Ni-59, Ni-63, Sr-90, Nb-95, Zr-95, Tc-99,

Dry Ag-110m, Sb-125, Cs-137, Ce-1 44, PuActive General 238, Pu-239, Pu-241, Am-242, Cm-242,

AU Waste Design 152.35 1.102 Cm-243

H-3, C-14, Cr-51, Mn-54, Fe-55, Fe-59,

Co-58, Co-60, Ni-59, Ni-63, Sr-90, Tc-99,

Ru-106, Ag-11Orn, Sb-125, 1-129, Cs-137,

High Eu-154, Eu-155, U-233, U-238, Pu-238,

Integrity Pu-239, Pu-241, Am-241, Cm-242, CmC Resin Container 4.81 308 243

STotal 160.76 321.102

*All shipments went to waste processors and not direct to disposal. The volume

presented indicates shipment volume.

**Gamma isotopes are measured quantities, all other isotopes are estimated.

Page 1 of 1
ATTACHMENT 5

PALISADES NUCLEAR PLANT

RADIOACTIVE EFFLUENT RELEASE REPORT

LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS

JANUARY - DECEMBER 2008

Gaseous Release Type Type of Activity Analysis Lower Limit of

Detection

(pCi/ml)

Waste Gas Storage Tank Principal Gamma Emitters 1 E-04

Containment Purge Principal Gamma Emitters 1 E-04

Stack Gas Effluent 1-131, 1-133 1E-12

Principal Gamma Emitters (I-131, 1E-11 Others)..

Sr-89, Sr-90, and Gross Alpha 1E-11

Noble Gases Gross Beta or Gamma, 1 E-06

Liquid Release Type Type of Activity Analysis Lower Limit of

Detection

(pCi/ml)

Batch Waste Release Principal Gamma Emitters 5E-07

Tanks 1-131 1 E-06

Dissolved and Entrained Gases 1 E-05

(Gamma Emitters)

H-3 1 E-05

Gross Alpha 1 E-07

Sr-89, Sr-90 5E-08

Continuous Releases Principal Gamma Emitters 5E-07

1-131 1E-06

Dissolved and Entrained Gases 1 E-05

(Gamma Emitters)

H-3 1 E-05

Gross Alpha 1 E-07

Sr-89, Sr-90 5E-08

Page 1 of 1
ATTACHMENT 6

PALISADES NUCLEAR PLANT

RADIOACTIVE EFFLUENT RELEASE REPORT

RESULTS OF 2008 RADIOCHEMISTRY CROSS CHECK PROGRAM

NOTE: CROSS CHECKS ARE NOT TYPICALLY PERFORMED IN THE FIRST

QUARTER OF THE YEAR

21 Pages Follow
Eckert & Ziegler

Analytics

1380 Seaboard Industrial Blvd.

Atlanta, Georgia 30318 U.S.A.

Tel 404.352.8677

Fax 404-352-2837

RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

ENTERGY

PALISADES NUCLEAR PLANT

2nd QUARTER 2008

(Ref. Date 05/16/08)

Daniel M. Montgomery, QA Manager

ANA Fogm002 FRcv
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi microCi ANALYTICS RESOLUTION COMPARISON

A22633-66 Ce-141 7.10E-05 7.49E-05 0.95 20 AGREEMENT

SOLID Cr-51 7.18E-05 6.74E-05 1.07 20 AGREEMENT

DET. I Cs-134 1.49E-05 1.65E-05 0.90 20 AGREEMENT

Cs-137 2.35E-05 2.37E-05 0.99 20 AGREEMENT

Co-58 1.73E-05 1.80E-05 0.96 20 AGREEMENT

Mn-54 3.13E-05 3.03E-05 1.03 20 AGREEMENT

Fe-59 3.34E-05 3.24E-05 1.03 20 AGREEMENT

Zn-65 2.73E-05 2.90E-05 0.94 20 AGREEMENT

Co-60 2.15E-05 2.20E-05 0.98 20 AGREEMENT

A22633-66

SOLID

DET. 2

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.98E-05

7.10E-05

1.52E-05

2.46E-05

1.76E-05

3.20E-05

3.33E-05

2.89E-05

2.11E-05

7.49E-05

6.74E-05

1.65E-05

2.37E-05

1.80E-05

3.03E-05

3.24E-05

2.90E-05

2.20E-05

0.93

1.05

0.92

1.04

0.98

1.06

1.03

1.00

0.96

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

2ND QUARTER 2008 (Ref. Date 05/16/2008)

1
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22633-66 Ce-141 6.89E-05 7.49E-05 0.92 20 AGREEMENT

SOLID Cr-51 6.48E-05 6.74E-05 0.96 20 AGREEMENT

DET. 3 Cs-134 1.59E-05 1.65E-05 0.97 20 AGREEMENT

Cs-137 2.47E-05 2.37E-05 1.04 20 AGREEMENT

Co-58 1.77E-05 1.80E-05 0.98 20 AGREEMENT

Mn-54 3.21E-05 3.03E-05 1.06 20 AGREEMENT

Fe-59 3.23E-05 3.24E-05 1.00 20 AGREEMENT

Zn-65 2.83E-05 2.90E-05 0.97 20 AGREEMENT

Co-60 2.15E-05 2.20E-05 0.98 20 AGREEMENT

A22634-66 Ce-141 7.33E-05 7.63E-05 0.96 20 AGREEMENT

GAS Cr-51 7.42E-05 6.86E-05 1.08 20 AGREEMENT

SIMULATED Cs-134 1.61E-05 1.68E-05 0.96 20 AGREEMENT

DET. 1 Cs-137 2.47E-05 2.42E-05 1.02 20 AGREEMENT

Co-58 1.81E-05 1.84E-05 0.98 20 AGREEMENT

Mn-54 3.25E-05 3.09E-05 1.05 20 AGREEMENT

Fe-59 3.44E-05 3.30E-05 1.04 20 AGREEMENT

Zn-65 2.98E-05 2.96E-05 1.01 20 AGREEMENT

Co-60 2.25E-05 2.24E-05 1.01 20 AGREEMENT

2ND QUARTER 2008 (Ref. Date 05/16/2008)

2
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22634-66 Ce-141 6.84E-05 7.63E-05 0.90 20 AGREEMENT

GAS Cr-51 7.00E-05 6.86E-05 1.02 20 AGREEMENT

SIMULATED Cs-134 1.52E-05 1.68E-05 0.91 20 AGREEMENT

DET. 2 Cs-137 2.37E-05 2.42E-05 0.98 20 AGREEMENT

Co-58 1.67E-05 1.84E-05 0.91 20 AGREEMENT

Mn-54 3.06E-05 3.09E-05 0.99 20 AGREEMENT

Fe-59 3.24E-05 3.30E-05 0.98 20 AGREEMENT

Zn-65 2.92E-05 2.96E-05 0.99 20 AGREEMENT

Co-60 2.15E-05 2.24E-05 0.96 20 AGREEMENT

A22634-66 Ce-141 6.94E-05 7.63E-05 0.91 20 AGREEMENT

GAS Cr-51 6.30E-05 6.86E-05 0.92 20 AGREEMENT

SIMULATED Cs-134 1.58E-05 1.68E-05 0.94 20 AGREEMENT

DET. 3 Cs-137 2.35E-05 2.42E-05 0.97 20 AGREEMENT

Co-58 1.74E-05 1.84E-05 0.95 20 AGREEMENT

Mn-54 3.04E-05 3.09E-05 0.98 20 AGREEMENT

Fe-59 3.10E-05 3.30E-05 0.94 20 AGREEMENT

Zn-65 2.68E-05 2.96E-05 0.91 20 AGREEMENT

Co-60 2.09E-05 2.24E-05 0.93 20 AGREEMENT

2ND QUARTER 2008 [Ref. Date 05/16/2008)

3
PALISADES

VALUE

microCi/cc

ANALYTICS

VALUE

microCi/cc

RATIO

PALISADES:

SAMPLE ANALYSIS ANALYTICS RESOLUTION COMPARISON

A22635-66 Ce-141 1.1OE-03 1.09E-03 1.01 20 AGREEMENT

SOLID Cr-51 1.04E-03 9.78E-04 1.06 20 AGREEMENT

DET. I Cs-134 2.30E-04 2.39E-04 0.96 20 AGREEMENT

Cs-137 3.76E-04 3.45E-04 1.09 20 AGREEMENT

Co-58 2.76E-04 2.62E-04 1.05 20 AGREEMENT

Mn-54 4.88E-04 4.40E-04 1.11 20 AGREEMENT

Fe-59 5.03E-04 4.71E-04 1.07 20 AGREEMENT

Zn-65 4.35E-04 4.22E-04 1.03 20 AGREEMENT

Co-60 3.20E-04 3.19E-04 1.00 20 AGREEMENT

A22635-66 Ce-141 9.38E-04 1.09E-03 0.86 20 AGREEMENT

SOLID Cr-51 8.89E-04 9.78E-04 0.91 20 AGREEMENT

DET. 2 Cs-134 2.02E-04 2.39E-04 0.84 20 AGREEMENT

Cs-137 3.36E-04 3.45E-04 0.98 20 AGREEMENT

Co-58 2.35E-04 2.62E-04 0.90 20 AGREEMENT

Mn-54 4.33E-04 4.40E-04 0.98 20 AGREEMENT

Fe-59 4.48E-04 4.71E-04 0.95 20 AGREEMENT

Zn-65 3.99E-04 4.22E-04 0.95 20 AGREEMENT

Co-60 2.97E-04 3.19E-04 0.93 20 AGREEMENT

2ND QUARTER 2008 (Ref. Date 05/16/2008)

4
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22635-66 Ce-141 1.03E-03 1.09E-03 0.95 20 AGREEMENT

SOLID Cr-51 1.01E-03 9.78E-04 1.03 20 AGREEMENT

DET. 3 Cs-134 2.23E-04 2.39E-04 0.93 20 AGREEMENT

Cs-137 3.72E-04 3.45E-04 1.08 20 AGREEMENT

Co-58 2.71E-04 2.62E-04 1.03 20 AGREEMENT

Mn-54 4.80E-04 4.40E-04 1.09 20 AGREEMENT

Fe-59 4.94E-04 4.71E-04 1.05 20 AGREEMENT

Zn-65 4.42E-04 4.22E-04 1.05 20 AGREEMENT

Co-60 3.15E-04 3.19E-04 0.99 20 AGREEMENT

A22636-66 Ce-141 7.42E-05 7.41E-05 1.00 20 AGREEMENT

SOLID Cr-51 7.11E-05 6.66E-05 1.07 20 AGREEMENT

DET. 4 Cs-134 1.53E-05 1.63E-05 0.94 20 AGREEMENT

Cs-137 2.71E-05 2.35E-05 1.15 20 AGREEMENT

Co-58 1.92E-05 1.79E-05 1.08 20 AGREEMENT

Mn-54 3.52E-05 3.OOE-05 1.17 20 AGREEMENT

Fe-59 3.52E-05 3.21E-05 1.10 20 AGREEMENT

Zn-65 3.11E-05 2.87E-05 1.08 20 AGREEMENT

Co-60 2.21 E-05 2.17E-05 1.02 20 AGREEMENT

2ND QUARTER 2008 (Ref. Date 05/16/2008)

5
Eckert & Ziegler

Analytics

1380 Seaboard Industrial Blvd.

Atlanta, Georgia 30318 - U.S.A.

Tel 404.352-8677

Fax 404.352.2837

RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

ENTERGY

PALISADES PLANT

3rd QUARTER 2008

(Ref. Date 08/15/08)

Daniel M. Montgomery, QA Manager

ANA FormO=2 Rev. ---
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCilcc ANALYTICS RESOLUTION COMPARISON

A22803-66 Ce-141 9.67E-02 8.94E-02 1.08 20 AGREEMENT

CARTRIDGE Cr-51 2.66E-01 2.65E-01 1.00 20 AGREEMENT

DET. I Cs-134 6.05E-02 6.43E-02 0.94 20 AGREEMENT

Cs-137 4.63E-02 4.36E-02 1.06 20 AGREEMENT

Co-58 7.12E-02 6.72E-02 1.06 20 AGREEMENT

Mn-54 5.42E-02 4.81E-02 1.13 20 AGREEMENT

Fe-59 7.25E-02 6.59E-02 1.10 20 AGREEMENT

Zn-65 1.02E-01 9.44E-02 1.08 20 AGREEMENT

Co-60 6.50E-02 6.37E-02 1.02 20 AGREEMENT

A22803-66 Ce-141 8.64E-02 8.94E-02 0.97 20 AGREEMENT

CARTRIDGE Cr-51 2.59E-01 2.65E-01 0.98 20 AGREEMENT

DET. 2 Cs-134 6.03E-02 6.43E-02 0.94 20 AGREEMENT

Cs-137 4.75E-02 4.36E-02 1.09 20 AGREEMENT

Co-58 7.14E-02 6.72E-02 1.06 20 AGREEMENT

Mn-54 5.54E-02 4.81E-02 1.15 20 AGREEMENT

Fe-59 7.10E-02 6.59E-02 1.08 20 AGREEMENT

Zn-65 1.OOE-01 9.44E-02 1.06 20 AGREEMENT

Co-60 6.26E-02 6.37E-02 0.98 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

1
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22803-66 Ce-141 7.95E-02 8.94E-02 0.89 20 AGREEMENT

CARTRIDGE Cr-51 2.37E-01 2.65E-01 0.89 20 AGREEMENT

DET. 3 Cs-134 5.53E-02 6.43E-02 0.86 20 AGREEMENT

Cs-137 4.10E-02 4.36E-02 0.94 20 AGREEMENT

Co-58 6.23E-02 6.72E-02 0.93 20 AGREEMENT

Mn-54 4.83E-02 4.81E-02 1.00 20 AGREEMENT

Fe-59 6.42E-02 6.59E-02 0.97 20 AGREEMENT

Zn-65 8.93E-02 9.44E-02 0.95 20 AGREEMENT

Co-60 5.76E-02 6.37E-02 0.90 20 AGREEMENT

A22804-66 Ce-141 1.65E-03 1.51E-03 1.09 20 AGREEMENT

SIMULATED Cr-51 4.70E-03 4.48E-03 1.05 20 AGREEMENT

GAS Cs-134 1.05E-03 1.09E-03 0.97 20 AGREEMENT

DET. 1 Cs-137 7.92E-04 7.37E-04 1.07 20 AGREEMENT

Co-58 1.20E-03 1.14E-03 1.06 20 AGREEMENT

Mn-54 9.20E-04 8.14E-04 1.13 20 AGREEMENT

Fe-59 1.26E-03 1.11E-03 1.13 20 AGREEMENT

Zn-65 1.72E-03 1.60E-03 1.08 20 AGREEMENT

Co-60 1.11E-03 1.08E-03 1.03 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

2
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22804-66 Ce-141 1.50E-03 1.51E-03 0.99 20 AGREEMENT

SIMULATED Cr-51 4.32E-03 4.48E-03 0.97 20 AGREEMENT

GAS Cs-134 1.02E-03 1.09E-03 0.94 20 AGREEMENT

DET.2 Cs-137 7.83E-04 7.37E-04 1.06 20 AGREEMENT

Co-58 1.17E-03 1.14E-03 1.03 20 AGREEMENT

Mn-54 9.06E-04 8.14E-04 1.11 20 AGREEMENT

Fe-59 1.18E-03 1.11E-03 1.06 20 AGREEMENT

Zn-65 1.63E-03 1.60E-03 1.02 20 AGREEMENT

Co-60 1.04E-03 1.08E-03 0.97 20 AGREEMENT

A22804-66 Ce-141 1.33E-03 1.51E-03 0.88 20 AGREEMENT

SIMULATED Cr-51 4.04E-03 4.48E-03 0.90 20 AGREEMENT

GAS Cs-134 9.36E-04 1.09E-03 0.86 20 AGREEMENT

DET. 3 Cs-137 7.16E-04 7.37E-04 0.97 20 AGREEMENT

Co-58 1.03E-03 1.14E-03 0.91 20 AGREEMENT

Mn-54 8.06E-04 8.14E-04 0.99 20 AGREEMENT

Fe-59 1.06E-03 1.11E-03 0.95 20 AGREEMENT

Zn-65 1.49E-03 1.60E-03 0.93 20 AGREEMENT

Co-60 9.58E-04 1.08E-03 0.89 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

3
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCilcc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22805-66

SAND

DET. 1

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

3.68E-05

1.21E-04

2.61E-05

1.92E-05

2.83E-05

2.21E-05

2.70E-05

3.99E-05

2.60E-05

3.74E-05

1.11E-04

2.69E-05

1.83E-05

2.81E-05

2.01E-05

2.76E-05

3.95E-05

2.67E-05

0.98

1.09

0.97

1.05

1.01

1.10

0.98

1.01

0.97

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A22805-66 Ce-141 3.60E-05 3.74E-05 0.96 20 AGREEMENT

SAND Cr-51 1.09E-04 1.11E-04 0.98 20 AGREEMENT

DET. 2 Cs-134 2.56E-05 2.69E-05 0.95 20 AGREEMENT

Cs-137 1.87E-05 1.83E-05 1.02 20 AGREEMENT

Co-58 2.83E-05 2.81E-05 1.01 20 AGREEMENT

Mn-54 2.15E-05 2.01E-05 1.07 20 AGREEMENT

Fe-59 2.86E-05 2.76E-05 1.04 20 AGREEMENT

Zn-65 3.85E-05 3.95E-05 0.97 20 AGREEMENT

Co-60 2.60E-05 2.67E-05 0.97 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

4
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22805-66 Ce-141 3.49E-05 3.74E-05 0.93 20 AGREEMENT

SAND Cr-51 1.02E-04 1.11E-04 0.92 20 AGREEMENT

DET. 3 Cs-134 2.44E-05 2.69E-05 0.91 20 AGREEMENT

Cs-137 1.80E-05 1.83E-05 0.99 20 AGREEMENT

Co-58 2.64E-05 2.81E-05 0.94 20 AGREEMENT

Mn-54 1.96E-05 2.01E-05 0.97 20 AGREEMENT

Fe-59 2.68E-05 2.76E-05 0.97 20 AGREEMENT

Zn-65 3.74E-05 3.95E-05 0.95 20 AGREEMENT

Co-60 2.44E-05 2.67E-05 0.91 20 AGREEMENT

A22805-66

SAND

DET. 4

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

3.51E-05

9.96E-05

2.14E-05

1.85E-05

2.63E-05

2.18E-05

2.82E-05

3.98E-05

2.53E-05

3.74E-05

1.11E-04

2.69E-05

1.83E-05

2.81E-05

2.01E-05

2.76E-05

3.95E-05

2.67E-05

0.94

0.90

0.79

1.01

0.93

1.08

1.02

1.01

0.95

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

5
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22806-66 Ce-141 5.21E-02 4.94E-02 1.06 20 AGREEMENT

CARTRIDGE Cr-51 1.44E-01 1.46E-01 0.98 20 AGREEMENT

DET. 1 Cs-134 3.29E-02 3.55E-02 0.93 20 AGREEMENT

Cs-137 2.53E-02 2.41E-02 1.05 20 AGREEMENT

Co-58 3.82E-02 3.71E-02 1.03 20 AGREEMENT

Mn-54 2.93E-02 2.66E-02 1.10 20 AGREEMENT

Fe-59 3.94E-02 3.64E-02 1.08 20 AGREEMENT

Zn-65 5.43E-02 5.21E-02 1.04 20 AGREEMENT

Co-60 3.51E-02 3.52E-02 1.00 20 AGREEMENT

A22806-66 Ce-141 4.60E-02 4.94E-02 0.93 20 AGREEMENT

CARTRIDGE Cr-51 1.42E-01 1.46E-01 0.97 20 AGREEMENT

DET. 2 Cs-134 3.27E-02 3.55E-02 0.92 20 AGREEMENT

Cs-137 2.58E-02 2.41E-02 1.07 20 AGREEMENT

Co-58 3.85E-02 3.71E-02 1.04 20 AGREEMENT

Mn-54 3.02E-02 2.66E-02 1.14 20 AGREEMENT

Fe-59 3.85E-02 3.64E-02 1.06 20 AGREEMENT

Zn-65 5.49E-02 5.21E-02 1.05 20 AGREEMENT

Co-60 3.41E-02 3.52E-02 0.97 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

6
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22806-66 Ce-141 4.23E-02 4.94E-02 0.86 20 AGREEMENT

CARTRIDGE Cr-51 1.24E-01 1.46E-01 0.85 20 AGREEMENT

DET. 3 Cs-134 2.92E-02 3.55E-02 0.82 20 AGREEMENT

Cs-137 2.22E-02 2.41E-02 0.92 20 AGREEMENT

Co-58 3.34E-02 3.71E-02 0.90 20 AGREEMENT

Mn-54 2.50E-02 2.66E-02 0.94 20 AGREEMENT

Fe-59 3.40E-02 3.64E-02 0.93 20 AGREEMENT

Zn-65 4.75E-02 5.21E-02 0.91 20 AGREEMENT

Co-60 3.02E-02 3.52E-02 0.86 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

7
Eckert & Ziegler

Analytics

1380 Seaboard Industrial Blvd.

Atlanta, Georgia 30318 U.S.A.

Tel

Fax

404-352-8677

404"352-2837

RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

ENTERGY

PALISADES

4th QUARTER 2008

(Ref. Date 11/14/08)

Daniel M. ongo y7 -rag 

Daniel M. Montgomery, QA Manager

ANA FormG02 Rev --
a--

PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/ec ANALYTICS RESOLUTION COMPARISON

A23105A-66 Ce-141 2.98E-02 2.75E-02 1.08 20 AGREEMENT

CARTRIDGE Cr-51 4.31E-02 3.90E-02 1.11 20 AGREEMENT

RGEM Cs-134 1.I1E-02 1.11E-02 1.00 20 AGREEMENT

DET. I Cs-137 1.12E-02 9.68E-03 1.16 20 AGREEMENT

Co-58 1.22E-02 1.10E-02 1.11 20 AGREEMENT

Mn-54 1.50E-02 1.30E-02 1.15 20 AGREEMENT

Fe-59 1.48E-02 1.23E-02 1.20 20 AGREEMENT

Zn-65 1.80E-02 1.59E-02 1.13 20 AGREEMENT

Co-60 1.17E-02 1.08E-02 1.08 20 AGREEMENT

A23105A-66 Ce-141 2.64E-02 2.75E-02 0.96 20 AGREEMENT

CARTRIDGE Cr-51 3.84E-02 3.90E-02 0.98 20 AGREEMENT

RGEM Cs-134 1.07E-02 1.I1E-02 0.96 20 AGREEMENT

DET. 2 Cs-137 1.1OE-02 9.68E-03 1.14 20 AGREEMENT

Co-58 1.20E-02 .IOE-02 1.09 20 AGREEMENT

Mn-54 1.48E-02 1.30E-02 1.14 20 AGREEMENT

Fe-59 1.40E-02 1.23E-02 1.14 20 AGREEMENT

Zn-65 1.77E-02 1.59E-02 1.11 20 AGREEMENT

Co-60 1.11E-02 1.08E-02 1.03 20 AGREEMENT

4th QUARTER 2008 (Ref. Date 11/14/2008)

1
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A23105A-66 Ce-141 2.34E-02 2.75E-02 0.85 20 AGREEMENT

CARTRIDGE Cr-51 3.42E-02 3.90E-02 0.88 20 AGREEMENT

RGEM Cs-134 9.33E-03 I.I1E-02 0.84 20 AGREEMENT

DET. 3 Cs-137 9.08E-03 9.68E-03 0.94 20 AGREEMENT

Co-58 9.94E-03 1.1OE-02 0.90 20 AGREEMENT

Mn-54 1.25E-02 1.30E-02 0.96 20 AGREEMENT

Fe-59 1.21E-02 1.23E-02 0.98 20 AGREEMENT

Zn-65 1.50E-02 1.59E-02 0.94 20 AGREEMENT

Co-60 9.88E-03 1.08E-02 0.91 20 AGREEMENT

A23106-66 Ce-.141 8.55E-03 8.90E-03 0.96 20 AGREEMENT

SOLID Cr-51 1.20E-02 1.26E-02 0.95 20 AGREEMENT

7.2 mnL Cs-134 3.75E-03 3.59E-03 1.04 20 AGREEMENT

DET. I Cs-137 3.24E-03 3.13E-03 1.03 20 AGREEMENT

Co-58 3.74E-03 3.56E-03 1.05 20 AGREEMENT

Mn-54 4.17E-03 4.21E-03 0.99 20 AGREEMENT

Fe-59 4.30E-03 3.99E-03 1.08 20 AGREEMENT

Zn-65 4.85E-03 5.16E-03 0.94 20 AGREEMENT

Co-60 3.53E-03 3.51E-03 1.01 20 AGREEMENT

4th QUARTER 2008 (Ref. Date 11/14/2008)

2
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A23106-66 Ce-141 8.36E-03 8.90E-03 0.94 20 AGREEMENT

SOLID Cr-51 1.15E-02 1.26E-02 0.91 20 AGREEMENT

7.2 mL Cs-134 3.69E-03 3.59E-03 1.03 20 AGREEMENT

DET..¥ ,I- Cs-137 3.33E-03 3.13E-03 1.06 20 AGREEMENT

-¢• Co-58 3.68E-03 3.56E-03 1.03 20 AGREEMENT

Mn-54 4.34E-03 4.21E-03 1.03 20 AGREEMENT

Fe-59 3.75E-03 3.99E-03 0.94 20 AGREEMENT

Zn-65 5.03E-03 5.16E-03 0.97 20 AGREEMENT

Co-60 3.45E-03 3.51E-03 0.98 20 AGREEMENT

A23106-66 Ce-141 8.46E-03 8.90E-03 0.95 20 AGREEMENT

SOLID Cr-51 1.32E-02 1.26E-02 1.04 20 AGREEMENT

7.2 mL Cs-134 3.56E-03 3.59E-03 0.99 20 AGREEMENT

DET.< -'Cs-137 3.23E-03 3.13E-03 1.03 20 AGREEMENT

Co-58 3.39E-03 3.56E-03 0.95 20 AGREEMENT

Mn-54 4.15E-03 4.21E-03 0.99 20 AGREEMENT

Fe-59 3.76E-03 3.99E-03 0.94 20 AGREEMENT

Zn-65 4.98E-03 5.16E-03 0.97 20 AGREEMENT

Co-60 3.46E-03 3.51E-03 0.99 20 AGREEMENT

4th QUARTER 2008 (Ref. Date 11/14/2008)

3
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A23107-66 Ce-141 6.91E-02 6.74E-02 1.02 20 AGREEMENT

FILTER Cr-51 9.65E-02 9.57E-02 1.01 20 AGREEMENT

1 cc Cs-134 2.52E-02 2.72E-02 0.93 20 AGREEMENT

DET. 1 Cs-137 2.55E-02 2.37E-02 1.07 20 AGREEMENT

Co-58 2.79E-02 2.70E-02 1.03 20 AGREEMENT

Mn-54 3.45E-02 3.19E-02 1.08 20 AGREEMENT

Fe-59 3.55E-02 3.03E-02 1.17 20 AGREEMENT

Zn-65 4.25E-02 3.91E-02 1.09 20 AGREEMENT

Co-60 2.74E-02 2.66E-02 1.03 20 AGREEMENT

A23107-66 Ce-141 5.81E-02 6.74E-02 0.86 20 AGREEMENT

FILTER Cr-51 8.78E-02 9.57E-02 0.92 20 AGREEMENT

1 cc Cs-134 2.36E-02 2.72E-02 0.87 20 AGREEMENT

DET. 2 Cs-137 2.42E-02 2.37E-02 1.02 20 AGREEMENT

Co-58 2.66E-02 2.70E-02 0.99 20 AGREEMENT

Mn-54 3.27E-02 3.19E-02 1.02 20 AGREEMENT

Fe-59 3.16E-02 3.03E-02 1.04 20 AGREEMENT

Zn-65 3.96E-02 3.91E-02 1.01 20 AGREEMENT

Co-60 2.53E&02 2.66E-02 0.95 20 AGREEMENT

4th QUARTER 2008 (Ref. Date 11/14/2008)

4
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A23107-66 Ce-141 6.26E-02 6.74E-02 0.93 20 AGREEMENT

FILTER Cr-51 8.91E-02 9.57E-02 0.93 20 AGREEMENT

I cc Cs-134 2.43E-02 2.72E-02 0.89 20 AGREEMENT

DET. 3 Cs-137 2.40E-02 2.37E-02 1.01 20 AGREEMENT

Co-58 2.66E-02 2.70E-02 0.99 20 AGREEMENT

Mn-54 3.21E-02 3.19E-02 1.01 20 AGREEMENT

Fe-59 3.09E-02 3.03E-02 1.02 20 AGREEMENT

Zn-65 3.92E-02 3.91E-02 1.00 20 AGREEMENT

Co-60 2.58E-02 2.66E-02 0.97 20 AGREEMENT

A23108-66 Tritium 1.99E-03 1.52E-03 1.31 12.5 AGREEMENT

LIQUID

4th QUARTER 2008 (Ref. Date 11/14/2008)

5
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi/cc microCi/cc ANALYTICS RESOLUTION COMPARISON

A22806-66 Ce-141 4.23E-02 4.94E-02 0.86 20 AGREEMENT

CARTRIDGE Cr-51 1.24E-01 1.46E-01 0.85 20 AGREEMENT

DET. 3 Cs-134 2.92E-02 3.55E-02 0.82 20 AGREEMENT

Cs-137 2.22E-02 2.41E-02 0.92 20 AGREEMENT

Co-58 3.34E-02 3.71E-02 0.90 20 AGREEMENT

Mn-54 2.50E-02 2.66E-02 0.94 20 AGREEMENT

Fe-59 3.40E-02 3.64E-02 0.93 20 AGREEMENT

Zn-65 4.75E-02 5.21E-02 0.91 20 AGREEMENT

Co-60 3.02E-02 3.52E-02 0.86 20 AGREEMENT

3RD QUARTER 2008 (Ref. Date 08/15/2008)

7
ATTACHMENT 7

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

REVISION 20

93 Pages Follow
ODCM

Revision 21

Issued Date 2/10/09

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: OFFSITE DOSE CALCULATION MANUAL

Process Applicability Exclusion Eli

JBBurnett 213/09

Procedure Sponsor Date

JLFontaine 11/13/08

Technical Reviewer Date

JBBurnett 2/3/09

User Reviewer Date

TPKirwin 1/21/09

General Manager Plant Operations Date
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

Table of Contents

GA SEO US EFFLUENTS ............................................................................................... 1

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

1. Allowable Concentration .............................. 2

2. Monitor Response ......................................... 3

B. DOSE RATE CALCULATION .................................................................... 4

C. DESIGN BASIS QUANTITY (DBQ) LIMITS ON BATCH AND

CONTINUOUS RELEASES ..................................................................... 20

1. Batch Releases ........................................... 20

2. Continuous Releases .................. 20

3. Exceeding DBQ Limits ................. 21

4. Releasing Radionuclides Not Listed in

Table 1.9 ...................................................... 21

D. OPTIONAL QUARTERLY DOSE CALCULATIONS ............................... 22

1. Methodology for Optional Quarterly Dose

Calculations .................................................. 22

E. GASEOUS RADWASTE TREATMENT SYSTEM OPERATION ............. 25

1. System Description ..................................... 25

2. Determination of Satisfactory Operation ....... 25

F. RELEASE RATE FOR OFFSITE EC ...................................................... 26

G. PARTICULATE AND IODINE SAMPLING ............................................. 26

H. NOBLE GAS SAMPLING ........................................................................ 27

I. TRITIUM SAMPLING ............................................................................... 27

J. FIGURES AND TABLES .......................................................................... 28

LIQ UID EFFLUENTS ................................................................................................ 55

A. CONCENTRATION ................................................................................. 55

1. Requirements .............................................. 55

2. Prerelease Analysis ..................................... 55

3. Effluent Concentration (EC) - Sum of the

Ratios ........................................................... 56

B. INSTRUMENT SETPOINTS .................................................................... 57
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

Table of Contents

1. Setpoint Determination ................................... 57

2. Composite Samplers .................................. 57

3. Post-Release Analysis ................................ 58

C . D O S E ...................................................................................................... 58

1. RETS Requirement ...................................... 58

2. Release Analysis ......................................... 59

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT ......................... 63

E. RELEASE RATE FOR OFFSITE EC (50 MREM/YR) ................ 64

F. FIGURES AND TABLES .......................................................................... 65

II1. URANIUM FUEL CYCLE DOSE .............................................................................. 86

A. SPECIFICATIO N ..................................................................................... 86

B. ASSUM PTIO NS ....................................................................................... 86

C. DOSE CALCULATION ............................................................................ 87

IV. REVISIONS TO THE OFFSITE DOSE CALCULATION MANUAL ........................ 87

A. REQ UIREM ENTS .............................................. ....................................... 87

Attachment 1, "Offsite Dose Calculation Manual Change Reviews"

Appendix A, "Relocated Technical Specification"

Appendix B, "Request to Retain Soil in Accordance With 10 CFR 20.302"
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

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GASEOUS EFFLUENTS

A. ALARMITRIP SETPOINT METHOD

Appendix A, Section III.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-1 31, for iodine-1 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 ill.A.1 requires gaseous effluent monitors to have alarm/trip

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

be greater than Appendix A, Section Ill.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.

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Allowable Concentration

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:

R(k)=(-X)(F)7ý -L= < 5.0 (1.1)

If gaseous tritium and noble gasses are not present then:

R(k) •- 10

where:

C = Actual or measured concentration, at ambient temperature and

pressure of nuclide i (gCi/cc)

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

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

X/Q = Most conservative sector site boundary dispersion (sec/mi3) -

Table 1.3

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

considerations; variable for other monitors

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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 5.0.

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-1 33). Response of monitors used to define

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

Xe-1 33, however. Monitor response for the two categories of monitor is

determined as follows:

a. Normal Release (aged fission gasses)

Total gas concentration (pCilcc) at the monitor is calculated. The X4

detector response to isotopic activities (cpm/pCi/cc) is applied to 1

determine cpm expected. The setting for monitor alarms is established

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

times the measured concentration (c):

s = b x c (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 piCi/cc (or R/hr and j.Ci/cc), depending on monitor type, for

fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions,

either an appropriately decayed "accident" conversion curve may be

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

these cases, setpoints are established as in I.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.

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B. DOSE RATE CALCULATION

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

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

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

importance in the Palisades environs are considered.

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 Table 1.1, plus additional

nuclides.

d) Basic radionuclide data are given in Table 1.2.

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

D/Q's shown in Table 1.3.

g) Raw meteorological data consists of wind speed and

direction measurements at 10m and temperature

measurements at 10m 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.

i) Potential maximum population (resident) exposure points

are identified in Table 1.4.

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j) A semi-infinite cloud model is used.

k) Radioactive decay is considered for the plume.

I) Building wake effects on effluent dispersion are

considered.

m) A sector-average dispersion equation is used.

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

Wind Speed

Class Number Range (m/s) Midpoint (m/s)

1 0.0-0.4 0.2

2 0.4-1.5 0.95

3 1.5-3.0 2.25

4 3.0-5.0 4.0

5 5.0-7.5 6.25

6 7.5-10.0 8.75

7 > 10.0 --

105

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

through G classifications. The stability classes 1-7 will o

correspond to A=I, B=2, ..., G=7.

p) Terrain effects are not considered. I

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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:

9 7,zkuj 112ffl (2 x (1P

j=h k=e

where:

.3)

Xi

fik

Qi

p

Xzk

x

n

2nx/n

- Air concentration of radionuclide i, .Ci/m 3.

-- Joint relative frequency of occurrence of winds in

wind speed class j, stability class k, blowing

toward this exposure point, expressed as a

fraction.

- Average release rate of radionuclide i, [tCi/s.

- Fraction of radionuclide remaining in plume.

= Vertical dispersion coefficient for stability

class k (m).

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

= Downwind distance, m.

= Number of sectors, 16.

= Radioactive decay coefficient of radionuclide i, s'.

= Sector width at point of interest, m.

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For determining the total body dose rate:

DTB= Xi DFBi (1.4)

where:

DTB = Total body dose rate, mrem/y.

Xi = Air concentration of radionuclide I, pCi/m 3 .

DFBI = Total body dose factor due to gamma radiation,

mrem/y per [tCi/mi3 (Table 1.5).

For determining the skin dose rate:

Ds=i Xi (DFSi+1.11DFYi) (1.5)

where:

D, = Skin dose rate, mrem/y.

Xi = Air concentration of radionuclide i, PCi/m 3

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

pCi/m 3 (Table 1.5).

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 pLCi/m 3 (Table 1.5).

For determining dose rate to a point in air:

Da= X1 (DFYi or DFBI) (1.6)

where:

Da = Air dose rate, mrad/yr.

DFBj = Air dose factor for beta radiation (Table 1.5).

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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 Table 1.1.

d) Basic radionuclide data are given in Table 1.2.

e) All releases are treated as ground-level.

f) Mean annual average X/Q's are given in Table 1.3.

g) Raw meteorological data for ground-level releases

consist of wind speed and direction measurements at

lOm and temperature measurements at 10m and 60m.

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

points where maximum doses to man are expected to

exist.

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

Potential maximum exposure points (Table 1.4)

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.

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n) Radioactive decay is considered for

ground-concentration calculations.

o) Deposition is calculated based on the curves given in

Figure 1.2.

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

pasture grass May through October of each year. Use

default values of 0.58 for cows and 0.67 for goats for

fraction of year on pasture.

2) Equations

To calculate the dose for any one of the potential

maximum-exposure points, the following equations in

Section 1.2.2 are used.

a) Inhalation

Equation for calculating air concentration, X1 is the same

as in the Noble Gas Section (Equation 1.3).

For determining the organ dose rate:

Di =1x1 XX DFli BR (1.7)

where:

D = Organ dose rate due to inhalation, mremly.

Xi = Air concentration of radionuclide i, pCi/rm3 .

DFI1 = Inhalation dose factor, mrem/pCi

(Table 1.7).

BR = Breathing rate 1400 m3/y infant;

3700 m3

/y child; or 8000 m3/y teen and

adult.

1x10 6 = pCil/Ci conversion factor.

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b) Ground Contamination

For determining the ground concentration of any nuclide;

7

Gi=3.15x10 7 

y fkQiDR [1-exp-(,aitW) (1.8)

k=1 (2 , x/n) [ 

(

where:

G = Ground concentration of radionuclide i,

gCi/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 i,

i•Ci/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

27tx/n = Sector width at point of interest, m.

= Radioactive decay coefficient of

radionuclide i, y-1.

tb = Time for buildup of radionuclides on the

ground, 15 y.

3.15x 10 = s/y conversion factor.

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Corrected Figure 1.2 January 1977

10- 4

wj

I-0 0-

Iu

wl

0.1 1.0 10.0 100.0 200.0

PLUME TRAVEL DISTANCE (KILOMETERS)

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

Stablity Class.')

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For determining the total body or organ dose rate from

ground contamination:

DG = (8, 7 6 0)(1 X 106)(0. 7 ) ' Gi DFGi (1.9)

where:

DG = Dose rate due to ground contamination,

mrem/y.

G = Ground concentration of radionuclide i,

jiCi/m2.

DFG = Dose factor for standing on contaminated

ground, mrem/h per pCi/m 2 (Table 1.8).

8,760 Occupation time, h/y.

lx106 = pCi/ptCi 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:

7

cvi=3,600 Y- fkQDR Fr[1-exp(-eit)]Biv[ P ( Ai 0tb)] iexp (A• th)]] (1.10)

k= 1 (27r x/n) Y E

where:

CV = Concentration of radionuclide i in and on

vegetation, pCi/kg.

k = Stability class.

fk = Frequency of this stability class and wind

direction combination, expressed as a

fraction.

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Q = Average release rate of radionuclide i,

VICi/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

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

r = Fraction of deposited activity retained on

vegetation (1.0 for iodines, 0.2 for

particulates).

XEi = Effective removal rate constant,

XEi = ý, + Xw, where X, is the radioactive

decay coefficient, h-1, and 4 is a measure

of physical loss by weathering

(Xw=0.0021 h).

te = Period over which deposition occurs, 720 h.

Yv Agricultural yield, 0.7 kg/m 2.

Bv =. Transfer factor from soil to vegetation of

radionuclide i (Table 1.6).

), = Radioactive decay coefficient of

radionuclide i, h-1.

tb = Time for buildup of radionuclides on the

ground, 1.31x10 5 h (15Y).

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

3,600 s/h conversion factor.

th = Holdup time between harvest and

consumption of food (2,160 hours for stored

food).

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For determining the concentration of C-14 in vegetation:

CV14 1 X 103 X14 (0.11/0.16) (1.11)

where:

CV14 Concentration of C-14 in vegetation, 1iCi/kg.

X14 Air concentration of C-14, ýiCi/m 3.

0.11 = Fraction of total Plant mass that is natural

carbon.

0.16 = Concentration of natural carbon in the

atmosphere, g/m 3.

1x10 3 = g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

CVT = 1 x 103 XT (0.75)(0.5/H) (1.12)

where:

CVT = Concentration of H-3 in vegetation, ýiCi/m 3.

XT Air concentration of H-3, ýtCi/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.

Absolute humidity of the atmosphere, g/m 3.

g/kg conversion factor.

H=

IX10 3 =

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For determining the concentration of any nuclide in cow's

or goat's milk:

CMj = CVj FMi Qf exp (-Xi tf) (1.13)

where:

CM = Concentration of radionuclide i (including

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

CVi = Concentration of radionuclide i in and on

vegetation, p.Ci/kg.

FM, = Transfer factor from feed to milk for

radionuclide i, d/l (Table 1.6).

Qf Amount of feed consumed by the milk

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

goat 6 kg/d).

Xi Radioactive decay coefficient of

radionuclide i, d".

tf = Transport time of activity from feed to milk

to receptor, 2 days.

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For determining the organ dose rate from ingestion of

green leafy vegetables and milk:

D=1x106 CMiDFiUM (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).

DFi = Ingestion dose factor, mrem/pCi

(Table 2.1).

UM = Ingestion rate for milk, 330 I/y; for

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

infant.

lx1 06 - pCi/pCi conversion factor.

d) Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal

flesh:

Cn = Efi CVi Qfi exp (Qts) (1.15)

where:

CCf Concentration of nuclide i in the animal

flesh, pCi/kg.

Fn Fraction of animal's daily intake which

appears in each kg of flesh, days/kg

(Table 1.6).

CV = Concentration of radionuclide i in the

animal's feed (Equation 1.10).

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Qf = Amount of feed consumed by the cow per

day, 50 kg/d.

ts = Average time from slaughter to

consumption, 20 days.

To determine the organ dose from ingestion of beef:

D Cfl Df.Of (1.16)

where:

Dfi = Ingestion dose factor for age group,

mrem/pCi (Table 2.1) for nuclide i.

Uf = Ingestion rate of meat for age group,

kg/y (child-41, teen-65, adult-1 10).

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.

Di = Dose rate due to inhalation, mrem/y.

DG Dose rate due to ground contamination,

DM

Dv

DF

mrem/y.

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

= Dose rate due to vegetable ingestion,

mrem/y.

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

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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 I.B.1.3.

c. Design Basis Quantities

The design basis quantity of a radionuclide emitted to the atmosphere

is the amount of that nuclide, when released in one year, which would

result in a dose not exceeding any of the following:

1) 15 millirem to any organ of an individual from iodines and

particulates with half-life greater than 8 days (Appendix A,

Section III.D.1).

2) 15 millirem to skin of an individual from noble gas (Appendix A,

Section IIl.C.1.b).

3) 5 millirem to the total body of an individual from noble gas

(Appendix A, Section III.C.1 .a).

Design basis quantity (Ci) is the smallest value for each nuclide,

calculated by dividing the dose limits (a through c above) by.the

appropriate dose calculated from the amount of radionuclide (Ci) used

to conservatively estimate the doses of Section D, as listed in

Table 1.1 (or a hypothetical .1 Ci/year); the result is then multiplied by

the amount of radionuclide used.

DBQ =DA (Co;) (1.18)

Dc

where:

DAI = Appendix I dose limit (mrem or mrad).

Do = Calculated dose (mrem or mrad).

c = Quantity of nuclide resulting in dose Dc (Ci).

DBQ = Design Basis Quantity (Ci).

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The limiting values for Design Basis Quantities for radionuclides

released to the atmosphere are given in Table 1.9.

The inverse of the ratio CCDc in the above equation (ie, DJCC) is a

useful value, since it represents the most limiting dose per unit quantity

of each nuclide released. Use of the DcCC ratio in quarterly evaluation

of offsite dose is discussed in Section D. Values of DdCC are given in

Table 1.9.

d. Land Use Census and DBQ Changes

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

annual land use census and revision of the ODCM for use in the

following calendar year. Areas of the ODCM which will be reviewed,

and changed if appropriate, are Table 1.4 (Land Use Census Data by vN

Sector), Table 1.4a (Critical Receptors), and Table 1.9 (Gaseous

Design Basis Quantities). Changes will be effective on January 1 of I

the year following the year of the survey.

e. 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.

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C. DESIGN BASIS QUANTITY (DBQ) LIMITS ON BATCH AND CONTINUOUS

RELEASES

1. Batch Releases

For each batch release (waste decay tank release or Containment purge), the j

quantity of each nuclide identified is summed with the quantity of that nuclide

released since the first of the current calendar year. The cumulative total for

each nuclide then is divided by the design basis quantity for each nuclide

(from Table 1.9), and the resultant fractions are summed in order to assure

that the sum fraction of all nuclides does not exceed 1.0:

Z <10 (1.19)

i (DBQ)<

The amount in any calendar quarter should not exceed 0.5. This is checked

by subtracting the value obtained at the end of the previous quarter from the

value obtained from the cumulative total to date, including the batch to be

released.

2. Continuous Releases

Low level continuous releases from the vent gas collection header and other

low level sources are totaled on a weekly basis and summed with any batch

releases for the week in order to establish the cumulative DBQ fraction from

batch plus continuous released for the year-to-date. Calculations are

performed in the same manner as for batch releases described in C.1.

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3. Exceeding DBQ Limits

As discussed under B.1.3, the DBQ is a very conservative estimate of activity

which could give doses at Appendix I limits. Because different organs are

summed together and doses to different people are summed, the DBQ

typically overestimates dose by about a factor of five. Thus, if calculations of

DBQ fraction exceed 1.0 for year-to-date or 0.5 for the quarter, technical

specifications probably still would not be exceeded. However, further

discretionary releases should be deferred until an accurate assessment of

dose is made by use of GASPAR computer code or by analysis of-appropriate

release data via the segment gaussian dose model used in emergency

planning (inhalation dose, total body external dose, and boundary dose in air).

See also Section D.1.2.

It should be noted that Palisades Plant to date (based on review of

semiannual effluent data) has never exceeded the annual or quarterly DBQ

fraction, despite its conservatism. Thus, it is not expected that an alternate to

the DBQ method will be required unless the Plant is in a significantly

off-normal condition.

4. Releasing Radionuclides Not Listed in Table 1.9

Table 1.9 contains all nuclides identified to date as routine constituents of

gaseous releases at Palisades Plant, plus those common to PWRs in

general, even if not previously detected at Palisades. From time to time,

however, other nuclides may be detected.

If the unlisted nuclide constitutes less than 10% of the EC-fraction for the

release, and all unlisted nuclides total less than 25% of the EC-fraction, the

nuclide may be considered not present.

If the unlisted nuclide constitutes greater than 10% of the EC-fraction, or all

unlisted nuclides together constitute greater than 25%, then each nuclide

should be assigned a DBQ equal to the most conservative value listed for the

physical form of the nuclide involved (noble gas, halogen, or particulate).

Should a nuclide not listed in Table 1.9 begin to appear in significant

quantities on a routine basis, revision to this ODCM should be made in order

to include a design basis quantity specific to that nuclide.

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D. OPTIONAL QUARTERLY DOSE CALCULATIONS

'I. Methodology for Optional Quarterly Dose Calculations

This option may be used in place of, or in addition to, the Design Basis

Quantity (DBQ) fraction calculation described by Equation 1.19. This optional

conservative calculation relates the DBQ fraction to the doses from which it

was originally derived. Use of this method may assist in identification of the

critical dose pathway or characteristics of the assumed critical individual

(infant, child, teen, and adult), since Table 1.9 indicates these parameters.

a. Simplified Conservative Approach

This method utilizes a limiting dose concept such that the limiting dose

for each nuclide is summed with the limiting dose for each other

nuclide, regardless if such sum is physically possible. It also assumes

critical pathways, such as milk and vegetables, are in effect even in

winter when the pathway is absent.

As such, the method is highly conservative and significantly

over-estimates dose. If limits appear to be exceeded by this method,

Section D.1.2 (a concise method, but requiring computer support) will

be utilized.

1) Assumptions

a) All assumptions of Section 1.1 are utilized.

b) Limiting doses for each gaseous nuclide are summed,

regardless of limiting decay mode (gamma or beta).

c) Limiting doses for each particulate and iodine nuclide are

summed, regardless of dose point location, exposure

pathway, or organ affected.

d) Doses are summed for detected nuclides such that all

nuclides which contribute greater than 10% individually or

.25% in aggregate, to the EC of released radioactivity, are

included in the dose calculation.

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2) Equations

For determining gaseous effluent dose:

(D0IC

DG = Y AiG(DC/Cc, G <5 millirad/quarter, 10 mrad/yr (1.20

0

where:

DG = Dose from gaseous effluents (mrad).

AiG = Quantity of gaseous nuclide i released (Ci).

,c)iG = Dose per Ci factor for gaseous nuclide i (mrad/Ci).

The limit for this mixture is conservatively taken as that for

gamma exposure (5 mrem/quarter, 10 mrem/year) although as

indicated in Table 1.9, a majority of the gaseous effluents are

beta-limiting and on an individual basis have the higher limit of

10 millirem/quarter and 20 millirem/year.

For determining tritium, particulate and iodine dose to organs:

)

DTPI ATPII (D. / Cc)1 Pji < 7.5 mrem/q, 15 mrem/y (1.21)

where:

DTPI = Dose from particulates and iodines (mrem).

ATPHi Quantity of particulate or iodine nuclide i released

(Ci).

Dose per Ci factor for particulate or iodine nuclide i

(mrad/Ci).

(Dc/Cc-)TP~i =

23
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

b. Realistic Calculation

This methodology is to be used if the highly conservative calculations

described in C.1 or D.1 yield values that appear to exceed applicable

limits.

Doses for released particulates, iodines and noble gases will be

determined by use of the NRC GASPAR computer code. The

computer run will utilize the annual average joint frequency

meteorological data based on not less than 3 years of meteorological

measurement, and will reflect demographic and land use information

from the land use survey generated in the most recent prior year.

Where appropriate, seasonal adjustments will be applied to obtain

realistic dose estimates since both recreational and agricultural

activities can vary greatly in relation to season of the year.

An alternative to GASPAR for offsite dose calculation is the use of the

Palisades Segmented Gaussian Plume Emergency offsite dose

calculation program. This dose model allows evaluation of dose under

the actual meteorological conditions present at the time of release. It

is anticipated that the system may be used in major short-term

releases such as Containment purges are to be made under conditions

which depart significantly from mean annual conditions.

24
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

E. 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, displacing of cover gases

caused by liquid accumulation in the tanks connected to the vent header, and

boron recycle process operation.

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. I

Explosive mixtures of hydrogen and oxygen have been demonstrated

compatible with the system by operational experience.

2. Determination of Satisfactory Operation

Design basis quantity fraction will be calculated for batch and continuous

releases as described in Section I.C. 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.

25
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

F. 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 I to 10 CFR 50 provides

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

reasonably achievable requirement.

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

and inhalation. The source term used is listed in Table 1.1. The meteorology data is

given in Table 1.3. Dose using annual average meteorology, to the most limiting

organ of the person assume to be residing at the site boundary with highest X/Q,

is 2.15E-02 mrem (for one year). The release rate which would result in a dose rate

equivalent to 50 mrem/year (using the more conservative total body limit) is the

curies/year given in Table 1.1 multiplied by 50/2.15E-02 or 0.11 Ci/sec.

G. 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 design basis quantity fraction. 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.

26
PALISADES NUCLEAR PLANT

OFFSITE.DOSE CALCULATION MANUAL

Revision 21

Gamma analytical results for particulate and halogen filters are combined for

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

analysis will be performed per Appendix A, Table B-1 requirements.

H. 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. Nonroutine releases will be quantified from

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

and analysis will be performed per Appendix A, Table B-1 requirements.

TRITIUM SAMPLING

Tritium has a low dose consequence to the public because of low production rates.

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.

27
PAUSADE GASEOU EFFUENT

CA

m

VtAM0FMMTQR ME- E

WftOMK TANAVN

mom 0 > ow~w (0

----- --- OFF GAS m

C 0 (j

Smm

> NEVA08011MIJZ -rL- OMAW r

NEPARIA24AOBAL>

*1% 110. $71 AMD sn.P WfPY ANDOOW OF r.-o EIDWA)SYM

FLOW am." numamo

PALISADES EFFLUENT FLOW PATHS

GASEOUS
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.1

PALISADES GASEOUS AND LIQUID SOURCE TERMS. CURIESIYEAR (1)

Nuclide

H-3

Kr-85

Kr-85m

Kr-87

Kr-88

Ar-41

Xe-131m

Xe-1 33

Xe-1i33m

Xe-135

Xe-1 35m

1-131

1-132

1-133

1-134

1-135

Na-24

Cr-51

Mn-54

Co-57

Co-58

Fe-59

Co-60

Se-75

Nb-95

Zr-95

Mo-99

Ru-1 03

Sb-1 27

Cs-134

Cs-136

Cs-137

Ba-140

La-140

Unidentified beta

Gaseous(2)

5.5

4.1

0.12

8.4E-02

2.1E-01

3.1E-02

2.2

1493

0.43

1.11

0.3

0.025

2.91 E-03

6.5E-03

4.8E-04

1.84E-02

1.5E-06

2.5E-04

4.1 E-04

2.1E-06

8.6E-04

6.6E-06

1.1E-03

3.7E-06

2.4E-05

4.7E-06

1.5E-07

0.3E-07

NA

4.5E-05

NA

2.6E-04

2.8E-07

7.5E-07

3.9E-04

Liauid(2)

159

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

3.21 E-03

NA

4.7E-05

NA

NA

NA

3.9E-03

7.8E-03

3.2E-05

2.9E-02

4.1 E-04

i.24E-02

NA

4.53E-04

1.79E-04

NA

0.1 E-05

3.5E-05

0.7

1.8E-06

1.36E-02

NA

1.1 E-04

3.3E-03

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

January-June 1982 and dividing by 4.

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

streams.

29
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.2

BASIC RADIONUCLIDE DATA

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

21

22

23

24

25

26

27

28

29

30

31

32

33

34

35

36

37

38

39

40

NUCLIDE

Tritium

C-14

N-13

0-19

F-1 8

NA-24

P-32

AR-41

CR-51

MN-54

MN-56

FE-59

CO-58

CO-60

ZN-69m

ZN-69

BR-84

BR-85

KR-85m

KR-85

KR-87

KR-88

KR-89

RB-88

RB-89

SR-89

SR-90

SR-91

SR-92

SR-93

Y-90

Y-91m

Y-91

Y-92

Y-93

ZR-95

NB-95m

NB-95

MO-99

TC-99m

HALF-LIFE

(days)

4.49E 03

2.09E 06

6.94E-03

3.36E-04

7.62E-02

6.33E-01

1.43E 01

7.63E-02

2.78E 01

3.03E 02

1.07E-01

4.50E 01

7.13E 01

1.92E 03

5.75E-01

3.96E-02

2.21 E-02

2.08E-03

1.83E-01

3.93E 03

5.28E-02

1.17E-01

2.21 E-03

1.24E-02

1.07E-02

5.20E 01

1.03E 04

4.03E-01

1.13E-01

5.56E-03

2.67E 00

3.47E-02

5.88E 01

1.47E-01

4.29E-01

6.50E 01

3.75E 00

3.50E 01

2.79E 00

2.50E-01

LAMBDA

(1 Is)

1.79E-09

3.84E-12

1.16E-03

2.39E-02

1.05E-04

1.27E-05

5.61 E-07

1.05E-04

2.89E-07

2.65E-08

7.50E-05

1.78E-07

1.12E-07

4.18E-09

1.39E-05

2.03E-04

3.63E-04

3.86E-03

4.38E-05

2.04E-09

1.52E-04

6.86E-05

3.63E-03

6.47E-04

7.50E-04

1.54E-07

7.79E-10

1.99E-05

7.10E-05

1.44E-03

3.00E-06

2.31E-04

1.36E-07

5.46E-05

1.87E-05

1.23E-07

2.14E-06

2.29E-07

2.87E-06

3.21 E-05

BETA1 GAMMA1

(MEV/DIS) (MEV/DIS)

5.68E-03

4.95E-02

4.91 E-01

1.02E 00

2.50E-01

5.55E-01

6.95E-01

4.64E-01 3.862-03

3.80E-03

8.29E-01

1.18E-01

3.41 E-02

9.68E-02

2.21E-02

3.19E-01

1.28E 00

1.04E 00

2.53E-01

2.51E-01

1.32E 00

3.61E-01

1.36E 00

2.06E 00

1.01E 00

5.83E-01

1.96E-01

6.50E-01

1.95E-01

9.20E-01

9.36E-01

2.73E-02

6.062-01

1.44E 00

1.17E 00

1.16E-01

1.81E-01

4.44E-02

3.96E-01

1.56E-02

0.0

0.0

1.02E 00

1.05E 00

1.02E 00

4.12E 00

0.0

1.28E 00

3.28E-02

8.36E-01

1.69E 00

1.19E 00

9.78E-01

2.50E 00

4.16E-01

0.0

1.77E 00

6.60E-02

1.59E-01

2.21E-03

7.93E-01

1.96E 00

1.83E 00

6.26E-01

2.05E-00

8.45E-05

0.0

6.95E-01

1.34E 00

2.24E 00

0.0

5.30E-01

3.61E-03

2.50E-01

8.94E-02

7.35E-01

6.06E-02

7.64E-01

1.50E-01

1.26E-01

30
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.2 (continued)

BASIC RADIONUCLIDE DATA

41

42

43

44

45

46

47

48

49

50

51

52

53

54

55

56

57

58

59

60

61

62

63

64

65

66

67

68

NUCLIDE

TC-99

TC-104

RU-1 06

TE-132

1-129

1-131

1-132

1-133

1-134

1-135

XE-131m

XE-133m

XE-1 33

XE-1 35m

XE-1 35

XE-137

XE-138

CS-134

CS-1 35

CS-136

CS-1 37

CS-138

BA-1 39

BA-140

LA-140

CE-144

PR-143

PR-144

HALF-LIFE

(days)

7.74E 07

1.25E-02

3.67E 02

3.24E 00

6.21E 09

8.05E 00

9.58E-02

8.75E-01

3.61E-02

2.79E-01

1.18E 01

2.26E 00

5.27E 00

1.08E-02

3.83E-01

2.71E 03

9.84E-03

7.48E 02

1.10E 09

1.30E 01

1.10E 04

2.24E-02

5.76E-02

1.28E 01

1.68E 00

2;84E 02

1.36E 01

1.20E-02

LAMBDA

(f/s)

1.04E-1 3

6.42E-04

2.19E-08

2.48E-06

1.29E-1 5

9.96E-07

8.37E-05

9.17E-06

2.22E-04

2.87E-05

6.80E-07

3.55E-06

1.52E-06

7.43E-04

2.09E-05

2.96E-03

8.15E-04

1.07E-08

7.29E-15

6.17E-07

7.29E-1 0

3.58E-04

1.39E-04

6.27E-07

4.77E-06

2.82E-08

5.90E-07

6.68E-04

BETA'

(MEV/DIS)

8.46E-02

1.60E 00

1.01E-02

1.OOE-01

5.43E-02

1.94E-01

4.89E-01

4.08E-01

6.16E-01

3.68E-01

1.43E-01

1.90E-01

1.35E-01

9.58E-02

3.17E-01

1.77E 00

6.65E-01

1.63E-01

5.63E-02

1.37E-01

1.71E-01

1.20E 00

8.96E-01

3.15E-01

5.33E-01

9.13E-02

3.14E-01

1.21E 00

GAMMA'

(MEV/DIS)

0.0

1 .95E 00

0.0

2.33E-01

2.46E-02

3.81E-01

2.24E 00

6.02E-01

2.59E 00

1.55E 00

2.01 E-02

4.15E-02

4.60E-02

4.32E-01

2.47E-01

1.88E-01

1.10E 00

1.55E 00

0.0

2.15E 00

5.97E-01

2.30E 00

3.53E-02

1.71E-01

2.31E 00

1.93E-02

0.0

3.18E 00

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

Radionuclide Transformations: Energq 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.

31
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.3

USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 8 October 2008

***** PALISADES XOQDOQ82 --*** USING 01/01/2003 - 12/31/2007 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTAINMENT BUILDING

TYPE OF

LOCATION

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

SITE BOUNDARY

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

RESIDENCE

GARDEN

GARDEN

GARDEN

GARDEN

GARDEN

GARDEN

BEEF CATTLE

DIRECTION DISTANCE X/Q

FROM SITE (MILES) (METERS) (SEC/CUB.METER)

NO DECAY

NNE

NE

ENE

a ESE

SE

SSE

S

SSW

NNENE

RN2 E

ESE

SE SSE

S

SSW

NNE

NE

ENE

E

SE

S

SE

0.50

0.65

0.87

0.82

0.76

0.63

0.48

0.42

0.48

1.50

1.50

1.20

1.70

0.99

0.90

0.80

0.72

0.49

1.70

1.70

2.30

2.10

1.49

4.20

4.30

805.

1046.

1400.

1320.

1223.

1014.

772.

676.

772.

2414.

2414.

1931.

2736.

1593.

1448.

1287.

1159.

789.

2736.

2736.

3701.

3380.

2398.

6759.

6920.

UNDEPLETED

1.47E-06

1.10E-06

5.25E-07

5.72E-07

7.74E-07

1.38E-06

2.51E-06

2.12E-06

1.35E-06

2.81E-07

3.27E-07

3.25E-07

1 93E-07

5.18E-07

7.98E-07

1.15E-06

9.41E-07

1.30E-06

2.36E-07

2.64E-07

1.24E-07

1. 41E-07

3.77E-07

7.55H-08

7. 97E-08

XJQ X/Q D/Q

(SEC/CUB.METER) (SEC/CUB.METER) (PER SQ.METER)

2.260 DAY DECAY 8.000 DAY DECAY

UNDEPLETED DEPLETED

1.46E-06 1.34E-06 7.21E-09

1.10E-06 9.90B-07 8.48E-09

5.23E-07 4.63E-07 4.11E-09

5.70E-07 5.072-07 4.78E-09

7.72E-07 6.89E-07 7.46E-09

1.38E-06 1.242-06 .1.30E-08

2.50E-06 2.29E-06 2.11E-08

2.12E-06 1.96B-06 1.06E-08

1.34E-06 1.233-06 6.10E-09

2.79E-07 2.38E-07 1.13E-09

3.152-07 2.69E-07 2.04E-09

3.24E-07 2.81E-07 2;37R-09

1.92E-07 1.62E-07 1.37E-09

5.16E-07 4.53E-07 4.77B-09

7.95E-07 7.03E-07 7.142-09

1.14E-06 1.02E-06 9.09E-09

9.36E-07 8.39E-07 4.39E-09

1.30E-06 1.19B-06 5.89E-09

2.34E-07 1.98E-07 9.13E-10

2.62E-07 2.21E-07 1.64E-09

1.23E-07 1.01E-07 7.67E-10

1.40E-07 1.16E-07 9.48E-10

3.74E-07 3.20E-07 3.01E-09

7.35E-08 5.72E-08 2.05E-10

7.80E-08. 6.03E-08 4.65E-10

%

32
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.4

2008 PALISADES LAND USE CENSUS Vt

Distance to the nearest residence, garden, dairy/beef cattle, and goat in each sector.

Sector Residence Garden Beef Cattle Dairy Cow Goat

NNE 1.5 1.7 > 5 mi > 5 mi >5mi

NE 1.5 1.7 > 5 mi > 5 mi >5mi

ENE 1.2 2.3 >'5 mi > 5 mi >5mi

E 1.7 2.1 > 5 mi > 5 mi > 5 mi

ESE 0.99 >5mi > 5 mi > 5 mi > 5 mi

SE 0.90 1.49 4.3 > 5 mi > 5 mi

SSE 0.80 >5 mi > 5 mi > 5 mi > 5 mi

S 0.72 4.2 > 5 mi > 5 mi >5mi

SSW 0.49 > 5 mi >5mi >5mi >5mi

TABLE 1.4a

2008 PALISADES LAND USE CENSUS

Critical Receptor Items

Sector Distance Item X/Q (seclm 3) D/Qi(1 Inm)

(miles) I

SSE 0.48 Site Boundary 2.51 E-6 2.11E-8

SSW 0.49 Residence 1.30E-6 5.89E-9

SE 1.49 Garden 3.77E-7 3.01 E-9

SE 4.3 Beef Cattle 7.97E-8 4.65E-10

*Based on Palisades 5-year composite meteorological data, 2003 - 2007.

|

33
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.5

DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

Kr-85m

Kr-85

Kr-87

Kr-88

Kr-89

Xe-131m

Xe-133m

Xe-1 33

Xe-135m

Xe-1 35

Xe-137

Xe-138

DFR 1

1 .17(+3)3

1.61(+1)

5.92(+3)

1.47(+4)

1.66(+4)

9.15(+1)

2.51(+2)

2.94(+2)

3.12(+3)

1.81(+3)

1.42(+3)

8.83(+3)

8.84(+3)

DFY2

1.23(+3)

1.72(+1)

6.17(+3)

1.52(+4)

1.73(+4)

1.56(+2)

3.27(+2)

3.53(+2)

3.36(+3)

1.92(+3)

1.51(+3)

9.21(+3)

9.30(+3)

DFS1

1.46(+3)

1.34(+3)

9.73(+3)

2.37(+3)

1.01(+4)

4.76(+2)

9.94(+2)

3.06(+2)

7.11(+2)

1.86(+3)

1.22(+4)

4.13(+3)

2.69(+3)

DFB2

1.97(+3)

1.95(+3)

1.03(+4)

2.93(+3)

1.06(+4)

1.11(+3)

1.48(+3)

1.05(+3)

7.39(+3)

2.46(+3)

1.27(+4)

4.75(+3)

Ar-41 3.28(+3)

1. mrem/y per ý,Ci/m 3

2. mrad/y per [,Ci/m3

3. 1.17(+3) = 1.17x 103

*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).

34
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATIONMANUAL

Revision 21

TABLE 1.6

STABLE ELEMENT TRANSFER DATA

ELEMENT

H

C

Na

P

Cr

Mn

Fe

Co

Ni

Cu

Zn

Rb

Sr

Y

Zr

Nb

Mo

Tc

Ru

Rh

Ag

Te

I

Cs

Ba

La

Ce

Pr

Nd

W

Np

Fm - MILK (COW)

(DAYS/L)

1.OE-02

1.2E-02

4.OE-02

2.5E-02

2.2E-03

2.5E-04

1.2E-03

1.OE-03

6.7E-03

1.4E-02

3.9E-02

3.0E-02

8.OE-04

1.OE-05

5.OE-06

2.5E-03

7.5E-03

2.5E-02

I.OE-06

1.OE-02

5.OE-02

1.OE-03

6.OE-03

1.2E-02

4.OE-04

5.OE-06

1.OE-04

5.OE-06

5.OE-06

5.OE-04

5.OE-06

F, - MILK (GOAT)

(DAYS/L)

1.7E-01

1.QE-01

4.OE-02

2.5E-01

2.2E-03

2.5E-04

1.3E-04

1.OE-03

6.7E-03

1.3E-02

3.9E-02

3.OE-02

1.4E-02

1.OE-05

5.OE-06

2.5E-03

7.5E-03

2.5E-02

1.OE-06

1.OE-02

5.OE-02

I.OE-03

6.OE-02

3.OE-01

4.OE-04

5.OE-06

1.OE-04

5.OE-06

5.OE-06

5.OE-04

5.OE-06

Ff- MEAT

(DAYS/KG)

1.2E-02

3.1 E-02

3.OE-02

4.6E-02

2.4E-03

8.OE-04

4.OE-02

1.3E-02

5.3E-02

8.OE-03

3.OE-02

3.1 E-02

6.OE-04

4.6E-03

3.4E-02

2.8E-01

8.OE-03

4.QE-01

4.OE-01

1.5E-03

1.7E-02

7.7E-02

2.9E-03

4.OE-03

3.2E-03

2.OE-04

1.2E-03

4.7E-03

3.3E-03

1.3E-03

2.OE-04

Bgi

(VEG/SOIL)

4.8E-00

5.5E-00

5.2E-02

1.1E-00

2.5E-04

2.9E-02

6.6E-04

9.4E-03

1.9E-02

1.2E-01

4.OE-01

1.3E-01

1.7E-02

2.6E-03

1.7E-04

9.4E-03

1.2E-01

2.5E-01

5.OE-02

1.3E+01

1.5E-01

1.3E-00

2.OE-02

1.OE-02

5.OE-03

2.5E-03

2.5E-03

2.5E-03

2.4E-03

1.8E-02

2.5E-03

35
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y 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

BE10 9.49E-04 1.25E-04 2.65E-05 0. 0. 1.49E-03 1.73E-05

C14 1.89E-05 3.79E-06 3.79E-06 3.79E-06 3179E-06 3.79E-06 3.79E-06

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

F18 3.92E-06 0. 3.33E-07 0. 0. 0. 6.10E-07

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

NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-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. 1.00E-08 0.

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

CA41 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 4.11E-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. 1.10E-09 1.58E-10 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. 2.71E-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 8.41E-06 0. 0. 3.22E-03 2.28E-05

N159 1.81E-05 5.44E-06 3.10E-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-10 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+D 8.98E-09 1.84E-08 1.67E-09 0. 7.45E-09 1.91E-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+D 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.

KR88+D 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+D 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08

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

SR90+D 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05

SR91+D 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05

SR92+D 7.50E-09 0. 2.79E-10 0. 0. 1.70E-05 1.00E-04

Includes a 50% increase to account for percutaneous transpiration..

36
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC 101

RU103+D

RU105+D

RU106+D

RH105

PD107

PD109

AG1 10M+D

AG111

CD113M

CD1 15M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE 132+D

TE133M+D

TE134+D

1129

1130

1131+D

BONE

2.35E-06

2.91E-10

4.20E-04

1.17E-08

1.07E-07

2.24E-04

8.24E-05

1.07E-07

1.38E-04

1.12E-05

2.44E-10

0.

0.

9.98E-13

2.09E-07

4.65E-14

1.44E-06

8.74E-10

6.20E-05

8.26E-09

0.

0.

7.13E-06

3.75E-07

0.

0.

2.09E-04

1.01 E-05

8.30E-04

2.71 E-05

3.69E-05

3.08E-06

2.82E-07

3.40E-06

1.19E-05

1.59E-09

1.01 E-05

5.63E-1 1

7.62E-08

1.24E- 11

2.66E-07

6.13E-11

3.18E-11

2.16E-05

4.54E-06

2.71 E-05

LIVER

0.

0.

0.

0.

0.

9.51 E-05

1.99E-05

1.83E-08

3.59E-05

4.59E-06

5.21E- 11

6.46E-06

1.18E-07

2.06E-12

2.68E-07

5.88E-14

0.

0.

0.

5.41 E-09

4.92E-07

3.92E-09

5.16E-06

1.45E-07

6.67E-04

1.73E-04

4.21 E-06

2.51E-07

1.44E-05

3.97E-07

3.41 E-07

6.01E-08

5.04E-09

1.42E-06

4.93E-06

6.81E-10

4.35E-06

2.48E-1 1

3,93E-08

5.87E-12

1.69E-07

3.59E-1 1

2.04E-11

1.59E-05

9.91 E-06

3.17E-05

TOTAL BODY

6.30E-08

9.90E-12

1.12E-05

3.29E-10

2.91 E-09

6.18E-05

1.45E-05

8.36E-09

1.15E-05

2.70E-06

1.88E-11

2.22E-07

2.31E-08

2.66E-1 1

8.85E-08

5.80E-1 3

4.85E-07

2.93E-10

7.77E-06

3.63E-09

4.11E-08

1.05E-09

3.57E-06

7.75E-08

2.64E-05

6.19E-06

7.28E-06

6.OOE-07

3.52E-05

8.56E-06

7.78E-06

1.11 E-06

8.76E-08

4.70E-07

1.48E-06

3.49E-1 0

1.59E-06

1.34E-11

2.59E-08

3.57E-12

1.26E-07

2.74E-11

1.68E- 11

1.16E-05

3.98E-06

1.40E-05

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

4.27E-06

2.47E-07

3.84E-06

7.18E-08

4.45E-08

2.35E-08

3.60E-09

1.16E-06

3.48E-06

1.32E-09

3.91 E-06

4.82E-11

6.38E-08

1.13E-11

1.99E-07

5.52E-11

2.91 E-11

1.04E-02

1.14E-03

1.06E-02

KIDNEY

0.

0.

0.

0.

0.

3.19E-04

2.22E-05

1.85E-08

3.68E-05

3.37E-06

4.07E- 11

1.54E-06

1.89E-07

.2,22E-11

2.49E-06

6.99E-13

3.03E-06

6.42E-10

7.61 E-05

1.50E-08

2.75E-06

1.28E-08

7.80E-06

3.05E-07

5.80E-04

9.41 E-05

0.

0.

0.

0.

0.

0.

0.

0.

2.68E-05

3.47E-09

2.27E-05

1.25E-10

1.89E-07

2.85E-1 1

7.39E-07

1.72E-10

9.59E-1 1

1.88E-05

1.09E-05

3.70E-05

LUNG

1.92E-04

1.99E-06

1.75E-03

1.75E-05

5.46E-05

1.37E-03

1.25E-03

7.88E-05

2.09E-04

3.42E-04

2.37E-06

3.40E-04

9.63E-05

5.79E-07

6.77E-04

4.17E-07

3.94E-04

1.12E-05

8.26E-03

2.08E-05

6.34E-05

1.68E-05

2.62E-03

2.06E-04

1.40E-03

1.47E-03

2.22E-03

6.43E-04

4.93E-03

1.89E-03

1.17E-03

6.88E-04

1.54E-04

3.19E-04

9.37E-04

7.39E-06

1.20E-03

2.14E-06

1.42E-04

1.47E-06

2.43E-04

3.92E-06

2.93E-06

0.

0,

0.

GI-LLI

7.43E-05

1.68E-06

5.02E-05

9.04E-05

1.19E-04

1.48E-05

1.55E-05

1.OOE-04

2.47E-06

9.05E-06

1.92E-05

3.76E-06

3.48E-05

1.45E-06

7.82E-06

6.03E-07

1.15E-05

3.46E-05

1.17E-04

1.37E-05

7.33E-07

2.85E-05

2.36E-05

3.02E-05

1.65E-05

5.02E-05

4.08E-05

7.26E-05

1.65E-05

4.22E-05

1.05E-05

5.33E-05

3.78E-05

9.22E-06

1.95E-05

1.74E-05

4.93E-05

1.88E-05

8.51 E-05

5.87E-06

3.15E-05

1.59E-05

2.53E-06

2.12E-07

1.42E-06

7.56E-07

37
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

1132

11 33+D

1134

1135+D

XE131M

XE133M

XE133

XE135M

XE1 35

XE137

XE138+D

CS134M+D

CS134

CS135

CS136

CS1 37+D

CS138

CS139+D

BA 139

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE141

CE143+D

CE144+D

PR143

PR144

ND147+D

PM147

PM148M+D

PM148

PM149

PM151

SM151

SM153

EU152

EU154

EU155

EU156

TB160

H0166M

W181

W185

W187

BONE

1.21 E-06

9.46E-06

6.58E-07

2.76E-06

0.

0.

0.

0.

0.

0.

0.

1.32E-07

2.83E-04

1.OOE-04

3.45E-05

3.92E-04

3.61 E-07

2.32E-07

1.06E-09

4.OOE-05

1.12E-10

2.84E- 11

3.61 E-07

4.85E-09

7.36E-10

1.98E-05

2.09E-07

2.28E-03

1.OOE-05

3.42E-1 1

5.67E-06

3.91 E-04

5.OOE-05

3.34E-06

3.10E-07

7.52E-08

3.38E-04

1.53E-07

7,83E-04

2.96E-03

5.97E-04

1.56E-05

1.12E-04

1.45E-03

4.86E-08

1,57E-06

9.26E-09

LIVER

2.53E-06

1.37E-05

1.34E-06

5.43E-06

0.

0.

0.

0.

0.

0.

0.

2.1 OE-07

5.02E-04

8.66E-05

9.61 E-05

4.37E-04

5.58E-07

3.03E-07

7.03E-13

4.OOE-08

7.70E-14

2.36E-14

1.43E-07

1.40E-09

2.69E-10

1.19E-05

1.38E-07

8.65E-04

3.74E-06

1.32E-11

5.81 E-06

3.07E-05

1.24E-05

4.82E-07

4.08E-08

1.10E-08

6.45E-05

1.18E-07

1.77E-04

3.46E-04

5.72E-05

9.59E-06

0.

3.07E-04

1.46E-08

4.83E-07

6.44E-09

TOTAL BODY

8.99E-07

4.OOE-06

4.75E-07

1.98E-06

0.

0.

0.

0.

0.

0.

0.

1.11E-07

5.32E-05

4.73E-06

3.78E-05

3.25E-05

2.84E-07

1.22E-07

3.07E-1 1

2.07E-06

3.55E-12

1.40E-12

3.68E-08

2.45E-10

6.46E-11

1.42E-06

1.58E-08

1.26E-04

4.99E-07

1.72E-12

3.57E-07

1.56E-05

9.94E-06

2,44E-07

1 .78E-08

5.55E-09

1.63E-05

9.06E-09

1.72E-04

2.45E-04

3.46E-05

1.54E-06

1.40E-05

2.51 E-04

1.67E-09

5.58E-08

2.23E-09

THYROID

1.21E-04

2.54E-03

3.18E-05

4.97E-04

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0..

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

KIDNEY

2.82E-06

1.60E-05

1.49E-06

6.05E-06

0.

0.

0.

0.

0.

0.

0.

8.50E-08

1.36E-04

2.58E-05

4.03E-05

1.23E-04

2.93E-07

1.65E-07

4.23E- 13

9.59E-09

4.64E-14

1.36E-14

0.

0.

0.

3.75E-06

4.03E-08

3.84E-04

1.41E-06

4.80E-12

2.25E-06

4.93E-05

1.45E-05

5.76E-07

4.96E-08

1.30E-08

5.24E-05

2.47E-08

5.94E-04

1.14E-03

1.58E-04

4.48E-06

3.20E-05

4.22E-04

0.

0.

0.

LUNG

0.

0.

0.

0.

6.77E-09

8.89E-09

7.41 E-09

8.05E-09

1.80E-08

8.30E-08

9.78E-08

2.OOE-08

5.69E-05

1.01E-05

8.40E-06

5.09E-05

4.67E-08

2.53E-08

4.25E-06

1.14E-03

2.12E-06

1.11E-06

1.20E-04

1.22E-05

5.87E-06

3.69E-04

8.30E-05

7.03E-03

3.09E-04

1.15E-06

2.30E-04

4.55E-04

1.22E-03

3.20E-04

6.50E-05

3.25E-05

2.98E-04

3.70E-05

1.48E-03

3.05E-03

5.20E-04

6.12E-04

1.11E-03

2.05E-03

1.33E-05

4.48E-04

2.83E-05

GI.LLI

1.36E-06

1.54E-06

9.21 E-07

1.31E-06

0.

0.

0.

0.

0.

0.

0.

1.16E-07

9.53E-07

2.18E-07

1.02E-06

9.53E-07

6.26E-07

1.33E-08

3.64E-05

2.74E-05

3.39E-06

4.95E-07

6.06E-05

5.96E-05

4.25E-05

1.54E-05

3.55E-05

1.06E-04

2.66E-05

3.06E-06

2.23E-05

5.75E-06

3.37E-05

6.04E-05

3.01 E-05

2.58E-05

3.46E-06

1.93E-05

9.88E-06

2.84E-05

5.19E-05

4.144E-05

2.14E-05

1.65E-05

2.63E-07

1.12E-05

2.54E-05

38
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

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

B1210+D 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-705

RN222+D 0. 0. 0. 0. 0. 9.88E-06 0.

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

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

RA225+D 2.57E-03 2.88E-06 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04

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

RA228+D 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+D 5.29E+00 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+00 5.27E-05

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

TH228+D 8.46E-01 1.10E-02 2.86E-02 0. 5.61E-02 4.65E+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+D 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+D 9.10E+00 3.00E-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+D 2.57E-01 0. 2.13E-02 0. 2.40E-02 1.49E+00 4.36E-05

U233+D 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+D 5.01E-02 0. 3.52E-03 0. 1.01E-02 3.28E-01 5.02E-05

U236 5.01 E-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+D 4.79E-02 0. 3.29E-03 0. 9.40E-03 3.06E-01 3.54E-05

NP237+D 3.03E+00 2.32E-01 1.26E-01 0. 7.69E-01 3.49E-01 5.10E-05

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

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

PU238 5.02E+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 6.71E-01 1.34E-01 0. 4.94E-01 8.47E-01 4.36E-05

PU241+D 1.55E-01 6.69E-03 3.11E-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 6.01E-05

AM243 1.82E+00 8.10E-01 1.27E-01 0. 7.72E-01 3.85E-01 5.60E-05

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

CM243 1.73E+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. 3.21E-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+D 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 1.10E+00 0. 4.24E+00 3.23E+00 9.43E-04

CF252 4.26E+00 0. 1.01E-01 0. 0. 1.37E+00 1.85E-04

39
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

H3*

BE10

C14

N13

F18

NA22

NA24

P32

AR39

AR41

CA41

SC46

CR51

MN54

MN56

FE55

FE59

C057

C058

C060

N(59

N163

N165

CU64

ZN65

ZN69M+D

ZN69

SE79

BR82

BR83+D

BR84

BR85

KR83M

KR85M

KR85

KR87

KR88+D

KR89

RB86

RB87

RB88

RB89+D

SR89+D

SR90+D

SR91+D

SR92+D

BONE

0.

8.43E-04

9.70E-06

2.33E-08

1.88E-06 "

4.41 E-05

4.35E-06

7.04E-04

0.

0.

7.06E-05

1.97E-04

0.

0.

0.

1.28E-05

5.59E-06

0.

0.

0.

1.66E-05

2.22E-04

8.08E-10

0.

1.15E-05

4.26E-09

1.81 E-11

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.62E-04

2.73E-02

3.28E-08

3.54E-09

LIVER

3.04E-07

9.83E-05

1.82E-06

2.33E-08

0.

4.41 E-05

4.35E-06

3.09E-05

0.

0.

0.

2.70E-04

0.

1.16E-05

4.48E-10

6.80E-06

9.04E-06

2.44E-07

4.79E-07

3.55E-06

4.67E-06

1.25E-05

7.99E-11

5.39E-10

3.06E-05

7.28E-09

2.61 E-11

1.23E-06

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

5.36E-05

3.16E-05

1.52E-07

9.33E-08

0.

0.

0.

0.

TOTAL BODY THYROID

3.04E-07 3.04E-07

2.12E-05 0.

1.82E-06 1.82E-06

2.33E-08 2.33E-08

1.85E-07 0.

4.41E-05 4.41E-05

4,35E-06 4.35E-06

2.67E-05 0.

0. 0.

0. 0.

7.70E-06 0.

1.04E-04 0.

4.17E-08 2.31E-08

2.57E-06 0.

8.43E-11 0.

2.1OE-06 0.

4.51E-06 0.

2.88E-07 0.

8.55E-07 0.

6.12E-06 0.

2.83E-06 0.

7.56E-06 0.

4.44E-11 0.

2.90E-10 0.

1.90E-05 0.

8.59E-10 0.

2.41E-12 0.

2.60E-07 0.

5.66E-06 0.

1.28E-07 0.

1.48E-07 0.

6.84E-09 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

3.09E-05 0.

1.37E-05 0.

9.90E-08 0.

7.83E-08 0.

4.66E-06 0.

1.74E-03 0.

1.24E-09 0.

1.42E-10 0.

KIDNEY

3.04E-07

0.

1.82E-06

2.33E-08

0.

4.41 E-05

4.35E-06

0.

0.

0.

0.

2.39E-04

6.57E-09

2.71E-06

4.52E-10

0.

0.

0.

0.

0.

0.

0.

0.

1.63E-09

1.93E-05

4.22E-09

1.58E-11

1.71 E-06

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

LUNG

3.04E-07

7.41 E-04

1.82E-06

2.33E-08

0.

4.41 E-05

4.35E-06

0.

4.89E-09

1.68E-08

7.21 E-02

0.

4.59E-06

4.26E-04

3.55E-06

3.OOE-05

3.43E-04

1.37E-04

2.99E-04

1.91E-03

2.73E-05

7.43E-05

2.21 E-06

2.59E-06

2.69E-04

7.36E-06

3.84E-07

1.49E-04

0.

0.

0.

0.

1.22E-09

6.58E-09

5.66E-09

3.38E-08

6.99E-08

4.55E-08

0.

0.

0.

0.

5.83E-04

3.99E-03

1.44E-05

6.49E-06

GI-LLI

3.04E-07

1.72E-05

1.82E-06

2.33E-08

3.37E-07

4.41 E-05

4.35E-06

1.14E-05

0.

0.

2.94E-07

2.45E-05

2.93E-07

6.19E-06

3.33E-05

7.75E-07

1.91 E-05

3.58E-06

9.29E-06

2.60E-05

6.29E-07

1.71E-06

2.27E-05

9.92E-06

4.41E-06

2.71 E-05

2.75E-06

3.43E-06

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

2.16E-06

2.96E-07

4.66E-09

5.11E-10

4.52E-05

9.28E-05

4.70E-05

6.55E-05

*Includes a 50% increase to account for percutaneous transpiration,

40
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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+D 1.37E-10 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-10 0. 0. 6.46E-06 6.46E-05

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

ZR93+D 2.07E-04 7.80E-05 5.55E-05 0. 3.00E-04 7.10E-04 1,47E-05

ZR95+D 5.13E-05 1.13E-05 1.00E-05 0. 1.61E-05 6.03E-04 1.65E-05

ZR97+D 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05

NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06

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

NB97 1.16E-10 2.08E-11 9.74E-12 0. 2.31E-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+D 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05

TC99M 4.81E-13 9.41 E-13 1.56E- 11 0. 1.37E-11 2.57E-07 1.30E-06

TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06

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

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

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

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

RH105 3,91E-09 2.1OE-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05

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

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

AG110M+D 4.56E-06 3,08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71 E-05

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

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

CD115M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05

SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 .4.05E-05

SN125+D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05

SN126+D 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 5.41E-06 3.41E-08 0. 8.76E-04 4.43E-05

SB125+D 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

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

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

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

TE129M+D 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

TE131M+D 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05

TE131+D 5.87E-12 2.28E-12. 1.78E-12 4.59E-12 1.59E-11 5.55E-07 3.60E-07

TE132+D 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05

TE133M+D 2.93E-11 1.51E-11 1.50E-11 2.32E-11 1.01E-10 1.60E-06 4.77E-06

TE134+D 1.53E-11 8.81 E-12 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+D 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07

41
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

I Revision 21

TABLE 1.7 (continued)

CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INHALED IN FIRST YR)

ISOTOPE

1132

1133+D

1134

1135+D

XE131M

XE133M

XE133

XE135M

XE135

XE137

XE138+D

CS134M+D

CS134

CS135

CS136

CS137+D

CS138

CS139+D

BA139

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE141

CE143+D

CE144+D

PR143

PR144

ND147+D

PM147

PM148M+D

PM148

PM149

PM151

SM151

SM153

EU152

EU154

EU155

EU156

TB160

HO166M

W181

W185

W187

BONE

5.72E-07

4.48E-06

3.17E-07

1.33E-06

0.

0.

0.

0.

0.

0.

0.

6.33E-08

1.76E-04

6.23E-05

1.76E-05

2,45E-04

1.71E-07

1.09E-07

4.98E-10

2.00E-05

5.29E-1 1

1.35E- 11

1.74E-07

2.28E-09

3.50E-10

1.06E-05

9.89E-08

1.83E-03

4.99E-06

1.61 E-11

2.92E-06

3.52E-04

3.31 E-05

1.61 E-06

1.47E-07

3.57E-08

3.14E-04

7.24E-08

7.42E-04

2.74E-03

5.60E-04

7.89E-06

7.79E-05

1.34E-03

2.66E-08

8.31 E-07

4.41 E-09

LIVER

1.1OE-06

5.49E-06

5.84E-07

2.36E-06

0.

0.

0.

0.

0.

0.

0.

8.92E-08

2.74E-04

4.13E-05

4.62E-05

2.23E-04

2.27E-07

1.15E-07

2.66E-13

1.75E-08

2.95E-14

9.73E-15

6.08E-08

5.31 E- 10

1.11 E- 10

5.28E-06

5.37E-08

5.72E-04

1.50E-06

4.99E-12

2.36E-06

2.52E-05

6.55E-06

1.94E-07

1.56E-08

4.33E-09

4.75E-05

4.51 E-08

1.37E-04

2.49E-04

4.05E-05

4.23E-06

0.

2.81 E-04

6.52E-09

2.08E-07

2.61 E-09

TOTAL BODY THYROID

5.07E-07 5.23E-05

2.08E-06 1.04E-03

2.69E-07 1.37E-05

1,12E-06 2.14E-04

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

0. 0.

6.12E-08 0.

6.07E-05 0.

4.45E-06 0.

3.14E-05 0.

3.47E-05 0.

1.50E-07 0.

5.80E-08 0.

1.45E-11 0.

1.17E-06 0.

1.72E-12 0.

7.54E-13 0.

2.04E-08 0.

1.15E-10 0.

3.49E-11 0.

7.83E-07 0.

7.77E-09 0.

9.77E-05 0.

2.47E-07 0.

8.10E-13 0.

1.84E-07 0.

1.36E-05 0.

6.55E-06 0.

1.25E-07 0.

8.45E-09 0.

2.82E-09 0.

1.49E-05 0.

4.35E-09 0.

1.61E-04 0.

2.27E-04 0.

3.18E-05 0.

8.75E-07 0.

9.67E-06 0.

2.37E-04 0.

8.99E-10 0.

2.91 E-08 0.

1.17E-09 0.

KIDNEY

1.69E-06

9.13E-06

8.92E-07

3.62E-06

0.

0.

0.

0.

0.

0.

0.

4.94E-08

8.93E-05

1.53E-05

2.58E-05

7.63E-05

1.68E-07

9.08E-08

2.33E-13

5.71E-09

2.56E-14

7.87E-15

0.

0.

0.

2.31 E-06

2.26E-08

3.17E-04

8.11E-07

2.64E- 12

1.30E-06

4.45E-05

9.74E-06

3,30E-07

2.75E-08

7.35E-09

4.89E-05

1.37E-08

5.73E-04

1.09E-03

1.51 E-04

2.72E-06

2.32E-05

4.01 E-04

0.

0.

0.

LUNG

0.

0.

0.

0.

3.30E-09

4.36E-09

3.66E-09

4.48E-09

9.09E-09

4.07E-08

5.17E-08

8.35E-09

3.27E-05

5.22E-06

3.93E-06

2.81 E-05

1.84E-08

9.36E-09

1.56E-06

4.71E-04

7.89E-07

4.44E-07

4.94E-05

4.48E-06

2.35E-06

1.47E-04

3.12E-05

3.23E-03

1.17E-04

4.23E-07

8.87E-05

2.20E-04

5.72E-04

1.24E-04

2.40E-05

1.24E-05

1.48E-04

1.37E-05

9.00E-04

1.66E-03

2.79E-04

2.54E-04

5.34E-04

1.13E-03

5,71E-06

1.86E-04

1. 11E-05

GI-LLI

8.65E-07

1.48E-06

2.58E-07

1.20E-06

0.

0.

0.

0.-

0.

0.

0.

7.92E-08

1.04E-06

2.17E-07

1.13E-06

9.78E-07

7.29E-08

7.23E-12

1.56E-05

2.75E-05

7.44E-08

7.41 E-10

6.10E-05

4.37E-05

2.05E-05

1.53E-05

3.44E-05

1.05E-04

2.63E-05

5.32E-08

2.22E-05

5.70E-06

3.58E-05

6.01 E-05

2.92E-05

2.50E-05

3.43E-06

1.87E-05

1.14E-05

2.98E-05

5.39E-05

4.24E-05

2.28E-05

1.63E-05

2.61E-07

1.11E-05

2.46E-05

42
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

CHILD INHALATION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INHALED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

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

B1210+D 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+D 0. 0. 0. 0. 0. 4.82E-06 0.,

RA223+D 7.69E-04 8.89E-07 1.54E-04 0. 2.36E-05 8.48E-02 3.OOE-04

RA224+D 8.44E-05 1.53E-07 1.69E-05 0. 4.06E-06 2.92E-02 3.34E-04

RA225+D 1.28E-03 1.14E-06 2.56E-04 0. 3.02E-05 9.74E-02 2.84E-04

RA226+D 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04

RA228+D 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+D 4.96E+00 8.05E-01 3.07E-01 0. 1.77E-01 8.04E-01 5.22E-05

TH227+D 9.24E-04 1.26E-05 2.67E-05 0. 6.67E-05 1.26E-01 3.49E-04

TH228+D 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+D 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 6.31E-04 7.32E-05

PA231 +D 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+D 2.19E-01 0. 1.56E-02 0. 1.67E-02 7.42E-01 4.33E-05

U233+D 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+D 4.27E-02 0. 2.59E-03 0. 7.01E-03 1.63E-01 4.98E-05

U236 4.27E-02 0. 2.65E-03 0. 7.16E-03 1.67E-01 3.67E-05

U237 1.57E-07 0. 4.17E-08 0. 4.53E-07 3.40E-05 1.29E-05

U238+D 4.09E-02 0. 2.42E-03 0. 6.55E-03 1.53E-01 3.51E-05

NP237+D 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+D 1.46E-01 6.33E-03 2.93E-03 0. 1.10E-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 7.10E-01 1.41E-01 0. 5.27E-01 6.30E-01 6.20E-05

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 2.10E-01 4.98E-05

CM244 1.33E+00 6.48E-01 8.31E-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+D 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

43
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y 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

BE10 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. 7.1OE-08 0. 0. 0. 3189E-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. 4.00E-09 0.

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

CA41 4.05E-05 0. 4.38E-06 0. 0. 1.01E-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-10 3.15E-11 0. 2.24F-10 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. 1.91 E-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-10 3.66E-11 1.59E-11 0. 0. 1.17E-06 4.59E-06

CU64 0. 2.54E-10 1.06E-10 0. 8.01E-10 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+D 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 8.71 E-08 0. 8.13E-07 7.71E-05 3.53E-06

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

BR83+D 0. 0. 4.30E-08 0. 0. 0. 0.

BR84 0. 0. 5.41E-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+D 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+D 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17

SR89+D 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05

SR90+D 1.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05

SR91+D 1.1OE-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05

SR92+D 1.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05

*Includes a 50% increase to account for percutaneous transpiration.

44
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC101

RU103+D

RU105+D

RU106+D

RH105

PD107

PD109

AG110M+D

AG111

CD113M

CD115M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+D

BONE

3,73E-07

4.63E-11

8.26E-05

1.84E-09

1.69E-08

6.83E-05

1.82E-05

1.72E-08

4.14E-05

2.32E-06

3.92E-11

0.

0.

1.73E-13

4.48E-08

7.40E-15

2.63E-07

1.40E-10

1.23E-05

1.32E-09

0.

0.

1.73E-06

6.07E-08

0.

0.

4.31 E-05

1.66E-06

2.18E-04

5.38E-06

9.23E-06

6.19E-07

4.64E-08

6.10E-07

2.25E-06

2.51E-10

1.74E-06

8.87E-12

1,23E-08

1.97E-12

4.50E-08

1.01E-11

5.31E-12

3.53E-06

7.80E-07

4.43E-06

LIVER

0.

0.

0.

0.

0.

3.38E-05

5.73E-06

3.40E-09

1.36E-05

1.29E-06

9.72E-12

1.66E-06

2.11E-08

4.83E-13

6.58E-08

1.05E-14

0.

0.

0.

9,48E-10

1.17E-07

6.56E-10

1.64E-06

2.52E-08

2,17E-04

3148E-05

9.44E-07

4.42E-08

5.39E-06

9.92E-08

1.01 E-07

1.27E-08

9.92E-10

2.80E-07

1.02E-06

1.14E-10

8.23E-07

4.22E-12

7.51 E-09

1.04E-12

3.63E-08

7.33E-12

4.35E-12

2.94E-06

2.24E-06

6.14E-06

TOTAL BODY

1 .OOE-08

1.77E-12

2.21 E-06

5.36E-1 1

4.65E-10

1.84E-05

3.94E-06

1.57E-09

3.41 E-06

7.08E-07

3.55E-12

4.52E-08

4.03E-09

6.24E-12

1.79E-08

1.03E-13

1.12E-07

5.42E-1 1

1.55E-06

6.24E-10

8.39E-09

1.66E-10

9.99E-07

1.26E-08

7.1OE-06

1.14E-06

1.40E-06

9.99E-08

8.24E-06

2.1OE-06

2.15E-06

2.23E-07

1.75E-08

8.34E-08

2.73E-07

5.52E-1 1

2.81E-07

2.20E-12

5.03E-09

6.30E-1 3

2.74E-08

5.71E-12

3.64E-1 2

4.90E-06

8&96E-07

3.30E-06

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

7.55E-07

3.45E-08

1.42E-06

1.22E-08

8.80E-09

3.50E-09

5.21 E-10

1,75E-07

5.48E-07

1.77E-10

5.72E-07

6.48E-12

9.06E-09

1.55E-12

3.07E-08

8.18E-12

4.46E-12

3.66E-03

1.86E-04

1.83E-03

KIDNEY

0.

0.

0.

0.

0.

1.16E-04

8.42E-06

5.15E-09

1.59E-05

1.25E-06

1.14E-11

5.06E-07

5.14E-08

7.20E-12

8.35E-07

1.90E-13

9.29E-07

1.76E-10

2.38E-05

4.04E-09

9.39E-07

3.36E-09

3.13E-06

8.17E-08

2.43E-04

2.82E-05

0.

0.

0.

0.

0.

0.

0.

0.

8.17E-06

9.10E-10

6.49E-06

3.32E-11

5.49E-08

7.72E-12

2.44E-07

5.07E-11

2,91E-11

5.26E-06

3.44E-06

1.05E-05

LUNG

3.66E-05

4.OOE-07

3.67E-04

3.35E-06

1.04E-05

3.67E-04

3.36E-04

1.62E-05

5.36E-05

9.39E-05

4.91 E-07

8.81 E-05

1.92E-05

1.44E-07

1.74E-04

8.34E-08

9.79E-05

2.27E-06

2.01 E-03

4.09E-06

1.63E-05

3.19E-06

8.44E-04

4.OOE-05

3.59E-04

3.03E-04

4.96E-04

1.26E-04

1.72E-03

4.81E-04

3.42E-04

1.55E-04

3.31 E-05

6.70E-05

2.07E-04

1.40E-06

2.47E-04

4.12E-07

2.97E-05

2.92E-07

5.61 E-05

8.71E-07

6.75E-07

0.

0.

0.

GI-LLI

6,99E-05

3.77E-09

5.11E-05

2.06E-05

7.24E-05

1.60E-05

1.86E-05

7.88E-05

2.52E-06

1.21E-05

2.71 E-07

3.99E-06

3.36E-05

7.66E-07

7.99E-06

1.09E-16

1.36E-05

1.13E-05

1.20E-04

1.23E-05

7.49E-07

1.96E-05

3.41 E-05

3.OOE-05

1.68E-05

5.1 OE-05

4.16E-05

7.29E-05

1.68E-05

4.98E-05

1.24E-05

6.01 E-05

3.94E-05

9.38E-06

1.99E-05

1.01 E-05

5.06E-05

2.02E-07

7.76E-05

1.89E-09

5.79E-05

1.23E-07

1.37E-09

2.29E-07

1.14E-06

8.11E-07

45
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

1132

1133+D

1134

1135+D

XE131M

XE133M

XE133

XE135M

XE135

XE137

XE138+D

CS134M+D

CS134

CS135

CS136

CS137+D

CS138

CS139+D

BA139

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE 141

CE143+D

CE144+D

PR143

PR144

ND147+D

PM147

PM148M+D

PM148

PM149

PM151

SM151

SM153

EU152

EU154

EU155

EU156

TB160

HO166M

W181

W185

W187

BONE

1.99E-07

1.52E-06

1.11E-07

4.62E-07

0.

0.

0.

0.

0.

0.

0.

2.20E-08

6.28E-05

2.08E-05

6.44E-06

8.38E-05

5.82E-08

3.65E-08

1.67E-1,0

6.84E-06

1.78E- 11

4.62E-12

5.99E-08

7.63E-10

1.20E-10

3.55E-06

3.32E-08

6.11E-04

1.67E-06

5.37E-12

9.83E-07

1.15E-04

1.32E-05

5.44E-07

4.91 E-08

1.20E-08

1.07E-04

2.43E-08

2.96E-04

9.43E-04

2.OOE-04

2.70E-06

3.04E-05

4.40E-04

8.90E-09

2.78E-07

1.50E-09

LIVER

5.47E-07

2.56E-06

2.90E-07

1.18E-06

0.

0.

0.

0.

0.

0.

0.

4.35E-08

1.41 E-04

1.82E-05

2.42E-05

1.06E-04

1.07E-07

5.12E-08

1.18E-13

8.38E-09

1.32E-14

4,63E-15

2.95E-08

2.35E-10

5.31 E-11

2.37E-06

2.42E-08

2.53E-04

6.64E-07

2.20E-12

1.07E-06

1.1OE-05

3.35E-06

8.88E-08

6.89E-09

1.99E-09

2.10E-05

2.01E-08

7.19E-05

1.23E-04

1.96E-05

2.03E-06

0.

1.36E-04

2.88E-09

9.17E-08

1.22E-09

TOTAL BODY

1.97E-07

7.78E-07

1.05E-07

4.36E-07

0.

0.

0.

0.

0.

0.

0.

2.35E-08

6.86E-05

4.47E-06

1.71 E-05

3.89E-05

5.58E-08

1.97E-08

4.87E-12

4.40E-07

5.93E-13

2.84E-13

7.82E-09

3.87E-1 1

1.32E- 11

2.71E-07

2.70E-09

3.28E-05

8.28E-08

2.72E-13

6.41 E-08

4.50E-06

2.62E-06

4.48E-08

2.84E-09

1.01E-09

4.86E-06

1.47E-09

6.30E-05

8.60E-05

1.21 E-05

3.30E-07

3.79E-06

9.87E-05

3.01E-10

9.73E-09

4.29E-10

THYROID

1.89E-05

3.65E-04

4.94E-06

7.76E-05

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

KIDNEY

8.65E-07

4.49E-06

4.58E-07

1.86E-06

0.

0.

0.

0.

0.

0.

0.

2.54E-08

4.69E-05

7.30E-06

1.38E-05

3.80E-05

8.28E-08

4.34E-08

1.11E-13

2.85E-09

1.23E-14

3.92E-15

0.

0.

0.

1.11E-06

1.08E-08

1.51 E-04

3.86E-07

1,26E-12

6.28E-07

2.10E-05

5.07E-06

1.60E-07

1.31E-08

3.57E-09

2.27E-05

6.56E-09

3.34E-04

5.44E-04

7.65E-05

1.36E-06

1.20E-05

2.OOE-04

0.

0.

0.

LUNG

0.

0.

0.

0.

2.70E-09

3.59E-09

2.99E-09

3.88E-09

7.55E-09

3.33E-08

4.38E-08

4.56E-09

1.83E-05

2.70E-06

2.22E-06

1.51E-05

9.84E-09

4.86E-09

8.08E-07

2.54E-04

4.11E-07

2.39E-07

2.68E-05

2.31 E-06

1.27E-06

7.67E-05

1.63E-05

1.67E-03

6.04E-05

2.19E-07

4.65E-05

1.14E-04

3.20E-04

6.52E-05

1.24E-05

6.56E-06

7.68E-05

7.11E-06

5.01E-04

9.12E-04

1.51 E-03

1,37E-04

2.97E-04

6.24E-04

2.95E-06

9.60E-05

5.92E-06

GI-LLI

1.59E-07

1.29E-06

2.55E-09

B.69E-07

0.

0.

0.

0.

0.

0.

0.

2.02E-08

1.22E-06

2.23E-07

1.36E-06

1.06E-06

3.38E-1 1

1.66E-23

8.06E-07

2.86E-05

9.33E-14

5.99E-20

6.09E-05

1.54E-05

1.50E-06

1.58E-05

3.19E-05

1.08E-04

2.67E-05

2.94E-14

2.28E-05

5.87E-06

4.1 OE-05

6.14E-05

2.79E-05

2.27E-05

3.53E-06

1.77E-05

1.35E-05

3.34E-05

5.97E-05

4.56E-05

2.60E-05

1.68E-05

2.69E-07

1.14E-05

2.21E-05

46
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB210+D 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05

B1210+D 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+D 0. 0. 0, 0. 0. 3.94E-06 0.

RA223+D 2.57E-04 3.93E-07 5.14E-05 0. 1.12E-05 4,39E-02 3.04E-04

RA224+D 2.83E-05 6.77E-08 5.65E-06 0. 1.93E-06 1.51E-02 3.29E-04

RA225+D 4.28E-04 5.04E-07 8.56E-05 0. 1.44E-05 5.04E-02 2.89E-04

RA226+D 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.11E-04

RA228+D 5,34E-02 1.74E-06 5.88E-02 0. 4.97E-05 2.78E-01 5.30E-05

AC225 6.04E-04 8.25E-04 4.06E-05 0. 9.47E-05 3.81E-02 2.70E-04

AC227+D 2.49E+00 3.69E-01 1.48E-01 0. 1.07E-01 4.16E-01 5.38E-05

TH227+D 3.09E-04 5.56E-06 8.93E-06 0. 3.18E-05 6.50E-02 3.57E-04

TH228+D 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

TH230 2.34E+00 1.34E-01 6.49E-02 0. 6.55E-01 8.98E-01 3.95E-05

TH232+D 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+D 5.32E+00 2.00E-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.OE-05

U232+D 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05

U233+D 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+D 1.42E-02 0. 8.67E-04 0. 3.34E-03 8.44E-02 5.13E-05

U236 1.42E-02 0. 8.86E-04 0. 3.41E-03 8.62E-02 3.79E-05

U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05

U238+D 1.36E-02 0. 8.1OE-04 0. 3.12E-03, 7.89E-02 3.62E-05

NP237+D 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. 3.10E-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+D 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. 3.31E-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 7.10E-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 9.91E-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 5.00E-02 0. 2.34E-01 1.09E-01 5.13E-05

CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81E-01 1.05E-01 4.96E-05

CM245 1,32E+00 4.11E-01 7.53E-02 0. 3.52E-01 1.01E-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+D 1.28E+00 4.04E-01 7.41E-02 0. 3.46E-01 1.01E-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

47
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

ADULT INHALATION DOSE COMMITMENT FACTORS (MREM/50Y 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

BE10 1.98E-04 3.06E-05 4.96E-06 0. 0. 2.22E-04 1.67E-05

C14 2.27E-06 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07 4.26E-07

N13 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6.27E-09 6,27E-09 6.27E-09

F18 4.71E-07 0. 5.19E-08 0. 0. 0. 9.24E-09

NA22 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05 1.30E-05

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

P32 1.65E-04 9.64E-06 6.26E-06 0. 0. 0. 1.08E-05

AR39 0. 0. 0. 0. 0. 2.08E-09 0.

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

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

SC46 5.51E-05 1.07E-04 3.11E-05 0. 9.99E-05 0. 3.23E-05

CR51 0. 0. 1.25E-08 7.44E-09 2.85E-09 1.80E-06 4.15E-07

MN54 0. 4.95E-06 7.87E-07 0. 1.23E-06 1.75E-04 9.67E-06

MN56 0. 1.55E-10 2.29E-11 0. 1.63E-10 1.18E-06 2.53E-06

FE55 3.07E-06 2.12E-06 4.93E-07 0. 0. 9.01E-06 7.54E-07

FE59 1.47E-06 3.47E-06 1.32E-06 0. 0. 1.27E-04 2.35E-05

C057 0. 8.65E-08 8.39E-08 0. 0. 4.62E-05 3.93E-06

C058 0. 1.98E-07 2.59E-07 0. 0. 1.16E-04 1.33E-05

C060 0. 1.44E-06 1.85E-06 0. 0. 7.46E-04 3.56E-05

N159 4.06E-06 1.46E-06 6.77E-07 0. 0. 8.20E-06 6.11E-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. 7.00E-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+D 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+D 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+D 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 3.21 E-06 0. 0. 0. 2.88E-07

RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19

RB89+D 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21

SR89+D 3.80E-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05

SR90+D 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05

SR91+D 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05

SR92+D 8.43E-10 0. 3.64E-11 0. 0. 2.06E-06 5.38E-06

*Includes a 50% increase to account for percutaneous transpiration.

48
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

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

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

Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81E-05

Y92 1.29E-09 0. 3.77E-11 0. 0. 1.96E-06 9.19E-06

Y93 1.18E-08 0. 3.26E-10 0. 0. 6.06E-06 5.27E-05

ZR93+D 5.22E-05 2.92E-06 1.37E-06 0. 1.11E-05 2.13E-05 1.51E-06

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

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

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

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

M099+D 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

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

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

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

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

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

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

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

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

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

CD113M 0. 1,54E-04 4.97E-06 0. 1.71E-04 2.08E-04 1.59E-05

CD115M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.80E-05

SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05

SN125+D 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81E-05

SN126+D 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. 3.1OE-04 5.08E-05

SB125+D 6.67E-06 7.44E-08 1.58E-06 6.75E-09 0. 2.18E-04 1.26E-05

SB126 4.50E-07 9.13E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.01E-05

SB127 3.30E-08 7.22E-10 1,27E-08 3.97E-10 0. 2.05E-05 3.77E-05

TE125M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06

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

TE127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8.14E-07 7.17E-06

TE129M+D 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+D 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05

TE131+D 1.39E-12 7.44E-13 4.49E-13 1.17E-12 5.46E-12 1.74E-07 2.30E-09

TE132+D 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05

TE133M+D 7.24E-12 5.40E-12 4.17E-12 6.27E-12 3.74E-11 5.51E-07 5.49E-08

TE134+D 3.84E-12 3.22E-12 1.57E-12 3.44E-12 2.18E-11 4.343-07 2.97E-11

1129 2.48E-06 2.11E-06 6.91E-06 5.54E-03 4.53E-06 0. 2.22E-07

1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0. 9.61E-07

1131+D 3.15E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 7.85E-07

49
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE

1132

1133+D

1134

1135+D

XE131M

XE133M

XE133

XE135M

XE 135

XE137

XE138+D

CS134M+D

CS134

CS135

CS136

CS137+D

CS138

CS139+D

BA139

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE141

CE143+D

CE144+D

PR143

PR144

ND147+D

PM147

PM148M+D

PM148

PM 149

PM 151

SM151

SM153

EU152

EU154

EU155

EU156

TB 160

H0166M

W181

W185

W187

BONE

1.45E-07

1.08E-06

8.05E-08

3.35E-07

0.

0.

0.

0.

0.

0.

0.

1.59E-08

4.66E-05

1.46E-05

4.88E-06

5.98E-05

4.14E-08

2.56E-08

1.17E-10

4.88E-06

1.25E-11

3.29E-12

4.30E-08

5.34E-10

8.54E-1 1

2.49E-06

2.33E-08

4.29E-04

1.1 7E-06

3.76E-12

6.59E-07

8.37E-05

9.82E-06

3.84E-07

3.44E-08

8.50E-09

8.59E-05

1.70E-08

2.38E-04

7.40E-04

1.01E-04

1.93E-06

2.21 E-05

3.37E-04

6.23E-09

1,95E-07

1.06E-09

LIVER

4.07E-07

1.85E-06

2.16E-07

8.73E-07

0.

0.

0.

0.

0.

0.

0.

3.20E-08

1.06E-04

1.29E-05

1.83E-05

7.76E-05

7.76E-08

3.63E-08

8.32E-14

6.13E-09

9.41E-15

3.38E-15

2.17E-08

1.66E-10

3.88E- 11

1.69E-06

1. 72E-08

1 ,79E-04

4.69E-07

1.56E-12

7.62E-07

7.87E-06

2.54E-06

6.37E-08

4.87E-09

1.42E-09

1.48E-05

1.42E-08

5.41 E-05

9.1OE-05

1.43E-05

1.48E-06

0.

1.05E-04

2.03E-09

6.47E-08

8.85E-10

TOTAL BODY

1.45E-07

5.65E-07

7.69E-08

3.21 E-07

0.

0.

0.

0.

0.

0.

0.

1.72E-08

9.1OE-05

5.99E-06

1.38E-05

5.35E-05

4.05E-08

1.39E-08

3.42E-12

3.21 E-07

4.20E-13

2.07E-13

5.73E-09

2.71 E-11

9.65E-12

1.91 E-07

1.91 E-09

2.30E-05

5.80E-08

1.91E-13

4.56E-08

3.19E-06

1.94E-06

3.20E-08

1.99E-09

7221E-10

3.55E-06

1.04E-09

4.76E-05

6.48E-05

9.21 E-06

2.40E-07

2.75E-06

8.00E-05

2.17E-10

6.81 E-09

3.10E-10

THYROID

1.43E-05

2.69E-04

3.73E-06

5.60E-05

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

KIDNEY

6.48E-07

3.23E-06

3.44E-07

1.39E-06

0.

0.

0.

0.

0.

0.

0.

1.83E-08

3.59E-05

5.11E-06

1,07E-05

2.78E-05

6.00E-08

3.05E-08

7.78E-14

2.09E-09

8.75E-15

2.86E-15

0.

0.

0.

7.83E-07

7.60E-09

1.06E-04

2.70E-07

8.81 E- 13

4.45E-07

1.49E-05

3.85E-06

1.20E-07

9.19E-09

2.55E-09

1.66E-05

4.59E-09

3.35E-04

4.36E-04

6.59E-05

9.95E-07

9.10E-06

1.57E-04

0.

0.

0.

LUNG

0.

0.

0.

0.

1.40E-09

1.89E-09

1.57E-09

2.22E-09

4.05E-09

1.74E-08

2.44E-08

2.93E-09

1.22E-05

1.57E-06

1.50E-06

9.40E-06

6.07E-09

2.84E-09

4.70E-07

1.59E-04

2.42E-07

1.49E-07

1.70E-05

1.35E-06

7.91 E-07

4.52E-05

9.97E-06

9.72E-04

3.51 E-05

1.27E-07

2.76E-05

6.60E-05

2.14E-04

3.91 E-05

7.21E-06

3.94E-06

4.45E-05

4.14E-06

3.43E-04

5.84E-04

9.46E-05

8.56E-05

1.92E-04

3.94E-04

1.71E-06

5.57E-05

3.63E-06

GI-LLI

5.08E-08

1.11E-06

1.26E-10

6.56E-07

0.

0.

0.

0.

0.

0.

0.

7.92E-09

1.30E-06

2.11E-07

1.46E-06

1.05E-06

2.33E-13

5.49E-31

1.12E-07

2.73E-05

1.45E-17

1.96E-26

5.73E-05

7.31 E-06

2.64E-07

1.50E-05

2.83E-05

1.02E-04

2.50E-05

2.69E-18

2.16E-05

5.54E-06

4.18E-05

5.80E-05

2.50E-05

2.OOE-05

3.25E-06

1.58E-05

1.59E-05

3.40E-05

5.95E-06

4.50E-05

2.68E-05

1.59E-05

2.53E-07

1.07E-05

1.94E-05

50
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O+D 2.64E-02 6.73E-03 8.37E-04 0. 2.12E-02 2.62E-02 3.65E-05

B1210+D 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+D 0. 0, 0. 0. 0. 2.05E-06 0.

RA223+D 1.80E-04 2.77E-07 3.60E-05 0. 7.85E-06 2.55E-02 2.84E-04

RA224+D 1.98E-05 4.78E-08 3.96E-06 0. 1.35E-06 8.77E-03 3.01E-04

RA225+D 3.00E-04 3.56E-07 5.99E-05 0. 1.01E-05 2.92E-02 2.71E-04

RA226+D 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04

RA228+D 4.41E-02 1.23E-06 4.78E-02 0. 3.48E-05 1.61E-01 5.00E-05

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

AC227+D 2.30E+00 3.05E-01 1.36E-01 0. 9.82E-02 2.41E-01 5.08E-05

TH227+D 2.17E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04

TH226+D 2.OOE-01 3.39E-03 6.77E-03 0. 1.89E-02 1.01E+00 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 6.21 E-01 3.73E-05

TH232+D 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+D 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+D 5.14E-02 0. 3.66E-03 0. 5.56E-03 2.22E-01 , 4.21E-05

U233+D 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+D 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+D 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41E-05

NP237+D 1.69E+00 1.47E-01 6.87E-02 0. 5.10E-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+D 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 1.01E+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. 5.01E-01 2.44E-02 5.79E-05

AM243 1.01E+00 3.47E-01 6.57E-02 0. 4.95E-01 5.75E-02 5.40E-05

CM242 1.48E-02 1.51E-02 9.84E-04 0. 4.48E-03 3,92E-02 4.91E-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 3.51E-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+D 1.22E+00 3.53E-01 7.03E-02 0. 3.28E-01 5.85E-02 5.63E-05

CM248 1.01E+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

51
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.8

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG!)

(MREM/HR PER PCI/MI)

ELEMENT TOTAL BODY SKIN

H-3

C-14

Na-24

P-32

Cr-51

Mn-54

Mn-56

Fe-55

Fe-59

Co-58

Co-60

Ni-63

Ni-65

Cu-64

Zn-65

Zn-69

Br-83

Br-84

Br-85

Rb-86

Rb-88

Rb-89

Sr-89

Sr-91

Sr-92

Y-90

Y-91m

Y-91

Y-92

Y-93

Zr-95

Zr-97

Nb-95

Mo-99

Tc-99m

Tc-101

0.0

0.0

2.50E-08

0.0

2.20E-10

5.80E-09

1.10E-08

0.0

8.OOE-09

7.OOE-09

1.70E-08

0.0

3.70E-09

1.50E-09

4.OOE-09

0.0

6.40E-1 1

1.20E-08

0.0

6.30E-10

3.50E-09

1.50E-08

5.60E-13

7.1OE-09

9.OOE-09

2.20E-12

3.80E-09

2.40E-1 1

1.60E-09

5.70E-10

5.OOE-09

5.50E-09

5.1OE-09

1.90E-09

9.60E-10

2.70E-09

0.0

0.0

2.90E-08

0.0

2.60E-1 0

6.80E-09

1.30E-08

0.0

9.40E-09

8.20E-09

2.OOE-08

0.0

4.30E-09

.1.70E-09

4.60E-09

0.0

9.30E-1 1

1.40E-08

0.0

7.20E-10

4.0OE-09

1.80E-08

6.50E-13

8.30E-09

1.OOE-08

2.60E-12

4.40E-09

2.70E-1 1

1.90E-09

7.80E-10

5.80E-09

6.40E-09

6.OOE-09

2.20E-09

1.1OE-09

3.OOE-09

52
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 1.8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFG1 )

(MREM/HR PER PCI/M')

Fl IFMFNT TOTAl BODY SKIN

ELE ENT

Ru-103

Ru- 105

Ru-1 06

Ag-I1 Om

Te-125m

Te-127m

Te-127

Te-129m

Te-129

Te-131 m

Te-131

Te-132

1-130

1-131

1-132

1-133

1-134

1-135

Cs-134

Cs-1 36

Cs-137

Cs-1 38

Ba-139

Ba-140

Ba-141

Ba-142

La-140

La-142

Ce-141

Ce-143

Ce-144

Pr-143

Pr-144

Nd-147

W-187

Np-239

3.60E-09

4.50E-09

1.50E-09

1.80E-08

3.50E-1 I

1.10E-12

1.00E- 11

7.70E-10

7.10E-10

8.40E-09

2.20E-09

1.70E-09

1.40E-08

2.80E-09

1.70E-08

3.70E-09

1.60E-08

1.20E-08

1.20E-08

1.50E-08

4.20E-09

2.1 OE-08

2.40E-09

2.1 OE-09

4.30E-09

7.90E-09

1.50E-08

1.50E-08

5.50E-10

2.20E-09

3.20E-10

0.0

2.OOE-10

1.OOE-09

3.1 OE-09

9.50E-10

4.20E-09

5.10E-09

1.80E-09

2.1 OE-08

4.80E-1I

1.30E-12

1.10E-11

9.OOE-10

8.40E-1 0

9.90E-09

2.60E-06

2.OOE-09

1.70E-08

3.40E-09

2.OOE-08

4.50E-09

1.90E-08

1.40E-08

1.40E-08

1.70E-08

4.90E-09

2.40E-08

2.70E-09

2.40E-09

4.90E-09

9.00E-09

1.70E-08

1.80E-08

6.20E-1 0

2.50E-09

3.70E-10

0.0

2.30E-10

1.20E-09

3.60E-09

1.10E-09

I,

I

53
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

Table 1.9

Palisades Annual Gaseous

Design Basis Quantities

Nuclide

AR 41

KR 85

KR 85M

XE131M

XE133

XE133M

XE135

H3

MN 54

FE 59

CO 58

CO 60

NI 65

ZN 65

SR89

SR90

NB 95

AG110M

SB125

1131

1132

1133

1135

CS137

CE141

PU238

PU239

PU241

AM241

CM242

CM244

Dose Factor

(mrem/Ci)

2.55E-04

1.07E-05

3.38E-05

4.24E-05

8.48E-06

8.51 E-05

5.22E-05

3.42E-05

3.03E-01

1.88E-01

8.31 E-02

5.09E+00

3.23E-03

3.54E-01

5.64E+00

1.98E+02

1.OOE-01

7.51 E-01

5.01E-01

1.11E+01

7.76E-03

1.52E-01

3.14E-02

3.60E+00

1.10E-01

4.53E+02

5.22E+02

1.13E+01

5.34E+02

2.04E+01

2.77E+02

DBQ

(Ci)

1.96E+04

1.87E+05

1.48E+05

4.72E+05

5.90E+05

2.35E+05

9.58E+04

4.39E+05

4.95E+01

7.99E+01

1.81E+02

2.95E+00

4.65E+03

4.23E+01

2.66E+00

7.56E-02

1.49E+02

2.OOE+01

2.99E+01

1.35E+00

1.93E+03

9.85E+01

4.77E+02

4.17E+00

1.37E+02

3.31 E-02

2.87E-02

1.33E+00

2.81E-02

7.35E-01

5.42E-02

Age Group, Organ

T Body

Site Boundary Beta DR

T Body

Site Boundary Beta DR

T Body

Site Boundary Beta DR

T Body

Child T. Body

Skin

Teen GILLI

Skin

Skin

Child GILLI

Child Liver

Child Bone

Child Bone

Teen GILLI

Skin

Skin

Child Thyroid

Child Thyroid

Child Thyroid

Child Thyroid

Chiild Bone

Teen GILLI

Teen Bone

Teen Bone

Teen Bone

Teen Bone

Teen Lung

Teen Bone

'0

54
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

LIQUID EFFLUENTS

A. CONCENTRATION

1. Requirements

Appendix A, Section 111.G requires that the concentration of radioactive

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

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

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

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

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

approach will be used for each release.

2. Prerelease Analysis

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

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

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

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

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

data, may be used to determine appropriate recirculation time.

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

concentration of each radionuclide determined.

n

C = Ci, (2.1)

i=1

where:

C Total concentration in the liquid effluent at the release

point, iCi/ml.

C Concentration of a single radionuclide i, ýiCi/ml.

55
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

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

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

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

.C,

R - _<10.0 (2.2) iECI

where:

C = Effluent concentration of radionuclide i, 1iCi/ml.

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

Column 2 - gCi/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:

f1(Ri - 1) + f2(R2 - 1) +'f3 (R3 -1) _ F (2.3)

where:

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

releases, determined by Plant personnel.

R1,R2,R3 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 bi is a conservative factor

greater than 1.0.

56
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

B. INSTRUMENT SETPOINTS

1. Setpoint Determination

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

monitor will be established using Plant instructions to ensure the

requirements of Appendix A, Section III.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 analysis requirements

of Appendix A, Table D-1. In the event that a compositor is not operational,

effluent releases via this pathway may continue provided that grab samples

are collected and analyzed for gross beta or gamma radioactivity at least

once per 24 hours per Appendix A, Table C-1, Action 3.

57
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

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 (C1 ), 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

1. RETS Requirement

Appendix A, Section III.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.

58
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

2. Release Analysis

Calculations shall be performed for each batch release, and weekly for

continuous releases according to the formula:

.A •Ic,0.5 (2.5)

where:

A1 = Cumulative quarterly activity of nuclide i identified in liquid

release (CQ).

Ci = Design basis quantity of radionuclide i from Table 2.2. I?

The design basis quantities are derived in such a conservative manner that

doses may be greatly overestimated by this technique. As a consequence of

this conservatism, and in light of historically consistent operations with

releases well below annual design basis quantities, the Appendix A, effluent

requirements do not require monthly dose projections. Instead, if at any time,

calculations by Equation (2.5) results in values greater than 0.5 for a given

quarter or 1.0 for year-to-date, the NRC LADTAP code will be run to ensure

that Appendix A, Section III.H.1 has been met.

Values for the design basis quantities (Ci), and the dose per Curie (Dc/Cc)i for

each nuclide i shown in Table 2.2, were calculated as follows in Sections 2.1

and 2.2.

a. Water Ingestion

The dose to an individual from ingestion of radioactivity from any

source as described by the following equation:

Di Y- (DCF~jxli (2,6)

where:

Dj = Dose for the jth organ from radionuclides releases,

mrem.

j = The organ of interest.

59
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

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

the ith radionuclide mrem/pCi, see Table 2.1.

i = Activity ingested of the ith radionuclide, pCi.

I is described by:

(Ai)(V)( 3 6 5 )( 1E0 6 ) (2.7)

(1 060)(d)

where:

365 = Days per year.

Ai = Annual activity released of ith radionuclide, jiCi.

V = Average rate of water consumption (2000 mild - adult,

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

358).

d = Dilution water flow for year, ml.

1000 = Dispersion factor from discharge to nearest drinking

water supply.

1 E06 = Conversion ýtCi to pCi.

The dose equation then becomes:

= (3.65E05)(V) Y (DCF)ij x Aimrem (2.8) i=1

60
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

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

(Ii) is described by:

AiBiF(1E09) _ pci (2.9)

15d

where:

Ai = Annual released of ith radionuclide, IaCi.

Bi = Fish concentration factor of ith radionuclide pCi/gm

pCi/ml

(see Table 2.0).

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.

1 E09 = Conversion of VCi and Kgm to gross.

Substitution of Equation 2.9 into Equation 2.6 gives:

(6.7E07)F E AixBixDCFimrem (2.10) i=1

61
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

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 jt organ from m

radionuclides, Dj, is described by:

m

Dj Y- Di, mrem (2.11)

i=1

m

Z (DCF) xIjmrem

i=1

where:

Dj = Dose to the jth organ from the ith radionuclide, mrem.

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

kidney, lung, or total body).

(DCF)ij = Adult ingestion dose commitment factor for the jth organ

from the ith radionuclide, mrem/pCi (see Table 2.1).

li = Activity ingested of the ith radionuclide, jiCi.

I• for water ingestion is described by:

A. Vr (2.13)

and for fish ingestion I is described by:

li= AiBiFr /ICi

vd

62
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

where:

A = Activity release of jth radionuclide during the year, pCi.

V = Average rate of water consumption (2000 mi/d).

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

v = Dispersion factor from point of discharge to point of

exposure.

d = Dilution water volume (ml).

Bi = Fish concentration factor of the ith radionuclide,

'U Cilgm

Table 2.0, pCi/ml

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

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT

The Palisades liquid radwaste system is designed to reduce the radioactive

materials in liquid wastes prior to their discharge (by recycle or shipment for

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

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

cumulative fraction if allowable release for each batch release and weekly for

continuous releases assures compliance with this requirement. In addition, 13 years

of operating experience (to the date this ODCM was first adopted) has shown that

design basis quantities never have been exceeded.

63
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

E. RELEASE RATE FOR OFFSITE EC (50 MREM/YR)

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

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

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

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

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

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

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

achievable requirement.

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

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

The nominal average source term used is given in Table 1.1. Dose to the most

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

This is only 0.13% of the more conservative 50 mrem/yr total body value.

64
-J

z 

<

w-J

0~0

LIWW

~00

LiL 0

C.,' c

'-I

I I

C.,'

0)1

I..

LL*1 *.0"

U, z

UtL
PALISADES RADWASTE EFFLUENTS - LIQUID

W'AAST{

-1

z

Lii

w

T

a.:

z

z

0,

0

0

,0

I--

U0

I f- A r . 1)

WASTE

TANKIS 01

TRIP & FLOW CONTROL cJ

04

U,

0,

C14

IL

114SCEI I ANFOFIS WASTE SYSTFM

(VIlIN Y WAS[()

I AIMJ9PY UTILITY SYlIFM WATER

STORAGE

TANK

1593 IIF 11 1 i V WAST I It AFIK

LAKE

SERVICE WATER
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.0

BIOACCUMULATION FACTORS

utCi/qm per itCi/ml

FRESHWATER

ELEMENT FISH

H

C

NA

P

CR

MN

FE

CO

NI

CU

ZN

BR

RB

SR

Y

ZR

NB

MO

TC

RU

RH

TEI

CS

BA

LA

CE

PR

ND

W

NP

9.OE-01

4.6E 03

1.OE 02

1.OE 05

2.OE 02

4.OE 02

1.OE 02

5.OE 01

1.0E 02

5.OE 01

2.OE 03

4.2E 02

2.OE 03

3.OE 01

2.5E 01

3.3E 00

3.OE 04

1.OE 01

1.5E 01

1.OE 01

1.OE 01

4.OE 02

1.5E 01

2.OE 03

4.OE 00

2.5E 01

1.OE 00

2.5E 01

2.5E 01

1.2E 03

1.OE 01

67
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

H3 0. 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.08E-07 3.083-07

BE10 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 1.01E-05 1.01E-05 1.01E-05 1.01E-05 1,01E-05 1.01E-05 1.01E-05

P32 1.70E-03 1.00E-04 6.59E-05 0. 0. 0. 2.30E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA41 3.74E-04 0. 4.08E-05 0. 0. 0. 1.91E-07

SC46 3.75E-08 5.41E-08 1.69E-08 0. 3.56E-08 0. 3.53E-05

CR51 0. 0. 1.41E-08 9.20E-09 2.01E-09 1.79E-08 4.11E-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

N163 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+D 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. 2.10E-05 3.90E-06 0. 2.43E-05 0. 5.58E-07

BR82 0. 0. 1.27E-05 0. 0. 0. 0.

BR83+D 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+D 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+D 0. 2.86E-07 1.97E-07 0. 0. 0. 9.74E-08

SR89+D 2.51 E-03 0. 7.20E-05 0. 0. 0. 5.16E-05

SR90+D 1.85E-02 0. 4.71E-03 0. 0. 0. 2.31E-04

SR91+D 5.OOE-05 0, 1.81E-06 0. 0. 0. 5.92E-05

SR92+D 1.92E-05 0. 7.13E-07 0. 0. 0. 2.07E-04

68
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC101

RU103+D

RU105+D

RU106+D

RHI05

PD107

PD109

AG110M+D

AG111

CD113M

CD115M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+D

BONE

8,69E-08

8.10E-10

1.13E-06

7.65E-09

2.43E-08

1.93E-07

2.06E-07

1.48E-08

1.23E-07

4.20E-08

4.59E-10

0.

0.

1.92E-09

1.08E-06

2.27E-09

1.48E-06

1.36E-07

2.41 E-05

1.09E-06

0.

0.

9.96E-07

5.20E-07

0.

0.

2.49E-04

7.41 E-05

5.53E-04

2.14E-05

1.23E-05

8.06E-06

2.23E-06

2.33E-05

5.85E-05

1.OOE-06

1.OOE-04

2.84E-07

1.52E-05

1.76E-07

2.08E-05

3.91 E-07

2.67E-07

2.86E-05

6.OOE-06

3.59E-05

LIVER

0.

0.

0.

0.

0.

9.18E-08

5.02E-08

2.54E-09

3.33E-08

1.73E-08

9.79E-11

5.65E-05

3.40E-05

3.96E-09

1.46E-06

2.86E-09

0,

0.

0.

7.13E-07

1.19E-06

1.50E-06

7.27E-07

2.02E-07

1.77E-05

1.42E-05

3.89E-06

1.38E-06

7.26E-06

3.15E-07

1.19E-07

1.58E-07

3.98E-08

7.79E-06

1,94E-05

3,35E-07

3.43E-05

9.79E-08

6.12E-06

6.50E-08

1.03E-05

1.79E-07

1.34E-07

2.12E-05

1.32E-05

4.23E-05

TOTAL BODY

2,33E-09

2.76E-1 1

3.01 E-08

2.15E-10

6.62E-10

5.54E-08

3.56E-08

1.16E-09

1.04E-08

1.00E-08

3.53E-11

1.82E-06

6.63E-06

5.1 OE-08

4.55E-07

2.83E-08

4.95E-07

4.58E-08

3.01 E-06

4.79E-07

8.45E-08

3.62E-07

4.81 E-07

1.07E-07

6.52E-07

4.93E-07

6.50E-06

3.29E-06

1.80E-05

6.63E-06

2.53E-06

2.91 E-06

6.90E-07

3.15E-06

7.08E-06

2.15E-07

1.54E-05

6.63E-08

5.05E-06

4.94E-08

9.61 E-06

1.71 E-07

1.38E-07

1.55E-05

5.30E-06

1.86E-05

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0. 0.

3.91 E-06

1.36E-06

1.91E-06

5.68E-08,

1.54E-08

6.19E-08

2.84E-08

7.84E-06

1.69E-05

8.14E-07

3.84E-05

2.38E-07

1.24E-05

1.57E-07

1.52E-05

3.45E-07

2.39E-07

1.36E-02

1.48E-03

1.39E-02

KIDNEY

0.

0.

0.

0.

0.

2.71 E-07

5.41 E-08

2.56E-09

3.25E-08

1.24E-08

7,65E-1 1

1.13E-05

5.08E-05

4.26E-08

1.23E-05

3.40E-08

3.08E-06

1.OOE-06

2.85E-05

1.98E-06

6.79E-06

5.51 E-06

1.04E-06

4.22E-07

1.34E-05

7.41 E-06

0.

0.

0.

0.

0.

0.

0.

0.

1.44E-04

2.44E-06

2.50E-04

7.07E-07

4.21 E-05

4.50E-07

6.44E-05

1.22E-06

9.03E-07

2.51 E-05

1.45E-05

4.94E-05

LUNG GI-LLI

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

2.07E-09

1.42E-07

1.56E-09

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.34E-05

7.72E-06

5.07E-06

1.15E-06

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.20E-04

2.70E-06

8.10E-05

1.46E-04

1.92E-04

2.39E-05

2.50E-05

1.62E-04

3.98E-06

1.46E-05

3.09E-05

1.21E-06

1.12E-05

1.1 5E-06

6.31 E-06

4.86E-07

1.80E-05

5.41 E-05

1.83E-04

1.77E-05

9.46E-07

3.68E-05

3.77E-05

4.82E-05

2.66E-05

8.09E-05

6.58E-05

1.11E-04

2.52E-05

6.60E-05

1.64E-05

8.35E-05

5.91E-05

1.11 E-05

2.36E-05

2.1 OE-05

5.97E-05

2.27E-05

1.03E-04

7.11E-06

3.81 E-05

1.93E-05

3.06E-06

4.24E-07

2.83E-06

1.51E-06

69
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y 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+D 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+D 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06

XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

XE135M 0, 0. 0. 0. 0. 0. 0.

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

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

XE138+D 0. 0. 0. 0. 0. 0. 0.

CS134M+D 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 1.10E-05 2.05E-06

CS137+D 5.22E-04 6.11E-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+D 3.10E-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08

BA139 8.81E-07 5.84E-10 2.55E-08 0. 3.51E-10 3.54E-10 5.58E-05

BA140+D 1.71E-04 1.71E-07 8.81E-06 0. 4.06E-08 1.05E-07 4.20E-05

BA141+D 4.25E-07 2.91E-10 1.34E-08 0. 1.75E-10 1.77E'-10 5.19E-06

BA142+D 1.84E-07 1.53E-10 9.06E-09 0. 8.81E-1I 9.26E-11 7.59E-07

LA140 2.11E-08 8.32E-09 2.14E-09 0. 0. 0. 9.77E-05

LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.61E-05

LA142 1.10E-09 4.04E-10 9.67E-11 0. 0. 0. 6.86E-05

CE141 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2,48E-05

CE143+D 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5,73E-05

CE144+D 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+D 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

PM148M+D 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

PM151 6.18E-09 9.01E-10 4.56E-10 0. 1.07E-09 0. 4.17E-05

SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06

SM153 7.72E-09 5.97E-09 4.58E-10 0. 1.25E-09 0. 3.12E-05

EU152 6.74E-07 1.79E-07 1.51E-07 0. 5.02E-07 0. 1.59E-05

EU 154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05

EU155 5.42E-07 6.25E-08 3.23E-08 0, 1.40E-07 0. 8.37E-05

EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05

TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05

H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0.

W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07

W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05

W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05

70
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TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB210+D 5.28E-02 1.42E-02 2.38E-03 0. 4.33E-02 0. 5.62E-05

BI210+D 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05

P0210 3.10E-03 5.93E-03 7.41E-04 0. 1,26E-02 0. 6.61E-05

RN222+D 0. 0. 0. 0. 0. 0. 0.

RA223+D 4.41E-02 6.42E-05 8.82E-03 0. 1.17E-03 0. 3.43E-04

RA224+D 1.46E-02 3.29E-05 2.91 E-03 0. 6.00E-04 0. 3.86E-04

RA225+D 5.78E-02 6.42E-05 1.15E-02 0. 1.19E-03 0. 3.24E-04

RA226+D 6.20E-01 4.76E-05 5.14E-01 0. 8.71 E-04 0. 3.44E-04

RA228+D 4.32E-01 2.58E-05 4.86E-01 0. 4.73E-04 0. 5.86E-05

AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.36E-04

AC227+D 4.49E-03 7.67E-04 2.79E-04 0. 1.56E-04 0. 8.50E-05

TH227+D 1,20E-04 2.01E-06 3.45E-06 0. 7.41E-06 0. 5170E-04

TH228+D 2.47E-03 3.38E-05 8.36E-05 0. 1.58E-04 0. 5.84E-04

.TH229 1.48E-02 1.94E-04 7.29E-04 0. 9.29E-04 0. 5.31 E-04

TH230 3.80E-03 1.90E-04 1.06E-04 0. 9.12E-04 0. 6.24E-05

TH232+D 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.OOE-08 0. 1.39E-07 0. 1.19E-04

PA231+D 7.57E-03 2.50E-04 3.02E-04 0. 1.34E-03 0. 7.44E-05

PA233 3.11E-08 6.09E-09 5.43E-09 0. 1.67E-08 0. 1.46E-05

U232+D 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05

U233+1D 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.51E-05

U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.37E-05

U235+D 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.1OE-05

U236 4.67E-03 0. 3.64E-04 0. 1.01E-03 0. 5.98E-05

U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.11E-05

U238+D 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.71 E-05

NP237+D 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.23E-05

NP238 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.17E-05

NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05

PU238 1.34E-03 1.69E-04 3.40E-05 0. 1.21E-04 0. 7.57E-05

PU239 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 6.91E-05

PU240 1.45E-03 1.77E-04 3.54E-05 0. 1.28E-04 0. 7.04E-05

PU241+D 4.38E-05 1.90E-06 8.82E-07 0. 3.17E-06 0. 1.45E-06

PU242 1.35E-03 1.70E-04 3.41E-05 0. 1.23E-04 0. 6.77E-05

PU244 1.57E-03 1.95E-04 3.91E-05 0. 1.41E-04 0. 1.01E-04

AM241 1.53E-03 7.18E-04 1.09E-04 0. 6.55E-04 0. 7.70E-05

AM242M 1.58E-03 7.02E-04 1.13E-04 0. 6.64E-04 0. 9.69E-05

AM243 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.03E-05

CM242 1.37E-04 1.24E-04 9.10E-06 0. 2.62E-05 0. 8&23E-05

CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.10E-05

CM244 1.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05

CM245 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.30E-05

CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31E-04 0. 7.17E-05

CM247+D 1.82E-03 7.36E-04 1.11E-04 0. 4.24E-04 0. 9.43E-05

CM248 1.51E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.52E-03

CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.99E-04

71
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TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07

BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05

C14 1.21E-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 3.10E-08 3.1OE-08 3.1OE-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.

CA41 3.47E-04 0. 3.79E-05 0. 0. 0. 1.90E-07

SC46 1.97E-08 2.70E-08 1.04E-08 0. 2.30E-08 0. 3.95E-05

CR51 0. 0. 8.90E-09 4.94E-09 1.35E-09 9.02E-09 4.72E-07

MN54 0. 1.07E-05 2.85E-06 0. 3.00E-06 0. 8.98E-06

MN56 0. 3.34E-07 7.54E-08 0. 4.04E-07 0. 4.84E-05

FE55 1.15E-05 6.10E-06 1.89E-06 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. 7,10E-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. 6.41E-06

ZN69M+D 7.10E-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+D 0. 0. 1.71 E-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+D 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. 3195E-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+D 0. 1.17E-07 1.04E-07 0. 0. 0. 1,02E-09

SR89+D 1.32E-03 0. 3.77E-05 0. 0. 0. 5.11E-05

SR90+D 1.70E-02 0. 4.31E-03 0. 0. 0. 2.29E-04

SR91+D 2.40E-05 0. 9.06E-07 0. 0. 0. 5.30E-05

SR92+D 9.03E-06 0. 3.62E-07 0. 0. 0. 1.71E-04

72
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TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC101

RU103+0

RU105+D

RU106+D

RH105

PD107

PD109

AG110M+D

AG111

CD113M

CDI15M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+D

BONE LIVER

4.11E-08 0.

3.82E-10 0.

6.02E-07 0.

3.60E-09 0.

1.14E-0,8 0.

1.67E-07 6.25E-08

1.16E-07 2.55E-08

6.99E-09 1.01E-09

1.05E-07 2.62E-08

2.25E-08 8.76E-09

2.17E-10 3.92E-11

0. 2.41 E-05

0. 1.33E-05

9.23E-10 1.81E-09

5.35E-07 5.96E-07

1.07E-09 1.12E-09

7.31 E-07 0.

6.45E-08 0.

1.17E-05 0.

5.14E-07 2.76E-07

0. 4.72E-07

0. 5.67E-07

5.39E-07 3.64E-07

2.48E-07 7.76E-08

0. 1.02E-05

0. 5.89E-06

1.33E-04 1.65E-06

3.55E-05 5.35E-07

3.33E-04 4.15E-06

1.11E-05 1.44E-07

7.16E-06 5.52E-08

4.40E-06 6.73E-08

1.06E-06 1.64E-08

1.14E-05 3.09E-06

2.89E-05 7.78E-06

4.71 E-07 1.27E-07

4.87E-05 1.36E-05

1.34E-07 3.74E-08

7.20E-06 2.49E-06

8&30E-08 2,53E-08

1.01E-05 4.47E-06

1.87E-07 7.56E-08,

1.29E-07 5.80E-08

1.39E-05 8.53E-06

2.92E-06 5.90E-06

1.72E-05 1.73E-05

TOTAL BODY

1.10E-09

1.39E-11

1.61 E-08

1.03E-10

3.13E-10

4.45E-08

2.27E-08

5.96E-10

8.61 E-09

6.26E-09

1.83E-1 1

8.65E-07

3.29E-06

3.00E-08

2.14E-07

1.42E-08

2.81 E-07

2.34E-08

1.46E-06

2.36E-07

4.01 E-08

1,70E-07

2.91 E-07

5.12E-08

4.34E-07

2.51 E-07

3.24E-06

1.59E-06

9.46E-06

3.89E-06

1.50E-06

1.58E-06

3.68E-07

1.52E-06

3.43E-06

1.01E-07

7.56E-06

3.18E-08

2.65E-06

2.47E-08

5.40E-06

9.37E-08

7.74E-08

7.62E-06

3.04E-06

9.83E-06

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.75E-06

5.55E-07

1.14E-06

2.45E-08

6.63E-09

2.58E-08

1.18E-08

3.20E-06

6.91 E-06

3.26E-07

1.57E-05

9.56E-08

5.12E-06

6.35E-08

6.51 E-06

1.45E-07

1.02E-07

5.58E-03

6.50E-04

5.72E-03

KIDNEY

0.

0.

0.

0.

0.

2.42E-07

3.65E-08

1.45E-09

2.83E-08

8.23E-09

4.35E-1 1

6.35E-06

2.84E-05

2.63E-08

7.02E-06

1.91 E-08

1.84E-06

5.67E-07

1.58E-05

1.1OE-06

3.95E-06

3.04E-06

6.78E-07

2.34E-07

1.05E-05

4.38E-06

0.

0.

0.

0.

0.

0.

0.

0.

8.24E-05

1.34E-06

1.43E-04

3.92E-07

2.41 E-05

2.51 E-07

4.15E-05

7.1 8E-07

5.37E-07

1.44E-05

8.82E-06

2.84E-05

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

9.19E-10

5.27E-08

5.92E-1 0

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

6.16E-06

3.99E-06

2.1 OE-06

4.60E-07

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

GI-LLI

1.17E-04

7.48E-07

8.02E-05

1.04E-04

1.70E-04

2.37E-05

2.66E-05

1.53E-04

3.95E-06

1.62E-05

1.21 E-05

1.22E-06

1.1OE-05

1.03E-06

6.25E:06

3.56E-09

1.89E-05

4.21 E-05

1.82E-04

1.71 E-05

9,37E-07

3,35E-05

4.33E-05

4.75E-05

2.63E-05

8.01 E-05

6.52E-05

1.1OE-04

2.50E-05

6.94E-05

1.71E-05

8.87E-05

5.97E-05

1.1OE-05

2.34E-05

1.84E-05

5.94E-05

8.34E-06

1.01 E-04

4.36E-07

4.50E-05

5.77E-06

5.89E-07

4.29E-07

2.76E-06

1.54E-06

73
PALISADES NUCLEAR PLANT

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Revision 21

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

1132 8,00E-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06

1133+D 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+D 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06

XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

XE138+D 0. 0. 0. 0. 0. 0. 0.

CS134M+D 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 8.1OE-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+D 3.27E-04 3.13E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06

CS138 2.28E-07 3.17E-07 2.01E-07 0. 2.23E-07 2.40E-08 1.46E-07

CS139+D 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-10 2.39E-05

BA140+D 8.31 E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21 E-05

BA141+D 2.00E-07 1,12E-10 6.51E-09 0. 9.69E-11 6.58E-10 1.14E-07

BA142+D 8.74E-08 6.29E-11 4.88E-09 0. 5.09E-11 3.70E-11 1.14E-09

LA140 1.01E-08 3153E-09 1.19E-09 0. 0. 0. 9.84E-05

LA141 1.35E-09 3.17E-10 6.88E-11 0. 0. 0. 7.05E-05

LA142 5.24E-10 1.67E-10 5.23E-11 0. 0. 0. 3.31E-05

CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05

CE143+D 6.99E-09 3.79E-06 5.49E-10 0. 1.59E-09 0. 5.55E-05

CE144+D 2.08E-06 6.52E-07 1.11E-07 0. 3.61E-07 0. 1.70E-04

PR143 3.93E-08 1.18E-08 1.95E-09 0. 6.39E-09 0. 4.24E-05

PR144 1.29E-10 3.99E-11 6.49E-12 0. 2.11E-11 0. 8.59E-08

ND147+D 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.58E-05

PM147 3.18E-07 2.27E-08 1.22E-08 0. 4.01E-08 0. 9.19E-06

PM148M+D 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.78E-05

PM148 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.70E-05

PM149 6.49E-09 6.90E-10 3.74E-10 0. 1.22E-09 0. 4.71E-05

PM151 2.92E-09 3.55E-10 2.31E-10 0. 6.02E-10 0. 4.03E-05

SM151 2.56E-07 3.81E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06

SM153 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05

EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05

EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81E-05

EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05

EU156 5.62E-08 3.01E-08 6,23E-09 0. 1.94E-08 0. 6.83E-05

TB160 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.68E-05

H0166M 1.08E-06 2.26E-07 1.91E-07 0. 3.22E-07 0. 0.

W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.79E-07

W185 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61E-05

W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05

74
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB210+D 4.75E-02 1.22E-02 2.09E-03 0. 3.67E-02 0. 5.57E-05

B1210+D 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+D 0. 0. 0. 0. 0. 0. 0.

RA223+D 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.38E-04

RA224+D 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.78E-04

RA225+D 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21 E-04

RA226+D 5.75E-01 1.84E-05 4.72E-01 0. 4.88E-04 0. 3.41E-04

RA228+D 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+D 4.12E-03 6.63E-04 2.55E-04 0. 1.46E-04 0. 8.43E-05

TH227+D 5.85E-05 7.96E-07 1.69E-06 0. 4.22E-06 0. 5.63E-04

TH228+D 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+D 3.96E-03 1.52E-04 3.01E-04 0. 7.41E-04 0. 5.27E-05

TH234 3.42E-07 1.51E-08 9.88E-09 0. 8.01E-08 0. 1.18E-04

PA231 +D 7.07E-03 2.34E-04 2.81 E-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+D 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.98E-05

U233+D 3.72E-03 0; 2.25E-04 0. 6.1OE-04 0. 6.45E-05

U234 3.57E-03 0. 2.21E-04 0. 5.98E-04 0. 6.32E-05

U235+D 3.42E-03 0. 2.07E-04 0. 5.61E-04 0. 8.03E-05

U236 3.42E-03 0. 2.12E-04 0. 5.73E-04 0. 5.92E-05

U237 2.36E-07 0. 6.27E-08 0. 6.81E-07 0. 2.08E-05

U238+D 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05

NP237+D 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+D 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. 4.1OE-04 0. 7.11E-05

CM247+D 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05

CM248 1.41 E-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

75
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y 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

BE10 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 1.15E-08 1.15E-08 1.15E-08 1.15E-08 1.15E-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,

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

CA41 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 6.00E-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+D 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+D 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+D 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 6.11E-06 0. 0. 0. 6.11E-07

RB88 0. 8.52E-08 4.54E-08 0. 0. 0. 7.30E-15

RB89+D 0. 5.50E-08 3.89E-08 0. 0. 0. 8.43E-17

SR89+D 4.40E-04 0. 1.26E-05 0. 0. 0. 5.24E-05

SR90+D 8.30E-03 0. 2.05E-03 0. 0. 0. 2.33E-04

SR91+D 8.07E-06 0. 3.21E-07 0. 0. 0. 3.66E-05

SR92+D 3.05E-06 0. 1.30E-07 0. 0. 0. 7. 77E-05

76
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC101

RU103+D

RU105+D

RU106+D

RH105

PD107

PD109

AG110M+D

AG 111

CD113M

CD115M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE 134+D

1129

1130

1131 +D

BONE

1.37E-08

1.29E-10

2.01 E-07

1.21E-09

3.83E-09

5.53E-08

4.12E-08

2.37E-09

3.44E-08

8.22E-09

7.37E-1 1

0.

0.

3.32E-10

1.79E-07

3.60E-10

2.55E-07

2.18E-08

3.92E-06

1.73E-07

0.

0.

2.05E-07

8.29E-08

0.

0.

4.44E-05

1.19E-05

1.16E-04

3.87E-06

2.48E-06

1.59E-06

3.63E-07

3.83E-06

9.67E-06

1.58E-07

1.63E-05

4.48E-08

2.44E-06

2.79E-08

3.49E-06

6.44E-08

4.47E-08

4.66E-06

1.03E-06

5.85E-06

LIVER

0.

0.

0.

0.

0.

2.73E-08

1.30E-08

4.69E-10

1.13E-08

4.56E-09

1.83E-11

1.06E-05

6.03E-06

9.26E-10

2.63E-07

5.12E-10

0.

0.

0,

1.25E-07

2.08E-07

2.51 E-07

1.94E-07

3.44E-08

4.51 E-06

2.60E-06

7.29E-07

2.37E-07

2.16E-06

7.13E-08

2.71 E-08

3.25E-08

7.76E-09

1.38E-06

3.43E-06

5.60E-08

6.05E-06

1.67E-08

1.17E-06

1.15E-08

2.21 E-06

3.66E-08

2.87E-08

3.92E-06

2.98E-06

8.19E-06

TOTAL BODY THYROID

3.69E-10 0.

4.93E-12 0.

5.39E-09 0.

3.50E-11 0.

1.05E-10 0.

1.49E-08 0.

8.94E-09 0.

2.16E-10 0.

2.83E-09 0.

2.51 E-09 0.

6.68E-12 0.

2.90E-07 0.

1.15E-06 0.

1.20E-08 0.

7.17E-08 0.

5.03E-09 0.

1.09E-07 0.

8.46E-09 0.

4,94E-07 0.

8.20E-08 0.

1.34E-08 0.

5.70E-08 0.

1.18E-07 0.

1.73E-08 0.

1.45E-07 0.

8.39E-08 0.

1.08E-06 5.84E-07

5.37E-07 1.86E-07

3.30E-06 5.69E-07

1.51E-06 8.78E-09

5.80E-07 2.37E-09

5.71 E-07 8.99E-09

1.37E-07 4.08E-09

5.12E-07 1.07E-06

1.15E-06 2.30E-06

3.40E-08 1.09E-07

2.58E-06 5.26E-06

1.09E-08 3.20E-08

9.76E-07 1.76E-06

8.72E-09 2.15E-08

2.08E-06 2.33E-06

3.56E-08 5.11E-08

3,00E-08 3.67E-08

6.54E-06 4.77E-03

1.19E-06 2.43E-04

4.40E-06 2.39E-03

KIDNEY

0.

0.

0.

0.

0.

9.65E-08

1.91E-08

7.11 E-1 0

1.32E-08

4.42E-09

2.14E-1 1

3.04E-06

1.38E-05

1.38E-08

3.34E-06

9.26E-09

8.99E-07

2.75E-07

7,56E-06

5.31 E-07

1.88E-06

1.45E-06

* 3.70E-07

1.12E-07

4.99E-06

2.08E-06

0.

0.

0.

0.

0.

0.

0.

0.

3.92E-05

6.40E-07

6.82E-05

1.88E-07

1.22E-05

1.22E-07

2.12E-05

3.62E-07

2.74E-07

7.01 E-06

4.59E-06

1,41 E-05

LUNG GI-LLI

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

5.14E-10

2.72E-08

3.12E-10

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

3.38E-06

2.18E-06

1.14E-06

2.47E-07

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.13E-04

6.09E-09

8.24E-05

3.32E-05

1.17E-04

2.58E-05

3.OOE-05

1.27E-04

4.07E-06

1.95E-05

4.37E-07

1.29E-06

.1.08E-05

6.08E-07

6.44E-06

8.75E-17

2.13E-05

1.76E-05

1.88E-04

1.59E-05

9.66E-07

2.53E-05

5.45E-05

4.80E-05

2.71 E-05

8.23E-05

6.71 E-05

1.12E-04

2.58E-05

7.80E-05

1.93E-05

9.41 E-05

6.16E-05

1.13E-05

2.41E-05

1.22E-05

6.12E-05

2.45E-07

9.39E-05

2.29E-09

7.OOE-05

1.48E-07

1.66E-09

4.57E-07

2.29E-06

1.62E-06

77
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y 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+D 2.01E-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 6.10E-07 0. 5.10E-09

1135+D 6.1OE-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0. 1.74E-06

XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

XE138+D 0. 0. 0. 0. 0. 0, 0.

CS134M+D 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+D 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.12E-06

CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.10E-07 1.28E-08 6.76E-11

CS139+D 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.33E-23

BA139 1.39E-07 9.78E-11 4.05E-09 0. 9.22E-11 6.74E-11 1.24E-06

BA140+D 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.38E-05

BA141+D 6.71E-08 5.01E-11 2.24E-09 0. 4.65E-11 3.43E-11 1,43E-13

BA142+D 2.99E-08 2.99E-11 1,84E-09 0. 2.53E-11 1.99E-11 9,18E-20

LA140 3.48E-09 1.71E-09 4,55E-10 0. 0. 0. 9.82E-05

LA141 4.55E-10 1.40E-10 2.31E-11 0. 0. 0. 2,48E-05

LA142 1.79E-10 7.95E-11 1.98E-11 0. 0. 0. 2.42E-06

CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05

CE143+D 2.35E-09 1.71E-06 1.91E-10 0. 7.67E-10 0. 5.14E-05

CE144+D 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. 1.01E-11 0. 4.74E-14

ND147÷D 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.68E-05

PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06

PM148M+D 4.14E-08 1.05E-08 8.21E-09 0. 1.59E-08 0. 6.61E-05

PM148 1.02E-08 1.66E-09 8.36E-10 0. 3.00E-09 0. 9.90E-05

PM149 2.17E-09 3.05E-10 1.25E-10 0. 5.81E-10 0. 4.49E-05

PM151 9.87E-10 1.63E-10 8.25E-11 0. 2.93E-10 0. 3.66E-05

SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06

SM153 1.22E-09 1.01E-09 7.43E-11 0. 3.30E-10 0. 2.85E-05

EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05

EU154 7.91E-07 1.02E-07 7.19E-08 0. 4,56E-07 0. 5.39E-05

EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05

EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.36E-05

TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05

H0166M 3.57E-07 1.10E-07 7.96E-08 0. 1.61E-07 0. 0.

W181 1.42E-08 4.58E-09 4.79E-10 0. 0. 0. 3.90E-07

W185 5.79E-07 1.91E-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

78
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

PB210+D

B121 0+D

P0210

RN222+1D

RA223+D

RA224+D

RA225+D

RA226+D

RA228+D

AC225

AC227+D

TH227+D

TH228+D

TH229

TH230

TH232+D

TH234

PA231 +0

PA233

U232+D

U233+D

U234

U235+D

U236

U237

U238+D

NP237+D

NP238

NP239

PU238

PU239

PU240

PU241 +D

PU242

PU244"

AM241

AM242M

AM243

CM242

CM243

CM244

CM245

CM246

CM247+D

CM248

CR252

BONE

1.81 E-02

6.59E-07

6.09E-04

0.

7.11E-03

2.31 E-03

9.37E-03

3.22E-01

1.37E-01

6.29E-06

2.05E-03

1.96E-05

6.80E-04

8.39E-03

2.16E-03

2.42E-03

1.14E-07

4.31 E-03

7.33E-09

5.89E-03

1.24E-03

1.19E-03

1.14E-03

1.14E-03

7.89E-08

1.09E-03

1.44E-03

1.95E-08

1.76E-09

7.21 E-04

8.27E-04

8.26E-04

1.84E-05

7.66E-04

8.95E-04

8.62E-04

8.70E-04

8.60E-04

2.94E-05

6.91 E-04

5.32E-04

1.07E-03

1.06E-03

1.03E-03

8.60E-03

3.51 E-04

LIVER

5.44E-03

4.51 E-06

1.07E-03

0.

1.08E-05

5.52E-06

1.10E-05

8.13E-06

4.41 E-06

8.59E-06

3.03E-04

3.52E-07

1.14E-05

1.26E-04

1.23E-04

1.05E-04

6.68E-09

1.62E-04

1.41E-09

0.

0.

0.

0.

0.

0.

0.

1.25E-04

5.22E-10

1.66E-10

1.02E-04

1.12E-04

1.12E-04

9.42E-07

1.08E-04

1.23E-04

3.29E-04

3.19E-04

3.17E-04

2.97E-05

2.86E-04

2.49E-04

3.33E-04

3.32E-04

3.27E-04

2.69E-03

0.

TOTAL BODY

7.01 E-04

5.66E-08

1.23E-04

0.

1.42E-03

4.61E-04

1.87E-03

2.39E-01

1.51E-01

4.22E-07

1..22E-04

5.65E-07

2.30E-05

4.11E-04

6.OOE-05

1.63E-04

3.31E-09

1,68E-04

1.26E-09

421 E-04

7.543-05

7.39E-05

6.94E-05

7.09E-05

2.1OE-08

6.49E-05

5.85E-05

3.04E-10

9.22E-1 1

1.82E-05

2.01E-05

2.01E-05

3.69E-07

1.94E-05

2.22E-05

5.75E-05

5.80E-05

5.62E-05

1.95E-06

4.09E-05

3.19E-05

6.1 OE-05

6,09E-05

6.OOE-05

4.95E-04

8.37E-06

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0,

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

KIDNEY

1.72E-02

5.48E-05

3.60E-03

0.

3.1 OE-04

1.58E-04

3.15E-04

2.32E-04

1.26E-04

9.85E-07

8.81 E-05

2.01E-06

6.41 E-05

6.10E-04

5.99E-04

5.11E-04

3.81 E-08

9.10E-04

5.32E-09

6.38E-04

2.90E-04

2.85E-04

2.67E-04

2.73E-04

3.24E-07

2.50E-04

4.33E-04

1.79E-09

5.21 E- 10

7.80E-05

8.57E-05

8.56E-05

1.71 E-06

8,25E-05

9.45E-05

4.31 E-04

4.30E-04

4.22E-04

8.89E-06

1.91 E-04

1.49E-04

2.85E-04

2.84E-04

2.80E-04

2.31E-03

0.

LUNG GI-LLI

0.

0.

0,

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

5.74E-05

5.15E-05

6.75E-05

0.

3,43E-04

3.71E-04

3.27E-04

3.51 E-04

5.98E-05

4.36E-04

8.68E-05

5.75E-04

5.97E-04

5.43E-04

6.38E-05

5.43E-05

1.21E-04

7.60E-05

1.61 E-05

7.19E-05

6.65E-05

6.51E-05

8.28E-05

6.11E-05

2.09E-05

5.83E-05

8.41 E-05

3.83E-05

2.67E-05

7.73E-05

7.06E-05

7.19E-05

1.48E-06

6.92E-05

1.03E-04

7.87E-05

9.90E-05

9.23E-05

8.40E-05

8.28E-05

8.OOE-05

7.46E-05

7.33E-05

9.63E-05

1.55E-03

3.05E-04

79
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

H3 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07

BE10 3.18E-06 4.91E-07 7.94E-08 0. 3.71E-07 0. 2.68E-05

C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07

N13 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09 8.36E-09

F18 6.24E-07 0. 6.92E-08 0. 0. 0. 1.85E-08

NA22 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05 1.74E-05

NA24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06

P32 1.93E-04 1.20E-05 7.46E-06 0. 0. 0. 2.17E-05

AR39 0. 0. 0. 0. 0. 0. 0.

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

CA41 1.83E-05 0. 2.00E-05 0. 0. 0. 1.84E-07

SC46 5.51E-09 1.07E-08 3.11E-09 0. 9.99E-09 0. 5.21E-05

CR51 0. 0. 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07

MN54 0. 4.57E-06 8.72E-07 0. 1.36E-06 0. 1.40E-05

MN56 0. 1.15E-07 2.04E-08 0. 1.46E-07 0. 3.67E-06

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 2.91E-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

N159 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07

NI63 1.30E-04 9.01E-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+D 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+D 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+D 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+D 0. 4.01 E-08 2.82E-08 0. 0. 0. 2.33E-21

SR89+D 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05

SR90+D 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04

SR91+D 5.67E-06 0. 2.29E-07 0. 0. 0. 2.70E-05

SR92+D 2.15E-06 0. 9.30E-08 0. 0. 0. 4.26E-05

80
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91M+D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+D

TC99M

TC99

TC101

RU103+D

RU105+D

RU1O6+D

RH105

PD107

PD109

AG1IOM+D

AG111

CD113M

CD1I 5M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE125M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+D

BONE LIVER

9.62E-09 0.

9.09E-11 0.

1.41 E-07 0.

8.45E-10 0.

2.68E-09 0.

4.18E-08 2.34E-09

3.04E-08 9.75E-09

1.68E-09 3.39E-10

2.55E-08 8.32E-09

6.22E-09 3.46E-09

5.22E-11 1.32E-11

0. 7.51 E-06

•0. 4.31E-06

2.47E-10 6.98E-10

1.25E-07 1.86E-07

2.54E-10 3.66E-10

1.85E-07 0.

1.54E-08 0.

2.75E-06 0.

1.21 E-07 8.85E-08

0. 1.47E-07

0. 1.77E-07

1.60E-07 1.48E-07

5.81E-08 2.43E-08

0. 3.18E-06

0. 1.84E-06

3.11E-05 5.15E-07

8.33E-06 1.68E-07

8.45E-05 1.67E-06

2.80E-06 5.29E-08

1.79E-06 2.OOE-08

1.15E-06 2.34E-08

2.58E-07 5,65E-09

2.68E-06 9.71 E-07

6.77E-06 2.42E-06

1.1OE-07 3.95E-08

1.15E-05 4.29E-06

3.14E-08 1.1 8E-08

1.73E-06 8.46E-07

1.97E-08 8.23E-09

2.52E-06 1.63E-06

4.62E-08 2.70E-08

3.24E-08 2.12E-08

3.27E-06 2.81 E-06

7.56E-07 2.23E-06

4,16E-06 5.95E-06

TOTAL BODY

2.58E-10

3.52E-12

3.77E-09

2.47E-11

7.40E-11

1.09E-09

6.60E-09

1.55E-10

2.05E-09

1.86E-09

4.82E-12

2.03E-07

8.20E-07

8.89E-09

5.02E-08

3.59E-09

7.97E-08

6.08E-09

3.48E-07

5.83E-08

9.40E-09

3.99E-08

8.79E-08

1.21 E-08

1.02E-07

5.87E-08

7.59E-07

3.78E-07

2.40E-06

1.11E-06

4.26E-07

4.15E-07

9.90E-08

3.59E-07

8.25E-07

2.38E-08

1.82E-06

7.65E-09

7.05E-07

6.22E-09

1.53E-06

2.60E-08

1.30E-08

9.21 E-06

8.80E-07

3.41 E-06

THYROID

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0..

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

4.38E-07

1.39E-07

4.92E-07

6.79E-09

1!.82E-09

7.04E-09

3.10E-09

8.06E-07

1.73E-06

8.15E-08

3.95E-06

2.41 E-08

1.34E-06

1.62E-08

1.80E-06

3.91 E-08

2,83E-08

7.23E-03

1.89E-04

1.95E-03

KIDNEY

0.

0.

0.

0.

0.

8.87E-09

1.53E-08

5,12E-10

9.57E-09

3.42E-09

1.54E-1 1

2.13E-06

9.76E-06

1.06E-08

2.34E-06

6.59E-09

7.06E-07

1.99E-07

5.31E-06

3.76E-07

1.32E-06

1.01E-06

2.91 E-07

7.84E-08

3.50E-06

1.46E-06

0.

0.

0.

0.

0.

0.

0.

1.09E-05

2,75E-05

4.48E-07

4.80E-05

1.32E-07

8.57E-06

8.63E-08

1.57E-05

2.67E-07

2.05E-07

6.04E-06

3.48E-06

1.02E-05

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

3.42E-10

1.58E-08

1.87E-10

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

2.18E-06

1.38E-06

7.05E-07

1.53E-07

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

GI-LLI

1.02E-04

2.67E-10

7.76E-05

1.48E-05

8.50E-05

2.43E-06

3.09E-05

1.05E-04

3.84E-06

2.1 OE-05

4,87E-08

1.22E-06

9.99E-06

4.13E-07

6.08E-06

1.10E-21

2.16E-05

9.42E-06

1.78E-04

1.41 E-05

9.11E-07

1.96E-05

6.04E-05

4.46E-05

2.56E-05

7.74E-05

6.33E-05

1.04E-04

2.43E-05

7.95E-05

1.97E-05

9.40E-05

5.90E-05

1.07E-05

2.27E-05

8.68E-06

5.79E-05

2.37E-08

8.40E-05

2.79E-09

7.71 E-05

6.64E-08

3.59E- 11

4.44E-07

1.92E-06

1.57E-06

81
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI50Y 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+D 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31E-06 0. 2.22E-06

1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51E-10

1135+D 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.

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+D 0. 0. 0. 0. 0. 0. 0.

CS134M+D 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+D 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11E-06

CS138 6.52E-08, 1.09E-07 5.40E-08 0. 8.01E-08 7.91E-09 4.65E-13

CS139+D 3.41E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.10E-30

BA139 9.70E-08 6.91E-11 2.84E-09 0. 6.46E-11 3,92E-11 1.72E-07

BA140+D 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.18E-05

BA141+D 4.71E-08 3.56E-11 1.59E-09 0. 3.31E-11 2.02E-11 2.22E-17

BA142+D 2.13E-08 2.19E-11 1.34E-09 0. 1.85E-11 1.24E-11 3.00E-26

LA140 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05

LA141 3.19E-10 9.90E-11 1.62E-11 0. 0. 0. 1.18E-05

LA142 1.28E-10 5.82E- 11 1.45E-11 0. 0. 0. 4.25E-07

CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05

CE143+D 1.65E-09 1.22E-06 1.35E-10 0. 5.37E-10 0. 4.56E-05

CE144+D 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 3.01E-11 1.25E-11 1.53E-12 0. 7.05E-12 0. 4.33E-18

ND147+D 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+D 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

PM151 6.97E-10 1.17E-10 5.91E-11 0. 2.09E-10 0. 3.22E-05

SM151 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.25E-06

SM153 8,57E-10 7.15E-10 5.22E-11 0. 2.31E-10 0. 2.55E-05

EU152 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.56E-05

EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.48E-05

EU155 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.60E-06

EU156 1.37E-08 1.06E-08 1.71E-09 0. 7.08E-09 0. 7.26E-05

TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.33E-05

H0166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.

W181 9.91E-09 3.23E-09 3.46E-10 0. 0. 0. 3.68E-07

W185 4.05E-07 1.35E-07 1,42E-08 0. 0. 0. 1.56E-05

W187 1.03E-07 8.61E-08 3.01E-08 0. 0. 0. 2,82E-05

82
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMJ50Y PER PCI INGESTED IN FIRST YR).

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21O+D 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.42E-05

B1210+D 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+D 0. 0. 0. 0. 0. 0. 0.

RA223+D 4.97E-03 7.65E-06 9.94E-04 0. 2.17E-04 0. 3.21E-04

RA224+D 1.61E-03 3.90E-06 3.23E-04 0. 1.10E-04 0. 3.40E-04

RA225+D 6.56E-03 7.78E-06 1.31E-03 0. 2.21E-04 0. 3,06E-04

RA226+D 3.02E-01 5.74E-06 2.20E-01 0. 1.63E-04 0. 3.32E-04

RA228+D 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+D 1.87E-03 2.48E-04 1.11E-04 0. 8.00E-05 0. 8.19E-05

TH227+D 1.37E-05 2.48E-07 3.95E-07 0. 1.41 E-06 0. 5.40E-04

TH228+D 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+D 2.30E-03 1,00E-04 1.50E-04 0. 4.82E-04 0. 5.12E-05

TH234 8.01E-08 4.71E-09 2.31E-09 0. 2.67E-08 0. 1.13E-04

PA231+D 4.10E-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05

PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05

U232+D 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.78E-05

U233+D 8.71E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05

U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05

U235+D 8.01E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81E-05

U236 8.01E-04 0. 4.96E-05 0. 1.91E-04 0, 5.76E-05

U237 5,52E-8 0. 1.47E-08 0. 2.27E-07 0. 1.94E-05

U238+D 7.67E-04 0. 4.54E-05 0. 1.75E-04 0. 5.50E-05

NP237+D 1.37E-03 1.19E-04 5.54E-05 0. .4.12E-04 0. 7.94E-05

NP238 1.37E-08 3.69E-10 2.13E-10 0. 1.25E-09 0. 3.43E-05

NP239 1.19E-09 1.17E-10 6.45E-11 0. 3.65E-10 0. 2.40E-05

PU238 6.80E-04 9.58E-05 1.71E-05 0. 7,32E-05 0. 7.30E-05

PU239 7.87E-04 1.06E-04 1.91E-05 0. 8.11E-05 0. 6.66E-05

PU240 7.85E-04 1.06E-04 1.91E-05 0. 8.10E-05 0. 6.78E-05

PU241+D 1.65E-05 8,44E-07 3.32E-07 0. 1.53E-06 0, 1.40E-06

PU242 7.29E-04 1.02E-04 1.84E-05 0. 7.81E-05 0. 6.53E-05

PU244 8.52E-04 1.17E-04 2.11E-05 0. 8.95E-05 0. 9.73E-05

AM241 8.19E-04 2.88E-04 5.41E-05 0. 4.07E-04 0. 7.42E-05

AM242M 8.24E-04 2.78E-04 5.43E-05 0. 4.05E-04 0. 9.34E-05

AM243 8.18E-04 2.78E-04 5.30E-05 0. 3.99E-04 0. 8.70E-05

CM242 2.06E-05 2.10E-05 1.37E-06 0. 6.22E-06 0. 7.92E-05

CM243 6.39E-04 2.41E-04 3.75E-05 0. 1.75E-04 0. 7.81E-05

CM244 4.83E-04 2.07E-04 2.87E-05 0, 1.34E-04 0. 7.55E-05

CM245 1.02E-03 2.87E-04 5.76E-05 0. 2.69E-04 0. 7.04E-05

CM246 1.01E-03 2.87E-04 5.75E-05 0. 2.68E-04 0. 6.91E-05

CM247+D 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

83
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.2

PALISADES

Liquid Effluent

Design Basis Quantity 0>

Nuclide

H-3

Na-24

Sc-46

Cr-51

Mn-54

Fe-55

Mn-56

Co-57

Co-58

Fe-59

Co-60

Cu-64

Ni-65

Zn-65

Br-84

Rb-86

Rb-88

Sr-89

Sr-90

Sr-91

Sr-92

Y-92

Nb-95

Zr-95

Nb-97

Zr-97

Mo-99

Tc-99m

Ru-103

Ag-110m

Half-Life

12.3 yr

15 h

83.9 d

27.8 d

303 d

2.6 yr

2.576 h

270 d

71.3 d

45.6 d

5.26 yr

12.8 h

2.56 h

245 d

31,8 mo

1.02 mo

17.8 mo

52.7 d

27.7 yr

9.67 h

2.71 h

3.53 h

35 d

65.5 d

72 mo

17 h

66.7 h

6.05 h

39.5 d

255 d

Dose Conversion

Factors (mrem/Ci)

1.75E-06

5.44E-03

2.02E-02

1.56E-03

3.50E-02

Design Basis

Quantity

(Curies)

4.48E-03

1.86E-03

4.39E-03

1.03E-02

4.08E-02

4.71 E-01

1.32E-03

5.82E-04

1.83E-01

2.02E-03

3.06E-01

6.92E-04

1.56E-01

2.71E-00

1.16E-03

1.51 E-03

2.69E-04

7.24E+00

6.17E-03

6.95E-04

9.28E-04

1.11 E-03

1.42E-04

2.74E-03

7.75E-02

Individual/Organ

Adult/TB

Teen/TB

TeenrTB

Adult/GI (LLI)

Teen/TB

Child/Bone

Teen/TB

Teen/TB

Teen/TB

Adult/GI (LLI)

Teen/TB

Teen/GI (LLI)

Teen/TB

Teen/TB

Teen/TB

Child/TB

Teen/TB

Child/Bone

Adult/Bone

Teen/TB

Teen/TB

Teen/TB

Adult/GI (LLI)

Teen/TB

Teen/TB

Teen/TB

Teen/Kidney

Teen/TB

Teen/TB

TeenfTB

1.71E+06

551.5

148.5

6,410.0

85.7

2,232.0

1,612.0

683.4

291.3

245.1

6.37

7,575.0

5,154.0

16.4

1,485.2

9.80

4,335.3

64.1

3.69

2,586.0

1,986.8

11,150.0

1.38

486.2

4,316.6

3,232.8

9,009.0

21,126.8

1,094.9

38.7

84
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

TABLE 2.2 (continued)

PALISADES

Liquid Effluent

Design Basis Quantity -

C3

Design Basis

Dose Conversion Quantity Nuclide Half-Life Factors (mrem/Ci) IndcMdual/Ornan (Cures)

Cd-113m 13.6 yr 6.02E-02 Adult/GI (LLI) 166.1

Sb-124 60 d 1.51 E-02 Teen/TB 198.7

Sb-125 2.7 yr 5.11E-02 Teen/TB 58.7

Te-127 9.4 h 7.38E-03 Teen/GI (LLI) 1,355.0

Te-127m 109 d 1.39E-01 Teen/Kidney 71.9

Te-129m 34.1 d 2.66E-01 Adult/GI (LLI) 37.6

1-130 12.3 h 1.17E-02 Child/Thyroid 854.7

1-131 8.05 d 3.27E-01 Child/Thyroid 30.6

Te-131m 30 h 2.27E-01 Adult/GI (LLI) 44.0

1-132 2.26 h 3.18E-05 TeernTB 94,339.0

Te-132 77.7 h 2,93E-01 AdulVGI (LLI) 34.1

1-133 20.3 h 3.94E-02 Child/Thyroid 253.8

Cs-134 2 yr 2.86E+00 Adult/TB 1.04

1-134 52 mo 2.43E-03 Teen/TB 1,234.0

1-135 6.68 h 1.64E-03 Child/Thyroid 6,097.0

Cs-136 13.7 d 4.13E-01 Adult/TB 7.26

Cs-137 30 yr 1.71E+00 Adult/TB 1.75

Cs-138 32.2 mo 2.31 E-03 Teen/TB 1,298.0

Ba-139 82.9 mo 4.66E-05 Teen/TB 64,377.0

Ba-140 12.8 d 7.96E-04 Teen/TB 3,768.0

La-140 40.22 h 1.85E-02 Adult/GI (LLI) 540.5

Ce-141 32.5 d 3.70E-04 Teen/TB 8,108,0

Ce-144 284 d 1.56E-03 Teen/TB 1,923.0

Eu-152 12.7 yr 3.24E-01 Teen/TB 9.25

W-187 23.9 h 1.98E-01 Adult/GI (LLI) 50.5

Np-239 2.346 d 2.26E-03 Adult/GI (LLI) 4,424.0

85
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

III. URANIUM FUEL CYCLE DOSE

A. SPECIFICATION

In accordance with Appendix A, Section II1.1.1, if either liquid or gaseous quarterly

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

limit of Appendix A, Sections III.C.1, IlI.D.1, or III.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 I1.C.2.1 and I1.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.

86
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 21

C. DOSE CALCULATION

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

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

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

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

question, times the assumed fishing time.

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

where:

D4 = 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. REVISIONS TO THE OFFSITE DOSE CALCULATION MANUAL

A. REQUIREMENTS

1. For all revisions to the Offsite Dose Calculation Manual, complete

Attachment 1.

2. All revisions to the Offsite Dose Calculation Manual are required to be

reviewed by the Onsite Safety Review Committee.

87
Proc No ODCM

Attachment I

Revision 21

Page 1 of 3

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

1. Description and Evaluation:

Provide a brief description of each change and provide sufficient information to

support the change, with appropriate analyses or evaluations justifying the change if

needed.

2. Determination:

Answer the following questions:

a. Does the proposed change maintain the level of radioactive effluent control

required by 10 CFR 20.1302? (Compliance with dose limits for individual

members of the public, where annual average concentrations of radioactive

material released in gaseous and liquid effluents at the boundary of the

unrestricted area do not exceed the values specified in Table 2 of Appendix B

Part 20.)

Fi Yes

LI No

b. Does the Droposed change maintain the level of radioactive effluent control

required by 40 CFR 190? (Total dose uranium fuel cycle - less than or equal

to 25 mrem total body or any organ, or less than or equal to 75 mrem thyroid.)

["I Yes

[L No
Proc No ODCM

Attachment I

Revision 21

Page 2 of 3

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

c. Does the proposed change maintain the level of radioactive effluent control

required by 10 CFR 50.36a? (Technical Specifications on effluents from

nuclear power reactors, where the Offsite Dose Calculation Manual is the

document where the effluent controls are specified, and all the requirements

of this regulation are demonstrated.)

MI Yes

MI No

d. Does the Proposed change maintain the level of radioactive effluent control

required by 10 CFR 50, Appendix I? (Numerical guides for design objectives

and limiting conditions for operation to meet the criterion "as low as

reasonably achievable," for radioactive material in light-water-cooled nuclear

power reactor effluents, lists the annual dose commitments to unrestricted

areas for liquid and gaseous effluents.)

r-i Yes

LI No

e. Does the Proposed change adversely impact the accuracy or reliability of

effluent calculations?

L] Yes

L] No
Proc No ODCM

Attachment I

Revision 21

Page 3 of 3

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

f. Does the proposed changqe adversely impact the accuracy or reliability of

dose calculations?

LI Yes

L'I No

g. Does the proposed change adversely impact the accuracy or reliability of

setpoint calculations?

LI Yes

I-I No

3. Conclusion:

Changes to the ODCM were made in accordance to the provisions of Technical

Specification 5.5.1, Section c.

Prepared By: /

Date

Reviewed By:

Date
ENCLOSURE 2

BRP RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF RELEASES

JANUARY - DECEMBER 2008

This report provides information relating to radioactive effluent releases and solid

radioactive waste disposal at Big Rock Point (BRP) for the year 2008. The report

format is detailed in the BRP Offsite Dose Calculation Manual (ODCM), Section II1.

Effluent releases from BRP are controlled by the Defueled Technical Specifications and

the ODCM requirements.

2008 Plant Operating History

During 2008, normal independent spent fuel storage installation (ISFSI) operations

continued. There were no operational activities that generated any solid radioactive

waste.

Liquid and gaseous effluent monitoring is no longer conducted as the former BRP

.nuclear plant property has been released from the license. Short-lived radionuclides,

including 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

2008. 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 2008.

C. Radioactive Effluent Monitoring Instrumentation

BRP ODCM, Section I, currently specifies required actions when less

than the minimum number of radioactive effluent monitoring instrument

channels are operable. The ODCM also specifies these actions be

taken when installed effluent monitoring systems are removed from

service for decommissioning.

As decommissioning of the former operating plant is complete, all plantinstalled liquid and gaseous radioactive effluent monitoring instrument

channels have been permanently removed and dismantled.

Page 1 of 8
2. Gaseous Effluents

Although there were no gaseous effluents released during 2008, Table 2

provides a summary of all gaseous radioactive effluent monitoring conducted

during the reporting period as required by the ODCM.

3. Liquid Effluents

There were no liquid effluent batch releases during 2008. Table 3 lists and

summarizes liquid effluent releases in accordance with the ODCM.

4. Solid Waste

There was no solid radioactive waste generated or shipped during 2008.

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 1 millirem to an organ or total body of any individual or

more than 1 person-rem to the population within 50 miles. During 2008, 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 2008.

7. Process Control Program (PCP)

The Process Control Program (PCP) describes solid waste processing and

disposal methods at the BRP site. The PCP was not revised during 2008.

Page 2 of 8
TABLE 1

BATCH RELEASES

January 1, 2008 to December 31, 2008

A. GASEOUS

B. LIQUID Units 1ST QTR 2NDQTR 3RD QTR 4TH QTR

Number of Releases N/A N/A N/A N/A

Total Release Time Minutes N/A N/A N/A N/A

Maximum Release Time Minutes N/A N/A N/A N/A

Average Release Time Minutes N/A N/A N/A N/A

Minimum Release Time Minutes N/A N/A N/A N/A

Page 3 of 8
TABLE 2

GASEOUS EFFLUENT RELEASES

January 1, 2008 to December 31, 2008

1ST

QTR

2ND

QTR

3RD

QTR

4TH

QTR

Est Total

A. FISSION AND ACTIVATION GASES Units Error %

1. Total release Ci N/A N/A N/A N/A

2. Average release rate for period P Ci/sec N/A N/A N/A N/A N/A

3. Percent of annual avg EC % N/A N/A NiA N/A

B. IODINES

1. Total iodine Ci N/A N/A N/A N/A

2. Average release rate for period p Ci/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

C. PARTICULATES

1. Particulates with half-life >8 day Ci N/A N/A N/A N/A

2. Average release rate for period p Ci/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 NIA N/A N/A N/A

2. Average release rate for period Jp 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 (ODCM 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/quarter) % N/A N/A N/A N/A

Page 4 of 8
TABLE 2

GASEOUS EFFLUENT RELEASES

January 1, 2008 to December 31, 2008

1. FISSION GASES Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR

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-133 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 Peiod Ci N/A N/A N/A N/A

2. IODINES

Iodine-131 Ci N/A N/A N/A N/A

Iodine-132 Ci NIA N/A N/A N/A

Iodine-133 Ci N/A N/A -- N/A N/A

Iodine-134 Ci N/A N/A N/A N/A

Iodine-135 Ci N/A N/A N/A N/A

Total for Period Ci N/A N/A N/A N/A

Page 5 of 8
TABLE 2

GASEOUS EFFLUENT RELEASES

January 1, 2008 to December 31, 2008

3. PARTICULATEST 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-11Orn Ci N/A N/A N/A N/A

Cesium-134 Ci N/A N/A N/A N/A

Cesium-137 Ci N/A N/A N/A N/A

Barium-140 Ci N/A N/A N/A. N/A

Europium-152 Ci N/A NIA 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 6 of 8
TABLE 3

LIQUID EFFLUENT RELEASES

January 1, 2008 to December 31, 2008

4TH QTR

Est Total,

A. FISSION AND ACTIVATION PRODUCTS Units 1STQTR 2ND OTR 3RD QTR 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 p Ci/ml 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 p Ci/ml N/A N/A N/A N/A

3. Percent of EC % N/A 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 -p Ci/ml N/A N/A N/A N/A

3. Percent of EC % N/A N/A N/A N/A

D. GROSS ALPHA RADIOACTIVITY Ci N/A N/A N/A { N/A

E. VOLUME OF WASTE RELEASED I

(Prior to dilution) Liters N/A N/A. NA N/A

F. VOLUME OF DILUTION WATERUSED DURING1

PERIOD Liters N/A N/A N/A N/A

G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem N/A N/A N/A N/A

Percent of ODCM Section 1, 2.3.2 a (1.5 mrem) % 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

Page 7 of 8
TABLE 3

LIQUID EFFLUENT RELEASES

January 1, 2008 to December 31, 2008

1. NUCLIDES

RELEASED Units 1ST QTR 2ND QTR 3RD QTR 4TH QTR

Chromium-51 Ci .... .

Man ,anese 54 Ci .......

Cobalt-58 Ci .......

Iron-59 Ci ........

Cobatt-60 Ci ........

Zinc-65 Ci .. ,, --

Strontium-89 Ci ....

Strontium-90 Ci ........

Molybdenum-99 Ci ......

Silver 1 1Cm Ci ........

lodine-131 Ci ........

Cesium-134 Ci ........

Cesium-137 Ci Q.

Antimony-125 Ci ........

Tin-113 Ci ........

Net Unidentified Beta Ci .....

Fission & Activation

Product Total Ci .....

Xenon-133 Ci -- -.

Tritium Ci .....

Grand Total Ci ........

Page 8 of 8
ATTACHMENT 1

BIG ROCK POINT

OFFSITE DOSE CALCULATION MANUAL

REVISION 30

63 Pages Follow
VOLUME 25 OFF-SITE DOSE CALCULATION MANUAL

AND RELATED DOCUMENTS

A. OFF-SITE DOSE CALCULATION MANUAL

SECTION I - PROCEDURAL AND

SURVEILLANCE REQUIREMENTS

Revision 30

Page 1 of 63

ODCM SECTION I

PROCEDURAL AND SURVEILLANCE REQUIREMENTS

(Relocated Technical Specifications)

25-PartA.doc 01/04/07
VOLUME 25 OFF-SITE DOSE CALCULATION MANUAL Revision 30

AND RELATED DOCUMENTS Page 2 of 63

A. OFF-SITE DOSE CALCULATION MANUAL

SECTION I - PROCEDURAL AND

SURVEILLANCE REQUIREMENTS

1.0 GASEOUS EFFLUENTS

1.1 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

1.1.1 Applicability

All installed gaseous effluent monitoring equipment has been removed form

service as a result of decommissioning and dismantlement activities. When

required for activities that have the potential for significant releases of

particulate airborne radioactivity, air sampling and analyses shall be utilized to

document that effluents do not exceed the levels specified by ODCM,

Section I, Requirement 1.2.2.

1.1.2 Requirement

Work areas shall be sampled during evolutions that have potential for

releasing dusts of concentration greater than ten times the Effluent

Concentration (EC) values of 10CFR20, Appendix B, Table 2, Column 1, for

the mixture of radionuclides present. Grab samples or continuous air monitor

systems set up for personnel monitoring shall be analyzed for particulate

concentrations over the interval of activity release from such areas. If remote

techniques of demolition are utilized for activities in such areas and no local

area samples are available, downwind sampling shall be utilized.

1.1.3 Action

With air particulate data unavailable for demolition areas that have

beta-gamma surface activity greater than ten times the levels specified in

Regulatory Guide 1.86, Table I, AND effluents have potential to enter the

environment (contaminated particulate matter is expected to become

suspended in air and is not confined), either:

a. Suspend operations until local or downwind sampling is instituted, or

b. Utilize conservative analyses for release from similarly contaminated

areas to calculate dose at the site boundary in accordance with

methodology of ODCM, Section II, Part 1.2.2.b.

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1.1.4 Surveillance Requirements

Equipment utilized for particulate air sampling shall be calibrated, source

checked, maintained and operated in accordance with Radiological Protection

procedures applicable to worker protection.

1.1.5 Basis

Plant systems have been dismantled and fuel is present only in sealed dry

storage containers at a location separate from the dismantlement area.

Equipment, concrete and other structural materials having significant levels of

activation or contamination have been shipped off as radiological waste.

Radioactive materials that remain are predominantly of concentrations less

than detectable at the lower limits of detection established for environmental

analyses of solids (sediments) in ODCM, Section I, Table 1-3.

Worker protection monitoring is performed for all atmospheres with potential

to reach 0.3 DAC over a 40-hour work week, and any short-term

concentration above 1.0 DAC. At maximum (Cs-137*), DAC-to-EC ratio is

(6E-8)/(2E-1 0)=300 at the work location. One DAC equals only 0.282 EC at

off-site locations, due to atmospheric dilution of 9.4E-4 times local on-site

concentration at the site boundary (EA-BRP-RAE-0501).

Suspension of particulate radioactivity from surfaces has been calculated to

provide higher potential concentrations than releases from bulk materials

during decontamination and dismantlement activities (EA-BRP-RAE-0301).

Maximum off-site dose with surface radioactivity at a level equal to ten times

the Regulatory Guide 1.86 levels for beta-gamma radioactivity is

0.16 mrem/year, assuming 2000 hours per year of release.

Removal of plant-installed monitoring equipment has been performed in

accordance with ODCM, Section III, Part 4.2.2. Since that time, conservative

use of airborne samples from work areas as estimates of airborne release

concentrations has shown no 31-day dose greater than 0.01% of the annual

guideline (highest month was December 2004 at 0.0064% of the annual

guideline value).

*Co-60 ratio is 200 or 350 (mean = 275), depending on chemical form.

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1.2 GASEOUS EFFLUENTS DOSE RATE

1.2.1 Applicability

This section remains applicable only for tritium and radionuclides in

particulate form. Surveillance requirements will cease to be applicable when

analyses show no further potential for releases above the action levels of

Requirement 1.2.3.

1.2.2 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: NA

b. For tritium and for all radionuclides in particulate form with half-lives

greater than eight days: Less than or equal to 1500 mrem/year to any

organ.

1.2.3 Action

With the dose rate averaged over a period of one hour exceeding the above

limits (>35 DAC in the on-site work area); upon discovery, promptly restore

the release rate to within the above limit(s).

1.2.4 Surveillance Requirements

a. For noble gases: NA.

b. The dose rate due to tritium and all radionuclides in particulate form

with half lives greater than eight days in gaseous effluents shall be

determined to be within the limits of Requirement 1.2.2 above by

utilizing the methodology and parameters in Section II of this ODCM.

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1.2.5 Basis

This specification is provided to allow the Licensee operational flexibility in

meeting the limits of 10CFR50, Appendix I. The instantaneous dose rates of

this specification are higher than the implied dose rates of 1 OCFR20,

Appendix B, Table 2, Column 1, Effluent Concentrations for Members of the

Public. However, the ALARA philosophy for atmospheric effluents ensures

doses to the public at and beyond the site boundary are minimized and less

than the annual doses of 10CFR50, Appendix I.

The required detection capabilities for radioactive materials in gaseous

effluent samples are tabulated in terms of the lower limits of detection (LLDs).

See Notation c of Table 1-3.

The relationship between DAC and the 10 EC of Requirement 1.1.2 is

provided in Basis 1.1.5: one DAC at the work location equals 0.282 EC at the

site boundary. Therefore, the hourly maximum of 10 EC at the site boundary

equals (10 EC)/(0.282 EC/DAC)=35.4 DAC at the work location.

1.3 AIRBORNE RADIOACTIVITY DOSE

1.3.1 Applicability

This section remains applicable only for doses due to tritium and

radionuclides in particulate form. Surveillance requirements will cease to be

applicable when analyses show no further potential for releases above the

action levels of Requirements 1.3.3.b.

1.3.2 Requirements

a. The air dose due to noble gases released in gaseous effluents is not

applicable.

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b. The dose to a member of the public from tritium and all radionuclides in

particulates form with half lives greater than eight days in gaseous

effluents released to areas at and beyond the site boundary (see

Figure 2.1) shall be limited to the following:

1) During any calendar quarter: Less than or equal to 7.5 mrem to

any organ, and

2) During any calendar year: Less than or equal to 15 mrem to any

organ.

1.3.3 Actions

a. With the calculated dose from the release of radioactive material

exceeding any of the above limits, prepare and submit to the

Commission within 30 days a Special Report that identifies the

cause(s) for exceeding the limit 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.

b. With projected dose in the next 31 days greater than two percent of the

annual limits defined by Requirement 1.3.2.b above, institute controls

to reduce release below two percent of the annual limit per month.

1.3.4 Surveillance Requirement

a. Cumulative and projected dose contributions for the current calendar

quarter and current calendar year for radioactive materials shall be

determined at least once per 31 days in accordance with the

methodology and parameters in this ODCM.

b. Projected dose for the next 31 days shall be calculated at least once

per 31 days.

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1.3.5 Basis

This specification is provided to implement the guides set forth in

Sections II.B and II.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

material in airborne effluents to unrestricted areas will be kept "as low as is

reasonably achievable."

The Surveillance Requirements implement the requirements in Section III.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 Section II,

Parts 1.2 and 1.3 of this ODCM 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

10CFR50, 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.

Section II, Part 1.2.2.b, provides methodology for evaluation of releases from

unconfined areas. This methodology may be used for releases from

contaminated structures in the process of dismantlement, in the absence of,

or in lieu of, airborne analyses in the work area itself.

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2.0 LIQUID EFFLUENTS

2.1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

2.1.1 Applicability

Installed liquid effluent monitoring equipment is no longer required. Effluents

purposefully discharged to the lake form surface and groundwater that have

been detained for sedimentation will undergo precautionary sampling and

analysis for tritium and radionuclides other than dissolved or entrained noble

gases.

2.1.2 Requirement

Pending determination that such precaution is not necessary, any systems

containing water detained for sedimentation or other purposes shall be

sampled prior to initiation of a season of release and a minimum of monthly

throughout the season thereafter, from grab samples or effluent composites.

2.1.3 Action

a. With a detained water sample indicating radioactivity boncentration

greater than twice the lower limit of detection for environmental water

samples as specified in ODCM, Section I, Table 1-1, prohibit further

release of water until calculations confirm that the EC fraction is less

than the requirement of ODCM, Section I, Part 2.2.2, AND

b. With a sample indicating detectable radioactivity concentration greater

than twice the lower limit of detection for environmental water samples

as specified in ODCM, Section I, Table 1-1, prohibit release until

calculations confirm that monthly release will not exceed the

requirement of ODCM, Section I, Part 2.3.2.

2.1.4 Surveillance Requirements

Analytical accuracy for liquid samples is documented in routine calibration

and quality control checks sufficient to demonstrate that the results are valid

for the purposes of Section IV.B.2 of Appendix I to 1 OCFR50.

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2.1.5 Basis

Sampling of detained water is provided to indicate and quantify presence of

radioactive material prior to and during releases of clarified liquids such that

controls may be applied, as applicable, to limit such releases.

With the exception of tritium, previous experience has shown that site

drainage water has contained radioactive materials only in association with

suspended soils. Water is detained to allow sedimentation. This

sedimentation serves to clarify the water for release and to minimize the

potential for effluent to contain detectable radioactivity. Sampling is

precautionary.

2.2 LIQUID EFFLUENTS CONCENTRATION

2.2.1 Applicability

Effluents purposefully discharged to the lake from surface and groundwater

that have been detained for sedimentation will undergo precautionary

sampling and analysis for tritium and radionuclides other than dissolved or

entrained noble gases.

2.2.2 Requirement

The concentration of radioactive material released in liquid effluents from the

site to UNRESTRICTED AREAS (identified as the site boundary, see

Figure 2-1) shall be limited to ten times the concentration values specified in

Appendix B, Table 2, Column 2, to 1 OCFR20 for radionuclides other than

dissolved or entrained noble gases.

2.2.3 Action

With liquid effluent concentrations in areas at or beyond the site boundary

(see Figure 2-1) exceeding limits, upon discovery, promptly restore the

concentration to within the above limits.

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2.2.4 Surveillance Requirements

a. A representative grab sample of water to be released shall be

analyzed prior to initiating a season of release.

b. Composite or grab samples of potentially radioactive effluents shall be

sampled and analyzed at least monthly during release periods for

radionuclides other than dissolved and entrained noble gases.

c. The results of the radioactivity analyses shall be used in accordance

with the methodology and parameters in this ODCM, to assure that the

concentrations at the point of release are maintained within the limits of

Requirement 2.2.2 above.

2.2.5 Basis

This requirement ensures that the concentration of radioactive materials

released in effluents to unrestricted areas will be less than ten times the

concentration levels specified in 10CFR20, 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 (1) the Section II.A design objectives of Appendix I, 1 OCFR50, to a

member of the public, and (2) the limits of 1OCFR20.1301(e) to the

population. lodines, noble gases and short-lived particulates (t1/2 less than

approximately five years) are no longer observed at Big Rock Point (BRP)

due to the time period elapsed since permanent shut down.

See Notation c to Table 1-3 for further information on the LLDs referenced in

this section.

2.3 LIQUID EFFLUENT DOSE

2.3.1 Applicability

All installed liquid radioactive waste treatment systems have been removed in

the plant dismantlement process, after being shown not necessary for

maintenance of public doses below two percent of Requirements 2.3.2.a and

2.3.2.b, below. However, effluents purposefully discharged to the lake from

surface and groundwater sources will undergo precautionary sampling and

analysis for tritium and radionuclides other than dissolved or entrained noble

gases.

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2.3.2 Requirement

The dose or dose commitment to a member of the public from radioactive

materials in liquid effluents released to areas at and beyond the site boundary

(see Figure 2-1) shall be limited:

a. During any calendar quarter: to less than or equal to 1.5 mrem to the

total body and to less than or equal to five mrem to any organ, and

b. During any calendar year: to less than or equal to three mrem to the

total body and to less than or equal to 10 mrem to any organ.

2.3.3 Actions

a. With the calculated dose from the release of radioactive material

exceeding any of the above limits, prepare and submit to the

Commission within 30 days a Special Report that identifies the

cause(s) for exceeding the limit 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.

b. With projected dose in the next 31 days greater than two percent of the

annual limit of Requirement 2.3.2.b, take action to ensure further

releases do not exceed the two percent level.

2.3.4 Surveillance Requirements

a. Cumulative and projected dose contributions for the current calendar

quarter and current calendar year for radioactive materials shall be

determined in accordance with the methodology and parameters in this

ODCM at least once per 31 days.

b. Projected dose for the next 31 days shall be calculated prior to each

batch release, or at least once every 31 days if continuous release is in

progress.

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2.3.5 Basis

This specification is provided to implement the requirements of

Sections II.A, III.A and IV.A of Appendix I, 10CFR Part 50. The

Requirement 2.3.2 for Operation implements the guides set forth in

Section II.A of Appendix I. The ACTION statements provide the required

operating flexibility and at the same time implement the guides set forth in

Section IV.A of Appendix I to assure that the releases of radioactive material

in liquid effluents to unrestricted areas will be kept "as low as is reasonably

achievable." Also, 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 40CFR141.

The dose calculation methodology and parameters in this ODCM implement

the requirements in Section III.A of Appendix I that conformance be shown by

calculational procedures based on models and data, such that the actual

exposure of the public through appropriate pathways is unlikely to be

substantially underestimated.

The methods specified in the ODCM for calculating the doses due to the

actual and estimated release rates of radioactive materials in liquid effluents

are consistent with the methodology of Regulatory Guide 1.109, Calculation

of Annual Doses to Man from Routine Releases of Reactor Effluents for the

Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I,

Revision 1, October, 1977 and Regulatory Guide 1.113, Estimating Aquatic

Dispersion of Effluents from Accidental and Routine Reactor Releases for the

Purpose of Implementing Appendix I, April 1977.

The requirement for action when effluents are projected to exceed two

percent of the annual Appendix I guidelines in any 31 days dose due to

effluents will be minimized.

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3.0 TOTAL FUEL CYCLE DOSE

3.1 APPLICABILITY

Requirement and actions set forth below are applicable when liquid effluent

dose exceeds twice the limits of Requirement 1.3.2.a, 1.3.2.b.1), 1.3.2.b.2),

2.3.2.a, or 2.3.2.b of this section.

3.2 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 mrem to the total body or

any organ, except the thyroid, which shall be limited to less than or equal to

75 mrem.

3.3 ACTION

With the calculated doses from the release of radioactive materials in liquid or

gaseous effluents exceeding twice the limits of Requirements 1.3.2.a,

1.3.2.b.1), 1.3.2.b.2), 2.3.2.a, or 2.3.2.b of this section, calculations should be

made including direct radiation contributions from fuel pool systems and from

outside storage tanks to determine whether the limits of Requirement 3.2

above have been exceeded. If such is the case:

Prepare and submit to the Commission 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 10CFR20.2203(a)(4), 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.

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3.4 SURVEILLANCE REQUIREMENTS

a. Cumulative dose contributions from liquid and gaseous effluents shall

be determined to comply with Requirement 3.2 above at a minimum of

once per 31 days, and in accordance with the methodology and

parameters described in Section II of this ODCM.

b. Cumulative dose contributions from direct radiation from spent fuel and

from radwaste storage shall be determined in accordance with the

methodology and parameters in ODCM, Section II, Part 3.2,

Assumptions, and 3.3, Dose Calculation.

3.5 BASIS

This specification is provided to meet the dose limitations of 40CFR190 that

have been incorporated into 10CFR20 by 46FR18525. The specification

requires the preparation and submittal of a Special Report whenever the

calculated doses from plant generated radioactive effluents and direct

radiation exceed 25 mrem to the total body or any organ, except the thyroid,

which shall be limited to less than or equal to 75 mrem.

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

40CFR1 90 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

five miles must be considered.

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If the dose to any member of the public is estimated to exceed the

requirements of 40CFR1 90, the Special Report with a request for a variance

(provided the release conditions resulting in violation of 40CFR1 90 have not

already been corrected), in accordance with the provisions of 40CFR190.11

and 1 OCFR20.2203(a)(4) is considered to be a timely request and fulfills the

requirements of 40CFR1 90 until NRC staff action is completed. The

requested variance relates only to the limits of 40CFR1 90 and shall not apply

in any way to the other requirements for dose limitation of 1 OCFR20, as

addressed in Specifications.

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.

4.0 RADIOLOGICAL ENVIRONMENTAL MONITORING

4.1 APPLICABILITY

The requirements and actions for environmental monitoring are applicable

until the Final Status Survey (FSS) has been completed in accordance with

the License Termination Plan (LTP). However, if any groundwater monitoring

well exceeds, or is projected to exceed, 20,000 pCi/I at the time the FSS

report is submitted, monitoring of groundwater will continue as specified (see

Table 1-1).

4.2 REQUIREMENT

The radiological environmental monitoring program shall be conducted as

specified in Table 1-1.

4.3 ACTION

a. With the radiological environmental monitoring program not being

conducted as specified in Table 1-1, prepare and submit to the

Commission, in the Annual Radiological Environmental Operating

Report required by Section III of this ODCM, a description of the

reasons for not conducting the program as required and the plans for

preventing a recurrence.

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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 1-2 when averaged over any calendar quarter,

prepare and submit to the Commission 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 1-2 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 1-2 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 Requirements 1.3.2 or 2.3.2 of

ODCM, Section I. 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.

4.4 SURVEILLANCE REQUIREMENTS

a. The radiological environmental monitoring samples shall be collected

and analyzed pursuant to the requirements of Table 1-1 and the

detection capabilities required by Table 1-3.

b. A final land use census was undertaken in the last year of plant

operation. No further census data is required.

c. Analytical Accuracy

Records of instrument calibrations and quality control data for the

instrumentation used for environmental analyses shall be maintained.

Interlaboratory comparison participation shall be required for off-site

environmental sample analyses. Environmental TLD readouts will be

performed by an NVLAP-accredited facility.

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4.5 BASIS

a. Monitoring Program

The radiological environmental monitoring program required by this

specification provides representative measurements of radiation and of

radioactive resulting from post-operational conditions. This monitoring

program implements Section IV.B.2 of Appendix I to 10CFR50 by

verifying that the measurable concentrations of radioactive materials

and levels of radiation are not higher than expected on the basis of low

effluent levels due to the defueled conditions and the modeling of the

environmental exposure pathways.

Upon termination of the current radiological environmental monitoring

program, this program may be used to confirm that the Independent

Spent Fuel Storage Installation (ISFSI) is meeting the requirements of

10CFR72.104. Specifically, calculated annual doses frorm

plant-generated radioactive effluents and direct radiation, including

ISFSI operations, cannot exceed 25 mrem to the total body or any

organ, except the thyroid, which shall be limited to less than or equal to

75 mrem to any real individual beyond the controlled area.

b. Basis, Radiological Monitoring

The iodine and noble gas source terms for the defueled facility are

negligible, and particulate release has been reduced more than a

thousandfold, compared to power operations. Consequently, off-site

sampling of the food chain, and off-site air particulate and iodine

sampling for radionuclides normally linked to atmospheric releases

have been deleted from the ODCM. Liquid releases during initial

stages of decommissioning, although much smallerthan during power

operation, will continue to be monitored for food chain uptake at the

most sensitive indicator location: the lake environment in the area that

clarified ground and surface water effluents reach the lake.

Guidance for this monitoring program is provided by the Radiological

Assessment Branch Technical Position on Environmental Monitoring.

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 1-3 are considered optimum for routine

environmental measurements in industrial laboratories.

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c. Land Use Census

A land use census from the final year of plant power operation is

provided in ODCM, Section II, Table 2-4, for informational purposes.

Use of an assumed garden and milk animal (critical receptors) at the

site boundary in the downwind sector of highest D/Q, per ODCM,

Section II, Table 2-4, is conservative for ground level release, with

respect to any actual garden and milk animal locations.

d. Analytical Accuracy

Participation in an approved Interlaboratory Comparison Program is

required for off-site environmental monitoring sample analyses.

Analytical accuracy of radioactive material in effluent and other on-site

samples is documented in routine calibration and quality control

checks in order to demonstrate that the results are valid for the

purposes of Section IV.B.2 of Appendix I to 1OCFR50.

ThermoLuminescent Dosimetry (TLD) readouts are performed by a

NVLAP Accredited laboratory in order to assure analytical reliability

and accuracy.

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TABLE 1-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Revision 30

Page 19 of 63

Exposure Pathway and/or

Sample

1. Direct Radiation b

Number of Representative Samples and Sample

Locations a

21 monitoring stations either with two or more

TLDs or one instrument for measuring and

recording dose rate continuously, placed as

follows d.

a) Miscellaneous site locations (4)

b) A ring of stations (6) at or near the Site

boundary

c) Balance of stations (3) placed to serve as

control stations

d) Outside perimeter of ISFSI (4)"

e) ISFSI protected area fence line (4)e

Sampling and

Collection Frequency

Quarterly

Type and frequency of

Analysis

Gamma dose

quarterly

2. Waterborne

a. Lake 1 sample near site Semiannual (grab) Tritium and gamma

isotopic d

b. Well (drinking) and 1 sample from Site well, if in use, and Semiannual (grab) Tritium and gamma

groundwater 1 sample from minimum of 6 monitor wells Semiannual (grab) isotopic semiannually

monitoring wells

3. Biota

a. Marine 1 fish or invertebrate sample where clarified, Semiannual (grab) Gamma Isotopic

detained water enters lake Apr-Nov Semiannually

4. Lake Sediment

a. Shoreline 1 sample where clarified, detained water enters Semiannual (grab) Gamma Isotopic

lake Apr-Nov Semiannually

b. Shoreline 1 sample each side of 4.a (above), within -1/2 mile Semiannual (grab) Gamma Isotopic

Apr-Nov Semiannually

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TABLE 1-1

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

Notations

a. Deviations are permitted from the required sampling schedule if specimens are

unobtainable due to hazardous conditions, seasonal unavailability, malfunction of

automatic sampling equipment and other legitimate reasons. If specimens are

unobtainable due to sampling equipment malfunction, every effort shall be made

to complete corrective action prior to the end of the next sampling period. All

deviations from the sampling schedule shall be documented in the Annual

Radiological Environmental Operating Report pursuant to the Reporting

Requirements of ODCM, Section III. Alternative media and locations may be

chosen for any particular pathway if designated locations or media are not

available, and appropriate substitutions are made within 30 days in the

radiological environmental monitoring program.

b. One or more instruments, such as a pressurized ion chamber, for measuring and

recording dose rate continuously may be used in place of, or in addition to,

integrating dosimeters. The background dosimetry requirement also may be met

through use of dosimeters shared with another facility, or from data provided by

another entity, such as the State of Michigan, as appropriate for this site.

c. Gamma isotopic analysis means the identification and quantification of

gamma-emitting radionuclides that may be attributable to licensed materials in

the effluents from the facility.

d. For the purposes of this table, a TLD is considered to be one phosphor; two or

more phosphors or phosphor readout zones in a packet are considered as two or

more dosimeters.

e. TLDs designated for ISFSI only operation.

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TABLE 1-2

REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS

IN ENVIRONMENTAL SAMPLES

Reporting Level

Analysis

H-3

Mn-54**

Fe-59**

Co-58"*

Co-60

Zn-65**

Zr-Nb-95**

1-131**

Cs-1 34

Cs-137

Ba-La- 140**

Water

(pCi/ 1

20,000*

1,000

400

1,000

300

300

400

2

30

50

200

Fish

(pCi/kg)

30,000

10,000

30,000

10,000

20,000

1,000

2,000

* For drinking water samples from site domestic water well (20,000 pCi/I is the

40CFR141 value).

** Short half-lives of these radionuclides may preclude presence due to plant

effluents, but these nuclides may be observed from weapons testing.

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TABLE 1-3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a

LOWER LIMIT OF DETECTION (LLD) b, c

Water Fish Sediment

Analysis (pCi/-1) (pCi/kg, wet) (pCi/kg, dry)

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 -

Cs-134 15 130 150

Cs-137 18 150 180

Ba-La-140 15 -

* Short half-lives of these radionuclides may preclude presence due to plant

effluents, but these nuclides may be observed from weapons testing.

Notations

a. This list does not mean that only these nuclides are to be considered. Other peaks that

are identifiable, together with those of the above nuclides, shall also be analyzed and

reported in the Annual Radiological Environmental Operating Report pursuant to the

Reporting Requirements of ODCM, Section III.

b. Required detection capabilities for thermoluminescent dosimeters used for

environmental measurements are given in Regulatory Guide 4.13.

c. The LLD is defined, for purposes of these specifications, as the smallest concentration of

radioactive material in a sample that will yield a net count, above system background,

that will be detected with 95% probability, with only five percent probability of falsely

concluding that a blank observation represents a "real" signal.**

**NUREG-0473, Draft Radiological Technical Specifications for BWRs, November 1978.

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TABLE 1-3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS a

LOWER LIMIT OF DETECTION (LLD) b, c

Notations

For a particular measurement system, which may include radiochemical separation:

LLD =4.66 Sb

Ex V x2.22x Yxe-t

Where:

LLD is the predetermined lower limit of detection as defined above, as pico-curies per

unit mass or volume.

Sb is the standard deviation of the background counting rate or of the counting rate

of a blank sample as appropriate, as counts per minute,

E is the counting efficiency, as counts per disintegration,

V is the sample size inunits of mass or volume,

2.22' is the number of disintegrations per minute per pico-curie,

Y is the fractional radiochemical yield, when applicable,

x is the radioactive decay constant for the particular radionuclide, and

At for environmental samples is the elapsed time between sample collection or end

of the sample collection period, and time of counting.

Typical values of E, V, Y, and At should be used in the calculation.

d. LLD for drinking water samples.

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5.0

5.1

TEMPORARY LIQUID STORAGE IN OUTSIDE TANKS

REQUIREMENT

The concentration of radioactive material contained in any unprotected

outside tank used for temporary liquid radwaste storage shall be limited such

that the mixture of radionuclides do not exceed 8000 times the Effluent

Concentration (EC) as listed in 1OCFR20, Appendix B, Table 2, Column 2.

Ca +Cb C. E+... + . = < 8000 ECa ECb ECj

5

5.2 ACTION

With the quantity of radioactive material in any of the tanks exceeding the

above concentration, immediately suspend all additions of radioactive

material to the tank, within 48 hours reduce the tank activity 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 tank shall be

determined to be within the above limit by analyzing a representative sample

of the tank's contents at least once per seven days when radioactive

materials are being added to the tank.

An outdoor unprotected liquid storage tank is any vessel which does not have dikes or

walls capable of holding the vessel contents, or does not have overflows or drains

which route leaks, overflows or other losses back to a containment system. A vessel

or container that is intended for use as a containment system or packaging is not

considered an outdoor unprotected storage tank.

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5.4 BASIS

This requirement will provide reasonable assurance that in the event of an

uncontrolled release of the tanks' contents, the resulting concentrations,

averaged over not more than one year, would be less than 10 EC per

1 OCFR20, Appendix B, Table 2, Column 2, at the nearest potable water

supply and the nearest surface water supply in the Unrestricted Area (the

dilution between BRP and the Charlevoix drinking water supply has been

established as 800). Such an uncontrolled release would not exceed the

1 OCFR20 annual dose limits for the public or 1 OCFR50, Appendix I guidelines

due to the short interval over which that any such release would occur.

6.0 DEFINITIONS AND SURVEILLANCE REQUIREMENT TIME INTERVALS

6.1

6.2

6.3

APPLICABILITY

Requirements do not apply to equipment removed from service for

dismantlement.

REQUIREMENT

Unless otherwise specified, each surveillance requirement shall be performed

with time extensions not to exceed 25%.

ACTION

A surveillance not performed within the defined interval (including the

allowable extension) shall constitute noncompliance with the operability

requirements.

SURVEILLANCE REQUIREMENT

NA

BASIS

Terms and Surveillance interval extensions are as defined in Defueled

Technical Specifications.

6.4

6.5

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ODCM SECTION II

METHODOLOGIES FOR REQUIREMENTS IMPLEMENTATION

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1.0 GASEOUS EFFLUENTS

1.1 CALCULATION OF ALLOWABLE CONCENTRATION AND DOSE

This section of the ODCM describes appropriate methods for determination of

allowable concentrations and dose from gaseous effluents.

1.1.1 Allowable Concentration

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

relationship defined by Note 1 of Appendix B, 10CFR20.

R X)Q(F) A- =<10 (1.1)

Q ECi

Where:

R = The total EC-fraction for the release point.

X/Q = Most conservative sector site boundary dispersion

(8.1OE-08 sec/m; for ground level releases from Table 2-4).

F Release flow rate cubic feet per minute (cfm).

Ai = The measured or calculated concentration, at ambient

temperature and pressure, of nuclide i (pCi/cc) at the release

point.

EC = The EC of nuclide i from 1OCFR20, Appendix B.

1.1.2 Monitor Response

Due to lack of installed instrumentation, this section has been deleted.

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1.2 DOSE CALCULATION

1.2.1 Dose Pathway Analyses

Doses are calculated for radionuclides detected in accordance with the

analytical requirements of ODCM, Section I. All dose pathways of major

importance in the BRP environs are considered. Dose calculation is by direct

use of the NRC-approved GASPAR computer program, or by use of the

constants of Table 2-6. Site-specific parameters for GASPAR use in such

analyses are provided in Tables 2-4 and 2-5.

1.2.2 Equations for Determining Air Concentration

a. For determining the air concentration at distance x:

Xi = 7 7 ( fek Q, P xxp exp -_h 2 (1.3)

k1 ( n=1 2 Ozk)

Where:

X i Air concentration of radionuclide i, pCi/m;.

f jk Joint relative frequency of occurrence of winds in wind

speed class j, stability class k, blowing toward this

exposure point, expressed as a fraction.

Q = Average release rate of radionuclide i, pCi/s.

P = Fraction of radionuclide remaining in plume.

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

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

x = Downwind distance, m.

n = Number of sectors, 16.

A = Radioactive decay coefficient of radionuclide i, s-1 .

2-7x/n = Sector width at point of interest, m.

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h

2T~

= Release height (formerly 73 meters).

= Vertical dispersion coefficient of stability class k.

b. Special Case for Ground Level Release with Unknown Release Rate

When dismantlement of significantly contaminated structures (those

with surface contamination levels greater than ten times the Table I,

Acceptable Surface Contamination Levels, of Regulatory Guide 1.86)

occurs in such a way that contaminated dust is released to the

environment, there may be no identifiable release rate (parameter Qj of

Equation 1.2) by which calculations may be performed using the

previously discussed methods. However, by use of Figure 2-2,

particulate air concentration at the site boundary may be calculated

from Equation 1.3:

X id2 = (X idl) ~(/Q)d2/(X/Q)dl * (1.3)

And

Qi = X id2/(X/Q)d2 (1.4)

Where:

X id2 = Site boundary air concentration (ptCi/rn 3)

X idl = Measured air concentration at distance d, from source

(typically from downwind portable air sampler), in pCi/m3

(X/Q)d2 = Dispersion constant at site boundary (ground level value

from Table 2-4)

(X/Q)dl = Dispersion constant at sample point (from Figure 2-2)

Q = Release Rate (pCi/sec)

* (x/Qd2/0(/Q)dl= 9 .

4 E-0 4 may be used as default for dilution to site boundary for

samples taken within work areas.

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1.2.2 Design Basis Quantities

The design basis quantity (DBQ) of a radionuclide emitted to the atmosphere

is the amount of that nuclide, when released in one year, which would result

in a dose not exceeding any of the following:

a. The 1OCFR50 Appendix I limit of 15 millirems to any organ of an

individual from iodines and particulates with half-life greater than

eight days.

b. Fifteen-millirad air dose for beta radiation from noble gas (this is

conservatively less than the 10CFR50 Appendix I limit of 20 millirad).

c. Five-millirad air dose for gamma radiation from noble gas (this is

conservatively less than the 1OCFR50 Appendix I limit of 10 millirad).

Design basis quantity values corresponding to the above annual limits are

provided in Table 2-9. Design basis quantity (Ci) is the smallest value for

each nuclide, calculated by dividing the dose limits (as indicated in

Sections 1.2.2.a through 1.2.2.c above) by the appropriate dose calculated in

Section 1.2; the result then is multiplied by the amount of radionuclide (Ci)

used to conservatively estimate the doses as listed in Table 2-1 (or assumed

a hypothetical 1 Ci/year for nuclides not actually present):

DBQ=-•cc (CC) (1.5)

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Where:

DAI Appendix I dose limit for organ dose (mrem) and conservative

values less than the Appendix I limits as specified in b. and c.

above for beta and gamma air dose (mrad).

Dc = Calculated dose from GASPAR.

Cc = Quantity of nuclide resulting in dose Dc (Ci).

DBQ = Design Basis Quantity (Ci). The limiting values for Design Basis

Quantities for radionuclides released to the atmosphere are

given in Table 2-6.

The inverse of the ratio Cc/Dc in the above equation (i.e., Dc/Cc) is a useful

value, since it represents the most limiting dose per unit quantity of each

nuclide released.

1.3 DESIGN BASIS QUANTITY (DBQ) LIMITS

1.3.1 Design Basis Quantity Fraction

Per Specification 2.3 of ODCM, Section I, the cumulative DBQ fraction for

nuclides released is summed at least every 31 days (or alternatively,

GASPAR may be run) to assure that the sum of the fractions of all nuclides

released does not exceed 1.0 year to date or 0.5 in any calendar quarter, and

forecast not to exceed 0.02 over the next 31 days. Forecasts should be

based on historical performance, consideration of upcoming scheduled tasks

and operational parameters, or a combination of factors. The equation for

forecasting the cumulative dose by means of DBQs is provided below.

(BA <1.0 Annual, <0.5 Quarter, < 0.02 Next 31 Day (1.6)

i(DBQ)i

Where:

Ai = Activity of nuclide i

DBQ = Design Basis Quantity of nuclide i

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1.3.2 Exceeding DBQ Limits

The DBQ is a very conservative estimate of activity which could give doses at

1OCFR50, Appendix I limits. Because different organs are summed together

and doses to different individuals are summed, the DBQ typically

overestimates dose by about a factor of five. Thus, if calculations of the DBQ

fraction exceed 1.0 for year to date, 0.5 for the quarter, or 0.02 forecast for

the following 31 days, an accurate assessment of dose should be made by

use of the NRC GASPAR computer code (either by running the code or by

normalizing a prior run's dose output on a nuclide by nuclide basis). If

GASPAR is not utilized to determine accurate doses, Actions of

Specifications 2.3 or 3.3, ODCM, Section I, shall be performed based on the

conservative DBQ fraction results of Equation 1.6.

1.3.3 Releasing Radionuclides not Listed in Table 2-6

Table 2-6 contains all nuclides identified to date as routine constituents of

gaseous releases at BRP Plant, plus those common to boiling water reactors

in general, even if not previously detected at BRP. From time to time,

however, other nuclides may be detected.

If the unlisted nuclide constitutes less than ten percent of the EC-fraction for

the release, and all unlisted nuclides total less than 25% of the EC-fraction,

the nuclide may be considered not present. If the unlisted nuclide constitutes

greater than ten percent of the EC-fraction, or all unlisted nuclides together

constitute greater than 25%, then each nuclide should be assigned a DBQ

equal to the most conservative value listed for the physical form of the nuclide

involved (noble gas, halogen or particulate).

Should a nuclide not listed in Table 2-6 begin to appear in significant

quantities (in concentrations greater than ten percent of its EC) on a routine

basis, revision to this ODCM should be made in order to include a design

basis quantity specific to that nuclide.

1.4 GASEOUS RADWASTE TREATMENT SYSTEM OPERATION

1.4.1 System Description

The gaseous radwaste system has been removed during the dismantlement

process.

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1.5 OFF-SITE RELEASE RATE

1 0CFR50.36a requires that the release of radioactive materials be kept as

low as reasonably achievable. Appendix I to 1 OCFR50 provides the

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

reasonably achievable requirement.

The GASPAR code has been run to determine a conservative relationship

between release rate in Ci/sec and annual dose due to external radiation and

inhalation. The source term used is listed in Table 2-1. Dose using annual

average meteorology, to the individual with most limiting off-site dose (whole

body) assumed to be residing at the residence with highest X/Q, is

0.105 mrem for one year. The release rate which would result in a dose

equivalent of 500 mrem/y (using the total body limit upon which ODCM,

Section I Requirement 3.1 is based) is the Curies/Year given in Table 2-1

(1.29E04) multiplied by 500/0.105 or 1.95 Ci/sec.

The above is a one-time calculation during power operation and is

informational only. Methods of exposure calculations to be used for specific

releases over specific periods are described in Section II, Part 1.2.

1.6 PARTICULATE SAMPLING

Particulate samples are obtained from the continuous air monitors and grab

samples from another areas of potential airborne radioactivity utilized through

the course of decommissioning for work area monitoring.

Gamma and beta counting is performed on particulate filters. Beta yields of

the gamma isotopes detected on individual particulate filters at the time of

sampling are applied to determine "identified" beta, and after suitable decay

time for decay of radon and thoron daughters, the "identified" count rate is

subtracted from the observed count rate to give "unidentified" beta. The

"unidentified" beta is assumed to be Sr-90 until results of an optional analysis

specific to Sr-90 (from a quarterly composite of filters) are obtained.

Alternatively, Cs-1 37, if detected, may be utilized as a surrogate for Sr-90,

with Sr-90 equal to 3.0% of the Cs-137 value.

1.7 NOBLE GAS MONITORING AND SAMPLING

Noble gas monitoring and sampling are no longer required, since all spent

fuel is stored at the ISFSI facility in hermetically sealed containers.

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1.8 TRITIUM SAMPLING

Tritium has a low dose consequence to the public because of the very small

fraction of allowable quantity which is available for release. The major

contributor to tritium gaseous effluents is evaporation from the barrels of

groundwater that are evaporated rather than released as liquid, due to

detectable gamma radioactivity levels (contamination sometimes occurs from

contact with plant equipment and structural materials during dismantlement

operations). Because of the low dose impact, and due to the continuous

reduction in tritium source term since cessation of to reactor operation,

gaseous tritium sampling will not be required. Gaseous tritium release is

estimated using conservative evaporation rate calculations from the fuel pool

(702 uCi/day) at a time when its water contained significant levels of tritium.

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TABLE 2-1

BIG ROCK POINT GASEOUS AND LIQUID SOURCE TERMS. CURIES/YEAR (1)

Nuclide

H-3

N-13

Na-24

Cr-51

Mn-54

Mn-56

Co-58

Fe-59

Co-60

Zn-65

Br-82

Kr-83m

Kr-85

Kr-85m

Kr-87

Kr-88

Kr-89

Sr-89

Kr-90

Sr-90

Kr-91

Sr-91

Sr-92

Nb-95

Mo-99

Ag110im

Gaseous

1.21 E+01

1.53E+03

3.52E-04

2.82E-04

5.50E-05

1.70E-04

1.65E-06

2.81 E-06

1.89E-04

3.16E-05

8.11 E-03

2.61 E+02

9.55E-01

3.12E+02

1.19E+03

7.80E+02

6.96E+02

NA

7.76E+02

NA

6.68E+00

5.61 E-03

NA

1.91E-06

3.1 OE-05

1.57E-05

8.63E+00

NA

1.12E-06

6.84E-03

2.60E-02

NA

6.17E-04

9.05E-03

4.21 E-02

9.01 E-04

NA

NA

NA

NA

NA

NA

NA

2.27E-04

NA

2.22E-03

NA

NA

1.54E-06

NA

NA

6.88E-05

Nuclide

Sb-124

1-131

Xe-131m

1-132

1-133

Xe-133

Xe-133m

Cs-134

1-134

1-135

Xe-135

Xe-135m

Cs-136

Cs-137

Xe-137

Cs-138

Xe-138

Ba-139

Xe-139

Ba-140

La- 140

Xe- 140

Hg-203

Np-239

Unidentified

Beta

Gaseous

NA

1.94E-03

4.38E-01

8.07E-03

1.99E-02

2.01 E+02

6.OOE+00

4.04E-07

1.24E-02

3.OOE-02

1.11 E+03

1.15E+03

4.74E-05

1.51 E-04

1.11 E+03

3.17E-01

6.03E+03

1.32E-03

1.04E+03

1.86E-03

7.80E-03

7.23E+01

1.32E-06

1.44E-04

4.01 E-04

1.57E-04

NA

NA

NA

8.86E-05

NA

1.75E-02

NA

NA

NA

NA

NA

2.04E-01

NA

NA

NA

NA

NA

NA

5.04E-05

NA

NA

NA

2.42E-03 6.76E-02

(1)Operating plant data derived from taking the effluents released during

January-June 1980 through July-December 1983 and dividing by four.

that the nuclide was not detected in that effluent stream.

"NA" indicates

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TABLE 2-2

BASIC RADIONUCLIDE DATA

1

2

3

4

5

6

7

8

9

10

11

12

13

14

15

16

17

18

19

20

21

22

23

24

25

26

27

28

29

30

31

32

33

34

35

36

37

38

NUCLIDE'

Tritium

C-14

N-1 3

0-19

F-18

Na-24

P-32

Ar-41

Cr-51

Mn-54

Mn-56

Fe-59

Co-58

Co-60

Zn-69m

Zn-69

Br-84

Br-85

Kr-85m

Kr-85

Kr-87

Kr-88

Kr-89

Rb-88

Rb-89

Sr-89

Sr-90

Sr-91

Sr-92

Sr-93

Y-90

Y-91m

Y-91

Y-92

Y-93

Zr-95

Nb-95m

Nb-95

HALF-LIFE

(days)

4.49E 03

2.09E 06

6.94E-03

3.36E-04

7.62E-02

6.33E-01

1.43E 01

7.63E-02

2.78E 01

3.03E 02

1.07E-01

4.50E 01

7.13E 01

1.92E 03

5.75E-01

3.96E-02

2.21 E-02

2.08E-03

1.83E-01

3.93E 03

5.28E-02

1.17E-01

2.21 E-03

1.24E-02

1.07E-02

5.20E 01

1.03E 04

4.03E-01

1.13E-01

5.56E-03

2.67E 00

3.47E-02

5.88E 01

1.47E-01

4.29E-01

6.50E 01

3.75E 00

3.50E 01

LAMBDA

(Ils)

1.79E-09

3.84E-12

1.16E-03

2.39E-02

1.05E-04

1.273-05

5.61 E-07

1.05E-04

2.89E-07

2.65E-08

7.50E-05

1.78E-07

1.12E-07

4.18E-09

1.39E-05

2.03E-04

3.63E-04

3.86E-03

4.38E-05

2.04E-09

1.52E-04

6.86E-05

3.63E-03

6.47E-04

7.50E-04

1.54E-07

7.79E-10

1.99E-05

7.10E-05

1.44E-03

3.OOE-06

2.31 E-04

1.36E-07

5.46E-05

1.87E-05

1.23E-07

2.14E-06

2.29E-07

BETA 1

(MEV/DIS)

5.68E-03

4.95E-02

4.91 E-01

1.02E 00

2.50E-01

5.55E-01

6.95E-01

4.64E-01

3.86E-03

3.80E-03

8.29E-01

1.18E-01

3.41 E-02

9.68E-02

2.21 E-2

3.19E-01

1.28E 00

1.04E 00

2.53E-01

2.51E-01

1.32E 00

3.61 E-01

1.36E 00

2.06E 00

1.01 E 00

5.83E-01

1.96E-01

6.50E-01

1.95E-01

9.20E-01

9.36E-01

2.73E-02

6.06E-01

1.44E 00

1.17E 00

1.16E-01

1.81 E-01

4.44E-02

GAMMA 1

(MEV/DIS)

0.0

0.0

1.02E 00

1.05E 00

1.02E 00

4.12E 00

0.0

1.28E 00

3.28E-02

8.36E-01

1.69E 00

1.19E 00

9.78E-01

2.50E 00

4.16E-01

0.0

1.77E 00

6.60E-02

1.59E-01

2.21 E-03

7.93E-01

1.96E 00

1.83E 00

6.26E-01

2.05E 00

8.45E-05

0.0

6.95E-01

1.34E 00

2.24E 00

0.0

5.30E-01

3.61 E-03

2.50E-01

8.94E-02

7.35E-01

6.06E-02

7.64E-01

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TABLE 2-2

BASIC RADIONUCLIDE DATA

39

40

41

42

43

44

45

46

47

48

49

50

51

52

53

54

55

56

57

58

59

60

61

62

63

64

65

66

67

68

69

NUCLIDE

Mo-99

Tc-99m

Tc-99

Tc-104

Ru-106

Te-132

1-129

1-131

1-132

1-133

1-134

1-135

Xe-131m

Xe-1 33m

Xe-1 33

Xe-1 35m

Xe-135

Xe-i 37

Xe-138

Cs-134

Cs-135

Cs-136

Cs-137

Cs-138

Ba-139

Ba-1 40

La-140

Ce-144

Pr-143

Pr-144

Eu-152

HALF-LIFE

(days)

2.79E 00

2.50E-01

7.74E 07

1.25E-02

3.67E 02

3.24E 00

6.21E 09

8.05E 00

9.58E-02

8.75E-01

3.61 E-02

2.79E-01

1.18E 01

2.26E 00

5.27E 00

1.08E-02

3.83E-01

2.71 E-03

9.84E-03

7.48E 02

1.10E 09

1.30E 01

1.10E 04

2.24E-02

5.76E-02

1.28E 01

1.68E 00

2.84E 02

1.36E 01

1.20E-02

4.84E 03

LAMBDA

(I/s)

2.87E-06

3.21 E-05

1.04E-13

6.42E-04

2.19E-08

2.48E-06

1.29E-15

9.96E-07

8.37E-05

9.17E-06

2.22E-04

2.87E-05

6.80E-07

3.55E-06

1.52E-06

7.43E-04

2.09E-05

2.96E-03

8.15E-04

1.07E-08

7.29E-15

6.17E-07

7.29E- 10

3.58E-04

1.39E-04

6.27E-07

4.77E-06

2.82E-08

5.90E-07

6.68E-04

1.66E-09

BETA'

(MEV/DIS)

3.96E-01

1.56E-02

8.46E-02

1.60E 00

1.01 E-02

1.OOE-01

5.43E-02

1.90E-01

4.89E-01

4.08E-01

6.16E-01

3.68E-01

1.43E-01

1.90E-01

1.35E-01

9.58E-02

3.17E-01

1.77E 00

6.65E-01

1.63E-01

5.63E-02

1.37E-01

1.71E-01

1.20E 00

8.96E-01

3.15E-01

5.33E-01

9.13E-02

3.14E-01

1.21E 00

8.22E-02

GAMMA'

(MEV/DIS)

1.50E-01

1.26E-01

0.0

1.95E 00

0.0

2.33E-01

2.46E-02

3.81 E-01

2.24E 00

6.02E-01

2.59E 00

1.55E 00

2.01 E-02

4.15E-02

4.60E-02

4.32E-01

2.47E-01

1.88E-01

1.10E 00

1.55E 00

0.0

2.15E 00

5.97E-01

2.30E 00

3.53E-02

1.71E-01

2.31E 00

1.93E-02

0.0

3.18E 02

1.06E 00

Average energy per disintegration values were obtained from ICRP Publication Number 38,

Radionuclide Transformations: Energy and Intensity of Emissions, 1983 and

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

Summary Table, D.C. Kocher, May 1980.

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TABLE 2-3

USNRC COMPUTER CODE - XOQDOQ, VERSION 2.0 RUN DATE: 940629

.... BIG ROCK POINT XOQDOQ82 *** USING 01/01/89 - 12/31/93 MET DATA

ELEVATED RELEASE - 240' STACK

RELEASE TYPE OF

ID LOCATION

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/O

A MAXIMUM CHI/O

A MAXIMUM CHI/Q

A MAXIMUM CHI/Q

A MAXIMUM CHI/O

A MAXIMUM CHI/Q

A MAXIMUM CHI/O

A MAXIMUM CHI/Q

A MAXIMUM CHI/O

A MAXIMUM CHI/Q

DIRECTION DISTANCE FROM SITE X/Q

(MILES) (METERS) (SEC/M3

)

NO DECAY

UNDEPLETED

E 0.57 917. 4.91 E-08

ESE 0.52 837. 4.11 E-08

SE 0.55 885. 3.09E-08

SSE 0.58 933. 2.25E-08

S 0.68 1094. 2.07E-08

SSW 0.71 1143. 1.95E-08

SW 0.50 805. 3.58E-09

S 2.00 3219. 3.37E-08

SSW 2.00 3219. 2.73E-08

SW 2.50 4023. 1.85E-08

WSW 50.00 80467. 0.OOE+00

W 50.00 80467. 0.00E+00

WNW 15.00 24140. 1.12E-07

NW 50.00 80467. 0.OOE+00

NNW 50.00 80467. 0.OOE+00

N 50.00 80467. 0.OOE+00

NNE 2.00 3219. 4.47E-08

NE 1.50 2414. 4.63E-08

ENE 1.50 2414. 5.32E-08

E 1.00 1609. 5.40E-08

ESE 0.75 1207. 4.29E-08

SE 1.50 2414. 3.40E-08

SSE 1.50 2414. 3.59E-08

X/Q

(SEC/M3 )

2.26 D DECAY

UNDEPLETED

4.90E-08

4.10E-08

3.08E-08

2.24E-08

2.06E-08

1.94E-08

3.57E-09

3.35E-08

2.71 E-08

1.84E-08

0.OOE+00

0.OOE+00

7.29E-08

O.OOE+00

0.OOE+00

0.OOE+00

4.46E-08

4.62E-08

5.30E-08

5.39E-08

4.28E-08

3.38E-08

3.58E-08

X/Q

(SEC/M3 )

8.0 D DECAY

DEPLETED

4.85E-08

4.07E-08

3.05E-08

2.22E-08

2.03E-08

1.91 E-08

3.55E-09

3.31 E-08

2.67E-08

1.82E-08

0.OOE+00

0.OOE+00

8.26E-08

0.OOE+00

0.OOE+00

0.OOE+00

4.43E-08

4.54E-08

5.22E-08

5.30E-08

4.21 E-08

3.32E-08

3.52E-08

D/Q

(PER SQ. METER)

1.25E-09

1.16E-09

8.19E-10

5.12E-10

3.68E-1 0

3.65E-10

1.16E-10

1.34E-10

1.31E-10

3.84E-1 1

O.OOE+00

O.OOE+00

1.30E-10

O.OOE+00

0.OOE+00

0.OOE+00

1.90E-10

5.46E-1 0

5.79E-10

8.96E-10

9.15E-10

3.60E-10

2.57E-10

VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 73.10 REP. WIND HEIGHT (METERS) 71.3

NOTE: Big Rock Point meteorological data was gathered from sensors mounted on the

73-meter stack. Sensors were mounted into the prevailing wind direction.

Because of interference to the wind flow by the stack when winds were from the

71 E to 159E (east, towards Lake Michigan), the meteorological data recorded in

these sectors are considered invalid. For dose calculational purposes, this

effectively invalidates six (6) lakeward sectors (WSW, W, WNW, NW, NNW,

and N). Therefore zeros are recorded in Table 2-3 for these sectors. However,

the program which calculates the annual average X/Q (Chi/Q) requires input of

the full years met data. Any data recorded for these six sectors are input in the

WNW sector to satisfy the program. Values of X/Q listed in the WNW sector

are invalid.

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TABLE 2-4

CONSERVATIVE BIG ROCK POINT GASPAR INPUT PARAMETERS

Critical Receptors

X/Q

X/Q Decay

Distance X/Q Decay and Dep

Sector (miles) (sec/m;) (sec/m;) (sec/m;)

Release

Location Tvpe

Residence/ Stack

Garden Ground

Site Stack

Boundary Ground

Beef Cattle Stack

Ground

Dairy Cow Stack

Ground

E

E

E

E

E

E

E

E

0.57

0.57

0.57

0.57

0.57

0.57

0.57

0.57

4.91 E-08

8.1 OE-08

4.91 E-08

8.1OE-08

4.91 E-08

8.1 OE-08

4.91 E-08

8.1 OE-08

4.90E-08

8.09E-08

4.90E-08

8.09E-08

4.90E-08

8.09E-08

4.90E-08

8.09E-08

4.85E-08

8.OOE-08

4.85E-08

8.OOE-08

4.85E-08

8.OOE-08

4.85E-08

8.OOE-08

D/Q

1.25E-09

2.06E-09

1.25E-09

2.06E-09

1.25E-09

2.06E-09

1.25E-09

2.06E-09

NOTE: Long term X/Q and D/Q values for ground level release have been calculated

for this table and for Figure 2-2 by multiplying the ratio of the elevated (stack)

long term to short term X/Q at 0.57 miles times the short term ground level X/Q

at various distances (in Table 2-4 above only at 0.57 miles).

Final (1998) Land Use Census illustrates actual land use:

Sector

WSW

SW

SSW

S

SSE

SE

ESE

E

ENE

Residence

2.5 mi

1.1 mi

1.3 mi

1.9 mi

1.7 mi

1.8 mi

1.5 mi

1.4 mi

2.3 mi

Garden

>5 mi

2.7 mi

>5 mi

2.1 mi

1.7 mi

1.8 mi

1.8 mi

2.4 mi

>5 mi

Dairy Cow

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

4.5 mi

>5 mi

3.5 mi

>5 mi

Beef Cattle

>5 mi

>5 mi

>5 mi

>5 mi

1.7 mi

1.7 mi

.3.2 mi

3.2 mi

>5 mi

Goat

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

>5 mi

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TABLE 2-5

BIG ROCK POINT SITE-SPECIFIC PARAMETERS FOR GASPAR

891.0 = Meters from facility to the NE corner of US 31"

0.33 = Fraction of year leafy vegetables are grown

0.58 = Fraction of year cows are on pasture

0.76 = Default value fraction of crop from garden

1.0 = Default value fraction of daily intake of cows, goats and

beef cattle derived from pasture while on pasture

2,160 = Hours hold-up for stored feed

50 = Kg/d feed consumed by cow and beef cattle

0.67 = Fraction of year goats are on pasture

6.0 = K /d feed consumed by goat

0.58 = Fraction of year beef cattle are on pasture

2.0 = Days transport time from feed to milk receptor

*NOTE: Independent Spent Fuel Storage Installation is located 300 meters from site

boundary, but source of gaseous effluents is plant dismantlement, not release

from ISFSI. Fuel containers at ISFSI are hermetically sealed, and provide no

detectable gaseous effluent.

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TABLE 2-6

BIG ROCK POINT GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES

BASED ON TABLE 2-4 CRITICAL RECEPTORS FOR STACK RELEASE

Nuclide

H-3

C-14

Cr-51

Mn-54

Fe-55

Co-58

Fe-59

Co-60

Zn-65

Sr-89

Sr-90

Zr-95

Sb-124

Ar-41

Kr-83m

Kr-85

Kr-85m

Kr-87

Kr-88

Kr-89

Xe-131m

Xe-133

Xe-1 33m

Xe-135

Xe-1 35m

Xe-137

Xe-138

1-131

1-133

Cs-134

Cs-136

Cs-137

Ba-140

Ce-141

Ce-144

N-1 3

Na-24

Mn-56

Co-57

Ni-63

Ni-65

Organ

Total Body - C

Bone - C

GI Tract - T

Gl Tract - T

Bone - C

GI Tract - T

GI Tract - T

GI Tract - T

Total Body - C

Bone - C

Bone - C

GI Tract - T

GI Tract - T

Total Body

Skin

Skin

Total Body

Skin

Total Body

Total Body

Skin

Total Body

Skin

Total Body

Total Body

Skin

Total Body

Thyroid - I

Thyroid- I

Liver - C

Total Body - I

Bone - C

Bone - C

GI Tract - T

GI Tract - T

Total Body - C

Total Body- I

GI Tract - C

GI Tract - T

Bone - C

GI Tract - T

Dose Factor

mrem/Ci

1.06E-05

8.70E-03

7.03E-04

9.OOE-02

4.15E-02

4.25E-02

7.37E-02

1.OOE+00

2.82E-01

1.42E+00

5.55E_01

8.85E-02

1.59E-01

9.07E-06

2.20E-08

2.21 E-06

1.24E-06

2.07E-05

1.54E-05

2.27E-06

9.29E-07

3.20E-07

1.94E-06

1.95E-06

2.22E-06

3.80E-06

6.02E-06

1.11E+01

1.08E-01

2.1OE+00

5.04E-02

2.14E+00

107E-02

2.10E-02

5.02E-01

6.81 E-08

8.19E-04

2.16E-04

1.47E-02

2.54E+00

1.35E-04

Design Obiective

Annual Quantity (Ci)

4.72E+05

1.72E+03

2.13E+04

1.67E+02

3.61 E+02

3.53E+02

2.04E+02

1.50E+01

1.77E+01

1.06E+01

2.70E-01

1.69E+02

9.43E+01

5.51 E+05

6.82E+08

6.79E+06

4.03E+06

7.25E+05

3.25E+05

2.20E+06

1.16E+07

1.56E+07

7.73E+06

2.56E-06

2.25E+06

3.95E+06

8.31 E+05

1.35E+00

1.39E+02

7.14E+00

9.92E+01

7.01 E+00

1.40E+03

7.15E+02

2.99E+01

7.34E+07

6.11 E+03

6.94E+04

1.02E+03

8.45E+00

1.11E+05

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TABLE 2-6

BIG ROCK POINT GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES

BASED ON TABLE 2-4 CRITICAL RECEPTORS FOR STACK RELEASE

CAUTION: To obtain ground-level release dose factors, multiply Table 2-6 values by 1.65.

To obtain ground-level release design objective annual quantities, multiply

I by 0.61. ,

Nuclide

Br-82

Rb-88

Sr-91

Sr-92

Nb-95

Mo-99

Tc-99

Tc-99m

Ru-103

Ru-105

Sb-1 25

Te-127

1-129

1-132

1-134

1-135

La-140

Tc-101

Ag-110m

Cs-138

Ba-139

Eu-1 52

Np-239

Pu-238

Pu-239

Pu-241

Am-241

Cm-242

Cm-244

Organ

Total Body - I

Total Body - C

Bone - I

GI Tract - C

GI Tract - A

Kidney- I

GI Tract - A

GI Tract - T

GI Tract - A

GI Tract - C

GI Tract - T

GI Tract - T

Thyroid - A

Thyroid - C

Thyroid - C

Thyroid - C

GI Tract - A

GI Tract - I

GI Tract - T

Total Body - C

GI Tract - C

Skin

GI Tract - A

Bone - T

Bone - T

Bone - T

Bone - T

Lung - T

Bone - T

Dose Factor

mrem/Ci

4.73E-03

1.29E-06

6.23E-02

3.88E-04

1.79E-01

6.81 E-03

5.47E-01

1.67E-05

2.66E-01

1.74E-04

7.05E-02

1.31 E-04

7.41 E+01

3.09E-04

7.69E-05

1.40E-03

2.42E-03

8.94E06

9.17E-01

1.16E-02

8.59E-05

8.19E-01

6.27E-04

3.75E+01

4.34E+01

9.17E-01

1.51 E+01

8.32E-01

9.70E+00

Design Objective Annual

Quantity (Ci)

1.06E+03

3.88E+06

2.41 E+02

3.87E+04

8.38E+01

2.20E+03

2.74E+01

8.98E+05

5.64E+01

8.62E+04

2.13E+02

1.15E+05

2.02E-01

4.85E+04

1.95E+05

1.07E+04

6.20E+03

1.68E+06

1.64E+01

4.31 E+02

1.75E+05

1.83E+01

2.39E+04

4.OOE-01

3.46E-01

1.64E+01

9.93E-01

1.80E+01

1.54E+00

NOTE: Ground-level releases result in doses that are 1.65 times the doses from stack

releases.

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2.0

2.1

LIQUID EFFLUENTS

ALLOWABLE CONCENTRATION

2.1.1 ODCM Requirement

Requirement 2.2.2 of ODCM, Section I specifies 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 specified in 1 OCFR20,

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

noble gases. Plant effluents contain no more dissolved or entrained noble

gases. The following approach will be used.

2.1.2 Pre-release Analysis

Prior to first release for a season from water detained for sedimentation, a

grab sample will be obtained and analyzed.

2.1.3 Total Release-fraction

The total release-fraction (R j) will be calculated by the relationship defined

as:

R

Where:

Ci.

lOxECi (2.1)

C j = Undiluted effluent concentration of radionuclide i, as determined

in Section II, Part 2.1.2, pCi/ml, at release point j.

EC = The 10CFR20 effluent concentration limit (EC) of radionuclide i,

as specified in Section II, Part 2.1.1, pCi/mI (Big Rock Point still

uses MPC terminology in some Liquid Analyses Programs,

although EC values are utilized).

R. = The total release-fraction for the release point.

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2.2 INSTRUMENT ALARM SET POINTS

No installed monitors are required.

2.3 LIQUID EFFLUENT DOSE CALCULATION

2.3.1 Applicability

This section provides methodology for calculating doses in compliance with

Section I, Requirement 2.3.2.

2.3.2 Calculation of Desiqn Basis Quantity Fraction

Calculations shall be performed according to the formula:

E A-= Fraction of DBQ

(DBQ)i

Where:

(2.2)

Ai = Cumulative or projected 31-day, quarterly or annual activity of

nuclide i identified or expected in liquid release (Ci).

(DBQ)I= Design objective annual quantity of radionuclide i from

Table 2-8 (Ci).

2.3.3 Use of LADTAP

As an alternative to use of the DBQ fraction, the NRC LADTOP code may be

run to confirm that ODCM, Requirement 2.3.2 of ODCM, Section I has been

met.

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2.3.4 Dose Calculation

Values for the design basis quantities (Ci), and the dose per curie (Dc/Cc)i for

each nuclide i shown in Table 2-8, were calculated by use of LADTAP.

Site-specific values for LADTAP runs are found in Tables 2-8 and 2-9.

F = Amount of fish eaten per year; adult - 21 kg, teen - 16 kg, child -

6.9 kg and infant - none.

15 = Dispersion factor from discharge to fish exposure point.

Releasing Radionuclides Not Listed in Table 2-9

Table 2-9 contains all nuclides identified to date as routine constituents of

liquid releases at BRP Plant, plus those common to boiling water reactors in

general, even if not previously detected at BRP. From time to time, however,

other nuclides may be detected.

If the unlisted nuclide constitutes less than ten percent of the EC-fraction for

the release, and all unlisted nuclides total less than 25% of the EC-fraction,

the nuclide may be considered not present.

If the unlisted nuclide constitutes greater than ten percent of the EC-fraction,

or all unlisted nuclides together constitute greater than 25%, then each

nuclide should be assigned a DBQ equal to the most conservative value listed

for the physical form of the nuclide involved.

Should a nuclide not listed in Table 2-9 begin to appear in significant

quantities on a routine basis, revision to this ODCM should be made in order

to include a design basis quantity specific to that nuclide.

2.3.5 Annual Analysis

A complete analysis utilizing the NRC computer code LADTAP (either by

running the code, or by normalization of data to results of a previous year's

run) for the total release source 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.

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2.4 FUNCTIONALITY OF LIQUID RADWASTE EQUIPMENT

All installed liquid radwaste systems have been removed from service for

dismantlement.

2.5 OFF-SITE RELEASE RATE

1 0CFR50.36a requires that the release of radioactive materials be kept as

low as is reasonably achievable. Appendix I to 1 OCFR50 provides the

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

as is reasonably achievable requirement.

Table 2-9 specifies a Design Basis Annual Quantity for the limiting

radionuclide currently present on-site (Cs-1 37) equal to 6.62E-03 Ci/y, or

release rate of 18.4 uCi/day. The other two radionuclides currently detected

in plant demolition debris are Co-60 and Eu-1 52. Both of these radionuclides

have Design Basis Annual Quantities approximately order of magnitude

higher Cs-1 37.

Annual analyses are run for the report specified in Part 1.5 of ODCM,

Section III. LADTAP is used to calculate estimates of dose to the total body

and limiting organs.

Radionuclides of highest dose consequence will remain predominately

Cs-1 37 and Co-60 throughout the decommissioning interval. lodine-131 and

Cs-1 34, which have been important dose contributors during power

operations, no longer are present in effluents in detectable concentrations

due to decay.

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TABLE 2-7

BIOACCUMULATION FACTORS

(uCi/c per uCi/mI)

Element Freshwater Fish

H 9.OE-01

C 4.6E+03

Na 1.OE+02

P 1.0E+03

Cr 2.OE+02

Mn 4.OE+02

Fe 1.OE+02

Co 5.OE+01

Ni 1.OE+02

Cu 5.OE+01

Zn 2.OE+03

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.OE+01

Tc 1.5E+01

Ru 1.OE+01

Rh 1.OE+01

Te 4.OE+02

I 1.5E+01

Cs 2.OE+03

Ba 4.0E+00

La 2.5E+01

Ce 1.OE+00

Pr 2.5E+01

Nd 2.5E+01

W 1.2E+03

Np 1.OE+01

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TABLE 2-8

BIG ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID

EFFLUENTS AS DETERMINED BY LADTAP

Design objective annual quantities for liquid effluents were calculated utilizing the

computer code LADTAP, a program for calculating radiation exposure to man from

routine releases of nuclear reactor liquid effluents (Reference NUREG/CR-1 276).

Input parameters used are as follows:

Process Times

Pathway Age Group (Hr)

Fish

Drinking

Shoreline

Swimming

Boating

Adult

Teen

Child

Infant

Adult

Teen

Child

Infant

Adult

Teen

Child

Infant

Adult

Teen

Child

Infant

Adult

Teen

Child

Infant

Usage

21.0 kg/yr

16.0

6.9

0.0

730.0 L/yr

510.0

510.0

330.0

12.0 hr/yr

67.0

14.0

0.0

12.0 hr/yr

67.0

14.0

0.0

100.0 hr/yr

100.0

50.0

0.0

15.0

15.0

15.0

15.0

800.0

800.0

800.0

800.0

2.0

2.0

2.0

2.0

2.0

2.0

2.0

2.0

15.0

15.0

15.0

15.0

24.0

24.0

24.0

24.0

4.6

4.6

4.6

4.6

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

0.0

Dilution

The usage figures are obtained from Regulatory Guide 1.109 and are default values.

Dilutions and the process time for drinking water were taken from the NUS study dated

June 4, 1976. Including the process times shown in this table, total transit time for sport

fish is 168 hours, commercial fish is 240 hours, and drinking water is 28.6 hours.

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TABLE 2-8

BIG ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID

EFFLUENTS AS DETERMINED BY LADTAP

The following input parameters are used when running LADTAP for BRP:

1. 50-mile population - 1.94E05

2. Shore width factor - 0.3

3. Total discharge (ft/sec) - Actual value

4. Transit time for all pathways - See note for Table 2-2.

5. Sport fish harvest (kg/yr) - 3.29E05

6. Commercial fish harvest (kg/yr) - 1.70E05

7. Invertebrate and algae consumption - 0

8. Drinking water population - 7.07E03

9. Shoreline population usage (man-hours) - 3.8E07

10. Swimming population usage (man-hours) - 1.2E07

11. Boating population usage (man-hours) - 3.7E07

12. Dilution factor to drinking water intake - 800

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TABLE 2-9

BIG ROCK POINT DESIGN OBJECTIVE ANNUAL QUANTITIES FOR LIQUID

EFFLUENTS AS DETERMINED BY LADTAP

Dose Conversion

Nuclide Factors (mrem/Ci)

Design Objective

Annual Quantity

Individual/Or-gan (Curies)

H-3

Sc-46

Mn-54

Fe-55

Co-57

Co-58

Co-60

Zn-65

Sr-89

Sr-90

Zr-95

Ag-110m

Cd-1 13m

Sb-124

Sb-1 25

Te-127m

Cs-134

Cs-137

Ce-1 44

Eu-152

5.11 E-04

2.71 E+00

1.83E+01

1.20E-00

6.12E-01

1.52E+00

6.33E+01

4.67E+01

4.21 E+01

7.29E+02

8.34E-01

1.04E+01

1.61 E+01

2.04E+00

6.84E+00

3.73E+01

7.63E+02

4.54E+02

8.91 E-01

4.33E+01

Adult/TB

Teen/TB

Adult/GI(LLI)

Child/Bone

Teen/TB

Teen/TB

Teen/TB

Child/TB

Child/Bone

Adult/Bone

Teen/TB

Teen/TB

Adult/GI(LLI)

Teen/TB

Teen/TB

Teen/Kidney

Adult/TB

Adult/TB

Adult/GI(LLI)

Teen/TB

5.87E+03

1.11 E+00

5.47E-01

8.36E00

4.91 EO0

1.97E00

4.74E-02

6.43E-02

2.37E-01

1.38E-02

3.60E+00

2.90E-01

6.23E-01

1.48E+00

3.39E-01

2.68E+01

3.93E-03

6.62E-03

1.12E+01

6.91 E-02

Based on a current average discharge flow rate of 224 gpm.

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FIGURE 2-1

N

SLowv Woter Lino % LAKE MCHIGAN

69Q0 Above

BIG ROCK POINT

SITE MAP~

* Gaseous release: point is at ground level (590' above sea level) now that the stack has

been removed for dismantlement.

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FIGURE 2-2

GROUND LEVEL X/Qs FOR GROUND LEVEL RELEASE CALCULATIONS

1.00EmN4

Ground Level XIQ)vs Dlistance (m)

1 OOE-05,

1.00&-O6

1.00E-07

1 .00E-08

0 200 400 600 800 1000, 1200 .1400 1600

meters

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A. OFF-SITE DOSE CALCULATION MANUAL

SECTION II- METHODOLOGIES FOR

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3.0 CALCULATION OF URANIUM FUEL CYCLE DOSE

3.1 APPLICABILITY

Uranium Fuel Cycle dose is calculated when effluent doses exceed twice the

levels specified in either ODCM, Section I, Requirement 1.3.2 or 3.2.2.

3.2 ASSUMPTIONS

3.2.1 The full time resident determined to be the 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 indicated by the input

parameters are summarized in Table 2-8.

3.2.2 Amount of shoreline fishing at accessible shoreline adjacent to the site 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 18 hours for the first quarter.

3.2.3 The dose contribution due to uranium fuel cycle sources other than the plant

(but including ISFSI) is ignored in the calculation. This is based on the lack of

any operations that fall in the "cycles" definition within a five-mile radius of

BRP.

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3.3 DOSE CALCULATION

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

determined by use of LADTAP and GASPAR computer codes or optionally,

by conservatively multiplying the mrem/Ci factors of Tables 2-6 and 2-9 by

quantity released. Doses to like organs and total body shall be summed

(organs are conservatively summed with total body when Tables 2-6 and 2-9

are utilized). Added to this sum will be a mean dose rate, calculated or

measured for the shoreline due to the plant (ISFSI) during the quarter in

question, times the assumed fishing time:

NOTE: For this calculation, the total body is conservatively assumed to be

an additional organ.

D40 , =DG+ DL+(RT)(T) (3.1)

Where:

D40, 40CFR190 dose to organ (i) (mrem).

DG = Cumulative dose to an individual organ from gaseous releases

(mrem).

DL = Cumulative dose to an individual organ from liquid releases

(mrem).

RT = Mean dose rate (direct radiation component) calculated to be

applicable to Lake Michigan shoreline adjacent to plant site

(mrem/hr).

T = Assumed shoreline fishing time for the quarter in question

(hours) (see 3.2.2 above).

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ODCM SECTION III

REPORTING AND MAJOR MODIFICATION REQUIREMENTS

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A. OFF-SITE DOSE CALCULATION MANUAL

SECTION III - REPORTING AND MAJOR

MODIFICATION REQUIREMENTS

1.0 RADIOLOGICAL EFFLUENT RELEASE REPORT

The Radioactive Effluent Release Report shall be submitted by May 1 of each

year. The report shall include a summary of the quantities of radioactive

liquid and gaseous effluents and solid waste released from the unit. The

material provided shall be (1) consistent with the objectives outlined in the

ODCM and Process Control Program, and (2) in conformance with

10CFR50.36a and Section IV.B.1 of Appendix I to 10CFR50.

1.1 ESTIMATE OF UNCERTAINTY

The report shall include an estimate of the uncertainty associated with the

measurement of radioactive effluents. This error term is included to provide

an estimate of the uncertainty and is not to be considered the absolute error

associated with the measurements or to be used in determining compliance

with these requirements.

Estimates for liquid releases will be based on a statistical analysis of a series

of sample results (weighed appropriately for counting statistics) taken once a

year from a minimum of one typical liquid radwaste tank or other liquid

effluent source. The error term for particulates released to the atmosphere

will be based on the counting statistics for one air particulate sample taken

during the year.

The report shall include an estimate of the lower level of detection (in uCi/ml)

if the unidentified portion of the release exceeds ten percent of the total

annual releases. This estimate of the lower level of detection will be made for

gamma emitting isotopes listed in Appendix B of Regulatory Guide 1.21

(June 1974) and will be provided based on a typical background spectrum.

1.2 SUPPLEMENTAL INFORMATION

a. Batch Releases

Although both liquid and gaseous releases occur with variable rates

and have variable durations, they shall be treated as continuous

releases, rather than batches.

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b. Abnormal Releases

The number of abnormal releases and number of curies of radioactive

material released to the environment during abnormal releases should

be reported.

1.3 GASEOUS EFFLUENTS

a. Gases (all plant contributions are zero).

b. lodines (all plant contributions are zero).

c. Particulates

1) Total curies of radioactive material in particulate form with

half-lives greater than eight days determined to have been

released.

2) Average release rate (uCi/s) of radioactive material in

particulate form with half-lives greater than eight days.

3) Percent of limit for radioactive material in particulate form with

half-lives greater than eight days.

4) Total curies for each of the radionuclides in particulate form

determined to be released based on analyses performed.

5) Total curies of gross alpha radioactivity of plant origin

determined to be released.

d. Tritium

1) Total curies of tritium estimated to be released in gaseous

effluent.

2) Average release rate (uCi/s) of tritium.

3) Percentage of applicable limits for tritium.

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1.4 LIQUID EFFLUENTS

a. Mixed Fission and Activation Products

1) Total curies of radioactive material determined to be released in

liquid effluents (not including tritium, dissolved and/or entrained

gases, and alpha-emitting material).

2) Average concentrations (uCi/ml) of mixed fission and activation

products released to unrestricted areas, averaged over the

quarterly periods covered by the report.

3) Percent of applicable limit of average concentrations released to

unrestricted areas.

4) Quarterly sums of total curies for each of the radionuclides

determined to be released in liquid effluents based on analyses

performed.

b. Tritium

1) Total curies of tritium determined to be released in liquid

effluents.

2) Average concentrations (uCi/ml) of tritium released to

unrestricted areas, averaged over the quarterly periods covered

by the report.

3) Percent of applicable limit of average concentrations released to

unrestricted areas.

c. Dissolved and/or Entrained Gases (all plant contributions are zero)

d. Alpha Radioactivity

Total curies of gross alpha-emitting materials of plant origin determined

to be released in liquid effluents.

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e. Volumes

1) Total measured volume (liters), prior to dilution, of liquid effluent

released.

2) Total determined volume, in liters, of dilution water used during

the period of the report.

1.5 SOLID WASTE

The Radioactive Effluent Release Reports shall include the following

information for each class of solid waste (as defined by 1 OCFR61) shipped

off-site during the report period:

a. Container burial volume,

b. Total curie quantity (specify whether determined by measurement or

estimate),

c. Principal radionuclides (specify whether determined by measurement

or estimate),

d. Source of waste and processing employed (i.e., dewatered spent resin,

compacted dry waste, evaporator bottoms),

e. Type of container (i.e., LSA, Type A, Type B, Large Quantity); and

f. Solidification agent or absorbent (i.e., cement, asphalt).

1.6 RADIOLOGICAL IMPACT ON MAN

The Radioactive Effluent Release Report shall include potential doses to

individuals and populations calculated using measured effluent and averaged

meteorological data in accordance with the methodologies of ODCM,

Section II.

a. Total body and significant organ doses (greater than 1 millirem) to

individuals in restricted areas from receiving water-related exposure

pathways.

b. Maximum off-site air doses greater than one millirad due to beta and

gamma radiation at locations near ground level from gaseous effluents.

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c. Organ doses greater than one millirem to individuals in unrestricted

areas from radioactive iodine and radioactive material in particulate

form from the major pathways of exposure.

d. Total body doses greater than one manrem to the population and

average doses greater than one millirem to individuals in the

population from receiving water-related pathways to a distance of

50 miles from the site.

e. Total body doses greater than one manrem to the population and

average doses greater than one millirem to individuals in the

population from gaseous effluents to a distance of 50 miles from the

site.

1.7 ODCM CHANGES

The Radiological Effluent Release Report shall include any changes made

during the reporting period to the Off-site Dose Calculation Manual (ODCM),

including identification of new locations for dose calculations and/or

environmental sampling (ODCM, Section II, Table 2-4 and ODCM, Section 1,

Table 1-1, respectively).

2.0 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Radiological Environmental Operating Report covering the operation of

the unit during the pervious calendar year shall be submitted before May 1 of

each year. The report shall include summaries, interpretations and analysis

of trends of results of the Radiological Environmental Monitoring Program for

the reporting period. The material provided shall be consistent with the

objectives outlined in the ODCM and Sections IV.B.2, IV.B.3 and IV.C of

Appendix I to 1OCFR50.

The Radiological Environmental Operating Report shall include summaries,

interpretation and statistical evaluation of the results of the radiological

environmental surveillance activities for the report period, including a

comparison with previous environmental surveillance report data of similar

type and an assessment of the observed impacts of the Plant operation on

the environment.

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MODIFICATION REQUIREMENTS

The Annual Radiological Environmental Operating Report shall include

summarized and tabulated results 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 report also shall provide a summary description of the environmental

monitoring program and a map depicting sample locations.

3.0 NON-ROUTINE REPORTS

A report shall be submitted to the NRC in the event that:

a. The Radiological Environmental Monitoring Program is not

substantially conducted as described in ODCM, Section I, Part 4.0.

b. Dose to an off-site individual is estimated to have exceeded the

requirements of 40CFR190, per ODCM, Section I, Part 3.0.

c. An unusual or important event occurs due to plant operations that

causes a significant radiological environmental impact or affects a

potential environmental impact.

d. Non-routine reports shall be submitted within 30 days of determining

that an event has occurred to require such report.

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SECTION III - REPORTING AND MAJOR

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4.0 MAJOR MODIFICATION OF RADIOACTIVE WASTE SYSTEMS

4.1 APPLICABILITY

All installed radioactive waste systems have been dismantled.

Dismantlement was performed after determining that removal would not

cause effluents to exceed Specifications 1.3 or 2.3 of ODCM, Section I, or

cause effluents to exceed two percent of the annual limit on a monthly basis.

4.1.1 Major modifications of the radwaste system, as defined in Requirement 4.2.2

below, shall be reported to the NRC pursuant to 1OCFR50.59. 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 10CFR50.59.

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 NRC.

4.1.2 Shall become effective upon review and acceptance by the Site General

Manager.

4.2 DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION OR

EQUIVALENT 0DCM REVISION

4.2.1 Purpose

The purpose of this definition is to assure that modifications (including

removal) of radwaste systems during decommissioning or revisions to ODCM

do not increase the potential for dose due to effluents to exceed the quarterly

or semiannual limits of Specifications 1.3 or 2.3, ODCM, Section I or cause

effluent dose to exceed two percent of the annual limit on a monthly basis.

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4.2.2 Definition

A major radwaste system modification is a modification which would cause

reduction in effluent treatment, monitoring or control that would result in

inability to meet the quarterly or semiannual off-site dose limits of

Specifications 1.3 (airborne release) or 2.3 (liquid release), of ODCM,

Section I. In addition, a major modification would be determined by inability of

new equipment or techniques to maintain effluents below two percent of the

annual limits in a month, provided that the original equipment would have

been capable of meeting that goal.

Improvements or additions to reduce radioactivity in effluents shall not be

considered major modifications, nor will any dismantlement activities that do

not cause effluents to exceed two percent of the Appendix I limits in any

31-day interval.

25-PartA.doc 01/04/07