CommmftdtoNucearExcp Palisades Nuclear Plant

Operated by Nuclear Management Company, LLC

March 29, 2006 10 CFR 50.36a

Technical Specification 5.6.3

U. S. Nuclear Regulatory Commission

ATTN: Document Control Desk

Washington, DC 20555-0001

Palisades Nuclear Plant

Docket 50-255

License No. DPR-20

2005 Annual Radioactive Effluent Release and Waste Disposal Report

Enclosed is the Nuclear Management Company, LLC, (NMC) 2005 Annual Radioactive

Effluent Release and Waste Disposal Report for the Palisades Nuclear Plant. This

report is submitted in accordance with 10 CFR 50.36a(a)(2) and Palisades Technical

Specification 5.6.3.

This report provides a summary of the quantities of radioactive liquid and gaseous

effluent releases and solid radioactive waste processed during the period of

January 1, 2005, through December 31, 2005.

Summary of Commitments

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

Paul A, Harden

Site Vice President, Palisades Nuclear Plant

Nuclear Management Company, LLC

Enclosure (1)

Attachments (7)

CC Administrator, Region l1l, USNRC

Project Manager, Palisades, USNRC

Resident Inspector, Palisades, USNRC

27780 Blue Star Memorial Highway * Covert, Michigan 49043-9530

Telephone: 269.764.2000
ENCLOSURE 1

2005 ANNUAL RADIOACTIVE EFFLUENT RELEASE

AND WASTE DISPOSAL REPORT

JANUARY 2005 - DECEMBER 2005

2005 Plant Operating History

Palisades Nuclear Plant (PNP) was in service until January 9, 2005, when the plant was

taken off line due to a loss of main condenser vacuum. The unit returned to service on

January 19, 2005. PNP was taken off line on September 1, 2005, due to a hydrogen

leak associated with the main generator. The unit was returned to service on

September 3, 2005. The plant was taken off line on December 31, 2005, for control rod

drive mechanism seal repair, and was off line for the remainder of the year.

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

None.

C. 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." In

addition, minimum detectable activities (MDA) achieved during typical batch

release processing are provided for reference.

D. Results of the 2005 Radiochemistry Cross Check Program with Analytics are

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

three detectors.

E. Radioactive Effluent Monitoring Instrumentation

The ODCM, Appendix A, "Relocated Technical Specifications per NRC

Generic Letter 89-01 (TAC No 75060)," Revision 11, requires that any

gaseous or liquid effluent monitor out of service for greater than 30 days be

included in this effluent report. From December 13, 2004, to March 24,

2005, RIA-2323, radiation indicating alarm for the "B" main steam safety and

dump valve discharge line was out of service. The time out of service was

due to lead time needed to obtain adequate parts and repairs. In

accordance with the ODCM, Table A-1, Action 4.b, a special report was

submitted to the NRC on January 10, 2005, detailing the cause of the event.

Page 1 of 5
RIA-2320, steam generator blowdown vent monitor, was out of service from

August 17, 2005, through the end of 2005. RIA-2320 monitors an

effluent pathway that is not used at PNP, and no compensatory actions wvere

required for this monitor being out of service.

RIA-1 113, waste gas discharge process monitor, was out of service from

September 6, 2005, through the end of 2005. The time out of service was

due to the original electronic module being damaged beyond repair during

shipment or receipt by the vendor, and it being an obsolete part. An

engineering change modification is in progress to replace the original analog

monitor with a digital monitor. ODCM required compensatory actions were

taken during subsequent waste gas decay tank releases.

2. Gaseous Effluents

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

all gaseous radioactive effluents released during the reporting period. The

unidentified beta was 6.44E-05% of the gaseous release (excluding tritium).

There were no fuel failures in 2005.

3. Licuid Effluents

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

liquid radioactive effluents released during the reporting period. The unidentified

beta was 4.18% of the liquid release (excluding tritium).

4. Estimate of Uncertainty

Both the Gaseous and Liquid Summation of Release data sheets include estimates

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 Total

Error %" columns on the Gaseous and Liquid Summation Reports.

5. Solid Waste

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

burial in 2005, 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.

Page 2 of 5
6. Summary of Radiological Impact on Man

Doses to individuals and populations were calculated using GASPAR and

LkDTAP computer program codes. The quarterly values for curies released were

input for each nuclide and are summarized as follows:

A. The offsite air doses at site boundary (0.48 miles south-south east (SSE')

due to noble gases were:

First Quarter -

Second Quarter -

Third Quarter -

Fourth Quarter -

2.38E-05 millirad beta and 8.32E-06 millirad gamma

4.51 E-05 millirad beta and 1.55E-05 millirad gamma

5.79E-05 millirad beta and 1.98E-05 millirad gamma

3.OOE-03 millirad beta and 9.91 E-04 millirad gamma

The maximum noble gas offsite air dose to the nearest residence (0.50 miles

south) occurred during the fourth quarter, when beta and gamma doses

were estimated at 1.95E-03 millirad and 6.44E-04 millirad, respectively.

B. The most restrictive organ dose to an individual in an unrestricted area

(based on identified critical receptors) from gaseous effluent releases were:

First Quarter -

Second Quarter -

Third Quarter

Fourth Quarter -

3.97E-02 millirem (child thyroid)

1.98E-02 millirem (child thyroid)

2.21 E-02 millirem (child thyroid)

2.93E-02 millirem (child skin)

C. Integrated total body doses to the general population, and average doses to

individuals within the population from gaseous effluent release pathways to a

distance of 50 miles from the site boundary were:

First Quarter -

Second QuarterThird Quarter -

Fourth Quarter -

1.49E-01 person-rem and 1.13E-04 millirem

7.30E-02 person-rem and 5.53E-05 millirem

8.18E-02 person-rem and 6.20E-05 millirem

1.08E-01 person-rem and 8.18E-05 millirem

D. The maximum total body dose to an individual in unrestricted water-related

exposure pathways was:

First Quarter -

Second QuarterThird Quarter -

Fourth Quarter -

1.42E-04 millirem (teen)

3.36E-04 millirem (adult)

1.09E-03 millirem (teen)

1.63E-03 millirem (teen)

Page 3 of 5
The maximum organ dose and critical receptor organ was:

First Quarter - 1.67E-04 millirem (teen liver)

Second Quarter- 5.04E-04 millirem (teen liver)

Third Quarter - 1.57E-03 millirem (teen liver)

Fourth Quarter - 1.74E-03 millirem (teen skin)

E. Integrated total body doses to the general population, and average doses to

individuals within the population from liquid effluent release pathways to a

distance of 50 miles from the site boundary were:

First Quarter - 8.83E-04 person-rem and 6.69E-07 millirem

Second Quarter- 1.82E-03 person-rem and 1.38E-06 millirem

Third Quarter - 3.82E-03 person-rem and 2.89E-06 millirem

Fourth Quarter - 2.25E-03 person-rem and 1.70E-06 millirem

7. Process Control Program

On December 16, 2005, PNP converted from using an evaporator to process liquid

wastes, to using a resin and charcoal advance liquid processing system (ALPS).

The change was made to reduce PNP occupational dose and to provide a more

reliable system. The change did not reduce the overall conformance of the

solidified waste product to existing criteria for solid waste. (Note: Solidification of

waste no longer takes place at PNP. The ALPS resin and charcoal waste are

dewatered in a high integrity container and sent to a vendor for processing prior to

burial).

8. Offsite Dose Calculation Manual

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

Specification 5.5.1.c.3.

Revision 20 to the ODCM became effective January 3, 2005. Based on the 2004

land use census, two changes were made to critical receptor locations. Goats and

beef cattle were found in a new location, in the SE sector at 1.9 miles. As a result,

the X/Q value for goats was changed from 2.14E-07 to 2.32E-07, and the X/Q value

for beef cattle was changed from 1.86E-07 to 2.32E-07. As a result of these two

criical receptor changes, the design basis quantities (DBQ) for 1-131, Cs-136,

Nl-95 and Ru-1 03 decreased. ODCM Tables 1.4, 1.4a, and 1.9 were updated.

In a comparison of the 1992-1996 meteorological data, with the most current

meteorological data, the results show that the site boundary X/Q currently used is

within 4.5% of the most current meteorological data. The other critical receptors

are nearly identical. Based on this comparison, no changes were made, and the

19,32-1996 meteorological data will continue to be used.

Page 4 of 5
An editorial change to the ODCM to require that the Plant Operating Review

C:mmittee (PORC) approve ODCM changes became effective on July 6, 2005. An

editorial change does not affect the revision number.

Attachment 7 also contains the ODCM, Appendix A, Revision 11. There were no

changes to Appendix A during 2005.

Page 5 of 5
ATTACHMENT 1

RADIOACTIVE EFFLUENT RELEASE REPORT

BATCH RELEASES

JANUARY - DECEMBER 2005

TABLE HP 10.5-1

GASEOUS Units 1st Otr 2nd Qtr 3rd Qtr 4th Qtr

Number of Releases N/A 5 4 4 9

Total Release Time Minutes 440 366 454 896

Maximum Release Minutes 142 127 142 160

Time__ _

Average Release Time Minutes 88 91.5 113.5 99.6

Minimum Release Minutes 55 72 67 60

Time

LIQUID Units 1St Qtr 2nd Otr 3rd Qtr 4th Qtr

NumbE~r of Releases N/A 1 2 5 1

Total Release Time Minutes 446 1565 6199 566

Maximum Release Minutes 446 1058 3070 566

Time

Average Release Time Minutes 446 782.5 1239.8 566

Minimum Release Minutes 446 507 13 566

Page 1 of 1
ATTACHMENT 2

RADIOACTIVE EFFLUENT RELEASE REPORT

GASEOUS EFFLUENTS - SUMMATION OF RELEASES

JANUARY - DEC'EMBER 2005

Est

'Total

A. Fission and Activation Gases Units 1 st Qtr 2nd Qtr 3rd Qtr | 4th Qtr Error %

1. Total Release Ci 3.37E-01 6.37E-01 8.18E-01 4.20E+01

2. Average release rate for period pCi/sec 4.33E-02 8.11 E-02 1.03E-01 5.29E+00 4.76

3. Percent of annual average EC** % 2.05E-05 3.68E-05 4.63E-05 2.78E-03 _ -

B. lod nes *

1. Total Iodine Ci 1.57E-04 3.17E-04 3.75E-04 4.55E-04 J

2. Average release rate for period pCi/sec 2.02E-05 4.03E-05 4.72E-05 5.73E-05 22.34

3. Perment of annual average EC** _ _ 8.80E-06 1.86E-05 2.12E-05 1.92E-05 _ -

C. Particulates

1. Total Release Ci 8.76E-07 1.14E-05 1.13E-05 7.56E-06 _

2. Average release rate for period pCi/sec 1.13E-07 1.46E-06 1.42E-06 9.51 E-07

3. Percent of annual average EC** _ _ 3.99E-06 3.82E-05 5.04E-05 3.37E-05 16.1

4. Gross alpha radioactivity Ci 2.66E-07 1.46E-06 1.83E-06 1.01 E-06 _ -

D. Trit um

1.Total Release Ci 3.94E+01 1.93E+01 2.16E+01 2.81E+01

2. Average release rate for period pCi/sec 5.07E+00 2.45E+00 2.72E+00 3.54E+00

3. Percent of annual average EC** % 1.03E-02 5.22E-03 5.78E-03 7.52E-03

E. Whole Body Dose __

1. Beta airdose at site boundary due

to noble gases (ODCM App A 111.C) mrads 2.38E-05 4.51 E-05 5.79E-05 3.OOE-03

2. Percent of limit % 2.38E-04 4.51 E-04 5.79E-04 3.00E-02

3. Gamma Airdose at Site boundary

due to noble gasses (ODCM App A

III.C) . mrads 8.32E-06 1.55E-05 1.98E-05 9.91E-04

4. Percent of Limit _ _% | 1.66E-04 3.1OE-04 3.96E-04 1.98E-02

F. Organ Dose

1. Maximum organ dose to public

based on critical receptors (ODCM

AppA lI.D) rmrem 3.97E-02 1 .98E-02 2.21E-02 2.89E-02

2. Percent of Limit | _|_% | 5.29E-01 2.64E-01 2.95E-01 3.85E-01

* Data are reported for 1-131 and 1-133 only.

** EC = Effluent Concentration

Page 1 of 3
ATTACHMENT 2

RADIOACTIVE EFFLUENT RELEASE REPORT

GASEOUS EFFLUENTS

JANUARY - DECEMBER 2005

1 FISSION GASES Units 1st Qtr 2nd Qtr 3rd Qtr 4th QIr

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

Kr-85 Ci <LLD <LLD <LLD 4.08E-01

Kr-85m Ci <LLD <LLD <LLD <LLD

FKr-87 Ci <LLD <LLD <LLD 3.90E-04

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

Xe-131rm Ci <LLD <LLD 4.82E-04 5.18E-03

:e-133 Ci 3.33E-01 6.33E-01 8.13E-01 4.16E+01

:e-133m Ci <LLD <LLD <LLD <LLD

>:e-135 Ci 1.43E-03 1.56E-03 1.69E-03 1.75E-03

>:e-135m Ci 2.54E-03 2.53E-03 3.20E-03 3.84E-*03

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

Total for Period Ci 3.37E-01 6.37E-01 8.18E-01 4.20E+01

2. IODINES Units 1 1t Qtr 2nd Qtr 3rd Qtr 4th Qtr

1-131 Ci 4.11 E-05 9.26E-05 1.04E-04 6.54E-*05

1-132 Ci <LLD <LLD <LLD <LLD

1-133 Ci 1.16E-04 2.24E-04 2.71 E-04 3.90E-04

1-134 Ci <LLD <LLD <LLD <LLD

1-135 Ci <LLD <LLD <LLD <LL[)

Total for Period Ci 1.57E-04 3.17E-04 3.75E-04 4.55E-04

Page 2 of 3
ATTACHMENT 2

RADIOACTIVE EFFLUENT RELEASE REPORT

GASEOUS EFFLUENTS

JANUARY - DECEMBER 2005

3. PARTICULATES* Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qir

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

Co-58 Ci <LLD 2.98E-06 <LLD <LLD

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

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

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

Sr-89 Ci <LLD <LLD <LLD <LLD

Sr-90 Ci <LLD <LLD <LLD <LLD

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

Net unidentified beta Ci 8.76E-07 8.46E-06 1.13E-05 7.56E-06

Total Ci 8.76E-07 1.14E-05 1.13E-05 7.56E*06

* Farticulates with half-lives > 8 days

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

Page 3 of 3
ATTACHMENT 3

RADIOACTIVE EFFLUENT RELEASE REPORT

LIQUID EFFLUENTS - SUMMATION OF RELEASES

JANUARY - DECEMBER 2005

Est

Total

Error

A. Fission and Activation Products Units 1st Qtr 2nd Qtr 3rd Qtr 4th Qtr %

1. To:al Release (not including

tritiun, gasses and alpha) Ci 3.33E-04 4.46E-04 4.04E-03 5.54E-03

2. Average release rate for period pCi/ml 9.09E-12 1.30E-11 1.02E-10 1.68E-10 9.15

3. Percent of EC _ _ 3.69E-04 7.05E-04 2.75E-03 3.84E-03

B. Tritium

1. Tolal release Ci 4.1 OE+01 4.68E+01 1.13E+02 1.04E+02

2. Average diluted concentration

durin(I period pCi/ml 1.12E-06 1.37E-06 2.86E-06 3.16E-06 4.01

3. Percent of EC ___ 1.12E-01 1.37E-01 2.86E-01 3.16E-01

C. Dissolved and Entrained

Gasses

1. Total release Ci <LLD <LLD <LLD 2.09E-04

2. Average diluted concentration

drnn period pCi/ml NA NA NA 6.35E-12 28.48

3. Percent of EC % NA NA NA 3.17E-06

D. Gross Alpha Radioactivity (Total 7

Release) I Ci 1.29E-06 | 7.68E-07 I 3.48E-03 | 5.46E-1t

E. Volume of Waste Released

(prior to dilution) R liters 1.42E+05 1.67E+05 | 2.70E+05 | 1.83E+9S

FVolume of dilution water used 7

durin period liters 3.66E+10 3.42E+10 3.95E+10 3.29E+1p

G. Maximum Dose Commitment -

Whole Body mrem 1.42E-04 3.36E-04 1.09E-03 1.63E-03

Percent of ODCM App A

III.H limit I % 9.47E-03 2.24E-02 7.27E-02 1.09E-01

H. MaKimum Dose Commitment -

Organ mrem 1 .67E-04 5.04E-04 1 .57E-03 1 .74E-03

Percel itof ODCM/AppA 3 1 E 3 3E

1lI.1-1limnit I % 3.34E-03 11.01E-02 3.14E-02 3.48E-02

*EC = Effluent Concentration

Page 1 of 2
ATTACHMENT 3

RADIOACTIVE EFFLUENlT RELEASE REPORT

LIQUID EFFLUENTS

JANUARY - DECEMBER 2005

NU(;,LIDES RELEASED Units 1st Qtr 2nd Qtr 3' Qtr 4t C)tr

Mn-54 Ci <LLD <LLD 2.80E-04 2.65E-04

Cco-57 Ci <LLD <LLD <LLD 6.87E:-05

Cc-58 Ci 1.1 6E-04 1.25E-04 1.03E-03 1.76E.-03

Cc.-60 Ci 1.67E-04 1.58E-04 1.73E-03 3.44E-03

Fe-59 Ci <LLD <LLD <LLD <LL)

Zn-65 Ci <LLD <LLD <LLD <LLE)

Sr-89 Ci <LLD <LLD <LLD <LLE)

Sr-90 Ci 2.39E-05 1.64E-05 3.73E-05 9.15E.-06

Mo-99 Ci <LLD <LLD <LLD <LLD

Cs-1 34 Ci <LLD 2.49E-05 <LLD <LLD

Cs*137 Ci 2.60E-05 1.22E-04 3.72E-04 <LLD

Ce *141 Ci <LLD <LLD <LLD <LLD

Ce..144 Ci <LLD <LLD <LLD <LLD_

Net unidentified beta Ci <LLD <LLD 5.89E-04 <LL)

Fission & Activation Ci 3.33E-04 4.46E-04 4.04E-03 5.54E-03

Prod ict Total

Xe-133 Ci <LLD <LLD <LLD 2.09E-04

Dissolved/Entrained Ci <LLD <LLD <LLD 2.09E-04

Page 2 of 2
ATTACHMENT 4

RADIOACTIVE EFFLUENT RELEASE REPORT

SOLID WASTE

JANUARY - DECEMBER 2005

Waste Source of Solidification Container Volume *Total Principal Class Waste Agent Type Curies Radionuclides

AU DAW N/A A 4.95 2.4 C-14, Mn-54, Fe-55,

Co-58, Co-60, Ni63, Sr-90, Nb-95,

Ag-1 1 Om, Sb-1 25,

Cs-137, Pu-241

AU DAW N/A LSA 71.5 1.1 C-14, Mn-54, Fe-55,

Co-58, Co-60,

Ni-63, Sr-90, Nb-95,

Ag-1 1 Om, Sb-1 25,

Cs-137, Pu-241

AS Evaporator N/A A 25.5 7.73 C-14, Mn-54, Fe-55, Bottoms Co-58, Co-60,

Ni-63, Nb-95,

Sb-1 25, Cs-1 34,

Cs-137

C Dewatered N/A B 0.75 335.6 Fe-55, Co-60, Ni-63, Spent Resin Cs-134, Cs-137

TOTAL 102.72m3 346.83 Ci

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

Page 1 of 1
ATTACHMENT 5

RADIOACTIVE EFFLUENT RELEASE REPORT

LOWER LIMITS OF DETECTION FOR PALISADES EFFLUENTS

JANUARY - DECEMBER 2005

Gasemus Effluents

ODCM Required

Nuclide MDA (uCi/cc) LLD (uCi/c).

05-014-ST

05-044-G

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Zr-95

Mo-99

1-131

1-133

Cs-134

Cs-137

Ce-1 41

Ce-1 44

Kr-87

Kr-88

Xe-133

Xe-133m

Xe-135

Xe-138

4.68E-14

2.03E-14

5.66E-14

8.73E-1 4

6.73E-14

4.48E-14

1.29E-13

2.07E-14

2.23E-14

3.85E-14

5.53E-14

2.69E-14

1.16E-13

8.63E-07

1.25E-06

5.21 E-07

2.OOE-06

4.06E-07

2.12E-06

1E-11

1E-11

1E-11

1E-11

1E-11

1E-11

1E-11

1E-12

1E-12

1E-11

1E-11

1E-11

1E-11

I E-04

1 E-04

1 E-04

1 E-04

1 E-04

1 E-04

ODCM Required

Liquid Effluents Nuclide MDA (uCi/ml) LLD uCi/ml

Liquid Batch Release

05-032-R

Mn-54

Co-58

Fe-59

Co-60

Zn-65

Mo-99

1-131

Cs-134

Cs-137

Ce-1 41

Ce-144

4.08E-08

1.03E-07

1.34E-07

1.87E-07

1.51 E-07

3.22E-07

6.96E-07

1.18E-07

1.33E-07

1.1 OE-07

5.03E-07

5E-07

5E-07

5E-07

5E-07

5E-07

5E-07

1 E-06

5E-07

5E-07

5E-07

5E-06

Page 1 of 1
ATTACHMENT 6

RADIOACTIVE EFFLUENT RELEASE REPORT

RESULTS OF 2005 RADIOCHEMISTRY CROSS CHECK PROGRAM

NOTE: CROSS CHECKS ARE NOT TYPICALLY PERFORMED IN THE FIRS1

QUARTER OF THE YEAR

14 Pages Follow
RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

NUCLEAR MANAGEMENT CO., LLC

PALISADES PLANT

2ND QUARTER 2005

Daniel M. Montgomery, QA Manager
PALISADES

VALUE

microCiicc

ANALYTICS

VALUE

microCiicc

RATIO

PALISADES:

SAMPLE ANALYSIS ANALY iCS RESOLUTiON COMPARiSON ***************************************************************************.

Al 9496-66

SOLID

1 Liter

Vol.

1000 mL

DET. 1

Ce-141

Cr-51

Cs-134

Cs-i 37

Mn-54

Fe-59

Zn-65

Co-60

Co-58

2.83E-05

1.06E-04

1.66E-05

3.38E-05

2.29E-05

1.74E-05

2.82E-05

2.43E-05

1.40E-06

2.77E-05

1.OOE-04

1.64E-05

3.18E-05

2.24E-05

1.64E-05

2.82E-05

2.46E-05

1.16E-06

1.02

1.06

1.01

1.06

1.02

1.06

1.00

0.99

1.21

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A19496-66

SOLID

I Liter

Vol.

1000 mL

DET. 2

Ce-I141

Cr-51

Cs-i 34

Cs-I 37

Mn-54

Fe-59

Zn-65

Co-60

Co-58

2.81 E-05

1.31 E-04

1.67E-05

3.34E-05

2.36E-05

1.62E-05

2.89E-05

2.40E-05

<1.92E-06

2.77E-05

1.OOE-04

1.64E-05

3.18E-05

2.24E-05

1.64E-05

2.82E-05

2.46E-05

1.16E-06

1.02

1.31

1.02

1.05

1.06

0.99

1.03

0.98

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

Al 9496-66

SOLID

1 Liter

Vol.

1000 mL

DET. 3

Ce-141

Cr-51

Cs-i 34

Cs-i 37

Mn-54

Fe-59

Co-60

Co-58

2.75E-05

1.06E-04

1.61 E-05

3.40E-05

2.25E-05

1.79E-05

- .o't-u05

2.46E-05

<1.62E-06

2.77E-05

1.OOE-04

1.64E-05

3.18E-05

2.24E-05

1.64E-05

n on- fC L.ULL.U.J

2.46E-05

1.16E-06

0.99

1.06

0.98

1.07

1.01

1.09

.4 A4

1.01

1.00

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A f- M C Ci At KM ~

AGREEMENT

2ND QUARTER 2005
PALISADES

VALUE

IIliui1UCix;

ANALYTICS

VALUE

*-,G uib

RATIO

PALISADES:

SAMPLE ANALYSiS so'dr1¶AL I, TI 1,C 

e

MC70ni I I-Tlr~kl I . .v v I I IJ fonlk DA DI Qr)

******************kk******************************************************.

A19497-66

SIMULATED

I Liter

Vol.

1 000 cc

DET. 

1

Ce-141

Cr-51

Cs-I 34

Cs-1 37

Mn-54

Fe-59

Zn-65

Co-60

Co-58

2.86E-05

1.OOE-04

1.66E-05

3.27E-05

2.36E-05

2.12E-05

2.29E-05

2.68E-05

1.30E-06

2.77E-05

11.OOE-04

1.64E-05

3.1 9E-05

2.24E-05

1.64E-05

2.82E-05

2.46E-05

1.16E-06

1.03

1.00

1.01

1.03

1.05

1.29

0.81

1.09

1.12

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ****************************************************************************

Al 9497-66

SIMULATED

1 Liter

Vol.

1 000 cc

DET. 

2

Ce-141

Cr-51

Cs-134

Cs-I 37

Mn-54

Fe-59

Zn-65

Co-60

Co-58

2.86E-05

1.14E-04

1.57E-05

3.21 E-05

2.20E-05

2.08E-05

3.OOE-05

2.37E-05

<1.65E-06

2.77E-05

1.OOE-04

1.64E-05

3.19E-05

2.24E-05

1.64E-05

2.82E-05

2.46E-05

1.16E-06

1.03

1.14

0.96

1.01

0.98

1.27

1.06

0.96

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

****************************************************************************

Al 9497-66

SIMULATED

I Liter

Vol.

1000 cc

DET. 

3

Ce-141

Cr-51

Cs-1 34

Cs-1 37

Mn-54

Fe-59

2n-65

Co-60

Co-58

2.94E-05

1.09E-04

1.64E-05

3.30E-05

2.38E-05

2.01 E-05

') 1 1 4nV

2.47E-05

1.45E-06

2.77E-05

1.OOE-04

1.64E-05

3.19E-05

2.24E-05

1.64E-05

92,9E-0j5

2.46E-05

1.16E-06

1.06

1.09

1.00

1.03

1.06

1.23

1.03

1.00

1.25

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

2ND QUARTER 2005
PALISADES

VALUE

nicroCiicc

ANALYTICS

VALUE

microClIcc

RATIO

PALISADES:

ANALYTICS CARA.1 If A IAlI %fleIf*

1-4rL- I 0 RESOLUTION COMPARISON **************************************************************************.

A19498-66

SOLID

Vol.

50 mL

DET. 1

Ce-141

Cr-51

Cs-1 34

Cs-137

Mn-54

Fe-59

Zn-65

Co-60

Co-58

4.56E-04

1.87E-03

2.41 E-04

5.19E-04

3.59E-04

3.24E-04

4.45E-04

3.62E-04

2.30E-05

4.48E-04

0.002

0.000

5.16E-04

3.62E-04

0.000

0.000

3.98E-04

1.88E-05

1.02

1.15E+00

9.07E-01

1.01 E+00

0.99

1.22E+00

9.75E-01

9.09E-01

1.22

20

20

AGREEMENT

20 AGREEMENT

20 AGREEMENT

20 AGREEMENT

AGREEMENT

20 AGREEMENT

20 AGREEMENT

20 AGREEMENT

20 AGREEMENT

Al 9498-66

SOLID

Vol.

50 mL

DET. 2

Ce-141

Cr-51

Cs-1 34

Cs-1 37

Mn-54

Fe-59

Zn-65

Co-60

Co-58

4.43E-04

1.52E-03

0.000

0.001

0.000

0.000

0.000

0.000

0.000

0.000

1.62E-03

0.000

0.001

0.000

0.000

0.000

0.000

0.000

9.88E-01

9.38E-01

0.911

1.010

0.983

1.018

0.988

0.914

0.914

20 AGREEMENT

20 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

Al 9498-66

SOLID

Vol.

50 mL

DET. 3

Ce-141

Cr-51

Cs-1 34

Cs-I 37

Mn-54

Fe-59

7n-65

Co-60

Co-58

0.000

0.002

0.000

0.001

0.000

0.000

A Ann

0.000

0.000

0.000

0.002

0.000

0.001

0.000

0.000

0.000

0.000

1.015

0.962

0.945

1.006

0.997

0.965

0.979

0.939

1.106

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGRtEMENT

20.000 AGREEMENT

20.000 AGREEMENT ... *****.......*********

2ND QUARTER 2005
PALISADES ANALYTICS RATIO

VALUE VALUE PALISADES:

CARAPfI C ANIAI VOIC ,;..,~,, m; r,~rr.;Ie, AN'vTIC PF5.'Qrl I ITWIhJ COMPAp~!SON~ *********************f***************************************************** **********************************************************************************************************

A19499-66 Ce-141 0.026 0.025 1.039 20.000 AGREEMENT

FILTER Cr-51 0.090 0.089 1.012 20.000 AGREEMENT

4 cm Cs-I 34 0.013 0.015 0.914 20.000 AGREEMENT

Vol. 1 cc Cs-137 0.030 0.028 1.066 20.000 AGREEMENT

DET. 1 Mn-54 0.021 0.020 1.060 20.000 AGREEMENT

Fe-59 0.016 0.015 1.130 20.000 AGREEMENT

Zn-65 0.027 0.025 1.092 20.000 AGREEMENT

Co-60 0.021 0.022 0.981 20.000 AGREEMENT

Co-58 0.001 0.001 1.165 20.000 AGREEMENT

A19499-66 Ce-141 0.025 0.025 1.023 20.000 AGREEMENT

FILTER Cr-51 0.101 0.089 1.138 20.000 AGREEMENT

4 cm Cs-I 34 0.015 0.015 1.004 20.000 AGREEMENT

Vol. 1 cc Cs-137 0.032 0.028 1.134 20.000 AGREEMENT

DET. 2 Mn-54 0.023 0.020 1.141 20.000 AGREEMENT

Fe-59 0.018 0.015 1.212 20.000 AGREEMENT

Zn-65 0.029 0.025 1.156 20.000 AGREEMENT

Co-60 0.023 0.022 1.050 20.000 AGREEMENT

Co-58 0.001 0.001 1.107 20.000 AGREEMENT

A19499-66 Ce-141 0.027 0.025 1.112 20.000 AGREEMENT

FILTER Cr-51 0.098 0.089 1.104 20.000 AGREEMENT

4cm Cs-134 0.015 0.015 1.031 20.000 AGREEMENT

Vol. 1 cc Cs-137 0.034 0.028 1.187 20.000 AGREEMENT

DET. 3 Mn-54 0.024 0.020 1.186 20.000 AGREEMENT

Fe-59 0.019 0.015 1.295 20.000 AGREEMENT

Zn-65 0.031 0.025 1.232 20.000 AGREEMENT

Co-60 0.024 0.022 1.087 20.000 AGREEMENT

Co-58 0.001 0.001 1.126 20.000 AGREEMENT

2ND QUARTER 2005
RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

NUCLEAR MANAGEMENT CO., LLC

PALISADES PLANT

3RD QUARTER 2005

Daniel M. Montgomery, QA Manager
PALISADES

VALUE

ir1ruCi icc

ANALYTICS

VALUE

micro(;i /cc

RATIO

PALISADES:

ANALYTICS CARADI C _, ..... AKOAL'.e'SeO

r1%114%L. I 131IQ RESOLUTION COMPARISON **************************************************************************.

Al 9500-66

CARTRIDGE

DET. 

1

SAIC

BG-300

Vol. 1 cc

Ce-141

Cr-51

Cs-1 34

Cs-1 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.39E-02

1.OOE-01

1.77E-02

3.16E-02

1.27E-02

1.62E-02

1.52E-02

2.21 E-02

2.53E-02

6.34E-02

1.02E-01

1.91 E-02

2.98E-02

1.26E-02

1.49E-02

1.42E-02

2.04E-02

2.58E-02

1.01

0.98

0.92

1.06

1.01

1.08

1.07

1.09

0.98

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ***************************************************************************.

Al 9500-66

CARTRIDGE

DET. 

2

SAIC

BG-300

Vol. 1 cc

Ce-141

Cr-51

Cs-1 34

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.49E-02

1.01 E-01

1.88E-02

3.32E-02

1.33E-02

1.68E-02

1.58E-02

2.30E-02

2.67E-02

6.34E-02

1.02E-01

1.91 E-02

2.98E-02

1.26E-02

1.49E-02

1.42E-02

2.04E-02

2.58E-02

1.02

0.99

0.98

1.11

1.05

1.12

1.11

1.13

1.03

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ***************************************************************************-

Al 9500-66

CARTRIDGE

DET. 

3

SAIC

BG-300

Vol. 1 cc

Ce-141

Cr-51

Cs-134

Cs-1 37

Co-58

Mn-54

Fe-.59

Zn-65

Co-60

6.74E-02

1.04E-01

1.83E-02

3.28E-02

1.32E-02

1.71 E-02

.1 QAC A)

2.34E-02

2.66E-02

6.34E-02

1.02E-01

1.91 E-02

2.98E-02

1.26E-02

1.49E-02

AI A flI fP

2.04E-02

2.58E-02

1.06

1.02

0.96

1.10

1.05

1.14

I.16

1.15

1.03

20

20

20

20

20

20

2U

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

3RD QUARTER 2005
PALISADES

VALUE

i, ,itic uCi U

ANALYTICS

VALUE

,,,-isouwi t;us

RATIO

PALISADES:

SAML _ A1d41LL I0 10 A N A L T ii 1 S IM-OULU I UIVN CuMPARiSOuN ***************************************************************************-

Al 9501-66

SIMULATED

GAS

25 cc

VOL. 25cc

DET. 1

Ce-1 41

Cr-51

Cs-i 34

Cs-i 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

1.12E-03

1.70E-03

3.06E-04

5.49E-04

2.15E-04

2.73E-04

2.54E-04

3.76E-04

4.31 E-04

1.07E-03

1.71 E-03

3.22E-04

5.01 E-04

2.12E-04

2.51 E-04

2.39E-04

3.42E-04

4.34E-04

1.05

1.00

0.95

1.10

1.01

1.09

1.06

1.10

0.99

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT **************************************************************************.

Al 9501-66

SIMULATED

GAS

25 cc

VOL. 25cc

DET. 2

Ce-1 41

Cr-51

Cs-I 34

Cs-I 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

1.13E-03

1.76E-03

3.21 E-04

5.59E-04

2.43E-04

2.91 E-04

2.89E-04

3.93E-04

4.61 E-04

1.07E-03

1.71 E-03

3.22E-04

5.01 E-04

2.12E-04

2.51 E-04

2.39E-04

3.42E-04

4.34E-04

1.06

1.03

1.00

1.12

1.15

1.16

1.21

1.15

1.06

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

Al 9501-66

SIMULATED

GAS

25cc

VOL. 25cc

DET. 3

Ce-141

Cr-51

Cs-134

Cs-i 37

Co-58

Mn-54

Fe-.59

Zn-65

Co-60

1.14E-03

1.81 E-03

3.14E-04

5.63E-04

2.35E-04

2.91 E-04

2.66E-4A

3.85E-04

4.57E-04

1.07E-03

1.71 E-03

3.22E-04

5.01 E-04

2.12E-04

2.51 E-04

2.39E-0fl

3.42E-04

4.34E-04

1.07

1.06

0.98

1.12

1.11

1.16

'1 *11

1.12

1.05

20

20

20

20

20

20

O'

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A fl D C C KA C ITr

AGREEMENT

AGREEMENT

3RD QUARTER 2005
PALISADES

VALUE

microCi icc

ANALYTICS

VALUE

microCi icc

RATIO

PALISADES:

SAMPLE ANALYSiS ANALYTi CS RESOLUTiON COMPARiSON ***************************************************************************.

Al 9502-66

SAND

1 LITER

VOL.

1 i0Og

DET. 1

Ce-141

Cr-51

Cs-I 34

Cs-I 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.47E-05

1.OOE-04

1.91 E-05

3.20E-05

1.41 E-05

1.61 E-05

1.30E-05

2.21 E-05

2.53E-05

6.07E-05

0.000

0.000

2.85E-05

1.21 E-05

0.000

0.000

1.95E-05

2.47E-05

1.07

1.03E+00

1.04E+00

1.12E+00

1.17

1.13E+00

9.57E-01

1.13E+00

1.02

20

20

20

AGREEMENT

20 AGREEMENT

20 AGREEMENT

20 AGREEMENT

AGREEMENT

20 AGREEMENT

20 AGREEMENT

20 AGREEMENT

AGREEMENT ***************************************************************************.

Al 9502-66

SAND

1 LITER

VOL.

1 OOOg

DET. 2

Ce-141

Cr-51

Cs-i 34

Cs-i 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.41 E-05

1.03E-04

0.000

0.000

0.000

0.000

0.000

0.000

0.000

0.000

9.72E-05

0.000

0.000

0.000

0.000

0.000

0.000

0.000

1.06E+00

1.06E+00

1.021

1.055

1.060

1.133

0.957

1.118

1.056

20 AGREEMENT

20 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT ***************************************************************************

Al 9502-66

SAND

1 LITER

VOL.

I OOOg

DET. 3

Ce-141

Cr-51

Cs-I 34

Cs-i 37

Co-58

Mn-54

C rn

Zn-65

Co-60

0.000

0.000

0.000

0.000

0.000

0.000

vJ .vvvu

0.000

0.000

0.000

0.000

0.000

0.000

0.000

0.000

A AAA

0.000

0.000

1.036

1.060

1.004

1.087

1.077

1.119

1 AO

1.047

1.020

20.000

20.000

20.000

20.000

20.000

20.000

20.000

20.000

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A - MC D 1 I A CN IT

AGREEMENT

AGREEMENT

3RD QUARTER 2005
PALISADES

VALUE

micr.Ci I'c

ANALYTICS

VALUE

Inicroci icc

RATIO

PALISADES:

ANALY-i IuS QAKA,2. D!= AKA, X/LIL .% V,5. 1... Il RESOLUTION COMPARISON

AtADI CU CL.S **************************************************************************.

Al 9503-66

CARTRIDGE

DE-500

LAPEL

VOL.

I cc

DET. 1

Ce-141

Cr-51

Cs-I 34

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

0.063

0.096

0.017

0.032

0.013

0.016

0.014

0.022

0.025

0.062

0.099

0.019

0.029

0.012

0.015

0.014

0.020

0.025

1.017

0.972

0.921

1.090

1.032

1.118

1.033

1.082

1.009

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT ***************************************************************************.

Al 9503-66

CARTRIDGE

SOLID

DE-500

LAPEL

VOL.

1 cc

DET. 2

Ce-141

Cr-51

Cs-1 34

Cs-1 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

0.064

0.100

0.018

0.032

0.013

0.017

0.017

0.022

0.026

0.062

0.099

0.019

0.029

0.012

0.015

0.014

0.020

0.025

1.038

1.006

0.953

1.111

1.089

1.139

1.199

1.127

1.032

20.000

20.000

20.000

20.000

20.000

20.000

20.000

20.000

20.000

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT *************************,***,**&******************************************

Al 9503-66

CARTRIDGE

SOLID

DE-500

LAPEL

VOL.

1 cc

DET. 3

Ce-1 41

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

0.065

0.102

0.018

0.033

0.013

0.017

A A1c

0.023

0.026

0.062

0.099

0.019

0.029

0.012

0.015

n n4 A

0.020

0.025

1.057

1.030

0.953

1.121

1.064

1.160

A.A 4fl

1.132

1.036

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMENT

20.000 AGREEMEN

20.000 AGREEMENT

20.000 AGREEMENT

3RD QUARTER 2005
RESULTS OF RADIOCHEMISTRY

CROSS CHECK PROGRAM

NUCLEAR MANAGEMENT CORP.

PALISADES PLANT

4th QUARTER 2005

Daniel M. Montgomery, QA Manager
PALISADES

VALUE

microCi

ANALYTICS

VALUE

. jj j. ;fo

RATIO

PALISADES:

AIIAU trle>L SAMPLE ANALYSIS ,',-L I ICS RE SO LUT!01,1 COMPARISON

.... ***********************. .*********************************************************************************************************

A19880-66

.SOLID

7.2 mL

BOMB

DET. 1

Ce-1 41

Cr-51

Cs-1 34

Cs-1 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

1.62E-03

1.60E-03

4.02E-04

8.23E-04

4.41 E-04

6.95E-04

5.81 E-04

7.27E-04

4.67E-04

1.71 E-03

1.63E-03

3.84E-04

8.12E-04

4.33E-04

6.93E-04

5.37E-04

7.12E-04

4.78E-04

0.95

0.98

1.05

1.01

1.02

1.00

1.08

1.02

0.98

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ***************************************************************************-

A19880-66

SOLID

7.2 mL

BOMB

DET. 2

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

1.67E-03

1.84E-03

4.29E-04

8.63E-04

4.40E-04

7.29E-04

5.60E-04

7.12E-04

4.35E-04

1.71 E-03

1.63E-03

3.84E-04

8.12E-04

4.33E-04

6.93E-04

5.37E-04

7.12E-04

4.78E-04

0.98

1.13

1.12

1.06

1.02

1.05

1.04

1.00

0.91

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

Al 9880-66

SOLID

7.2 mL

BOMB

DET. 3

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

r -

Zn-65

Co-60

1.79E-03

1.62E-03

3.78E-04

8.41 E-04

4.06E-04

7.16E-04

A A 1E-nA

6.88E-04

4.97E-04

1.71 E-03

1.63E-03

3.84E-04

8.12E-04

4.33E-04

6.93E-04

5.37E n4

7.12E-04

4.78E-04

1.05

1.00

0.99

1.04

0.94

1.03

0.82

0.97

1.04

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

14TH QUARTER 2005
PALISADES

VALUE

m~i'r^Ci

ANALYTICS

VALUE

--'cro'i

RATIO

PALISADES:

SAMPLE ANALYSIS ANALYT iCS RESOLu I ION COMPARISON *****.*********************************I*4.****4h**************************

A19879-66

CARTRIDGE

RGEM

DET. 1

Ce-141

Cr-51

Cs-134

Cs-137

Co-58

Mn-54

Fe-59

Zn-65

Co-60

7.61 E-02

7.08E-02

1.53E-02

3.80E-02

1.95E-02

3.37E-02

2.51 E-02

3.36E-02

2.04E-02

6.63E-02

6.32E-02

1.49E-02

3.16E-02

1.68E-02

2.69E-02

2.09E-02

2.77E-02

1.86E-02

1.15

1.12

1.03

1.20

1.16

1.25

1.20

1.21

1.10

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ***************************************************************************.

Al 9879-66

CARTRIDGE

RGEM

DET. 2

Ce-141

Cr-51

Cs-I 34

Cs-1 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

6.91 E-02

6.41 E-02

1.47E-02

3.55E-02

1.84E-02

3.1 OE-02

2.36E-02

3.09E-02

1.89E-02

6.63E-02

6.32E-02

1.49E-02

3.16E-02

1.68E-02

2.69E-02

2.09E-02

2.77E-02

1.86E-02

1.04

1.01

0.99

1.13

1.09

1.15

1.13

1.12

1.02

20

20

20

20

20

20

20

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

A19879-66

CARTRIDGE

RGEM

DET. 3

Ce-141

Cr-51

Cs-1 34

Cs-I 37

Co-58

Mn-54

Fe-59

Zn-65

Co-60

7.20E-02

6.76E-02

1.51 E-02

3.69E-02

1.92E-02

3.29E-02

2.51 E-02

3.23E-02

1.98E-02

6.63E-02

6.32E-02

1.49E-02

3.16E-02

1.68E-02

2.69E-02

2,09F-02

2.77E-02

1.86E-02

1.09

1.07

1.01

1.17

1.14

1.22

1.20

1.17

1.07

20

20

20

20

20

20

1AD

20

20

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT

AGREEMENT ************************ *******************************************2*********************************************

4 Tl QUARTER 2 d005
PALISADES

VALUE

.* * .. o*.j

ANALYTICS

VALUE

ri Ir, U2jICI,,

RATIO

PALISADES:

SAMPLE AKIAI VQIQ ANALYT ICS REISLUTi ION COMPARISON

A19882-66

LIQUID

COUNT 1

Tritium

PACKARD TRICARB

8.28E-04 7.86E-04 1.05 12.5 AGREEMENT

Al 9882-66

LIQUID

COUNT 2

Tritium

PACKARD TRICARB

8.30E-04 7.86E-04 1.06 12.5 AGREEMENT

A19882-66

LIQUID

Tritium

PACKARD TRICARB

8.29E-04 7.86E-04 1.05 12.5 AGREEMENT

4TH QUARTER 2005
ATTACHMENT 7

RADIOACTIVE EFFLUENT RELEASE REPORT

OFFSITE DOSE CALCULATION MANUAL

170 Pages Follow
ODCM

Revision 20

Issued Date 7/6/05

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: OFFSITE DOSE CALCULATION MANUAL

JBBurneft l 711/05

Procedure Sponsor Date

JLF'ontaine / 11/1/04

Technical Reviewer Date

I .......

User Reviewer Date

WGHettel / 12/30104

Plant Manager Date
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

Table of Contents

GASEOUS EFFLUENTS . . . I

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

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

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

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

C. DESIGN OBJECTIVE 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 Operal:ion ....... 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
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

Table of Contents

II. LIQUID EFFLUENTS .................................................. 67

A. CONCENTRATION ...................................................... 67

1. Requirements ................................................... 67

2. Prerelease Analysis ......................................... 67

3. Effluent Concentration (EC) - Sum ol the

Ratios ..................................................... 68

B. INSTRUMENT SETPOINTS . . .............................. 69

1. Setpoint Determination ................................... 69

2. Composite Samplers ....................................... 69

3. Post-Release Analysis .................................... 70

C. DOSE ..................................................... 70

1. RETS Requirement ........................................... 70

2. Release Analysis ............................................. 71

D. OPERABILITY OF LIQUID RADWASTE EQUIPMENT ... 75

E. RELEASE RATE FOR OFFSITE EC (50 MREMNYR) ... 76

F. FIGURES AND TABLES ...................................................... 77

Ill. URANIUM FUEL CYCLE DOSE ................................................... 98

A. SPECIFICATION ................................................... 98

B. ASSUMPTIONS .................................................. 98

C. DOSE CALCULATION ................................................... 99

IV. REVISIONS TO THE OFFSITE DOSE CALCULATION MANUAL ... 99

A. REQUIREMENTS ..................................... 99

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

Revision 20

GASEOUS EFFLUENTS

A. ALARM/TRIP 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 III.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 III.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 miKture to

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

order to establish the physical settings on the monitors.

1
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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): C._ < 5.0

Q i ECI

If gaseous tritium and noble gasses are not present then:

R(k) < 10

where:

C = Actual or measured concentration, at ambient temperature

(1.1)

and

pressure of nuclide i (ptCi/cc)

ECQ = 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/'m 3) -

Table 1.3

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

considerations; variable for other monitors

2
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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 cases.

Therefore, monitor response calibrations are performed to fission gas typical

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

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

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

determined as follows:

a. Normal Release (aged fission gasses)

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

calibration curve or constant for cpm/pCi/cc) is applied to determine

cpm expected. The setting for monitor alarms is established at some

factor (b) greater than 1 but less than 1/Rk (Equation 1.1) times the

measured concentration (c):

s=bxc (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 1tCi/cc (or R/hr and ttCi/cc), depending on monitor type, for

fission product mixtures as a function of mixture decay time.

When these monitors are utilized for other than accident conditions,

either an appropriately decayed "accident" conversion curve may be

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

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

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

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

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

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

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

three times background in order to detect leakage or inadvertent

releases of low level gases.

3
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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) AssumDtions

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 1Oim and temperature

measurements at 1lOm 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.

j) A semi-infinite cloud model is used.

4
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

k) For person exposures, credit is taken for shielding by

k) For person exposures, credit is taken for shielding by

residence (factor of 0.7).

I) Radioactive decay is considered for the plume.

m) Building wake effects on effluent dispersion are

considered.

n) A sector-average dispersion equation is used.

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

Wind Speed

Class Number Range (mWs) Midpoint (ms)

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 --

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

through G classifications. The stability classes 1-7 will

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

q) Terrain effects are not considered.

5
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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 (2V) 1/ jk Q, p F (x

XI j=1 kE1 YE t) zkUl (27rx/n) [p- Xi C

where:

1.3)

Xi

fjk

Qi

p

7zk

Uj

x

n

27rx/n

= Air concentration of radionuclide i, pCi/M3.

= Joint relative frequency of occurrence of winds in

wind speed class j, stability class k, blowing

toward this exposure point, expressed as a

fraction.

= Average release rate of radionuclide i, pCi/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 1.

- Sector width at point of interest, m.

6
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

For determining the total body dose rate:

DTB . Xi DFBi (1.4)

where:

DTB = Total body dose rate, mrem/y.

X = Air concentration of radionuclide 1, PCi/M3.

DFB1 = Total body dose factor due to gamma radiation,

mrem/y per pCi/M3 (Table 1.5).

For determining the skin dose rate:

Ds= Xi (DFSi+1.11DFY) (1.5)

where:

Ds = Skin dose rate, mrem/y.

X = Air concentration of radionuclide i, gCi/M 3

DFSj = Skin dose factor due to beta radiation, mrerm/y per

pCi/m3 (Table 1.5).

1.11 = The average ratio of tissue to air energy

absorption coefficients, mrem/mrad.

DFYI = Gamma-to-air dose factor for

radionuclide i, mrad/y per pCi/iM3 (Table 1.5).

For determining dose rate to a point in air:

Da= Xi (DFYi or DFBE) (1.6)

where:

Da = Air dose rate, mrad/yr.

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

7
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

lOim and temperature measurements at 1Om and 60m.

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

points where maximum doses to man are expected to

exist.

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

j) Potential maximum exposure points (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.

8
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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.

q) Credit is taken for shielding by residence (factor of 0.7).

2) Equations

To calculate the dose for any one of the potential

maximum-exposure points, the following equations in

Section 1.2.2 are used.

a) Inhalation

Equation for calculating air concentration, Xi is the same

as in the Noble Gas Section (Equation 1.3).

For determining the organ dose rate:

Di=1x10X 6 Xi DFlI BR (1.7)

where:

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

X = Air concentration of radionuclide i, giCi/m 3.

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.

1x1 06 = pCi/pCi conversion factor.

9
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

b) Ground Contamination

For determining the ground concentration of any nuclide;

7

Gi = 3.15 x10 7 E fQjDR [1 -exp- (Al t)] (1.8)

k I (2;rx/n)AI

where:

G = Ground concentration of radionuclide i, pCi/M2 .

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,

pci/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

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

= Radioactive decay coefficient of

radionuclide i, yV1.

tb = Time for buildup of radionuclides on the

ground, 15 y.

3.15x107 = s/y conversion factor.

10
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

10-3

10-4

aLU

10.

w

cI

u

w

4c

cc

w

E

10-8

1(r7

0.1 1. 10.0 100.0 200.0

PLUME TRAVEL DISTANCE (KILOMETERS) I

Figure 7. Relative Deoition for Ground Level Relass (All Atrospheric

Stability Cles) ._n_.. I

11
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

For determining the total body or organ dose rate from

ground contamination:

DG = (8,760)(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, tCi/m 2 .

DFGj = Dose factor for standing on contaminated

ground, mrem/h per pCi/M2 (Table '1.8).

8,760 = Occupation time, h/y.

l1X06 = pCi/jiCi conversion factor.

0.7 = Shielding factor accounting for a distance of

1.0 meter above ordinary ground,

dimensionless.

c) Milk and Vegetation Ingestion

For determining the concentration of any nuclide (except

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

CV,=3,600 I fkQDR (r[Be (AEie] +i[P (-Altb)])l[exp- (Ath)]] (1.10)

kI(2z' xln) YI AEI Pl

where:

CV1 = Concentration of radionuclide i in and on

vegetation, [tCi/kg.

k = Stability class.

fk = Frequency of this stability class and wind

direction combination, expressed as a

fraction.

12
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

Qj = Average release rate of radionuclide i,

PUGi/s.

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

x = Downwind distance, m.

n = Number of sectors, 16.

2itx/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 = ki + 4, where ? is the radioactive

decay coefficient, h-', and kw is a measure

of physical loss by weathering

(4 = 0.0021 h-).

te = Period over which deposition occurs, 720 h.

YV Agricultural yield, 0.7 kg/M2.

Bv = Transfer factor from soil to vegetation of

radionuclide i (Table 1.6).

xi = Radioactive decay coefficient of

radionuclide i, h1 .

tb = Time for buildup of radionuclides on the

ground, 1.31x105 h (15Y).

p = Effective surface density of soil, 240) kg/M2.

3,600 = s/h conversion factor.

th = Holdup time between harvest and

consumption of food (2,160 hours for stored

food).

13
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

For determining the concentration of C-14 in vegetation:

CV141X1O3 X4(0.11/O.16) (1.11)

where:

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

X14 = Air concentration of C-14, [ICi/m 3.

0.11 = Fraction of total Plant mass that is natural

carbon.

0.16 = Concentration of natural carbon in the

atmosphere, g/m3.

1x103 = g/kg conversion factor.

For determining the concentration of H-3 in vegetation:

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

where:

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

XT = Air concentration of H-3, [LCi/m 3 .

0.75 = Fraction of total Plant mass that is 'Nater.

0.5 = Ratio of tritium concentration in Plant water

to tritium concentration in atmospheric

water.

Absolute humidity of the atmosphere, g/m3.

g/kg conversion factor.

H =

1x103 =

14
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

For determining the concentration of any nuclide in cow's

or goat's milk:

CMI = CVI FM1 Qf exp (-Xi tf) (1.13)

where:

CM1 = Concentration of radionuclide i (including

C-14 and H-3) in milk, gCi/l.

CVW = Concentration of radionuclide i in and on

vegetation, J4Ci/kg.

FMI = 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).

i = Radioactive decay coefficient of

radionuclide i, d-1.

t = Transport time of activity from feed t:o milk

to receptor, 2 days.

15
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

For determining the organ dose rate from ingestion of

green leafy vegetables and milk:

D=1X1o6 CMIDFIUM (1.14)

where:

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

CM! = Concentration of radionuclide i in

vegetables or milk, J4Ci/kg (or liters).

DFj = 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.

1X106 = pCi/[Ci conversion factor.

d) Meat Ingestion (Beef)

To calculate the concentration of a nuclide in animal

flesh:

Cfi=Ffi CVj Qr, exp (qts) (1.15)

where:

Cfi Concentration of nuclide i in the animal

flesh, pCi/kg.

Efi = Fraction of animal's daily intake which

appears in each kg of flesh, days/kg

(Table 1.6).

CV1 = Concentration of radionuclide i in the

animal's feed (Equation 1.10).

16
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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:

Df =. CflDfi Uf (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-110).

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.

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

DG = Dose rate due to ground contamination,

DM

Dv

DF

mrrem/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.

17
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

and maximum skin dose rate calculated in the previous section

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

described in Section l.B.1.3.

c. 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 IlI.C.1.b).

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

(Appendix A, Section IlI.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 (C:i) 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 = DDA(CC) (1.18)

where:

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

Dc = Calculated dose (mrem or mrad).

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

DBQ = Design Basis Quantity (Ci).

18
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

The limiting values for Design Basis Quantities for radionuclides

released to the atmosphere are given in Table 1.9.

The inverse of the ratio CC/Dc in the above equation (ie, DC/CC) is a

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

of each nuclide released. Use of the DC/CC ratio in quarterly evaluation

of offsite dose is discussed in Section D. Values of DC/Cc 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

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

Design Basis Objective Annual Quantities). Changes will be effective

on January 1 of the year following the year of the survey.

e. Gaseous Releases From the Steam Generator Blowdown Veni: 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 blowclown

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.

19
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

RELEASES

1. Batch Releases

Prior to each batch release (waste decay tank release or Containment purge),

the 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 objective 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:

X Al < 1.0 (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 anm 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.

20
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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.

21
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

D. OPTIONAL QUARTERLY DOSE CALCULATIONS

1. 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.

22
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

2) Equations

For determining gaseous effluent dose:

DG = E AjG(DC/CC)G<5millirad/quarter,10mrad/yr (1.20)

0

where:

DG = Dose from gaseous effluents (mrad).

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

(DJCC)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 = ATPI (DC / CCPI <7.5 mremlq, 15 mrem/y (1.21)

where:

DTPI = Dose from particulates and iodines (mrem).

ATPII = Quantity of particulate or iodine nuclide i released

(Ci).

(DJCC)TPji = Dose per Ci factor for particulate or iodine nuclide i

(mrad/Ci).

23
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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 ob:ain

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 20

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.

Explosive mixtures of hydrogen and oxygen have been demonstrated

compatible with the system by operational experience over the past 13 years.

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 13-year operating

history (to date of writing the initial ODCM) 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 20

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 5D 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 an 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 20

Gamma analytical results for particulate and halogen filters are combined for

determination of total activity of particulates and halogens released. Beta arid alpha

counting also is performed on the particulate filters. Beta yields of the gamma

isotopes detected on particulate filters are applied to determine "identified" beta, an

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 on

actual Sr-90 (chemically separated from a quarterly composite of filters) are

obtained. 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 1 E-06 jtCi/cc. Sampling

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

I. 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
CIn

C

m

C/

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0,

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en

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- UJ.4Y

CD

_.

0.

C)

C)

'1

rn

-4

z

m

ui

m

C)

o

LI

:D

Cl

m

Uj)

z

C

m

rz

-I

"i 

FLO 

l 

5 

g. sytt 

NOT IIWMIWAT

MGD P1mw W Jw 1JUD OmFa r Cx asT

PALISADES EFFLUENT FLOW PATHS

GASEOUS
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.1

PALISADES GASEOUS AND LIQUID SOURCE TERMS, CURIESNEAR (1)

Nuclide

H-3

Kr-85

Kr-85m

Kr-87

Kr-88

Ar-41

Xe-131m

Xe-1 33

Xe-1 33m

Xe-1 35

Xe-135m

1-131

1-132

1-133

1-134

1-135

Na-24

Cr-51

Mn-54

Co-57

Co-58

Fe-59

Co-60

Se-75

Nb-95

Zr-95

Mo-99

Ru-103

Sb-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

2.1 E-01

3.1 E-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

2.1 E-06

8.6E-04

6.6E-06

1.1 E-03

3.7E-06

2.4E-05

4.7E-06

1.5E-07

0.3E-07

NA

4.5E-05

NA

2.6E-04

2.8E-07

7.5E-07

3.9E-04

Liquid(2)

159

NA

NA

NA

NA

NA

NA

NA

NA

NA

NA

3.21 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

1.24E-02

NA

4.53E-04

1.79E-04

NA

0.1 E-05

3.5E-05

0.7

1.8E-06

1.36E-02

NA

1.1 E-04

3.3E-03

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

January-June 1982 and dividing by 4.

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

streams.

(2)

29
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.2

BASIC RADIONUCLIDE DATA

NUCLIDE HALF-LIFE LAMBDA BETA' GAMMA1

(days) (1/s) (MEV/DIS) (MEV/DIS)

1 Tritium 4.49E 03 1.79E-09 5.68E-03 0.0

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

3 N-13 6.94E-03 1.16E-03 4.91 E-01 1.02E 00

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

5 F-18 7.62E-02 1.05E-04 2.50E-01 1.02E 00

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

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

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

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

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

11 MN-56 1.07E-01 7.50E-05 8.29E-01 1.69E 00

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

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

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

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

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

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

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

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

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

21 KR-87 5.28E-02 1.52E-04 1.32E 00 7.93E-01

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

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

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

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

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

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

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

29 SR-92 1.1 3E-01 7.1OE-05 1.95E-01 1.34E 00

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

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

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

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

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

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

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

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

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

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

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

30
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.2 (continued)

BASIC RADIONUCLIDE DATA

NUCLIDE HALF-LIFE LAMBDA BETA1 GAMMA'

(days) (1/s) (MEV/DIS) (MEVWDIS)

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

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

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

44 TE-132 3.24E 00 2.48E-06 1.OOE-01 2.33E-01

45 1-129 6.21E 09 1.29E-15 5.43E-02 2.46E-02

46 1-131 8.05E 00 9.96E-07 1.94E-01 3.81 E-01

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

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

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

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

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

52 XE-1 33m 2.26E 00 3.55E-06 1.90E-01 4.15E-02

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

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

55 XE-1 35 3.83E-01 2.09E-05 3.17E-01 2.47E-01

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

57 XE-1 38 9.84E-03 8.15E-04 6.65E-01 1.10E 00

58 CS-1 34 7.48E 02 1.07E-08 1.63E-01 1.55E 00

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

60 CS-1 36 1.30E 01 6.17E-07 1.37E-01 2.15E 00

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

62 CS-1 38 2.24E-02 3.58E-04 1.20E 00 2.30E 00

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

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

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

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

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

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

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

Radionuclide Transformations: Enerav and Intensity of Emissions 1983 and

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

Summary Table, DC Kocher, May 1980.

31
USNIRC CCtMPUTER CODE - XOQDOQ. VERSION 2.0 RUN DATE: 970513

**- PALISADES X00DOW82 *'** USING 01/01(92 - 12/31/96 MET DATA

GROUMD LEVEL RELZASE - TOP OF CONTAD4412Mr BUILDING

NO DECAY, UNDEPLETED

ANNUAL AVERAGE CHI/Q (SECK/ETER CUEED) DISTANCE IN MILES FROM THE SITE

SECTOR 0.250 0.500 0.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500

S 4.208-06 1.381E-06 7.556E-07 4.993E-07 2.782E-07 1.842E-07 1.340E-07 1.033E-07 8.298E-08 6.867E-08 5.813E-08

SSW 3.330E-06 1.086E-06 5.856E-07 3.870E-07 2.160E-07 1.437E-07 1.048E-07 8.108E-08 6.528E-08 5.413E-08 4.590E-08

SW 3.890E-06 1.242E-06 6.590E-07 4.333E-07 2.413E-07 1.614E-07 1.184E-07 9.203E-OB 7.440E-08 6.191E-08 5.267E-08

W9W 4.060E-06 1.279E-06 6.715E-07 4.401E-07 2.450E-07 1.648E-07 1.215E-07 9.484E-08 7.694E-08 6.422E-08 5.477E-08

W 5.554E-06 1.759E-06 9.224E-07 6.035E-07 3.349E-07 2.249E-07 1.657E-07 1.292E-07 1.047E-07 8.735E-08 7.447E-08

WNW 7.378E-06 2.346E-06 1.235E-06 8.084E-07 4.487E-07 3.010E-07 2.216E-07 1.726E-07 1.399E-07 1.166E-07 9.937E-08

NW 9.531E-06 2.974E-06 1.551E-06 1.012E-06 5.610E-07 3.784E-07 2.800E-07 2.191E-07 1.781E-07 1.490E-07 1.273E-07

NNW 1.286E-05 3.959E-06 2.052E-06 1.339E-06 7.443E-07 5.039E-07 3.741E-07 2.935E-07 2.391E-07 2.003E-07 1.715E-07

N 1.087E-05 3.347E-06 1.739E-06 1.1382-06 6.348E-07 4.300E-07 3.192E-07 2.504E-07 2.040E-07 1.709E-07 1.462E-07 O

NNE 5.487E-06 1.717E-06 9.119E-07 6.OOOE-07 3.353E-07 2.256E-07 1.664E-07 1.299E-07 1.054E-07 8.793E-08 7.501E-08 '1

NE 5.450E-06 1.803E-06 9.856E-07 6.476E-07 3.578E-07 2.355E-07 1.705E-07 1.310E-07 1.049E-07 8.657E-08 7.312E-08 Glt

ENE 4.258E-06 1.379E-06 7.464E-07 4.886E-07 2.697E-07 1.773E-07 1.282E-07 9.850E-08 7.885E-08 6.507E-08 5.496E-08 -1 >

E 4.618E-06 1.531E-06 8.321E-07 5.438E-07 2.990E-07 1.959E-07 1.413E-07 1.082E-07 8.645E-08 7.120E-08 6.002E-08 m r ESE 4.436E-06 1.479E-06 8.008E-07 5.210E-07 2.848E-07 1.860E-07 1.338E-07 1.023E-07 8.153E-08 6.104E-08 5.644E-08 _

SE 5.091E-06 1.678E-06 9.044E-07 5.872E-07 3.207E-07 2.096E-07 1.509E-07 1.155E-07 9.217E-08 7.586E-08 6.391E-08 0 > SSE 6.044E-06 2.000E-06 1.088E-06 7.106E-07 3.901E-07 2.557E-07 1.845E-07 1.415E-07 1.131E-07 9.317E-08 7.858E-08 clf0 M M

ANNUAL AVERAGE CHI/Q (SEC/METER CUBED) DISTANCE IN MILES FROM THE SITE CD 0 Cn SECTOP 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000 _. > Z r- e. r c

S 5.010E-08 2.837E-08 1.901E-08 1.086E-08 7.328E-09 5.410E-09 4.227E-09 3.433E-09 2.869E-09 2.450E-09 2.127E-09 m 0 C) o

SSW 3.9638-08 2.257E-08 1.519E-08 8.728E-09 5.913E-09 4.379E-09 3.431E-09 2.793E-09 2.338E-09 2.000E-09 1.740E-09 -& a rm SW 4.560E-08 2.627E-08 1.782E-08 1.037E-08 7.086E-09 5.284E-09 4.163E-09 3.405E-09 2.863E-09 2.458E-09 2.145E-09 . .) > >

WSW 4.753E-08 2.763E-08 1.886E-08 1.106E-08 7.602E-09 5.693E-09 4.501E-09 3.693E-09 3.113E-09 2.678E-09 2.342E-09 0 .4 i

W 6.459E-08 3.749E-08 2.557E-08 1.498E-08 1.029E-08 7.706E-09 6.091E-09 4.996E-09 4.211E-09 3.623E-09 3.168E-09 0 tJ

WNW 8.615E-08 4.992E-08 3.400E-08 1.989E-08 1.364E-08 1.021E-08 8.059E-09 6.606E-09 5.565E-09 4.785E-09 4.183E-09 Z r

NW 1.106E-07 6.471E-08 4.436E-08 2.618E-08 1.808E-08 1.359E-08 1.077E-08 8.857E-09 7.481E-09 6.449E-09 5.649E-09 >

Ntm 1.492E-07 8.772E-08 6.035E-08 3.579E-08 2.479E-08 1.867E-08 1.483E-08 1.221E-08 1.033E-08 8.915E-09 7.817E-09 Z

N 1.273E-07 7.475E-08 5.139E-08 3.0455-08 2.107E-08 1.586E-08 1.259E-08 1.036E-08 8.762E-09 7.559E-09 6.625E-09 Z

NNE 6.508E-08 3.782E-08 2.581E-08 1.513E-08 1.039E-08 7.781E-09 6.148E-09 5.042E-09 4.248E-09 3.654E-09 3.194E-09 a

NE 6.2915-08 3.539E-08 2.3615-08 1.342E-08 9.033E-09 6.656E-09 5.193E-09 4.213E-09 3.517E-09 3.000E-09 2.604E-09 >

ENE 4.729E-08 2.665E-08 1.781E-08 1.015E-08 6.847E-09 5.056E-09 3.951E-09 3.211E-09 2.684E-09 2.293E-09 1.993E-09

E 5.15SE-08 2.883E-08 1.915E-08 1.083E-08 7.262E-09 5.337E-09 4.155E-09 3.366E-09 2.806E-09 2.392E-09 2.074E-09

ESE 4.843E-08 2.698E-08 1.788E-08 1.007E-08 6.742E-09 4.948E-09 3.848E-09 3.114E-09 2.594E-09 2.210E-09 1.915E-09

SE 5.488E-08 3.069E-08 2.039E-08 1.154E-08 7.748E-09 5.702E-09 4.445E-09 3.604E-09 3.008E-09 2.566E-09 2.227E-09

SSE 6.753E-08 3.785E-08 2.519E-08 1.428E-08 9.595E-09 7.064E-09 5.507E-09 4.466E-09 3.727E-09 3.179E-09 2.758E-09

VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0

DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 58.1

EXIT VELOCITY (METERS) 0.00 BLDG.MIN.CRS.SWC.AREA (SQ.HETERS) 2000.0

HEAT EMISSION RATE (CAL/SEC) 0.0

ALL GROUND LEVEL RELEASES.
USNRC CO?4Pt7ER CODE - XOQDOQ. VERSION 2.0 RUN DATE: 970513

* .. PALISADES xoDQoQ82 ..... USING 01/01/92 - 12/31/96 MET DATA "I"

GROUND LEVEL RELEASE - TOP OF CCNrAINMENT BUILDING

NO DECAY, UNDEPLETED

CHI/Q (SECIMETER CUBED) FOR EACH SECMENr

DIREToION .5-1

FROM SITE

S 7.808E-07

SSW 6.085E-07

SW 6.883E-07

WSW 7.038E-07

W 9.666E-07

WNW 1.292E-06

NW 1.627E-06

NNW 2.159E-06

N 1.829E-06

NNE 9.521E-07

NE 1.017E-06

ENE 7.724E-07

E 8.592E-07

ESE 8.271E-07

SE 9.353E-07

SSE 1.123E-06

SESMENT BOUNDARIES IN MILES FROM THE SITE

1-2 2-3 3-4 4-S 5-10 10-20 20-30 30-40

2.856e-07

2.219E-07

2.484E-07

2.527E-07

3.457E-07

4.630E-07

S.800E-07

7.695E-07

6.557E-07

3.454E-07

3.678E-07

2.773E-07

3.076S-07

2.934E-07

3.305E-07

4.016E-07

1.351E-07

1.057E-07

1.193e-07

1.224E-07

1.669E-07

2.232E-07

2.819E-07

3.765E-07

3.212E-07

1.676E-07

1.720E-07

1.294E-07

1.426E-07

1.351E-07

1.524E-07

1.863E-07

8.334E-08 5.828E-08

6.555E-08 4.602E-08

7.468E-08 5.279E-08

7.721E-08 5.4893-08

1.051E-07 7.463E-08

1.404E-07 9.958E-08

1.787E-07 1.276E-07

2.399E-07 1.718E-07

2.046E-07 1.465E-07

1.057E-07 7.516E-08

1.054E-07 7.332E-08

7.922E-08 5.511E-08

8.686E-08 6.020E-08

8.193E-08 5.661E-08

9.262E-08 6.411E-08

1.136E-07 7.881E-08

2.904E-08

2.308E-08

2.681E-08

2.815E-08

3.821E-08

5.089E-08

6.587E-08

8.923E-08

7.604E-08

3.854E-08

3.627E-08

2.731E-08

2.958E-08

2.770E-08

3.149E-08

3.882E-08

1.110E-08

8.912E-09

1.057E-08

1.126E-08

1.525E-08

2.025E-08

2.662E-08

3.636E-08

3.093E-08

1.540E-08

1.374E-08

1.038E-08

1.109E-08

1.033E-08

1.182E-08

1.462E-08

5.448E-09

4.409E-09

5.316E-09

5.725E-09

7.749E-09

1.026E-08

1.366E-08

1.877E-08

1.594E-08

7.825E-09

6.704E-09

5.092E-09

5.378E-09

4.986E-09

5.745E-09

7.116E-09

3.445E-09

2.802E-09

3.415E-09

3.703E-09

5.010E-09

6.625E-09

8.879E-09

1.224E-08

1.039E-08

5.056E-09

4.227E-09

3.222E-09

3.378E-09

3.126E-09

3. 617E-09

4. 482E-09

40-50

2.454E-09

2.004E-09

2.462E-09

2.683E-09

3.629E-09

4.793E-09

6.458E-09

8.s92E-09

7.569E-09

3.660E-09

3.006E-09

2.298E-09

2.397E-09

2.214E-09

2.571E-09

3.186E-09 CA)

Cw rI-.

(Ai

0

(n

0. mn

Q

0

-n

'1cn

m

0

CO)

m

0

C)

I-

-I

0

z

z

c

IIcn

m

co)

z

c

Im

z

-I
USNRC CCHPUTER CODE - XOQDOQ VERSION 2.0 RtJN DATE: 970513

** PALISADES XOQDOQ82 ***** USIN3 01/01/92 - 12/31/96 MET DATA ^***

GROUND LEVEL RELEASE - TOP OF CONrAINFENr BUILDING

2.260 DAY DECAY, UNDEPLETED

ANNUAL AVERAGE CHI/Q (SEC/METER CUBED)

SECTOR 0.250 0.500 0

DISTANCE IN MILES FRCH THE SITE

.750 1.000 1.500 2.000 2.500 3.000 3.500 4.000 4.500

S

WSW

W

WSW

NW

NW

N

NNE

NE

ENE

E

ESE

SE

SSE

4.205E-06

3.327E-06

3.887E-06

4.057E-06

5.550E-06

7.373E-06

9.524E-06

1.285E-05

1.087E-05

5.483E-06

5.447E-06

4.255E-06

4.615E-06

4.433E-06

5.088E-06

6.040E-06

1.379E-06 7.540E-07 4.979E-07 2.769E-07

1.084E-06 5.842E-07 3.8586-07 2.150E-07

1.240E-06 6.575E-07 4.319E-07 2.402E-07

1.277E-06 6.699E-07 4.388E-07 2.439E-07

1.757E-06 9.203E-07 6.016E-07 3.334E-07

2.343E-06 1.232E-06 8.062E-07 4.468E-07

2.969E-06 1.547E-06 1.009E-06 5.58SE-07

3.953E-06 2.047E-06 1.335E-06 7.408E-07

3.341E-06 1.735E-06 1.134E-06 6.316E-07

1.714E-06 9.099E-07 5.982E-07 3.338E-07

1.800E-06 9.837E-07 6.458E-07 3.563E-07

1.377E-06 7.44BE-07 4.872E-07 2.685E-07

1.528E-06 8.303E-07 5.423E-07 2.977E-07

1.477E-06 7.992E-07 5.196E-07 2.837E-07

1.676E-06 9.026E-07 5.856E-07 3.194E-07

1.997E-06 1.086E-06 7.087E-07 3.885E-07

1.831E-07 1.330E-07 1.024E 07 8.212E-08 6.785E-08 5.735E-08

1.428E-07 1.040E-07 8.032E-08 6.457E-08 5.346E-08 4.526E-08

1.604E-07 1.175E-07 9.117E-08 7.359E-08 6.114E-08 5.193E-08

1.637E-07 1.206E-07 9.394E-08 7.609E-08 6.341E-08 5.400E-08

2.235E-07 1.644E-07 1.280E-07 1.036E-07 8.628E-08 7.344E-08

2.993E-07 2.200E-07 1.712E-07 1.385E-07 1.153E-07 9.810E-08

3.761E-07 2.779E-07 2.171E-07 1.762E-07 1.472E-07 1.256E-07

5.008E-07 3.712E-07 2.907E-07 2.365E-07 1.979E-07 1.691E-07

4.271E-07 3.165E-07 2.478E-07 2.016E-07 1.686E-07 1.440E-07

2.242E-07 1.652E-07 1.287E-07 1.042E-07 8.687E-08 7.398E-08

2.343E-07 1.693E-07 1.299E-07 1.039E-07 8.564E-08 7.223E-08

1.763E-07 1.273E-07 9.763E-08 7.804E-08 6.431E-08 5.423E-08

1.948E-07 1.403E-07 1.073E-07 8.559E-08 7.039E-08 5.925E-08

1.850E-07 1.328E-07 1.014E-07 8.075E-08 6.631E-08 5.575E-08

2.085E-07 1.499E-07 1.145E-07 9.128E-08 7.502E-08 6.312E-08

2.543E-07 1.833E-07 1.403E-07 1.120E-07 9.213E-08 7.760E-08

ANMIAL AVEPAGS CHIQ (SEC/MRTER CUBED) DISTANCE IN MILES FROM THE SITE

SECTOR 5.000 7.500 10.000 15.000 20.000 25.000 30.000 35.000 40.000 45.000 50.000

Ir

Im

.1

CD

0

0

'1

-n

U)

m

a

0

U)

W

m

0

C)

-4

0

z

z

c

II-cn

0

m

Cn

z

a

0

Im

Iz

-i1

S 4.936E-08 2.774E-08

SSW 3.901E-08 2.204E-08

SW 4.489E-08 2.566E-08

WSW 4.678E-08 2.698E-08

W 6.361E-08 3.664E-08

WmW 8.494E-08 4.886E-08

NW 1.0903-07 6.323E-08

NNW 1.469E-07 8.570E-08

N 1.251E-07 7.285E-08

NNE 6.410E-08 3.697E-08

NE 6.206E-08 3.468E-08

ENE 4.659E-08 2.607E-08

E 5.082E-08 2.822E-08

ESE 4.776E-08 2.643E-08

SE 5.413E-08 3.005E-08

SSE 6.659E-08 3.7063-08

1.845E-08

1.472E-08

1.727E-08

1.827E-08

2.480E-08

3.304E-08

4.301E-08

5.851E-08

4.966E-08

2.504E-08

2.298E-08

1.729E-08

1.861E-08

1.739E-08

1.9833E-08

2.449E-08

1.039E-08 6.911E-09

8.327E-09 5.55SE-09

9.893E-09 6.657E-09

1.05SE-08 7.141E-09

1.431E-08 9.688E-09

1.90SE-08 1.289E-08

2.500E-08 1.700E-08

3.417E-08 2.331E-08

2.893E-08 1.9693-08

1.446E-08 9.7863-09

1.289E-08 8.558E-09

9.711E-09 6.459E-09

1.037E-08 6.861E-09

9.664E-09 6.380E-09

1.106E-08 7.329E-09

1.369E-08 9.073E-09

5.029E-09

4.051E-09

4.889E-09

5.267E-09

7.147E-09

9.508E-09

1.259E-08

1.730E-08

1.458E-08

7.218E-09

6.223E-09

4.702E-09

4.973E-09

4.619E-09

5.320E-09

6.588E-09

3.874E-09 3.103E-09 2.557E-09 2.153E-09 1.844E-09

3.126E-09 2.506E-09 2.067E-09 1.742E-09 1.492E-09

3.793E-09 3.056E-09 2.531E-09 2.140E-09 1.840E-09

4.101E-09 3.314E-09 2.751E-09 2.332E-09 2.009E-09

5.566E-09 4.500E-09 3.738E-09 3.170E-09 2.732E-09

7.405E-09 5.987E-09 4.975E-09 4.220E-09 3.639E-09

9.836E-09 7.972E-09 6.638E-09 5.641E-09 4.872E-09

1.354E-08 1.099E-08 9.164E-09 7.796E-09 6.739E-09

1.139E-08 9.223E-09 7.6743-09 6.5163-09 5.622E-09

5.620E-09 4.541E-09 3.771E-09 3.196E-09 2.754E-09

4.791E-09 3.836E-09 3.160E-09 2.662E-09 2.280E-09

3.624E-09 2.904E-09 2.395E-09 2.0183-09 1.730E-09

3.819E-09 3.051E-09 2.509E-09 2.110E-09 1.805E-09

3.544E-09 2.830E-09 2.327E-09 1.956E-09 1.673E-09

4.091E-09 3.273E-09 2.695E-09 2.268E-09 1.943E-09

5.066E-09 4.053E-09 3.337E-09 2.808E-09 2.404E-09

VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (MErERS)

DIAMETER (HETERS)

EXIT VELOCITY (METERS)

58.10

0.00

0.00

REP. WIND HEIGHT

BUILDING HEIGHT

BLDG .HIN.CRS . SEC. AREA

HEAT EMISSION RATE

(METERS)

(HETERS)

tSQ.ETrERs)

(CAL/SEC)8

10.0

58.1

2000.0

0.0

AMJ CJ.RThlln TFRUFT. RrJ.Mq
USNRC COMPUXMER CODE - XOQEOQ, VERSION 2.0 RUN DATE: 970513

..... PALISADES XOODO082 .... * USIM Q1/01/92 - 12/31/96 VW5 DATA '***'

GROUND LEVEL RELEASE - TOP OF CONTAINKEN'r EUILDINS

2.260 DAY DECAY, UNDPLETED

CHr/VQ mSEC/Imrs CUBED) FOR EhCH saDm SEGMET BOUNDARIES IN MILES FROM THE SIE

DIRECTION .5-1 1-2 2-3 3-4 4-S 5-10 10-20

FROM SITE

S 7.791E-07

ssw 6.072E-07

sW 6.867E-07

WSW 7.022E-07

W 9.64SE-07

hN4 1.290E-06

NW 1.624E-06

NNW 2.154E-06

N 1.825E-D6

NNE 9.5DOE-07

NE 1.015E-06

MEN 7.708E-07

E 8.574E-07

ESE 8.255E-07

SE 9.33SE-07

SSE 1.121E-06

20-30 30-40 40-50

2.843E-07

2.209E-07

2.473E-07

2.516E-07

3.441E-07

4.611E-07

5.775E-07

7.661E-07

6.524z-07

3.438E-07

3.664E-07

2.761E-07

3.063E-07

2.922E-07

3.292E-07

4.000E-07

1.341E-07 8.248E-08 5.7soE-08

1.049E-07 6.484E-08 4.537E-08

1.184E-07 7.387E-08 5.20SE-08

1.214E-07 7.636E-08 5.412E-08

1.656E-07 1.040E-07 7.360E-08

2.216E-07 1.390E-07 9.832E-08

2.798E-07 1.768E-07 1.258E-07

3.736E-07 2.373E-07 1.694E-07

3.18sE-07 2.022E-07 1.443E-07

1.663E-07 1.046E-07 7.414E-08

1.709E-07 1.044E-07 7.244E-08

1.2858-07 7.840E-08 5.439E-08

1.416E-07 8.600E-08 5.943E-08

1.342E-07 8.115E-08 5.592E-08

1.514E-07 9.173E-08 6.332E-08

1.850E-07 1.125E-07 7.783E-08

2.842E-08

2.256E-08

2.621E-08

2.751E-08

3.737E-08

4.985E-08

6.441E-08

8.722E-08

7.415E-08

3.770E-08

3.557E-08

2.673e-08

2.897E-08

2.715E-08

3.086E-08

3.804E-08

1.064E-08

8.515E-09

1.010E-08

1.075E-08

1.459e-08

1.942E-08

2.545E-08

3.47SE-08

2.943E-08

1.473E-08

1.321E-08

9.950E-09

1.064E-08

9.921E-09

1. 13sE-08

1.404E-08

5.069E-09

4.082E-09

4.922E-09

5.300E-09

7.192E-09

9.569E-09

1.267E-08

1.740E-09

1.466E-08

7.263E-09

6.272E-09

4.739E-09

5. 015E-09

4.659E-09

5.364E-09

6.642E-09

3.115E-09

2.516E-09

3.066E-09

3.324E-09

4.514E-09

6.007E-09

7.996E-09

1.102E-08

9.251E-09

4.556E-09

3.851E-09

2.916E-09

3.064E-09

2.842E-09

3.286E-09

4.070E-09

2.158E-09

1.746E-09

2.145E-09

2.337E-09

3.176E-09

4.229E-09

5.651E-09

7.810E-09

6.52SE-09

3.203E-09

2.66SE-09

2.023E-09

2.115E-09

1.961E-09

2.274E-09

2.815E-09 v

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USNRC COKPU7ER CODE - YXQDOQ, VERSION 2.0 RUN DATE: 970513

PALISADES XOQDOQ82 -*** USING 01/01/92 - 12/31/96 MET DATA *

GROUND LEVEL RFELEASE - TOP OF CZNTAINMENT BUILDING

8.000 DAY DECAY, DEPLETED

ANNUAL AVERAGE CHi/Q (SEC1mT8R CUBED) DISTANCE IN MILES FRoM THE SITE

SECTOR 0.250 0.500 0.750 1.000 1.5DO 2.000 2.500 3.000 3.500 4.000 4.500

S 3.982e-06 1.261e-06 6.730E-07 4.367E-07 2.359E-07 1.523E-07 1.083E-07 8.1868-08 6.456E-08 5.254e-08 4.378E-08

ssW 3.150E-06 9.913E-07 S.215E-07 3.384E-07 1.832E-07 1.187E-07 8.473e-08 6.423E-08 5.078E-08 4.141E-08 3.457E-08

SW 3.681E-06 1.134E-06 5.869E-07 3.789E-07 2.047E-07 1.334E-07 9.572E-08 7.291E-08 5.787E-06 4.736E-OB 3.966E-08

hSW 3.842E-06 1.168E-06 S.980E-07 3.849E-07 2.078E-07 1.362E-07 9.823E-08 7.513E-08 5.985E-08 4.912E-08 4.12SE-08 w 5.256E-06 1.606E-06 8.215E-07 5.278E-07 2.841E-07 1.859E-07 1.339E-07 1.023E-07 8.146E-08 6.682E-08 5.608E-08

WNW 6.982E-06 2.141E-06 1.100E-06 7.071E-07 3.806E-07 2.488E-07 1.791E-07 1.368E-07 1.088E-07 8.923E-08 7.486E-08

NW 9.018E-06 2.71SE-06 1.381E-06 8.8488-07 4.75SE-07 3.128E-07 2.263E-07 1.736E-07 1.386E-07 1.140E-07 9.58BE-08 NNW 1.217E-05 3.613E-06 1.827E-06 1.171E-06 6.312E-07 4.16SE-07 3.024E-07 2.325e-07 1.860E-07 1.532E-07 1.291E-07 O

N 1.029E-05 3.058E-06 1.549E-06 9.954E-07 5.384E-07 3.554E-07 2.579E-07 1.983E-07 1.586E-07 1.307E-07 1.101E-07 n NNE 5.192E-06 1.567E-06 8.121E-07 5.248E-07 2.844E-07 1.86SE-07 1.345E-07 1.029E-07 8.196E-08 6.727E-08 5.649E-08 Gn NE 5.1578-06 1.646E-06 8.778E-07 5.6648-07 3.03SE-07 1.947E-07 1.378E-07 1.038E-07 8.162E-08 6.62SE-08 5.5098E-08 _ ENE 4.029E-06 1.259E-06 6.648E-07 4.273E-07 2.287E-07 1.466E-07 1.037E-07 7.804E-08 6.13SE-08 4.978E-08 4.139E-08 > E 4.370E-06 1.397E-06 7.410e-07 4.756E-07 2.536E-07 1.620E-07 1.142E-07 8.576E-08 6.727E-08 5.448E-08 4.522E-08 ESE 4.1988-06 1.350E-06 7.132E-07 4.557E-07 2.416E-07 1.538E-07 1.081E-07 8.103E-08 6.344E-08 5.130E-08 4.252E-08 0 t SE 4.817E-06 1.532E-06 8.055E-07 5.136E-07 2.720E-07 1.733E-07 1.220E-07 9.152E-08 7.172E-08 5.80SE-08 4.815E-08 0 tn SSE 5.719E-06 1.826E-06 9.691E-07 6.216E-07 3.309E-07 2.114E-07 1.492E-07 1.121E-07 8.798E-08 7.129E-08 5.920E-08 -o m m

cn ANmUAL AVERAGE CHI/Q (SEC/HETER CUBED) DISTANCE IN MILES FROM4 THE SITE co z

SECTOR 5.000 7.500 10.0C0 15.0C0 20.000 25.000 30.000 35.000 40.000 45.000 50.000 r . C m 0 0~

S 3.719E-08 1.987E-08 1.266E-08 6.668E-09 4.208E-09 2.931E-09 2.174Z-09 1.683E-09 1.345E-09 1.102E-09 9.195E-10 - C rm SSW 2.941E-08 1.580E-08 1.011E-08 5.35SE-09 3.392E-09 2.3708-09 1.762E-09 1.367E-09 1.094E-09 8.973E-10 7.499E-10 > >

S. 3.384E-08 1.840E-08 1.187E-08 6.362E-09 4.065E-09 2.860e-09 2.138E-09 1.667e-09 1.340e-09 1.103e-09 9.248E-10 0 _ ; WSW 3.527E-08 1.935E-08 1.256E-08 6.786E-09 4.361E-09 3.081e-09 2.311E-09 1.807E-09 1.457E-09 1.202E-09 1.010E-09 0 -D W 4.794E-08 2.626E-08 1.703E-08 9.195E-09 5.907E-09 4.173E-09 3.130E-09 2.448E-09 1.973E-09 1.628E-09 1.36SE-09 Z r WNM 6.396E-08 3.498E-08 2.266E-08 1.222E-08 7.839E-09 5.533E-09 4.148E-09 3.241E-09 2.612E-09 2.154E-09 1.818E-09 3 > NW 8.212E-08 4.532E-08 2.954E-08 1.607E-08 1.037E-08 7.352E-09 5.531E-09 4.335E-09 3.502E-09 2.894E-09 2.436E-09 t Z NNW 1.107E-07 6.143E-08 4.019E-08 2.196E-08 1.422E-08 1.011E-08 7.617E-09 5.980E-09 4.836E-09 4.002E-09 3.371e-09 Z I

N 9.439E-08 5.2318-08 3.419E-08 1.866E-08 1.207E-08 8.5648-09 6.449E-09 5.05SE-09 4.087E-09 3.379E-09 2.844E-09 C

NNE 4.831E-08 2.649E-08 1.719E-08 9.289E-09 5.967E-09 4.214E-09 3.160E-09 2.470E-09 1.9918-09 1.642E-09 1.379E-09 NE 4.671E-08 2.481E-08 1.574E-08 8.249E-09 5.194E-09 3.612E-09 2.676E-09 2.070E-09 1.653E-09 1.353Z-09 1.129E-09 r ENE 3.510E-08 1.867E-08 1.186E-08 6.231E-09 3.932E-09 2.740E-09 2.032E-09 1.574E-09 1.259E-09 1.031E-09 8.614E-10 E 3.827E-08 2.020E-08 1.276E-OR 6.651E-09 4.172E-09 2.894E-09 2.139E-09 1.6S2E-09 1.317E-09 1.077E-09 8.971E-10

ESE 3.596E-08 1.891E-08 1.192E-08 6.190E-09 3.875E-09 2.684E-09 1.981E-09 1.529E-09 1.219E-09 9.955E-10 8.292E-10

SE 4.07SE-08 2.15OR-08 1.359E-08 7.089E-09 4.453E-09 3.093E-09 2.288E-09 1.769E-09 1.413E-09 1.156E-09 9.641E-10

SSE 5.0148-08 2.653E-08 1.679E-08 8.772E-09 5.515E-09 3.831E-09 2.836E-09 2.192E-09 1.750E-09 1.432E-09 1.194E-09

VENT AIDM BUILDING PARAHETERS:

RELEASE HEIGNt (METERS) 58.10 REP. WIND HEIGTr hMErERS| 10.0

DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 58.1

EXIT VELOCIT!Y (ME'ERS) 0.00 BLDG.HIN.CRS.SEC.AREA (SQ.METERS) 2000.0

HEAT EDISSICY RATE (CAL/SEC) 0.0

ALL GROUND LEVEL RELEASES.
usNRC CauER coDe 

- XOQDOQ. VERSrON 2.0 RUN DATE: 970513

****' PALISADES XQ00M82 ***** USNIW 01/01/92 

- 12/31/96 MEr DATA *''''

GROUND LEVEL RELEASE 

- TOP OF CCrASMr BUILDING

8.000 DAY DEEAY, DEPLED

CHI/Q (SEWMETE CUBED) FOR EACH SBaEE

SE XW" BOUNDAIES IN MILES FROM MM SITI

DIRRXTION .5-1 1-2 2-3 3-4 4-5 5-10

FEO14 SrTE

S 6.986E-07 2.434E-07

SSW 5.445E-07 1.391E-07

SW 6.160E-07 2.117E-07 WSW 6.299e-07 2.153E-07

W 8.653E-07 2.946E-07

WNW 1.157E-06 3.946E-07

NW 1.457S-06 4.943E-07

NNW 1.932E-06 6.557E-07

N 1.637E-06 5.5S6E-07

NNE 8.521E-07 2.943E-07 NE 9.101E-07 3.136E-07

ENE 6.913E-07 2.364E-07

E 7.689E-07 2.622E-07

5EE 7.403E-07 2.502E-07

SE 8.371E-07 2.818E-07

SSE 1.OOSE-06 3.424E-07

10-20 20-30 30-40 40-50

1.094E-07

8.560E-08

9.664E-08

9.911E-08

1.351E-07

1.808E-07

2.283E-07

3.049E-07

2.601E-07

1.357E-07

1.394E-07

1.049E-07

1.156E-07

1.095E-07

1.235E-07

1.510E-07

6.492E-08 4.393E-08

5.105E-08 3.468E-08

5.816E-08 3.979E-08

6.013E-08 4.137e-08

8.194E-08 5.625E-08

1.094E-07 7.508E-08

1.392E-07 9.614E-08

1.868E-07 1.295E-07

1.593E-07 1.104E-07

8.234E-08 5.66SE-08

8.21oE-os 5.529E-08

6.171E-08 4.155E-08

6.768E-08 4.539E-08

6.384E-08 4.269E-08

7.217E-08 4.834E-08

8.852E-08 5.943E-08

2.052E-08 6.907E-09

1.630E-08 5.540E-09

1.893E-08 6.565E-09

1.987E-08 6.991E-09

2.697E-508 947SE-09

3.594e-08 1.259E-08

4.64se-08 1.653E-08

6.295E-08 2.257E-08

5.361E-08 1.918E-08

2.721E-08 9.569e-09

2.565E-08 8.556E-09

1.93OR-08 6.461E-09

2.0915-08 6.90SE-09

1.959E-08 6.434E-09

2.226E-08 7.362E-09

2.74se-08 9.106E-09

2.969E-09 1.695E-09

2.399E-09 1.3765-09

2.892E-09 1.677E-09

3.114E-09 1.81SE-09

4.218E-09 2.462E-09

5.594E-09 3.261E-09

7.429e-09 4.359E-09

1.021E-08 6.012E-09

8.652E-09 S.085E-09

4.260E-09 2.48SE-09

3.659E-09 2.084E-09

2.77sE-09 1.585E-09

2.932E-09 1.663E-09

2.721E-09 1.540E-09

3.134E-09 1.782E-09

3.882E-09 2.20SE-09

1. 106E-09

9.011E-10

1.107E-09

1.206E-09

1.634E-09

2.162E-09

2.904E-09

4.016E-09

3.391E-09

1.648E-09

1.359E-09

1.036E-09

1. 01E-09

1.OOOE-09

1.161E-09

-4 1.438E-09 -Im

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-4
USNRC COMPUTE CODE - XOQDOQ. VERSION4 2.0 INDT:901 RllN DATE: 970513

*'^ PALUSADES X0QDoQ82 '*'* USIhX 01/01/92 - 12/31/96 MET DATA 'h*^

GRUND LEVEL RELEASE - 'MP CP CtOrMAMr BUILDING

*-^^**^^9^^***-* nRELATVE DEPOSITICN PER UNIT AREA (H**-2) AT FXED POIWrS Elf DO I.ND SDTIORS ********..i*e*

DIRE2IaN DISTANES IN HILES

FROM SITE 0.25 0.50 0.75 1.00 1.50 2.00 2.50 3.00 3.50 4.00 4.50

S 2.600E-08 8.794E-09 4.515E-09 2.772E-09 1.382E-09 8.323E-10 5.668E-10 4.107E-10 3.123E-10 2.460E-10 1.992E-10

SSW 1.731E-08 5.852E-09 3.005E-09 1.845E-09 9.19SE-10 5.579E-10 3.772E-10 2.7338-10 2.078E-10 1.637E-10 1.325E-10

SW 1.866E-08 6.309E-09 3.239E-09 1.989E-09 9.916E-1O 6.0143-10 4.066E-10 2.9463-10 2.240e-10 1.765E-10 1.429E-10

WSW 1.829E-08 6.183E-09 3.175E-09 1.949E-09 9.719E-10 5.894E-10 3.985E-10 2.888E-10 2.196E-10 1.730E-10 1.401E-10

N 2.6738-08 9.040E-09 4.641E-09 2.850E-09 1.421E-09 8.618E-10 5.826E-10 4.222E-10 3.210E-10 2.529E-10 2.048e-10

mmW 4.142E-08 1.401E-08 7.191E-09 4.416E-09 2.201E-09 1.33SE-09 9.0273-10 6.541E-10 4.974E-10 3.919E-10 3.172e-10

NW 4.8473-08 1.639E-08 8.416E-09 5.168E-09 2.576B-09 1.563g-09 1.056E-09 7.656E-10 5.821E-10 4.586E-10 3.713E-10 NMw 5.897E-08 1.994E-08 1.024e-08 6.287E-09 3.135E-09 1.901E-09 1.2853-09 9.314E-10 7.082E-10 5.580E-10 4.517E-10

N 4.172E-08 1.411E-08 7.244E-09 4.448E-09 2.2183-09 1.345E-09 9.093E-10 6.589E-10 5.013E-10 3.947E-10 3.196E-10 NNE 2.423E-08 8.194E-09 4.207E-09 2.583E-09 1.288e-09 7.811E-10 5.281E-10 3.827E-10 2.910E-10 2.292E-10 1.856E-10 NE 4.2083-08 1.423E-08 7.306E-09 4.486E-09 2.237E-09 1.356E-09 9.171E-10 6.6463-10 S.OS33-10 3.981E-10 3.223E-10

ENE 3.387E-08 1.145E-08 5.881E-09 3.611E-09 1.800E-09 1.0928-09 7.3823-10 5.349E-10 4.067E-10 3.204E-10 2.594E-10 E 3.926E-08 1.328E-08 6.816E-09 4.185E-09 2.0873-09 1.266E-09 8.556E-10 6.200E-10 4.71sE-10 3.714E-10 3.007E-10

ESE 4.148E-08 1.403E-08 7.202E-09 4.423E-09 2.20SE-09 1.337E-09 9.041E-10 6.552E-10 4.982E-10 3.9253-10 3.177E-10

SE 4.9193-08 1.663E-08 8.5403-09 5.244E-09 2.614E-09 1.586E-09 1.072E-09 7.769E-10 5.907E-10 4.654E-10 3.768E-10

SSE 5.133E-08 1.736E-08 8.913E-09 5.473E-09 2.7288-09 1.655E-09 1.119E-09 8.107E-10 6.165E-10 4.857E-10 3.932E-10

CA

00

DIRECTIONI

FROM SITE

S

SSW

SW

WSW

N 14NW

NW4

mm4

N

NNE3

NE

DEN

E

ESE

SE

SSE

DISTAN4ES IN HILES 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00

1.6483-10 8.074E-11 5.066E-11 2.561E-11 1.550E-11 1.0393-11 7.446B-12 5.591E-12 4.347E-12 3.473E-12 2.834E-12

1.0963-10 5.373e-11 3.371E-11 1.704E-11 1.031E-11 6.91SE-12 4.9553-12 3.721E-12 2.8933-12 2.311E-12 1.886E-12

1.1823-10 5.7923-lt 3.634E-11 1.837E-11 1.112E-11 7.45SE-12 5.342E-12 4.011E-12 3.119E-12 2.491E-12 2.033E-12

1.159E-10 5.677E-11 3.562E-11 1.801E-11 1.0903-11 7.307E-12 5.236E-12 3.931E-12 3.057E-12 2.442E-12 1.993E-12

1.694E-10 8.300E-11 5.208E-11 2.632E-11 1.593E-11 1.0683-11 7.654E-12 5.7483-12 4.4693-12 3.570E-12 2.914E-12

2.624E-10 1.286E-10 8.069E-11 4.078E-11 2.468E-11 1.655E-11 1.186E-11 8.9053-12 6.924E-12 5.531E-12 4.514E-12

3.071E-10 1.505E-10 9.443E-11 4.773E-11 2.889E-l1 1.937E-11 1.388E-11 1.042E-11 8.103E-12 6.473E-12 5.283E-12

3.736E-10 1.831E-10 1.149E-10 5.807E-11 3.515E-11 2.357E-11 1.689E-11 1.268E-11 9.859E-12 7.87SE-12 6.428E-12

2.643E-10 1.295E-10 8.128E-11 4.108E-11 2.487E-11 1.667E-11 1.19SE-11 8.970E-12 6.975E-12 5.571E-12 4.547E-12

1.535E-10 7.523E-11 4.720E-11 2.386E-11 1.444E-11 9.682E-12 6.938E-12 5.210E-12 4.051E-12 3.236E-12 2.641E-12

2.6663-10 1.306E-10 8.19SE-11 4.143E-11 2.508E-11 1.681E-11 1.20SE-11 9.047E-12 7.034E-12 5.619E-12 4.586E-12

2.146E-10 1.052E-10 6.598E-11 3.335E-11 2.019E-11 1.353E-11 9.698E-12 7.282E-12 5.662E-12 4.523E-12 3.692E-12

2.487E-10 1.219E-10 7.648E-11 3.866E-11 2.3403-11 1.569E-11 1.124E-11 8.441E-12 6.563E-12 5.242E-12 4.279E-12

2.62SE-10 1.288E-10 8.081E-11 4.085E-11 2.472E-11 1.658E-11 1.188E-11 8.919E-12 6.935E-12 5.539E-12 4.521E-12

3.117E-10 1.527E-10 9.583E-11 4.844E-11 2.932E-11 1.966E-11 1.408E-11 1.058E-11 8.223E-12 6.569E-12 5.361E-12

3.252E-10 1.594E-10 1.000E-10 5.0553-11 3.059E-11 2.051E-11 1.470E-11 1.104E-11 8.581E-12 6.855E-12 5.59SE-12

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USNRC COHPUTER CODE 

- XQDOQ, VERSION 2.0 RUN DATE: 970513

*-.^ PALISADES XQOQ82 *'** USDIM 01/01/92 

- 12/31/96 MET DATA ** 

*

GROUND LEVEL RELEASE 

- TOP OF CONTAINfET BUILDING

DIRECTIO*N .5-1 FRROK SITE

S 4.691E-09

SSW 3.1222-09

SW 3.366E-09

WSW 3.299E-09

w 4.823e-09

WNW 7.472E-09

NW 8.745E-09

NR1 1.064E-08

N 7.527E-09

NWE 4.371E-09

NE 7.591E-09

ENE 6.110E-09

E 7.082E-09

ESE 7.484E-09

SE 8.874E-09

SSE 9.261E-09

"***** RELATIVE DEPOSITIoN PER UNIT AREA (m**-2) BY DOWNWIND SECrORS

SSGMETr BOUNDARIES IN MILES

1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50

1.449e-09

9.645E-10

1.040E-09

1.019E-09

1.490E-09

2.308E-09

2.702E-09

3.287E-09

2.325E-09

1.351E-09

2.345E-09

1.888s-09

2.188E-09

2.312E-09

2.742E-09

2.861E-09

5.768e-10

3.838E-10

4.138E-10

4.055E-10

5.929E-10

9.186E-10

1.075e-09

1.308E-09

9.253E-10

5.374E-10

9.333E-10

7.512E-10

8.707E-10

9.200E-10

1.091E-09

1.139E-09

3.152E-10

2.097E-10

2.261E-10

2.216E-10

3. 240E-10

5.020E-10

5.875E-10

7.147E-10

5.057E-10

2.937E-10

5.100E-10

4.105E-10

4.758E-10

5.029E-10

5.962E-10

6.222E-10

2.003E-10

1.333E-10

1.437E-10

1.409E-10

2.059E-10

3.190E-10

3.734E-10

4.543E-10

3.214g-10

1.866E-10

3.241E-10

2.609E-10

3.024E-10

3.195E-10

3.789B-10

3.954E-10

8.604E-11

5.726E-11

6.173E-11

6.050E-11

8.845E-11

1.370E-10

1.604E-10

1.951E-10

1.380E-10

8.017E-11

1.392E-10

1.121E-10

1.299E-10

1. 373E-10

1.628E-10

1.699E-10

2.668E-11

1.776E-11

1.914E-11

1. 876E-11

2.743E-11

4.249E-11

4.974E-11

6.051E-11

4.281E-11

2.4868-11

4.317E-11

3.475E-11

4.028E-11

4.256E-11

5.047E-11

5.267E-11

1.057E-11

7.037E-12

7.587E-12

7.436E-12

1.087E-11

1.684E-1l

1.971E-11

2.3988-11

1.697E-11

9.853E-12

1.711E-11

1.377E-11

1.596E-11

1.687E-11

2.000E-11

2.088E-11

5.647E-12

3.758E-12

4.051E-12

3.971E-12

5.805E-12

8.994E-12

1.053E-11

1.281E-11

9.060E-12

5.262E-12

9.138E-12

7.355E-12

8.525E-12

9.008E-12

1.068E-11

1.115E-11

3.495E-12

2.326E-12

2.508E-12

2.458E-12

3.593E-12

5.567E-12

6.516E-12

7.927E-12

5.608E-12

3.257E-12

5.656E-12

4.552E-12

5.271E-12

5.576E-12

6.612E-12

6.900E-12

CD VENr AND BUILDIiG PARAMETERS:

RELEASE MEIGHT (METERS) 58.10

DILMETER (MTERS) 0.00

EXIT VELOC1TY (METERS) 0.00

REP. WIND HEIGHT (METERS) 10.0 BUILDING HEI5GT (METERS) 58.1

WXG.MHN.-CRS-S..AREA (SQ.METES) 2000.0

HEAT EMISSIOTN RATE (cAL/SW) 0.0

-IwI-m

CA)

(0

5.

tJ) 0

0

'1

'1

com

tn00

Co m0aC

tIZI0r

Com

Co zc

I-z

-4

ALL GRONlD LEVEL RELEES.
USNRC COMPUTER CODE 

- XOQDOQ, VERSION 2.0 RUN DATE: 970513

***** PALISADES XOQDOQ82 **-** USING 01/01/92 

- 12/31/96 MET DATA **t*O

GROUND LEVEL RELEASE 

- TOP OF COHTAINMEN? BUILDING

SPECIFIC POINTS OF INTEREST

RELEASE TYPE OF DIRECTION DI:

ID LOCATION FROM SITE (MILES)

mS

A SITE BOUnDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A GARDEN

A GARDEN

A GARDEN

A GARDeN

A GARDEN

A GARDEN

A GARDEN

A BEEF CoW

A BEEF COW

A RR COW

A BEEF COW

A BEFD OOW

A DAIRY COW

A GOAT

A GOAT

NNE

DEN

ES

ESE

SE

SSE

SS

NE

ENE

DE

SE

SSE

ENE

55

0.50

0.65

0.87

0.82

0.76

0.63

0.48

0.42

0.48

1.60

1.20

2.70

2.20

2.30

1.80

1.60

1.50

2.90

4.00

3.50

4.00

3.00

4.30

3.20

3.00

`AJCE X/Q

(METERS) (SEC/CUD.NETER)

NO DECAY

UNDEPLETED

805. 1.72E-06

1046. 1.22E-06

1400. 5.99E-07

1320. 7.28E-07

1223. 7.85E-07

1014. 1.18E-06

772. 2.13E-06

676. 1.78E-06

772. 1.16E-06

2575. 3.06E-07

1931. 4.96E-07

4345. 1.15E-07

3541. 1.70E-07

3701. 1.51E-07

2897. 2.45E-07

2575. 3.55E-07

2414. 2.78e-07

4667. 1.385-07

6437. 6.51E-08

5633. 8.64e-08

6437. 6.70E-08

4828. 1.415-07

6920. 6.83E-08

5150. 1.19E-07

4828. 1.02E-07

1.71E-06

1.22E-06

5.98E-07

7.27E-07

7.83E-07

1.18E-06

2.12E-06

1.78E-06

1.15E-06

3.04E-07

4.95E-07

1.14E-07

1.69E-07

1.50E-07

2.44E-07

3.53E-07

2.77E-07

1.36E-07

6.43E-08

8.56E-08

6.63E-08

1.40E-07

6.75e-08

1.18E-07

1.01e-07

X/Q X/Q

(SEC/CUB.WETER) (SEC/CUB.METER)

2.260 DAY DECAY 8.000 DAY DECAY

DEPLErED

1.57E-06

1.10e-06

5.29e-07

6.45E-07

6.98e-07

1.06E-06

1.95E-06

1. 64E-06

1.06E-06

2.58E-07

4.28E-07

9.20E-08

1.40E-07

1.23E-07

2.04E-07

2.99E-07

2.36E-07

1.09E-07

4.98E-08

6.73E-08

5.13E-08

1.12E-07

5.18E-08

9.39E-08

8.10e-08

D/Q

(PER SQ.METER)

8.19E-09

9.30E-09

4.58E-09

5.86E-09

7.04E-09

1.14E-08

1.86E-08

1.16E-08

6.26E-09

1.15E-09

3.29E-09

6.45e-10

1.07e-09

1.05E-09

1.91E-09

2.44E-09

1.38E-09

7.06E-10

3.20e-10

4.71E-10

3.93E-10

8.11E-10

4.09E-10

5.93E-10

6 .s5E-10

0

Ir- m

-.

5.

0.0

K)

CD

0

-n

m i

m00

(nm00z

zi a

IIcnmcnz

1C

C)

I-m

X3

r-z

-I

VENT AND BUILDING PARAME1DS:

RELEASE HEIGHT (METERS)

DIAMETER (METERS|

EXIT VELOCITY (METERS)

58.10

0.00

0.00

REP. WIND HEIGHT

BUILDING HEIGHT

LDG. MICS.SEX. AREA

HEAT EHISSIONI RATE

(METERS)

(METERS)

(SQ.NMEERS)

(CAL/SEC)

10.0

58.1

2000.0

0.0

ALL GROUND LEVEL RELEASES.
USNRC CCtYrFER CODE - XOQOCQ VERSION 2.0 RMN DATE: 970513

*** * PALISADES X0QDOQ82 ***** USING 01/01/92 - 12/31/96 MET DATA *****

GROUND LEVEL RELEASE - TOP OF CONTANlMEWz BUILDING

SPECIFIC POINTS OF INTEREST

RELEASE TYPE OF DIRECTION

ID LOCATION FROM SITE

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A SITE BOUNDARY

A RESIDENCE

A RESIDENCE

A RESIDENCE

A RESIDENCE

A RESIDENCE

A RESIDIRCE

A RESIDENCE

A RESIDENCE

A RESIDENCE

A BEEF COW

A BEEF COW

A BEEF COW

A BEEF COW

A BEEF Cow

A DAIRY COW

A GOAT

A GOAT

NNE

NE

ENE

E

ESE

SE

SSE

S

SSW

NNE

NE

ENE

E

ESE

SSE

S

SSW

NE

ENE

E

ESE

SSE

SE

NE

ESE

DISTANCE X/Q

(ILES) (METERS) (SEC/CUB.METER)

NQ DECAY

UNDEPLETED

0.50 805. 1.72E-06

0.65 1046. 1.22E-06

0.87 1400. 5.99E-07

0.82 1320. 7.28E-07

0.76 1223. 7.85E-07

0.63 1014. 1.18E-06

0.48 772. 2.13E-06

0.42 676. 1.78E-06

0.48 772. 1.16E-06

1.10 1770. 5.23E-07

1.20 1931. 4.96E-07

1.30 2092. 3.33E-07

1.00 1609. 5.44E-07

1.00 1609. 5.21E-07

1.00 1609. 5.87E-07

0.70 1127. 1.21E-06

0.50 SOS. 1.38E-06

0.70 1127. 6.SOE-07

2.90 4667. 1.38E-07

4.00 6437. 6.51E-08

3.50 5633. 8.64E-08

4.00 6437. 6.70E-08

3.00 4828. 1.41E-07

4.30 6920. 6.83E-08

3.20 5150. 1.19E-07

3.00 4828. 1.02E-07

UNDEPLETED

1.71E-06

1.22E-06

5.98E-07

7.27E-07

7.83E-07

1.18E-06

2.12E-06

1.78E-06

1.15E-06

5.21E-07

4.95E-07

3.3lE-07

5.42E-07

5.20E-07

5.86E-07

1.20E-06

1.38E-06

6.49E-07

1.36E-07

6.43E-08

8.56E-08

6.63E-08

1.40E-07

6.75E-08

1.18E-07

1.01E-07

X/Q X/Q D/Q

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

2.260 DAY DECAY 8.000 DAY DECAY

DEPLETED

1.57E-06

1.10E-06

5.29E-07

6.45E-07

6.98E-07

1.06E-06

1.95E-06

1.64E-06

1.06E-06

4.55E-07

4.28E-07

2.85E-07

4.76E-07

4.56E-07

5.14E-07

1.08E-06

1.26E-06

5.81E-07

1.09E-07

4.98E-08

6.73E-08

5.13E-08

1.12E-07

5. 18E-08

9.39E-08

8.10E-08

8.19E-09

9.30E-09

4.58E-09

5.86E-09

7.04E-09

1.14E-08

1.86E-08

1.16E-08

6.26E-09

2.20E-09

3.29E-09

2.30E-09

4.19E-09

4.42E-09

5.25E-09

1.00E-08

8.79E-09

3.37E-09

7.06E-10

3.20E-10

4.71E-10

3.93E-10

8.11E-10

4.09E-10

5.93E-10

6.55E-10

rI

m

7A

0.

CD.

0

cn

m

0

m

C)

I-

-4

0

z

zi

C

aEC,)

m

CO)

z

C

rm

M

r,

z

-q

VErT AND BUILDINlG PARAMETERS:

RELEASE HEIGHT (MLrERS)

DIAMETER (METERS)

EXIT VELOCITY (METERS)

58.10

0.00

0.00

REP. WIND HEIGHT

BUILDING HEIGHT

BLDG .HIN .CRS . SEC . AREA

HEAT MISSION RATE

(METERS)

(METERS)

(SQ.MErERS)

(CAL/SEC)

10.0

58.1

2000.0

0.0

ALL GROUND LEVL RELEASES.

I
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.4

2004 PALISADES LAND USE CENSUS

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

I

SECTOR

NNE

NE

ENE

E

ESE

SE

,SSE

S

SSW

RESIDENCE GARDEN

1.1 mi 1.7 mi

1.2 mi 1.2 mi

1.3 ml 1.6 mi

1.0 mi 2.1 mi

1.0 mi *1.0 mi

1.0 mi *1.0 mi

0.7 mi 1.6 ml

0.5 mi 4.0 ml

0.7 mi >5.0 mi

BEEF CATTLE

>5 mi

>5 mi

4.0 ml

>5 mi

>5 ml

1.9 ml

>5 ml

>5 mi

>5 mi

DAIRY COW

>5 ml

>5 mi

>5 ml

>5 ml

>5 ml

4.3 mi

>5 ml

>5 mi

>5 mi

GOAT

>5 ml

>5 ml

1.8 ml

3.5 ml

>5 ml

1.9 ml

4.8 ml

4.7 ml

>5 ml

I

I

42
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.4a

2004 PALISADES LAND USE CENSUS

Critical Receptor Items

Sector

SSE:

S

SE

Distance

Miles

0.48

0.50

1.0

Location/Description

Site Boundary

Residence, Palisades Park;

1/2 mile west of 2 9 th Avenue and

Blue Star intersection

77550 2 8 th Avenue

Item

N/A

Residence

Garden

*X/Q (sec/m3 )

2.13E-06

1.38E-06

5.87E-07

I

SE

SE

SE

*Base(d on

1.9 SE corner of 76"' Street & 30 "' Beef Cattle

4.3 72401 36th Ave Dairy Cow

1.9 SE corner of 76th Street & 3 0th Goat

Palisades 5-year composite meteorological data, 1992 - 1996.

2.32E-07

6.83E-08

2.32E-07 I

43
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.5

DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

Kr-85m

Kr-85

Kr-87

Kr-88

Kr-89

Xe- 131 m

Xe- 133m

Xe-i 33

Xe- 135m

Xe-135

Xe-137

Xe-'138

Ar-41

DFR1

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)

3.28(+3)

1. mrem/y per giCi/m 3

2. mrad/y per jiCi/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).

44
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.6

STABLE ELEMENT TRANSFER DATA

ELEMENT

H

C

Na

p

Cl.

Mn

Fe

Co

Ni

Ci

Zn

Rb

Sr

y

Zr

Nb

MD)

Tc

Ru

Rh

Ag

Tio

Cs

Ba

La

CeI

Pl

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.OE-02

8.OE-04

1.OE-05

5.OE-06

2.5E-03

7.5E-03

2.5E-02

1.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

Fm- MILK (GOAT)

(DAYS/L)

1.7E-01

1.OE-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

3.0E-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

1.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

F.- MEAT

(DAYS/KG)

1.2E-02

3.1 E-02

3.OE-02

4.6E-02

2.4E-03

8.0E-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.OE-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

(VEG/SOQI

4.8E-OO

5.5E-OO

5.2E-02

1. IE-O0

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-OO

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

45
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/5OY 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 3.79E-06 3.79E-06 3.79E-06

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

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

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

NA24 7.54E-06 7.54E-06 7.54E-06 7.54E-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 1.81 E-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.

KR884D 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

RB894D 0. 2.29E-07 1.47E-07 0. 0. 0. 4.87E-08

SR894D 2.84E-04 0. 8.15E-06 0. 0. 1.45E-03 4.57E-05

SR904D 2.92E-02 0. 1.85E-03 0. 0. 8.03E-03 9.36E-05

SR914 D 6.83E-08 0. 2.47E-09 0. 0. 3.76E-05 5.24E-05

SR924 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.

46
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/5OY PER PCI INHALED IN FIRST YR)

ISOTOPE

Y90

Y91M-D

Y91

Y92

Y93

ZR93d-D

ZR95-i D

ZR974 D

NB93M

NB95

NB97

M093

M099 FD

TC99M

TC99

TC101

RU103+D

RU10'i+D

RU1 06+D

RH105

PD107'

PD109

AG110M+D

AG 11

CD113M

CD11iM

SN123

SN125+D

SN12E6+D

SB124

SB12E+D

SB12E

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+[)

BONE

2.35E-06

2.91 E-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-1 0

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

2.51 E-07

1.44E-05

3.97E-07

3.41 E-07

6.01 E-08

5.04E-09

1.42E-06

4.93E-06

6.81 E-10

4.35E-06

2.48E-1 1

3.93E-08

5.87E-12

1.69E-07

3.59E-1 I

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-1 0

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

2.31 E-08

2.66E-1 1

8.85E-08

5.80E-13

4.85E-07

2.93E-1 0

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

1.11E-06

8.76E-08

4.70E-07

1.48E-06

3.49E-10

1.59E-06

1.34E-11

2.59E-08

3.57E-12

1.26E-07

2.74E-1 1

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-1 1

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-1 1

1.54E-06

1.89E-07

2.22E-1 1

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

1.1 9E-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

47
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

INFANT INHALATION DOSE COMMITMENT FACTORS (MREM/5OY PER PCI INHALED IN FIRST YR)

ISOTOPE

1132

1133+1)

1134

1135+1)

XE13 zM

XE1 33M

XE1 33

XE1 35M

XE13'5

XE137

XE1 38+D

CS1 3'1M+D

CS 1 34

CS135

CS136

CS1 3'+D

CS138

CS1 39+D

BA1 39

BA14tl+D

BA141+D

BA1 42+D

LA140

LA141

LA1 42

CE14',

CE1 43+D

CE1 44+D

PR143

PR144

ND14;'+D

PM14.'

PM14l3M+D

PM148

PM149

PM15'1

SM1511

SM153

EU1 52

EU154.

EU155

EU156E

TB160

HO1 66M

W181

W1 85

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-1 1

3.61 E-07

4.85E-09

7.36E-1 0

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.

2.10E-07

5.02E-04

8.66E-05

9.61 E-05

4.37E-04

5.58E-07

3.03E-07

7.03E-1 3

4.OOE-08

7.70E-1 4

2.36E-1 4

1 .43E-07

1 .40E-09

2.69E-1 0

1.19E-05

1 .38E-07

8.65E-04

3.74E-06

1.32E-1 1

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-1 2

1.40E-12

3.68E-08

2.45E-1 0

6.46E-1 1

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

1.21 E-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

1.41 E-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

2.00E-08

5.69E-05

1.01 E-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

1.31 E-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

5.95E-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

4.14E-05

2.14E-05

1.65E-05

2.63E-07

1.12E-05

2.54E-05

48
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

PB211)+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-05

RN22:2+D 0. 0. 0. 0. 0. 9.88E-06 0.

RA22:3+D 1.56E-03 2.26E-06 3.12E-04 0. 4.16E-05 2.25E-01 3.04E-04

RA2241+D 1.77E-04 4.OOE-07 3.54E-05 0. 7.30E-06 7.91E-02 3.42E-04

RA22!5+D 2.57E-03 2.88E-06 5.13E-04 0. 5.31E-05 2.57E-01 2.87E-04

RA22(3+D 2.48E-01 1.46E-05 2.05E-01 0. 2.94E-04 7.83E-01 3.05E-04

RA2213+D 1.60E-01 7.61E-06 1.80E-01 0. 1.53E-04 1.09E-00 5.19E-05

AC22!5 3.69E-03 4.72E-03 2.48E-04 0. 3.49E-04 1.96E-01 2.71E-04

AC22.'+D 5.29E+00 8.76E-01 3.28E-01 0. 1.86E-01 1.62E+00 5.27E-05

TH22,+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

TH23() 3.46E+00 1.79E-01 9.65E-02 0. 8.82E-01 2.18E+00 3.87E-05

TH23,+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.OOE-01 3.62E-01 0. 1.62E+00 3.85E-01 4.61E-05

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

U232±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 5.01E-02 0. 3.60E-03 0. 1.03E-02 3.35E-01 3.71E-05

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

PU24' +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

AM24:3 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

CM24:3 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

CM241; 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

CM243 1.82E+01 7.12E+00 1.10E+00 0. 4.24E+00 3.23E+00 9.43E-04

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

49
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

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

BE10 8.43E-04 9.83E-05 2.12E-05 0. 0. 7.41E-04 1.72E-05

C14 9.70E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06 1.82E-06

N13 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08 2.33E-08

F18 1.88E-06 0. 1.85E-07 0. 0. 0. 3.37E-07

NA22 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05 4.41E-05

NA24 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06 4.35E-06

P32 7.04E-04 3.09E-05 2.67E-05 0. 0. 0. 1.14E-05

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

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

CA41 7.06E-05 0. 7.70E-06 0. 0. 7.21 E-02 2.94E-07

SC46 1.97E-04 2.70E-04 1.04E-04 0. 2.39E-04 0. 2.45E-05

CR51 0. 0. 4.17E-08 2.31E-08 6.57E-09 4.59E-06 2.93E-07

MN54 0. 1.16E-05 2.57E-06 0. 2.71 E-06 4.26E-04 6.19E-06

MN56 0. 4.48E-10 8.43E-11 0. 4.52E-10 3.55E-06 3.33E-05

FE55 1.28E-05 6.80E-06 2.10E-06 0. 0. 3.OOE-05 7.75E-07

FE59 5.59E-06 9.04E-06 4.51E-06 0. 0. 3.43E-04 1.91E-05

C057 0. 2.44E-07 2.88E-07 0. 0. 1.37E-04 3.58E-06

C058 0. 4.79E-07 8.55E-07 0. 0. 2.99E-04 9.29E-06

C060 0. 3.55E-06 6.12E-06 0. 0. 1.91E-03 2.60E-05

N159 1.66E-05 4.67E-06 2.83E-06 0. 0. 2.73E-05 6.29E-07

N163 2.22E-04 1.25E-05 7.56E-06 0. 0. 7.43E-05 1.71 E-06

N165 8.08E-10 7.99E-11 4.44E-11 0. 0. 2.21E-06 2.27E-05

CU64 0. 5.39E-10 2.90E-10 0. 1.63E-09 2.59E-06 9.92E-06

ZN65 1.15E-05 3.06E-05 1.90E-05 0. 1.93E-05 2.69E-04 4.41E-06

ZN69M+D 4.26E-09 7.28E-09 8.59E-10 0. 4.22E-09 7.36E-06 2.71 E-05

ZN69 1.81E-11 2.61E-11 2.41E-12 0. 1.58E-11 3.84E-07 2.75E-06

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

BR82 0. 0. 5.66E-06 0. 0. 0. 0.

BR83+1D 0. 0. 1.28E-07 0. 0. 0. 0.

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

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

KR83?A 0. 0. 0. 0. 0. 1.22E-09 0.

KR85MA 0. 0. 0. 0. 0. 6.58E-09 0.

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

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

KR884+D 0. 0. 0. 0. 0. 6.99E-08 0.

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

RB86 0. 5.36E-05 3.09E-05 0. 0. 0. 2.16E-06

RB87 0. 3.16E-05 1.37E-05 0. 0. 0. 2.96E-07

RB88 0. 1.52E-07 9.90E-08 0. 0. 0. 4.66E-09

RB89dD 0. 9.33E-08 7.83E-08 0. 0. 0. 5.11E-10

SR89d D 1.62E-04 0. 4.66E-06 0. 0. 5.83E-04 4.52E-05

SR90dD 2.73E-02 0. 1.74E-03 0. 0. 3.99E-03 9.28E-05

SR91 4 D 3.28E-08 0. 1.24E-09 0. 0. 1.44E-05 4.70E-05

SR924 D 3.54E-09 0. 1.42E-1 0 0. 0. 6.49E-06 6.55E-05

*Incluces a 50% increase to account for percutaneous transpiration.

50
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE

Y90

Y91M-D

Y91

Y92

Y93

ZR934 D

ZR954D

ZR974D

NB93M

NB95

NB97

M093

MO99-+D

TC99M

TC99

TC101

RU10$+D

RU10'+D

RU1O6.+D

RH10'

PD107

PD109

AG11CM+D

AG111

CD112M

CD11'M

SN123

SN125+D

SN 126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131 M+D

TE131 tD

TE132tD

TE133VM+D

TE134tD

1129

1130

1131+D

BONE

1.11E-06

1.37E-10

2.47E-04

5.50E-09

5.04E-08

2.07E-04

5.13E-05

5.07E-08

1.27E-04

6.35E-06

1.16E-10

0.

0.

4.81E-13

1.34E-07

2.19E-14

7.55E-07

4.13E-10

3.68E-05

3.91 E-09

0.

0.

4.56E-06

1.81 E-07

0.

0.

1.29E-04

4.95E-06

6.23E-04

1.55E-05

2.66E-05

1.72E-06

1.36E-07

1.82E-06

6.72E-06

7.49E-10

5.19E-06

2.64E-1 1

3.63E-08

5.87E-12

1.30E-07

2.93E-1 1

1.53E-11

1.05E-05

2.21 E-06

1.30E-05

LIVER

0.

0.

0.

0.

0.

7.80E-05

1.13E-05

7.34E-09

3.17E-05

2.48E-06

2.08E-1 1

3.76E-06

4.66E-08

9.41 E-13

1.49E-07

2.30E-14

0.

0.

0.

2.10E-09

2.65E-07

1.48E-09

3.08E-06

5.68E-08

4.93E-04

7.88E-05

2.14E-06

9.94E-08

1.04E-05

2.OOE-07

2.05E-07

2.62E-08

2.09E-09

6.29E-07

2.31 E-06

2.57E-10

1.85E-06

9.45E-12

1.60E-08

2.28E-12

7.36E-08

1.51 E-11

8.81 E-12

6.40E-06

4.43E-06

1.30E-05

TOTAL BODY

2.99E-08

4.98E-12

6.59E-06

1.57E-10

1.38E-09

5.55E-05

1.OOE-05

4.32E-09

1.04E-05

1.77E-06

9.74E-12

1.35E-07

1.15E-08

1.56E-1 1

5.35E-08

2.91 E-13

2.90E-07

1.50E-10

4.57E-06

1.79E-09

2.51 E-08

4.95E-10

2.47E-06

3.75E-08

2.12E-05

3.39E-06

4.19E-06

2.95E-07

2.36E-05

5.41 E-06

5.59E-06

6.16E-07

4.70E-08

2.47E-07

8.16E-07

1.65E-10

8.22E-07

6.44E-1 2

1.37E-08

1.78E-12

7.12E-08

1.50E-11

9.40E-12

5.71 E-06

2.28E-06

7.37E-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.

2.27E-06

1.03E-07

2.84E-06

3.41 E-08

2.46E-08

1.OOE-08

1.51E-09

5.20E-07

1.64E-06

5.30E-1 0

1.71 E-06

1.93E-11

2.64E-08

4.59E-12

8.58E-08

2.32E-1 1

1.24E-11

4.28E-03

4.99E-04

4.39E-03

KIDNEY

0.

0.

0.

0.

0.

3.OOE-04

1.61 E-05

1.05E-08

3.44E-05

2.33E-06

2.31 E-11

1.06E-06

1.06E-07

1.37E-11

1.75E-06

3.92E-1 3

1.90E-06

3.63E-10

4.97E-05

8.39E-09

1.97E-06

7.06E-09

5.74E-06

1.71 E-07

5.13E-04

5.93E-05

0.

0.

0.

0.

0.

0.

0.

0.

1.72E-05

1.91 E-09

1.36E-05

6.94E-1 1

1.08E-07

1.59E-1 I

4.79E-07

1.01E-10

5.71 E-11

1.08E-05

6.61 E-06

2.13E-05

LUNG

7.07E-05

7.60E-07

7.1 OE-04

6.46E-06

2.01 E-05

7.1 OE-04

6.03E-04

3.06E-05

1.04E-04

1.66E-04

9.23E-07

1.70E-04

3.66E-05

2.57E-07

3.37E-04

1.58E-07

1.79E-04

4.30E-06

3.87E-03

7.82E-06

3.16E-05

6.16E-06

1.48E-03

7.73E-05

6.94E-04

5.86E-04

9.59E-04

2.43E-04

3.02E-03

8.76E-04

6.27E-04

2.86E-04

6.17E-05

1.29E-04

4.OOE-04

2.71 E-06

4.76E-04

7.93E-07

5.56E-05

5.55E-07

1.02E-04

1.60E-06

1.23E-06

0.

0.

0.

GI-LLI

7.24E-05

4.64E-07

4.97E-05

6.46E-05

1.05E-04

1.47E-05

1.65E-05

9.49E-05

2.45E-06

1.OOE-05

7.52E-06

3.78E-06

3.42E-05

1.30E-06

7.75E-06

4.41 E-09

1.21 E-05

2.69E-05

1.16E-04

1.33E-05

7.26E-07

2.59E-05

2.71 E-05

2.98E-05

1.63E-05

4.97E-05

4.05E-05

7.17E-05

1.63E-05

4.43E-05

1.09E-05

5.67E-05

3.82E-05

9.13E-06

1.93E-05

1.52E-05

4.91 E-05

6.89E-06

8.32E-05

3.60E-07

3.72E-05

4.77E-06

4.87E-07

2.15E-07

1.38E-06

7.68E-07

51
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE

1132

1133+1)

1134

1135+1)

XE131M

XE133M

XE13'i

XE13E5M

XE13E

XE137

XE136+D

CS13'1M+D

CS13'.

CS135

CS136

CS137+D

CS138

CS139+D

BA13E9

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE141

CE143+D

CE144+D

PR143

PR14.

ND147+D

PM14,'

PM148M+D

PM148

PM149

PM15'1

SM151

SM153

EU152

EU154

EU155

EU15E

TB160

HO166M

Wi 81

W185

Wi 87

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

1.71 E-07

1.09E-07

4.98E-1 0

2.OOE-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

LIVER

1.10E-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

1.11E-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

TOTAL BODY

5.07E-07

2.08E-06

2.69E-07

1.12E-06

0.

0.

0.

0.

0.

0.

0.

6.12E-08

6.07E-05

4.45E-06

3.14E-05

3.47E-05

1.50E-07

5.80E-08

1.45E-11

1.17E-06

1.72E-12

7.54E-1 3

2.04E-08

1.15E-10

3.49E-1 I

7.83E-07

7.77E-09

9.77E-05

2.47E-07

8.10E-13

1.84E-07

1.36E-05

6.55E-06

1.25E-07

8.45E-09

2.82E-09

1.49E-05

4.35E-09

1.61 E-04

2.27E-04

3.18E-05

8.75E-07

9.67E-06

2.37E-04

8.99E-10

2.91 E-08

THYROID

5.23E-05

1.04E-03

1.37E-05

2.14E-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.

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

5.71 E-09

2.56E-14

7.87E-1 5

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

4.71 E-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.OOE-04

1.66E-03

2.79E-04

2.54E-04

5.34E-04

1.13E-03

5.71 E-06

1.86E-04

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

1.1 3E-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

2.61 E-07

1.11E-05

4.41E-09 2.61E-09 1.17E-09 0. 1.11E-05 2.46E-05

52
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21)+D 8.03E-02 1.85E-02 3.18E-03 0. 6.31E-02 8.74E-02 3.75E-05

Bl210+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 3.00E-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

RA223+D 2.34E-01 7.66E-06 1.92E-01 0. 2.03E-04 3.90E-01 3.02E-04

RA223+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

TH2213+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+1D 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+1D 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

NP23.'+D 2.88E+00 2.21E-01 1.19E-01 0. 7.41E-01 1.74E-01 5.06E-05

NP2381 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. 1.1OE-02 5.06E-04 8.90E-07

PU242 4.85E+00 6.20E-01 1.23E-01 0. 4.60E-01 5.50E-01 4.16E-05

PU244 5.67E+00 7.10E-01 1.41E-01 0. 5.27E-01 6.30E-01 6.20E-05

AM24-1 1.74E+00 7.85E-01 1.24E-01 0. 7.63E-01 2.02E-01 4.73E-05

AM24,!M 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

CM24:' 6.33E-02 4.84E-02 4.20E-03 0. 1.34E-02 1.31E-01 5.06E-05

CM24' 1.61 E+00 7.33E-01 9.95E-02 0. 3.74E-01 2.10E-01 4.98E-05

CM244 1.33E+00 6.48E-01 8.31 E-02 0. 3.06E-01 2.02E-01 4.82E-05

CM245 2.14E+00 8.16E-01 1.28E-01 0. 5.03E-01 1.95E-01 4.49E-05

CM246 2.13E+00 8.15E-01 1.28E-01 0. 5.03E-01 1.99E-01 4.41E-05

CM24,'+D 2.07E+00 8.02E-01 1.26E-01 0. 4.95E-01 1.95E-01 5.80E-05

CM2481 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

53
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

TEEN INHALATION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INHALED IN FIIRST 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. 7.10E-08 0. 0. 0. 3.89E-08

NA22 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05 1.76E-05

NA24 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06 1.72E-06

P32 2.36E-04 1.37E-05 8.95E-06 0. 0. 0. 1.16E-05

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

AR41 0. 0. 0. 0. O. 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 8.71E-08 0. 8.13E-07 7.71E-05 3.53E-06

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

BR834 D 0. 0. 4.30E-08 0. 0. 0. 0.

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

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

KR83hi 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.

KR88i 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

RB894D 0. 4.40E-08 2.91E-08 0. 0. 0. 4.22E-17

SR894 D 5.43E-05 0. 1.56E-06 0. 0. 3.02E-04 4.64E-05

SR904 D 1.35E-02 0. 8.35E-04 0. 0. 2.06E-03 9.56E-05

SR914D 1.10E-08 0. 4.39E-10 0. 0. 7.59E-06 3.24E-05

SR924D 1.19E-09 0. 5.08E-11 0. 0. 3.43E-06 1.49E-05

*Incluces a 50% increase to account for percutaneous transpiration.

54
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

ZR95i D

ZR97 0

NB93PA

NB95

NB97

M093

M099+D

TC99hl

TC99

TC101

RU 1 03+D

RU10'i+D

RU106+D

RH105'

PD107

PD10'

AG110M+D

AG111

CD11.M

CD11M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129\M+D

TE129

TE1311M+D

TE131+D

TE132+D

TE133:M+D

TE134 +D

1129

1130

1131 +ED

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.

4.31E-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

2.51 E-10

1.74E-06

8.87E-12

1.23E-08

1.97E-12

4.50E-08

1.01 E-1 1

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

3.48E-05

9.44E-07

4.42E-08

5.39E-06

9.92E-08

1.01E-07

1.27E-08

9.92E-10

2.80E-07

1.02E-06

1.14E-10

8.23E-07

4.22E-12

7.51E-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

2.21E-06

5.36E-11

4.65E-10

1.84E-05

3.94E-06

1.57E-09

3.41E-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-11

1.55E-06

6.24E-10

8.39E-09

1.66E-10

9.99E-07

1.26E-08

7.10E-06

1.14E-06

1.40E-06

9.99E-08

8.24E-06

2.10E-06

2.15E-06

2.23E-07

1.75E-08

8.34E-08

2.73E-07

5.52E-11

2.81E-07

2.20E-12

5.03E-09

6.30E-13

2.74E-08

5.71E-12

3.64E-12

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

4.00E-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

4.00E-05

3.59E-04

3.03E-04

4.96E-04

1.26E-04

1.72E-03

4.81 E-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

8.71 E-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

1.21 E-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

3.00E-05

1.68E-05

5.10E-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

55
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE

1132

1133+D

1134

1135+D

XE13lM

XE13:3M

XE13:3

XE1 3!5M

XE135

XE137

XE1 313+D

CS1 34M+D

CS131

CS135

CS13i;

CS1 3'r+D

CS1383

CS0139+0

BA139

BA140+D

BA14'1+D

BA1 42+D

LA14C

LA141

LA142

CE14'1

CE143+D

CE14'1+D

PR143

PR144

ND14,'+D

PM14.'

PM1411M+D

PM148

PM149

PM151

SM15',

SM153

EU15z

EU154

EU15E

EU15C

TB160

HO1 66M

W181

W185

W1 87

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-10

6.84E-06

1.78E-1 1

4.62E-1 2

5.99E-08

7.63E-1 0

1 .20E-1 0

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-1 0

5.31 E-11

2.37E-06

2.42E-08

2.53E-04

6.64E-07

2.20E-12

1.07E-06

1.10E-05

3.35E-06

8.88E-08

6.89E-09

1.99E-09

2.10E-05

2.01 E-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-1 3

2.84E-13

7.82E-09

3.87E-1 1

1.32E-1 1

2.71 E-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

1.31 E-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

2.00E-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

1.51 E-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

7.11 E-06

5.01 E-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

8.69E-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-11

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

4.10E-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

2.21 E-05

56
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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

PB21 D+D 3.09E-02 8.28E-03 1.07E-03 0. 2.95E-02 4.52E-02 3.87E-05

B121G+D 0. 2.26E-06 1.89E-07 0. 2.74E-05 1.91 E-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

RA22;+1D 1.33E-01 3.38E-06 9.87E-02 0. 9.67E-05 2.02E-01 3.11E-04

RA223+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

TH223+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 2.61 E+00 1.14E-01 9.21 E-02 0. 5.60E-01 8.60E-01 3.36E-05

TH234 2.32E-06 1.35E-07 6.71 E-08 0. 7.73E-07 3.26E-04 7.49E-05

PA231+D 5.32E+00 2.OOE-01 2.07E-01 0. 1.12E+00 9.91E-02 4.71E-05

PA233 1.68E-06 3.24E-07 2.89E-07 0. 1.22E-06 5.39E-05 1.OOE-05

U232+1D 7.31E-02 0. 5.23E-03 0. 7.94E-03 3.84E-01 4.46E-05

U233A-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

U235A-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. 3.41 E-03 8.62E-02 3.79E-05

U237 5.25E-08 0. 1.40E-08 0. 2.16E-07 1.76E-05 1.29E-05

U238+ D 1.36E-02 0. 8.10E-04 0. 3.12E-03 7.89E-02 3.62E-05

NP237+D 1.77E+00 1.54E-01 7.21 E-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

PU23l3 2.86E+00 4.06E-01 7.22E-02 0. 3.10E-01 3.12E-01 4.79E-05

PU239 3.31 E+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

PU24' +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. 3.31 E-01 2.82E-01 4.29E-05

PU24" 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

AM24.3 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

CM24:3 8.45E-01 3.50E-01 5.OOE-02 0. 2.34E-01 1.09E-01 5.13E-05

CM244 6.46E-01 3.03E-01 3.88E-02 0. 1.81E-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

CM24(3 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 7.41 E-02 0. 3.46E-01 1.01 E-01 5.97E-05

CM248 1.06E+01 3.33E+00 6.11 E-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

57
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

ADUJLT 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 1.81 E-06 0. 0. 2.23E-05 1.67E-06

N165 1.92E-10 2.62E-11 1.14E-11 0. 0. 7.OOE-07 1.54E-06

CU64 0. 1.83E-10 7.69E-11 0. 5.78E-10 8.48E-07 6.12E-06

ZN65 4.05E-06 1.29E-05 5.82E-06 0. 8.62E-06 1.08E-04 6.68E-06

ZN691A+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. 3.01E-08 0. 0. 0. 2.90E-08

BR84 0. 0. 3.91 E-08 0. 0. 0. 2.05E-1 3

BR85 0. 0. 1.60E-09 0. 0. 0. 0.

KR83fA 0. 0. 0. 0. 0. 5.19E-10 0.

KR85PM 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 3.21E-06 0. 0. 0. 2.88E-07

RB88 0. 4.84E-08 2.41E-08 0. 0. 0. 4.18E-19

RB894 D 0. 3.20E-08 2.12E-08 0. 0. 0. 1.16E-21

SR89i D 3.80E-05 0. 1.09E-06 0. 0. 1.75E-04 4.37E-05

SR904 D 1.24E-02 0. 7.62E-04 0. 0. 1.20E-03 9.02E-05

SR914D 7.74E-09 0. 3.13E-10 0. 0. 4.56E-06 2.39E-05

SR92x 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.

58
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE

Y90

Y91M+ID

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099--D

TC99M

TC99

TC1 01

RU103+D

RU105+D

RU106+D

RH105

PD107

PD109

AG11CM+D

AG111

CD113M

CD1 15M

SN123

SN 125+D

SN1 26+D

SB124

SB1251-D

SB126

SB127

TE1 25M

TE1 27M+D

TE127

TE129:M+D

TE129

TE131 M+D

TE131+D

TE132+D

TE1 33M+D

TE1 34+D

1129

1130

1131 +C

BONE

2.61 E-07

3.26E-1 I

5.78E-05

1 .29E-09

1.18E-08

5.22E-05

1 .34E-05

1.21 E-08

3.10E-05

1 .76E-06

2.78E-1 1

0.

0.

1 .29E-13

3.13E-08

5.22E-1 5

1.91 E-07

9.88E-1 I

8.64E-06

9.24E-1 0

0.

0.

1 .35E-06

4.25E-08

0.

0.

3.02E-05

1.16E-06

1 .58E-04

3.90E-06

6.67E-06

4.50E-07

3.30E-08

4.27E-07

1 .58E-06

1 .75E-1 0

1 .22E-06

6.22E-1 2

8.74E-09

1 .39E-12

3.25E-08

7.24E-12

3.84E-1 2

2.48E-06

5.72E-07

3.1 5E-06

LIVER

0.

0.

0.

0.

0.

2.92E-06

4.30E-06

2.45E-09

1.01E-05

9.77E-07

7.03E-1 2

1.17E-06

1.51 E-08

3.64E-1 3

4.64E-08

7.52E-1 5

0.

0.

0.

6.73E-1 0

8.27E-08

4.63E-1 0

1 .25E-06

1 .78E-08

1 .54E-04

2.46E-05

6.67E-07

3.12E-08

4.1 8E-06

7.36E-08

7.44E-08

9.1 3E-09

7.22E-1 0

1 .98E-07

7.21 E-07

8.03E-1 1

5.84E-07

2.99E-1 2

5.45E-09

7.44E-13

2.69E-08

5.40E-1 2

3.22E-12

2.11E-06

1 .68E-06

4.47E-06

TOTAL BODY

7.01 E-09

1 .27E-1 2

1 .55E-06

3.77E-1 1

3.26E-1 0

1 .37E-06

2.91 E-06

1.13E-09

2.49E-06

5.26E-07

2.56E-1 2

3.17E-08

2.87E-09

4.63E-1 2

1 .25E-08

7.38E-1 4

8.23E-08

3.89E-1 1

1 .09E-06

4.43E-1 0

5.87E-09

1.16E-10

7.43E-07

8.87E-09

4.97E-06

7.95E-07

9.82E-07

7.03E-08

6.OOE-06

1 .55E-06

1 .58E-06

1 .62E-07

1 .27E-08

5.84E-08

1.96E-07

3.87E-1 1

1 .98E-07

1 .55E-12

3.63E-09

4.49E-1 3

2.02E-08

4.17E-12

1 .57E-1 2

6.91 E-06

6.60E-07

2.56E-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.

5.67E-07

2.59E-08

1.23E-06

9.44E-09

6.75E-09

2.75E-09

3.97E-10

1.31E-07

4.11E-07

1.32E-10

4.30E-07

4.87E-12

6.88E-09

1.17E-12

2.37E-08

6.27E-12

3.44E-12

5.54E-03

1.42E-04

1.49E-03

KIDNEY

0.

0.

0.

0.

0.

1.11 E-05

6.77E-06

3.71 E-09

1.16E-05

9.67E-07

8.18E-12

3.55E-07

3.64E-08

5.52E-12

5.85E-07

1.35E-13

7.29E-07

1.27E-10

1.67E-05

2.86E-09

6.57E-07

2.35E-09

2.46E-06

5.74E-08

1.71 E-04

1.98E-05

0.

0.

0.

0.

0.

0.

0.

1.55E-06

5.72E-06

6.37E-1 0

4.57E-06

2.34E-1 1

3.86E-08

5.46E-12

1.82E-07

3.74E-1 1

2.18E-11

4.53E-06

2.61 E-06

7.66E-06

LUNG

2.12E-05

2.40E-07

2.13E-04

1.96E-06

6.06E-06

2.13E-05

2.21 E-04

9.84E-06

3.11E-05

6.31 E-05

3.OOE-07

5.11E-05

1.14E-05

9.55E-08

1.01 E-04

4.99E-08

6.31 E-05

1.37E-06

1.17E-03

2.41 E-06

9.47E-06

1.85E-06

5.79E-04

2.33E-05

2.08E-04

1.76E-04

2.88E-04

7.37E-05

1.17E-03

3.10E-04

2.18E-04

9.57E-05

2.05E-05

3.92E-05

1.20E-04

8.14E-07

1.45E-04

2.42E-07

1.82E-05

1.74E-07

3.60E-05

5.51 E-07

4.343-07

0.

0.

0.

GI-LLI

6.32E-05

1.66E-10

4.81 E-05

9.19E-06

5.27E-05

1.51 E-06

1.88E-05

6.54E-05

2.38E-06

1.30E-05

3.02E-08

3.79E-06

3.10E-05

5.20E-07

7.54E-06

1.36E-21

1.38E-05

6.02E-06

1.14E-04

1.09E-05

7.06E-07

1.52E-05

3.78E-05

2.79E-05

1.59E-05

4.80E-05

3.92E-05

6.81 E-05

1.59E-05

5.08E-05

1.26E-05

6.01 E-05

3.77E-05

8.83E-06

1.87E-05

7.17E-06

4.79E-05

1.96E-08

6.95E-05

2.30E-09

6.37E-05

5.49E-08

2.97E-11

2.22E-07

9.61 E-07

7.85E-07

59
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTCPE

1132

1133+E)

1134

1135+D

XE131M

XE133M

XE133

XE135M

XE135

XE137

XE138+D

CS134M+D

CS134

CS135

CS13E

CS137+D

CS13E

CS139+D

BA1 39

BA140+D

BA141+D

BA142+D

LA140

LA141

LA142

CE141

CE142+D

CE144+D

PR142

PR144

ND147 +D

PM147

PM14(.M+D

PM14E8

PM149

PM151

SM151

SM153

EU 152

EU154

EU155

EU156E

TB160

HO166M

Wi 81

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-1 1

3.29E-12

4.30E-08

5.34E-10

8.54E-11

2.49E-06

2.33E-08

4.29E-04

1.17E-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

1.01 E-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

9.41 E-15

3.38E-1 5

2.17E-08

1.66E-10

3.88E-1 1

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

9.1 OE-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

9.10E-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

1.91 E-13

4.56E-08

3.19E-06

1.94E-06

3.20E-08

1.99E-09

7.21 E-1 0

3.55E-06

1.04E-09

4.76E-05

6.48E-05

9.21 E-06

2.40E-07

2.75E-06

8.OOE-05

2.17E-10

6.81 E-09

3.1 OE-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.OOE-08

3.05E-08

7.78E-14

2.09E-09

8.75E-1 5

2.86E-1 5

0.

0.

0.

7.83E-07

7.60E-09

1.06E-04

2.70E-07

8.81 E-1 3

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

3.91E-05

7.21 E-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

1.71 E-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

2.11 E-07

1.46E-06

1.05E-06

2.33E-1 3

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

60
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OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 1.7 (continued)

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

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21)+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.

RA22.3+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

RA22:5+D 3.00E-04 3.56E-07 5.99E-05 0. 1.01E-05 2.92E-02 2.71 E-04

RA226'+D 1.25E-01 2.39E-06 9.14E-02 0. 6.77E-05 1.17E-01 2.94E-04

RA22,3+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 2.41 E-01 5.08E-05

TH22.'+D 2.17E-04 3.92E-06 6.25E-06 0. 2.22E-05 3.77E-02 3.34E-04

TH226+D 2.00E-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

TH23() 2.29E+00 1.31E-01 6.36E-02 0. 6.40E-01 6.21 E-01 3.73E-05

TH23:'+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

PA23-1+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

U2354D 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 5.00E-02 3.57E-05

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

U2384 D 9.58E-03 0. 5.67E-04 0. 2.18E-03 4.58E-02 3.41 E-05

NP23,'+D 1.69E+00 1.47E-01 6.87E-02 0. 5.10E-01 5.22E-02 4.92E-05

NP238 2.96E-07 8.00E-09 4.61E-09 0. 2.72E-08 1.02E-05 2.13E-05

NP239 2.87E-08 2.82E-09 1.55E-09 0. 8.75E-09 4.70E-06 1.49E-05

PU238 2.74E+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

PU24'. 3.45E+00 4.76E-01 8.54E-02 0. 3.64E-01 1.89E-01 6.03E-05

AM24-1 1.01E+00 3.59E-01 6.71E-02 0. 5.04E-01 6.06E-02 4.60E-05

AM24'2M 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

CM24: 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

CM24,'+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

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TABLE 1.8

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND (DFGi)

(MREM/HR PER PCIIM)

ELEMENT TOTAL BODY SKIN

H-3 0.0 0.0

C-14 0.0 0.0

Na-24 2.50E-08 2.90E-08

P-32 0.0 0.0

Cr-51 2.20E-10 2.60E-10

Mn-54 5.80E-09 6.80E-09

Mn-56 1.10E-08 1.30E-08

Fe-55 0.0 0.0

Fe-59 8.OOE-09 9.40E-09

Co-58 7.OOE-09 8.20E-09

Co-60 1.70E-08 2.OOE-08

Ni-63 0.0 0.0

Ni-65 3.70E-09 4.30E-09

Cu-64 1.50E-09 1.70E-09

Zn-65 4.OOE-09 4.60E-09

Zn-69 0.0 0.0

Br-83 6.40E-1 1 9.30E-1 1

Br-84 1.20E-08 1.40E-08

Br-85 0.0 0.0

Rb-86 6.30E-10 7.20E-10

Rb-88 3.50E-09 4.OOE-09

Rb-89 1.50E-08 1.80E-08

Sr-89 5.60E-13 6.50E-13

Sr-91 7.1OE-09 8.30E-09

Sr-92 9.OOE-09 1.OOE-08

Y-90 2.20E-12 2.60E-12

Y-91 m 3.80E-09 4.40E-09

Y-91 2.40E-1 1 2.70E-1 1

Y-92 1.60E-09 1.90E-09

Y-93 5.70E-10 7.80E-10

Zr-95 5.OOE-09 5.80E-09

Zr-97 5.50E-09 6.40E-09

Nb-95 5.1 OE-09 6.OOE-09

Mo-99 1.90E-09 2.20E-09

Tc-99m 9.60E-10 1.10E-09

Tc-101 2.70E-09 3.OOE-09

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TABLE 1.8 (continued)

EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATION GROUND ('DFG1)

(MREM/HR PER PCI/MI)

FL FMFNT TOTAL RBODY SKIN

Ru-1 03

Ru-1 05

Ru-106

Ag-1 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-136

Cs-1 37

Cs-1 38

Ba-139

Ba-140

Ba-141

Ba-142

La-140

La-142

Ce-141

Ce-143

Ce-144

Pr-143

Pr-1 44

Nd-147

W-187

Np-239

3.60E-09

4.50E-09

1.50E-09

1.80E-08

3.50E-11

1.10E-12

1.OOE-11

7.70E-10

7.1OE-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-1 0

2.20E-09

3.20E-1 0

0.0

2.OOE-1 0

1.OOE-09

3.1 OE-09

9.50E-1 0

4.20E-09

5.1 OE-09

1.80E-09

2.1 OE-08

4.80E-11

1.30E-12

1.1 OE-11

9.OOE-1 0

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.OOE-09

1.70E-08

1.80E-08

6.20E-1 0

2.50E-09

3.70E-I 0

0.0

2.30E-1 0

1.20E-09

3.60E-09

1.1OE-09

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TABLE 1.9

PALISADES GASEOUS DESIGN

OBJECTIVE ANNUAL QUANTITIES

Nuclide

Ac-110m

Ar*41

Ba-139

Ba-140

BrP82

C-14

CE-141

Ce!-144

Cc-57

Cc-58

Cc-60

Cr 51

Cs-134

Cs-136

Cs-137

Cs-1 38

Fe-55

Fe-59

H-:3

1-129

1-1.31

1-1:32

1-1:33

1-1:34

1-1:35

Oraan

GI-Tract-T

Total Body

GI Tract-C

Lung-T

total Body-C

Bone-C

Gl Tract-T

Gl Tract-T

Gl Tract-T

Gl Tract-T

Gl Tract-T

GI Tract-A

Liver-C

Liver-I

Bone-C

Total body-C

Bone-C

Gl Tract-T

Total Body-C

Thyroid-A

Thyroid-I

Thyroid-C

Thyroid-C

Thyroid-C

Thyroid-C

Dose Factor

Mrem/Ci

2.13E+00

3.64E - 04

2.97E - 03

1.26E - 01

4.97E - 03

1.48E - 01

1.34E - 01

3.37E+00

8.53E - 02

2.59E - 01

6.86E+00

3.75E - 03

8.77E+00

5.99E - 01

9.58E+00

1.OOE - 01

2.06E - 01

3.20E - 01

2.19E - 04

3.66E+02

2.21 E+01

1.12E - 02

2.46E - 01

2.45E - 03

4.93E - 02

Design

Objective

Annual Quantity

Ci

7.04E+00

1.37E+04

5.05E+03

1.19E+02

1.01 E+03

1.01 E+02

1.12E+02

4.45E+00

1.76E+02

5.79E+01

2.19E+00

1.33E+03

1.71 E+00

2.50E+01

1.57E+00

5.OOE+01

7.28E+01

4.69E+01

2.28E+04

4.1OE - 02

6.79E - 01

1.34E+03

6.11E+01

6.12E+03

3.04E+02

I

64
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TABLE 1.9

PALISADES GASEOUS DESIGN

OBJECTIVE ANNUAL QUANTITIES

Nuclide

Kr-83m

Kr-85

Kr-85m

Kr-87

Kr-88

Kr-89

La-140

Mn-54

Mn-56

Mo-99

N-13

Na-24

Nb-95

Ni -63

Ni.*65

Np-239

Rb-88

Ru-1 03

Ru-1 05

St,-124

St-125

Sr**89

Sr-*90

Sr**91

Sr-*92

Organ

Skin

Skin

Total Body

Skin

Total Body

Total Body

GI Tract-T

GI Tract-T

GI Tract-C

GI Tract-T

Total Body-C

Total Body-C

GI Tract-A

Bone-C

GI Tract-C

GI Tract-T

Total Body-C

GI Tract-A

GI Tract-C

GI Tract-T

GI Tract-T

Bone-C

Bone-C

Bone-I

GI Tract-C

Dose Factor

Mrem/Ci

8.82E - 07

9.14E - 05

5.22E - 05

8.03E - 04

6.35E - 04

5.08E - 04

3.04E - 02

6.29E - 01

6.91 E - 03

1.66E - 02

3.44E - 06

4.02E - 03

2.47E - 01

1.21 E+01

4.70E - 03

8.13E - 03

2.38E - 05

3.80E - 01

5.82E - 03

9.47E - 01

4.35E - 01

8.98E+00

3.73E+02

2.46E+00

1.37E - 02

Design

Objective

Annual Quantity

Ci

1.70E+07

1.64E+05

9.58E+04

1.87E+04

7.87E+03

9.84E+03

4.93E+02

2.38E+01

2.17E+03

9.04E+02

1.45E+06

1.24E+03

6.07E+01

1.24E+00

3.19E+03

1.84E+03

2.1 OE+05

3.95E+01

2.58E+03

1.58E+01

3.45E+01

1.67E+00

4.02E - 02

6.1 OE+00

1.09E+03

I

65
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TABLE 1.9

PALISADES GASEOUS DESIGN

OBJECTIVE ANNUAL QUANTITIES

Nuclide

Tc-99

Tc- 99m

Tc-*101

Te-127

Xe-131m

Xe-133

Xe-133m

Xe-135

Xe-135m

Xe-137

Xe-138

Zn*-65

Zr-95

Pu -238

Pu -239

Pu -241

Arm-241

Cm-242

Cm-244

Organ

GI Tract-T

GI Tract-T

GI Tract-T

GI Tract-T

Skin

Total Body

Skin

Total Body

Total Body

Skin

Total body

Liver-C

GI Tract-T

Bone-T

Bone-T

Bone-T

Bone-T

Lung-T

Bone-T

Dose Factor

Mrem/Ci

5.85E - 01

3.64E - 04

8.33E - 05

4.87E - 03

4.03E - 05

1.39E - 05

8.39E - 05

8.32E - 05

9.55E - 05

5.85E - 04

2.70E - 04

9.38E - 01

3.90E - 01

1.42E+03

1.64E+03

3.45E+01

5.25E+02

3.35E+01

3.20E+02

Design

Objective

Annual Quantity

Ci

2.62E+01

4.12E+04

1.80E+05

3.08E+03

3.72E+05

3.60E+05

1.79E+05

6.01 E+04

5.24E+04

2.56E+04

1.85E+04

1.60E+01

3.85E+01

1.06E - 02

9.15E - 03

4.35E - 01

2.86E - 02

4.48E - 01

4.69E - 02

66
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PALISADES NUCLEAR PLANT

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Revision 20

LIQUID EFFLUENTS

A. CONCENTRATION

1. Requirements

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

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

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

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

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

be limited to 2E-04 [4Ci/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 = EC 1 (2.1)

i=1

where:

C = Total concentration in the liquid effluent at the release

point, piCilml.

C1 = Concentration of a single radionuclide i, pCi/ml.

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

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

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

RJ = . E 10.0 (2.2) i EC1

where:

C1 = Effluent concentration of radionuclide i, gCi/ml.

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

Column 2 - itCi/ml.

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

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

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

assure this criterion is met:

fi(Ri-1)+ f2(R2-1)+ f3(R3-1)•F (2.3)

where:

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

releases, determined by Plant personnel.

RR2,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 = (bi)(F) where bi is a conservative factor

greater than 1.0.

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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 (cprn). 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.

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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 (CQ), 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.

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2. Release Analysis

Calculations shall be performed for each batch release, and weekly for

continuous releases according to the formula:

Ai/Ci<0.5 (2.5)

where:

A = Cumulative quarterly activity of nuclide i identified in liquid

release (CQ).

Ci = Design objective annual quantity of radionuclide i from

Table 2.2.

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 (CQ), 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:

Dj Y (DCFjxli (2.6)

i=1

where:

Dj = Dose for the jth organ from radionuclides releases,

mrem.

j = The organ of interest.

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(DCF)ij = 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.

Ii is described by:

(Ai)(V)(365) (1EO6 (2.7) (1000)(d) 06)

where:

365 = Days per year.

Ai = Annual activity released of ith radionuclide, [tCi.

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

1400 mI/d - teen and child, 900 ml/d - 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 jpCi to pCi.

The dose equation then becomes:

(3.65 E05)(V)C (DCF)jjxAjmrem (2.8)

i=1

72
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

------- - - --- - - - - -

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

(Is) is described by:

I= AiBjF(1E09) -pCi (2.9)

I 5d

where

Al

Bi

F

15

d

1 E09

Substil

Annual released of ith radionuclide, [tCi.

Fish concentration factor of ith radionuclide

pCilg n

pCi/ml

(see Table 2.0).

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

6.9 kg child, none infant).

= Dispersion factor from discharge to fish exposure point.

= Dilution water flow for year, ml.

= Conversion of piCi and Kgm to gross.

tution of Equation 2.9 into Equation 2.6 gives:

DJ =(6.7E07)F E AixBixDCFiMreM

d i=1

(2.10)

73
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

C. Annual Analysis

A complete analysis utilizing the NRC computer code LADTAF' with the

total source release will be done annually in conjunction with the

annual environmental report. This analysis will provide estimates of

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

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

approach is utilized on LADTAP. The dose to the jth organ from m

radionuclides, Dj, is described by:

m

Dj= E Djmrem (2.11)

i=1

m

= X (DCF ,jxIjmrem

1=1

where:

Dj = Dose to the jth organ from the ith radionuclide, mrom.

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).

I = Activity ingested of the ith radionuclide, pCi.

Is for water ingestion is described by:

I= Ai Vr pCi (2.13)

vd

and for fish ingestion 11 is described by:

L= AiBdFr ci

74
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

where:

Ai = Activity release of jth radionuclide during the year, [tCi.

V = Average rate of water consumption (2000 ml/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).

B1 = Fish concentration factor of the ith radionuclide,

pCi/gm

Table 2.0, pCi/mi

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, lll.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.

75
1--

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

E. RELEASE RATE FOR OFFSITE EC (50 MREMNYR)

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.

76
I

44

U 0 4--AK79 l.

Z > tIO4JIDDISCH4AfGE

0 -SWIi

0l S

A p w~tofsiuclul AREA N * AtG\ sil 0m~tAl SITE ENVIRONMENT

I £20 LO STATIONS

PAIAE UCLEARl PLANT

IL. Sill HOUNDANjY

tilGIlt 2.I

L~
PALISADES RADWASTE EFFLUENTS - LIQUID I:1 IAN

',YS11 M _.STtAM 

GN

BLOWDOOWN PRIMARY 

SYSTEM TANK

STORAGE ?f

RE 070

< ~~WASt fE9 C 2 TANKS0ll 

TRIP& FLOWCONTROL

< O . _-4 

P SflIArlt) WA33SS-\\§K

Ci C1 .-

RIC 

tAXY Qt u8"E*

.0 Ci 

D WAIIER

il( i~IT 

WAlA|SUIBN~RS2t\

Lj LMIEaIAjroI)SWAS~f 

SYSTEM

W W t tIIICY U7DLITY

STORAGE 

0

< 0 

TANK

o)ur191IT Iu IIWA'.TE IILIEREI)DRAINS TURBINE BLDG

URI U.TANK 

swiP-14
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.0

BIOACCUMULATION FACTORS

uCi/cm ner uCi/ml

ELEMENT

FRESHWATER

FISH

H

C

NA

P

CR

MN

FE

CO

NI

CU

ZN

BR

RB

SR

y

ZR

NB

MO

TC

RU

RH

TE

I

CS

BA

LA

CE

PR

ND

W

NP

9.OE-01

4.6E 03

1.OE 02

I.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

3.0E 04

1.OE 01

1.5E 01

1.OE 01

1.OE 01

4.OE 02

1.5E 01

2.OE 03

4.0E 00

2.5E 01

1.OE 00

2.5E 01

2.5E 01

1.2E 03

1.OE 01

79
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIFRST 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 3.0133-07

BE10 1.71E-05 2.49E-06 5.16E-07 0. 1.64E-06 0. 2.713E-05

C14 2.37E-05 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 5.0fiE-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. 1.2:2E-06

NA22 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.83E-05 9.8:3E-05

NA24 1.01E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01 E-05 1.01E-05 1.01 E-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. 1.91 E-07

SC46 3.75E-08 5.41 E-08 1.69E-08 0. 3.56E-08 0. 3.5:3E-05

CR51 0. 0. 1.41 E-08 9.20E-09 2.01 E-09 1.79E-08 4.1 lE-07

MN54 0. 1.99E-05 4.51 E-06 0. 4.41 E-06 0. 7.31 E-06

MN56 0. 8.18E-07 1.41 E-07 0. 7.03E-07 0. 7.4:3E-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. 3.9:2E-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. 2.57'E-05

N159 4.78E-05 1.45E-05 8.17E-06 0. 0. 0. 7.11iE-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 6.31 E-05 2.91 E-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. 2.1OE-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.

KR83NI 0. 0. 0. 0. 0. 0. 0.

KR85M1 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. 4.71 E-03 0. 0. 0. 2.31 E-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

80
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91MfD

Y91

Y92

Y93

ZR93--D

ZR95i-D

ZR97T-D

NB93M

NB95

NB97

M093

M099+D

TC99tA

TC99

TC10 0

RU103+D

RU 10!;+D

RU106+D

RH105

PD107

PD10"

AG11 (M+D AG11 l

CD113M

CD116M

SN123

SN12'+D

SN126+D

SB124-

SB12r +D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+C)

BONE

8.69E-08

8.1OE-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-1 0

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

1.1 9E-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.OOE-08

3.53E-1 I

1.82E-06

6.63E-06

5.10E-08

4.55E-07

2.83E-08

4.95E-07

4.58E-08

3.01E-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

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.

GI-LLI

1.20E-04

2.70E-06

8.1 GE-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

1.21 E-06

1.12E-05

1.15E-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

6.5BE-05

1.11 E-04

2.52E-05

6.6DE-05

1.64E-05

8.35E-05

5.91 E-05

1.11E-05

2.35E-05

2.1 OE-05

5.97E-05

2.27E-05

1.03E-04

7.11E-06

3.81 E-05

1.93E-05

3.05E-06

4.24E-07

2.83E-06

1.51 E-06

81
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

1132

11 33+ED

1134

1135+ED

XE131M

XE133M

XE133

XE135M

XE135

XE137

XE138*D

CS134M+D

CS134

CS135

CS136

CS137+D

CS138

CS139+D

BA139

BA140 FD

BA141 fD

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

1.66E-06

1.25E-05

8.69E-07

3.64E-06

0.

0.

0.

0.

0.

0.

0.

1.76E-07

3.77E-04

1.33E-04

4.59E-05

5.22E-04

4.81 E-07

3.10E-07

8.81 E-07

1.71 E-04

4.25E-07

1.84E-07

2.11E-08

2.89E-09

1.10E-09

7.87E-08

1.48E-08

2.98E-06

8.18E-08

2.74E-10

5.53E-08

3.88E-07

1.65E-07

6.32E-08

1.38E-08

6.18E-09

2.90E-07

7.72E-09

6.74E-07

2.64E-06

5.42E-07

1.14E-07

2.59E-07

1.25E-06

8.85E-08

3.62E-06

9.03E-07

LIVER

3.37E-06

1.82E-05

1.78E-06

7.24E-06

0.

0.

0.

0.

0.

0.

0.

2.93E-07

7.03E-04

1.21 E-04

1.35E-04

6.11E-04

7.82E-07

4.24E-07

5.84E-10

1.71 E-07

2.91 E-10

1.53E-10

8.32E-09

8.38E-10

4.04E-10

4.80E-08

9.82E-06

1.22E-06

3.04E-08

1.06E-10

5.68E-08

3.27E-08

4.18E-08

9.13E-09

1.81 E-09

9.01 E-1 0

6.67E-08

5.97E-09

1.79E-07

3.67E-07

6.25E-08

7.06E-08

0.

2.69E-07

2.72E-08

1.13E-06

6.28E-07

TOTAL BODY

1.20E-06

5.33E-06

6.33E-07

2.64E-06

0.

0.

0.

0.

0.

0.

0.

1.48E-07

7.1 OE-05

6.30E-06

5.04E-05

4.33E-05

3.79E-07

1.62E-07

2.55E-08

8.81 E-06

1.34E-08

9.06E-09

2.14E-09

1.46E-10

9.67E-1 1

5.65E-09

1.12E-09

1.67E-07

4.03E-09

1.38E-11

3.48E-09

1.59E-08

3.28E-08

4.60E-09

7.90E-1 0

4.56E-1 0

1.44E-08

4.58E-1 0

1.51 E-07

2.20E-07

3.23E-08

1.12E-08

3.24E-08

2.13E-07

3.04E-09

1.29E-07

2.17E-07

THYROID

1.58E-04

3.31 E-03

4.15E-05

6.49E-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

3.76E-06

2.14E-05

1.99E-06

8.07E-06

0.

0.

0.

0.

0.

0.

0.

1.13E-07

1.81 E-04

3.44E-05

5.38E-05

1.64E-04

3.90E-07

2.19E-07

3.51 E-1 0

4.06E-08

1.75E-10

8.81 E-11

0.

0.

0.

1.48E-08

2.86E-09

4.93E-07

1.13E-08

3.84E-1 1

2.19E-08

4.88E-08

4.80E-08

1.09E-08

2.20E-09

1.07E-09

4.53E-08

1.25E-09

5.02E-07

9.95E-07

1.40E-07

3.26E-08

7.37E-08

3.57E-07

0.

0.

0.

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

2.60E-08

7.42E-05

1.31 E-05

1.10E-05

6.64E-05

6.09E-08

3.30E-08

3.54E-10

1.05E-07

1.77E-1 0

9.26E-1 1

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.

GI-LLI

2.73E.06

3.08E-06

1.84E-06

2.62E-06

0.

0.

0.

0.

0.

0.

0.

2.32E-07

1.91 E-06

4.37E-07

2.0!5E-06

1.91 E-06

1 .25E-06

2.66E-08

5.58E-05

4.20E-05

5.1 9E-06

7.59E-07

9.7,'E-05

9.6-1 E-05

6.86E-05

2.48E-05

5.73E-05

1.7'1E-04

4.29E-05

4.93E-06

3.60E-05

9.27E-06

5.4':3-05

9.74E-05

4.86E-05

4.1;'E-05

5.58E-06

3.1,2E-05

1.59E-05

4.58E-05

8.37E-05

6.67E-05

3.45E-05

0.

3.82E-07

1.62E-05

3.69E-05

82
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

INFANT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIFRST 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

B1210iD 4.16E-06 2.68E-05 3.58E-07 0. 2.08E-04 0. 5.27E-05

PO210 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 2.91E-03 0. 6.OOE-04 0. 3.81,E-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. 5.8(3E-05

AC225 3.92E-05 5.03E-05 2.63E-06 0. 3.69E-06 0. 4.3(iE-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. 5.70E-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. 5.31E-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. 1.413E-05

U232+D 2.42E-02 0. 2.16E-03 0. 2.37E-03 0. 7.04E-05

U233+D 5.08E-03 0. 3.87E-04 0. 1.08E-03 0. 6.5 1E-05

U234 4.88E-03 0. 3.80E-04 0. 1.06E-03 0. 6.3'7E-05

U235+D 4.67E-03 0. 3.56E-04 0. 9.93E-04 0. 8.10E-05

U236 4.67E-03 0. 3.64E-04 0. 1.01 E-03 0. 5.9;3E-05

U237 4.95E-07 0. 1.32E-07 0. 1.23E-06 0. 2.1 lE-05

U238+D 4.47E-03 0. 3.33E-04 0. 9.28E-04 0. 5.7 lE-05

NP237+D 2.53E-03 1.93E-04 1.05E-04 0. 6.34E-04 0. 8.2:3E-05

NP23E 1.24E-07 3.12E-09 1.92E-09 0. 6.81E-09 0. 4.1'7E-05

NP239 1.11E-08 9.93E-10 5.61E-10 0. 1.98E-09 0. 2.87E-05

PU23E 1.34E-03 1.69E-04 3.40E-05 0. 1.21E-04 0. 7.5'7E-05

PU238 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

AM243I 1.51 E-03 6.88E-04 1.06E-04 0. 6.36E-04 0. 9.0;3E-05

CM242 1.37E-04 1.24E-04 9.1OE-06 0. 2.62E-05 0. 8.2;3E-05

CM243 1.45E-03 6.88E-04 8.98E-05 0. 3.27E-04 0. 8.1'0E-05

CM244 1.22E-03 6.16E-04 7.59E-05 0. 2.71E-04 0. 7.84E-05

CM245i 1.88E-03 7.49E-04 1.13E-04 0. 4.32E-04 0. 7.3'JE-05

CM246 1.87E-03 7.49E-04 1.13E-04 0. 4.31E-04 0. 7.1'7E-05

CM247'+D 1.82E-03 7.36E-04 1.11E-04 0. 4.24E-04 0. 9.43E-05

CM2413 1.51E-02 6.07E-03 9.16E-04 0. 3.50E-03 0. 1.5.2E-03

CF252 1.24E-03 0. 2.95E-05 0 0. 0. 2.93E-04

83
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/5OY PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG Gl!-LLI

H3 0. 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07 2.03E-07

BE10 1.35E-05 1.57E-06 3.39E-07 0. 1.11E-06 0. 2.75E-05

C14 1.21E-05 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06 2.42E-06

N13 3.10E-08 3.10E-08 3.1OE-08 3.1OE-08 3.10E-08 3.10E-08 3.1, OE-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.E4E-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 5.51 E-06 0. 0. 0. 1.05E-05

C060 0. 5.29E-06 1.56E-05 0. 0. 0. 2.S,3E-05

N159 4.02E-05 1.07E-05 6.82E-06 0. 0. 0. 7.10E-07

Nl63 5.38E-04 2.88E-05 1.83E-05 0. 0. 0. 1.94E-06

Nl65 2.22E-06 2.09E-07 1.22E-07 0. 0. 0. 2.E6E-05

CU64 0. 2.45E-07 1.48E-07 0. 5.92E-07 0. 1.15E-05

ZN65 1.37E-05 3.65E-05 2.27E-05 0. 2.30E-05 0. 6.41 E-06

ZN69M+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-FD 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.

KR83fA 0. 0. 0. 0. 0. 0. 0.

KR851A 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. 3.95E-05 1.83E-05 0. 0. 0. 5.92E-07

RB88 0. 1.90E-07 1.32E-07 0. 0. 0. 9.32E-09

RB89+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. 5.11 E-05

SR90+D 1.70E-02 0. 4.31 E-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. 1.71 E-04

84
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91 M+D

Y91

Y92

Y93

ZR931+D

ZR95 D

ZR97 0

NB93M

NB95

NB97

M093

M099 FD

TC99M

TC99

TC101

RU 1 03+D

RU105+D

RU 106+D

RHI105

PD107

PD10S

AG1 1C0M+D

AG111

CD1$1 3M

CD11 M

SN123

SN125+D

SN126+D

SB124

SB125+D

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE131 M+D

TE131 +D

TE132tD

TE133VM+D

TE134tD

1129

1130

1131 +D

BONE

4.11E-08

3.82E-1 0

6.02E-07

3.60E-09

1.14E-08

1 .67E-07

1.16E-07

6.99E-09

1 .05E-07

2.25E-08

2.17E-10

0.

0.

9.23E-1 0

5.35E-07

1 .07E-09

7.31 E-07

6.45E-08

1.17E-05

5.14E-07

0.

0.

5.39E-07

2.48E-07

0.

0.

1 .33E-04

3.55E-05

3.33E-04

1.11 E-05

7.16E-06

4.40E-06

1 .06E-06

1.14E-05

2.89E-05

4.71 E-07

4.87E-05

1 .34E-07

7.20E-06

8.30E-08

1.01 E-05

1 .87E-07

1 .29E-07

1 .39E-05

2.92E-06

1 .72E-05

LIVER

0.

0.

0.

0.

0.

6.25E-08

2.55E-08

1.01 E-09

2.62E-08

8.76E-09

3.92E-1 1

2.41 E-05

1 .33E-05

1.81 E-09

5.96E-07

1.12E-09

0.

0.

0.

2.76E-07

4.72E-07

5.67E-07

3.64E-07

7.76E-08

1 .02E-05

5.89E-06

1 .65E-06

5.35E-07

4.15E-06

1 .44E-07

5.52E-08

6.73E-08

1 .64E-08

3.09E-06

7.78E-06

1 .27E-07

1.36E-05

3.74E-08

2.49E-06

2.53E-08

4.47E-06

7.56E-08

5.80E-08

8.53E-06

5.90E-06

1 .73E-05

TOTAL BODY

1.10E-09

1.39E-1 1

1.61 E-08

1 .03E-1 0

3.13E-10

4.45E-08

2.27E-08

5.96E-1 0

8.61 E-09

6.26E-09

1.83E-1 1

8.65E-07

3.29E-06

3.OOE-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

1.01 E-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

1.10E-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

7.18E-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-10

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

6.16E-06

3.99E-06

2.10E-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

3.55E-09

1.89E-05

4.21 E-05

1.82E-04

1.71 E-05

9.37E-07

3.35E-05

4.33E-05

4.7.5E-05

2.63E-05

8.01 E-05

6.5:2E-05

1.10E-04

2.50E-05

6.94E-05

1.71 E-05

8.8.7E-05

5.97E-05

1.10E-05

2.34E-05

1.84E-05

5.94E-05

8.34E-06

1.0 IE-04

4.31jE-07

4.50E-05

5.7.7E-06

5.8!3E-07

4.29E-07

2.76E-06

1.54E-06

85
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRSTr YR)

ISOTC)PE

1132

1133+[)

1134

1135+1)

XE131M

XE1 3lM

XE133

XE1 35M

XE13t;

XE137'

XE138+D

CS13LM+D

CS13'-

CS13'

CS13E;

CS137,+D

CS138

CS1 39+D

BA1 39

BA14C0+D

BA141 +D

BA14z+D

LA140

LA141

LA142

CE141

CE143+D

CE144 +D

PR148

PR144

ND14,'+D

PM147

PM148M+D

PM148i

PM14"

PM15'

SM151

SM1 5'i

EU152

EU154

EU155

EU15C

TB160

HO1 66M

W181

W1 85

W187

BONE

8.OOE-07

5.92E-06

4.1 9E-07

1 .75E-06

0.

0.

0.

0.

0.

0.

0.

8.44E-08

2.34E-04

8.30E-05

2.35E-05

3.27E-04

2.28E-07

1 .45E-07

4.14E-07

8.31 E-05

2.00E-07

8.74E-08

1.01 E-08

1 .35E-09

5.24E-10

3.97E-08

6.99E-09

2.08E-06

3.93E-08

1.29E-10

2.79E-08

3.1 8E-07

1 .03E-07

3.02E-08

6.49E-09

2.92E-09

2.56E-07

3.65E-09

6.15E-07

2.30E-06

4.82E-07

5.62E-08

1 .66E-07

1 .08E-06

4.23E-06

1 .73E-06

4.29E-07

LIVER

1 .47E-06

7.32E-06

7.78E-07

3.15E-06

0.

0.

0.

0.

0.

0.

0.

1 .25E-07

3.84E-04

5.78E-05

6.46E-05

3.1 3E-04

3.1 7E-07

1.61 E-07

2.21 E-1 0

7.28E-08

1.12E-10

6.29E-1 I

3.53E-09

3.17E-10

1.67E-1 0

1.98E-08

3.79E-06

6.52E-07

1.18E-08

3.99E-1 1

2.26E-08

2.27E-08

2.05E-08

3.63E-09

6.90E-1 0

3.55E-1 0

3.81 E-08

2.27E-09

1.12E-07

2.07E-07

3.47E-08

3.01 E-08

0.

2.26E-07

1 .04E-08

4.32E-07

2.54E-07

TOTAL BODY

6.76E-07

2.77E-06

3.58E-07

1 .49E-06

0.

0.

0.

0.

0.

0.

0.

8.1 6E-08

8.10E-05

5.93E-06

4.18E-05

4.62E-05

2.01 E-07

7.74E-08

1 .20E-08

4.85E-06

6.51 E-09

4.88E-09

1.19E-09

6.88E-1 1

5.23E-1 1

2.94E-09

5.49E-1 0

1.11E-07

1 .95E-09

6.49E-12

1 .75E-09

1 .22E-08

2.05E-08

2.35E-09

3.74E-1 0

2.31 E-1 0

1 .20E-08

2.19E-10

1 .33E-07

1 .89E-07

2.72E-08

6.23E-09

2.06E-08

1.91 E-07

1.43E-09

6.05E-08

1.14E-07

THYROID

6.82E-05

1.36E-03

1.79E-05

2.79E-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

2.25E-06

1.22E-05

1.19E-06

4.83E-06

0.

0.

0.

0.

0.

0.

0.

6.59E-08

1.1 9E-04

2.04E-05

3.44E-05

1.02E-04

2.23E-07

1.21 E-07

1.93E-10

2.37E-08

9.69E-1 1

5.09E-1 1

0.

0.

0.

8.68E-09

1.59E-09

3.61 E-07

6.39E-09

2.11E-11

1.24E-08

4.01 E-08

3.04E-08

6.17E-09

1.22E-09

6.02E-1 0

3.94E-08

6.91E-10

4.73E-07

9.09E-07

1.30E-07

1.94E-08

4.94E-08

3.22E-07

0.

0.

0.

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

1.09E-08

4.27E-05

6.81 E-06

5.13E-06

3.67E-05

2.40E-08

1.22E-08

1.30E-10

4.34E-08

6.58E-1 0

3.70E-1 I

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.

GI-LLI

1.73E-06

2.95E-06

5.16E-07

2.40E-06

0.

0.

0.

0.

0.

0.

0.

1.58E-07

2.07E-06

4.33E-07

2.27E-06

1.96E-06

1.46E-07

1.45E-1 1

2.39E-05

4.21 E-05

1.14E-07

1.14E-09

9.84E-05

7.05E-05

3.31 E-05

2.47E-05

5.55E-05

1.7DE-04

4.24E-05

8.53E-08

3.53E-05

9.19E-06

5.73E-05

9.703E-05

4.71 E-05

4.03E-05

5.53E-06

3.02E-05

1.84E-05

4.81 E-05

8.69E-05

6.8.3E-05

3.63E-05

0.

3.7!9E-07

1.61 E-05

3.57E-05

86
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

CHILD INGESTION DOSE COMMITMENT FACTORS (MREMI5OY PER PCI INGESTED IN FIRST YR)

ISOTCOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-.LLI

PB21C+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

P021t0 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.

RA22$,+D 2.12E-02 2.45E-05 4.24E-03 0. 6.50E-04 0. 3.33E-04

RA224+D 6.89E-03 1.25E-05 1.38E-03 0. 3.31E-04 0. 3.7BE-04

RA22r +D 2.80E-02 2.50E-05 5.59E-03 0. 6.62E-04 0. 3.21E-04

RA22E;+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. 5.81E-05

AC22'; 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

TH22E+D 2.07E-03 2.65E-05 7.OE-05 0. 1.38E-04 0. 5.79E-04

TH22Ew 1.38E-02 1.81 E-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 1.51 E-08 9.88E-09 0. 8.01 E-08 0. 1.1 BE-04

PA231+D 7.07E-03 2.34E-04 2.81 E-04 0. 1.28E-03 0. 7.37E-05

PA23: 1.81E-08 2.82E-09 3.16E-09 0. 1.04E-08 0. 1.44E-05

U2324D 1.76E-02 0. 1.26E-03 0. 1.34E-03 0. 6.93E-05

U2334D 3.72E-03 0. 2.25E-04 0. 6.10E-04 0. 6.45E-05

U234 3.57E-03 0. 2.21 E-04 0. 5.98E-04 0. 6.32E-05

U2354D 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. 6.81 E-07 0. 2.08E-05

U2384D 3.27E-03 0. 1.94E-04 0. 5.24E-04 0. 5.66E-05

NP23,'+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 3.31 E-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.ODE-04

AM24-1 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 1.41 E-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. 4.1 OE-04 0. 7.11 E-05

CM247+D 1.70E-03 6.53E-04 1.03E-04 0. 4.04E-04 0. 9.35E-05

CM248 1.41E-02 5.38E-03 8.52E-04 0. 3.33E-03 0. 1.51E-03

CF252 1.07E-03 0. 2.54E-05 0. 0. 0. 2.96E-04

87
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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 2.3;0E-06

P32 2.76E-04 1.71 E-05 1.07E-05 0. 0. 0. 2.',2E-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.S'5E-07

SC46 7.24E-09 1.41E-08 4.18E-09 0. 1.35E-08 0. 4.EOE-05

CR51 0. 0. 3.60E-09 2.00E-09 7.89E-10 5.14E-09 6.C5E-07

MN54 0. 5.90E-06 1.17E-06 0. 1.76E-06 0. 1.21E-05

MN56 0. 1.58E-07 2.81 E-08 0. 2.00E-07 0. 1.04E-05

FE55 3.78E-06 2.68E-06 6.25E-07 0. 0. 1.70E-06 1.16E-06

FE59 5.87E-06 1.37E-05 5.29E-06 0. 0. 4.32E-06 3.24E-05

C057 0. 2.38E-07 3.99E-07 0. 0. 0. 4.44E-06

C058 0. 9.72E-07 2.24E-06 0. 0. 0. 1.34E-05

C060 0 2.81 E-06 6.33E-06 0. 0. 0. 3.66E-05

N159 1.32E-05 4.66E-06 2.24E-06 0. 0. 0. 7.31E-07

N163 1.77E-04 1.25E-05 6.OOE-06 0. 0. 0. 1.99E-06

N165 7.49E-07 9.57E-08 4.36E-08 0. 0. 0. 5.193-06

CU64 0. 1.15E-07 5.41E-08 0. 2.91E-07 0. 8.92E-06

ZN65 5.76E-06 2.00E-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.

BR83q 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.

KR83Al 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. 4.41 E-06

RB87 0. 1.75E-05 6.11 E-06 0. 0. 0. 6.11 E-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. 8.4:3E-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. 2.3:3E-04

SR91+D 8.07E-06 0. 3.21 E-07 0. 0. 0. 3.613E-05

SR92+D 3.05E-06 0. 1.30E-07 0. 0. 0. 7.77E-05

88
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

Y90

Y91 M D

Y91

Y92

Y93

ZR93+D

ZR95+D

ZR97+D

NB93M

NB95

NB97

M093

M099+1D

TC99M

TC99

TC1 01

RU1 03+D

RU1 05+D

RU1 06+D

RH105

PD107

PD109

AG11OM+D

AG111

CD113M

CD1 15M

SN123

SN 125+D

SN126+D

SB124

SB1254FD

SB126

SB127

TE125M

TE127M+D

TE127

TE129M+D

TE129

TE1 31 M+D

TE131+D

TE1 32+D

TE1 33M+D

TE134+D

1129

1130

1131+ED

BONE

1 .37E-08

1.29E-1 0

2.01 E-07

1.21 E-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-1 0

2.55E-07

2.1 8E-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-1 1

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

2.1 6E-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

8.1 9E-06

TOTAL BODY

3.69E-1 0

4.93E-1 2

5.39E-09

3.50E-1 1

1 .05E-1 0

1 .49E-08

8.94E-09

2.16E-10

2.83E-09

2.51 E-09

6.68E-12

2.90E-07

1.15E-06

1 .20E-08

7.17E-08

5.03E-09

1 .09E-07

8.46E-09

4.94E-07

8.20E-08

1 .34E-08

5.70E-08

1.18E-07

1 .73E-08

1 .45E-07

8.39E-08

1 .08E-06

5.37E-07

3.30E-06

1.51 E-06

5.80E-07

5.71 E-07

1 .37E-07

5.12E-07

1.15E-06

3.40E-08

2.58E-06

1 .09E-08

9.76E-07

8.72E-09

2.08E-06

3.56E-08

3.OOE-08

6.54E-06

1.19E-06

4.40E-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.

5.84E-07

1.86E-07

5.69E-07

8.78E-09

2.37E-09

8.99E-09

4.08E-09

1.07E-06

2.30E-06

1.09E-07

5.26E-06

3.20E-08

1.76E-06

2.15E-08

2.33E-06

5.11E-08

3.67E-08

4.77E-03

2.43E-04

2.39E-03

KIDNEY

0.

0.

0.

0.

0.

9.65E-08

1.91 E-08

7.11E-10

1.32E-08

4.42E-09

2.14E-11

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

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.

GI-LLI

1.13E-04

6.09E-09

8.24E-05

3.32E-05

1.1 YE-04

2.58E-05

3.OOE-05

1.2; E-04

4.0; E-06

1.9!;E-05

4.3 7E-07

1.29E-06

1.08E-05

6.08E-07

6.41E-06

8.7!iE-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

1.1 2E-04

2.58E-05

7.80E-05

1.93E-05

9.4'1 E-05

6.16E-05

1.13E-05

2.41 E-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

4.5; E-07

2.29E-06

1.6 2E-06

89
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTCPE

1132

1133+CI

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

PM 14;M+D

PM14£i

PM149

PM151

SM151

SM153

EU152

EU154

EU155

EU156

TB160

HO166M

W181

W185

W187

BONE

2.79E-07

2.01 E-06

1.46E-07

6.10E-07

0.

0.

0.

0.

0.

0.

0.

2.94E-08

8.37E-05

2.78E-05

8.59E-06

1.12E-04

7.76E-08

4.87E-08

1.39E-07

2.84E-05

6.71 E-08

2.99E-08

3.48E-09

4.55E-10

1.79E-10

1.33E-08

2.35E-09

6.96E-07

1.31 E-08

4.30E-1 I

9.38E-09

1.05E-07

4.14E-08

1.02E-08

2.17E-09

9.87E-10

8.73E-08

1.22E-09

2.45E-07

7.91 E-07

1.74E-07

1.92E-08

6.47E-08

3.57E-07

1.42E-08

5.79E-07

1.46E-07

LIVER

7.30E-07

3.41 E-06

3.87E-07

1.57E-06

0.

0.

0.

0.

0.

0.

0.

6.09E-08

1.97E-04

2.55E-05

3.38E-05

1.49E-04

1.49E-07

7.17E-08

9.78E-1 1

3.48E-08

5.01 E-11

2.99E-1 1

1.71 E-09

1.40E-10

7.95E-1 1

8.88E-09

1.71 E-06

2.88E-07

5.23E-09

1.76E-11

1.02E-08

9.96E-09

1.05E-08

1.66E-09

3.05E-1 0

1.63E-10

1.68E-08

1.01 E-09

5.90E-08

1.02E-07

1.68E-08

1.44E-08

0.

1.10E-07

4.58E-09

1.91 E-07

1.19E-07

TOTAL BODY

2.62E-07

1.04E-06

1.39E-07

5.82E-07

0.

0.

0.

0.

0.

0.

0.

3.13E-08

9.14E-05

5.96E-06

2.27E-05

5.19E-05

7.45E-08

2.63E-08

4.05E-09

1.83E-06

2.24E-09

1.84E-09

4.55E-10

2.31 E-11

1.98E-1 1

1.02E-09

1.91 E-10

3.74E-08

6.52E-10

2.18E-12

6.11E-10

4.06E-09

8.21 E-09

8.36E-10

1.25E-10

8.25E-1 1

3.94E-09

7.43E-1 I

5.20E-08

7.19E-08

1.04E-08

2.35E-09

8.07E-09

7.96E-08

4.79E-1 0

2.02E-08

4.17E-08

THYROID

2.46E-05

4.76E-04

6.45E-06

1.01E-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

1.15E-06

5.98E-06

6.10E-07

2.48E-06

0.

0.

0.

0.

0.

0.

0.

3.39E-08

6.26E-05

9.73E-06

1.84E-05

5.07E-05

1.10E-07

5.79E-08

9.22E-1 1

1.18E-08

4.65E-1 1

2.53E-1 1

0.

0.

0.

4.18E-09

7.67E-1 0

1.72E-07

3.04E-09

1.01E-11

5.99E-09

1.90E-08

1.59E-08

3.OOE-09

5.81 E-10

2.93E-1 0

1.84E-08

3.30E-10

2.74E-07

4.56E-07

6.57E-08

9.69E-09

2.56E-08

1.61 E-07

0.

0.

0.

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

5.95E-09

2.39E-05

3.52E-06

2.90E-06

1.97E-05

1.28E-08

6.34E-09

6.74E-11

2.34E-08

3.43E-1 1

1.99E-11

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.

GI-LLI

3.113E-07

2.513E-06

5.1 OE-09

1.74E-06

0.

0.

0.

0.

0.

0.

0.

4.05E-08

2.45E-06

4.4(6E-07

2.7:2E-06

2.1 :2E-06

6.76E-1 1

3.3:3E-23

1.24E-06

4.33E-05

1.4:3E-1 3

9.1,3E-20

9.8:2E-05

2.4.3E-05

2.4:2E-06

2.54E-05

5.14E-05

1 .7!5E-04

4.3 1E-05

4.74E-14

3.63E-05

9.47E-06

6.61 E-05

9.90E-05

4.43E-05

3.613E-05

5.70E-06

2.8 5E-05

2.17E-05

5.3'3E-05

9.63E-05

7.33 E-05

4.19E-05

0.

3.91)E-07

1.6,5E-05

3.2:2E-05

90
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

TEEN INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FllRST YR)

ISOTCPE

PB210+D

B1210+D

P021C

RN222+D

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

AM24.

CM24,'

CM243I

CM24'.

CM24'5

CM246

CM247,+D

CM248i

CR252

BONE LIVER

1.81 E-02 5.44E-03

6.59E-07 4.51 E-06

6.09E-04 1.07E-03

0. 0.

7.11E-03 1.08E-05

2.31 E-03 5.52E-06

9.37E-03 1.10E-05

3.22E-01 8.13E-06

1.37E-01 4.41 E-06

6.29E-06 8.59E-06

2.05E-03 3.03E-04

1.96E-05 3.52E-07

6.80E-04 1.14E-05

8.39E-03 1.26E-04

2.16E-03 1.23E-04

2.42E-03 1.05E-04

1.14E-07 6.68E-09

4.31E-03 1.62E-04

7.33E-09 1.41E-09

5.89E-03 0.

1.24E-03 0.

1.19E-03 0.

1.14E-03 0.

1.14E-03 0.

7.89E-08 0.

1.09E-03 0.

1.44E-03 1.25E-04

1.95E-08 5.22E-10

1.76E-09 1.66E-10

7.21 E-04 1.02E-04

8.27E-04 1.12E-04

8.26E-04 1.12E-04

1.84E-05 9.42E-07

7.66E-04 1.08E-04

8.95E-04 1.23E-04

8.62E-04 3.29E-04

8.70E-04 3.19E-04

8.60E-04 3.17E-04

2.94E-05 2.97E-05

6.91 E-04 2.86E-04

5.32E-04 2.49E-04

1.07E-03 3.33E-04

1.06E-03 3.32E-04

1.03E-03 3.27E-04

8.60E-03 2.69E-03

3.51 E-04 0.

TOTAL BODY

7.01 E-04

5.66E-08

1.23E-04

0.

1.42E-03

4.61 E-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

3.31 E-09

1.68E-04

1.26E-09

4.21 E-04

7.543-05

7.39E-05

6.94E-05

7.09E-05

2.10E-08

6.49E-05

5.85E-05

3.04E-10

9.22E-1 1

1.82E-05

2.01 E-05

2.01 E-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.

3.10E-04

1.58E-04

3.15E-04

2.32E-04

1.26E-04

9.85E-07

8.81 E-05

2.01 E-06

6.41 E-05

6.1OE-04

5.99E-04

5.11E-04

3.81 E-08

9.1OE-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

1.91E-04

1.49E-04

2.85E-04

2.84E-04

2.80E-04

2.31 E-03

0.

LUNG

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.

GI-LLI

5.74E-05

5.1 !;E-05

6.75E-05

0.

3.43E-04

3.71 E-04

3.2'E-04

3.51 E-04

5.9l3E-05

4.31,E-04

8.613E-05

5.75E-04

5.97E-04

5.43E-04

6.313E-05

5.43E-05

1.21 E-04

7.60E-05

1.61 E-05

7.19E-05

6.65E-05

6.51 E-05

8.28E-05

6.1 lE-05

2.09E-05

5.83E-05

8.41 E-05

3.83E-05

2.6'E-05

7.7:3E-05

7.0fE-05

7.1!9E-05

1.48E-06

6.92E-05

1.0:3E-04

7.87E-05

9.90E-05

9.2:3E-05

8.40E-05

8.2i3E-05

8.00E-05

7.4'3E-05

7.3:3E-05

9.6:3E-05

1.5:5E-03

3.0:5E-04

91
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GILLI

H3 0. 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07

BE10 3.18E-06 4.91 E-07 7.94E-08 0. 3.71 E-07 0. 2.68E-05

C14 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.6BE-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.OOE-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 3.91 E-06 0. 0. 2.85E-06 3.40E-05

C057 0. 1.75E-07 2.91E-07 0. 0. 0. 4.44E-06

C058 0. 7.45E-07 1.67E-06 0. 0. 0. 1.51 E-05

C060 0. 2.14E-06 4.72E-06 0. 0. 0. 4.02E-05

N159 9.76E-06 3.35E-06 1.63E-06 0. 0. 0. 6.90E-07

N163 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 3.91 E-08 0. 2.10E-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. 2.95E-09

SE79 0. 2.63E-06 4.39E-07 0. 4.55E-06 0. 5.3BE-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.

KR88iD 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. 4.1SE-06

RB87 0. 1.23E-05 4.28E-06 0. 0. 0. 5.76E-07

RB88 0. 6.05E-08 3.21 E-08 0. 0. 0. 8.36E-19

RB89dD 0. 4.01E-08 2.82E-08 0. 0. 0. 2.33E-21

SR894 D 3.08E-04 0. 8.84E-06 0. 0. 0. 4.94E-05

SR9O4D 7.58E-03 0. 1.86E-03 0. 0. 0. 2.19E-04

SR914D 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

92
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREMI50Y PER PCI INGESTED IN FIRST YR)

ISOTCOPE

Y90

Y91 M-D

Y91

Y92

Y93

ZR934D

ZR95i D

ZR974 D

NB93M

NB95

NB97

M093

MO99 FD

TC99M

TC99

TC101

RU 103+D

RU10';+D

RU106+D

RH 105

PD107

PD109

AG11()M+D

AG 11'

CD113M

CD1 'iM

SN123

SN125+D

SN 126+D

SB124.

SB12';+D

SB126

SB127'

TE12;M

TE12EM+D

TE127

TE12GM+D

TE12S

TE131M+D

TE131+D

TE132+D

TE133M+D

TE134+D

1129

1130

1131+1)

BONE

9.62E-09

9.09E-1 1

1.41 E-07

8.45E-10

2.68E-09

4.18E-08

3.04E-08

1.68E-09

2.55E-08

6.22E-09

5.22E-1 1

0.

0.

2.47E-10

1.25E-07

2.54E-10

1.85E-07

1.54E-08

2.75E-06

1.21 E-07

0.

0.

1.60E-07

5.81 E-08

0.

0.

3.11E-05

8.33E-06

8.45E-05

2.80E-06

1.79E-06

1.15E-06

2.58E-07

2.68E-06

6.77E-06

1.10E-07

1.15E-05

3.14E-08

1.73E-06

1.97E-08

2.52E-06

4.62E-08

3.24E-08

3.27E-06

7.56E-07

4.16E-06

LIVER

0.

0.

0.

0.

0.

2.34E-09

9.75E-09

3.39E-10

8.32E-09

3.46E-09

1.32E-1 1

7.51 E-06

4.31 E-06

6.98E-10

1.86E-07

3.66E-10

0.

0.

0.

8.85E-08

1.47E-07

1.77E-07

1.48E-07

2.43E-08

3.18E-06

1.84E-06

5.15E-07

1.68E-07

1.67E-06

5.29E-08

2.OOE-08

2.34E-08

5.65E-09

9.71 E-07

2.42E-06

3.95E-08

4.29E-06

1.18E-08

8.46E-07

8.23E-09

1.63E-06

2.70E-08

2.12E-08

2.81 E-06

2.23E-06

5.95E-06

TOTAL BODY

2.58E-10

3.52E-12

3.77E-09

2.47E-1 1

7.40E-1 1

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-11

2.13E-06

9.76E-06

1.06E-08

2.34E-06

6.59E-09

7.06E-07

1.99E-07

5.31 E-06

3.76E-07

1.32E-06

1.01 E-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

7.7'3E-05

1.43E-05

8.50E-05

2.43E-06

3.03E-05

1.05E-04

3.84E-06

2.1 DE-05

4.87E-08

1.22E-06

9.99E-06

4.1 3E-07

6.OBE-06

1.1OE-21

2.1 BE-05

9.42E-06

1.7BE-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-1 1

4.44E-07

1.92E-06

1.57E-06

93
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

ADULT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE

1132

1133+[)

1134

1135+[)

XE131M

XE13'M

XE13'i

XE13E5M

XE13';

XE137

XE138+D

CS 13-'M+D

CS134

CS13'i

CS136

CS137+D

CS138

CS139+D

BA13S'

BA14C+D

BA141+D

BA142z+D

LA140

LA141

LA142

CE141

CEl43+D

CE144+D

PR143

PR14z.

ND147+D

PM147

PM1411M+D

PM148

PM149

PM151'

SM151

SM153

EU15z

EU154

EU15E

EU15E

TB160

HO 166M

W181

W185

W187

BONE

2.03E-07

1.42E-06

1.06E-07

4.43E-07

0.

0.

0.

0.

0.

0.

0.

2.13E-08

6.22E-05

1.95E-05

6.51 E-06

7.97E-05

6.52E-08

3.41 E-08

9.70E-08

2.03E-05

4.71 E-08

2.13E-08

2.50E-09

3.19E-10

1.28E-10

9.36E-09

1.65E-09

4.88E-07

9.20E-09

3.01 E-1I

6.29E-09

7.54E-08

3.07E-08

7.17E-09

1.52E-09

6.97E-1 0

6.90E-08

8.57E-1 0

1.95E-07

6.15E-07

8.60E-08

1.37E-08

4.70E-08

2.70E-07

9.91 E-09

4.05E-07

1.03E-07

LIVER

5.43E-07

2.47E-06

2.88E-07

1.16E-06

0.

0.

0.

0.

0.

0.

0.

4.48E-08

1.48E-04

1.80E-05

2.57E-05

1.09E-04

1.09E-07

5.08E-08

6.91 E-11

2.55E-08

3.56E-1 1

2.19E-1 1

1.26E-09

9.90E-1 1

5.82E-1 1

6.33E-09

1.22E-06

2.04E-07

3.69E-09

1.25E-1 1

7.27E-09

7.09E-09

7.95E-09

1.19E-09

2.15E-10

1.17E-10

1.19E-08

7.15E-10

4.44E-08

7.56E-08

1.22E-08

1.06E-08

0.

8.43E-08

3.23E-09

1.35E-07

8.61 E-08

TOTAL BODY

1.90E-07

7.53E-07

1.03E-07

4.28E-07

0.

0.

0.

0.

0.

0.

0.

2.29E-08

1.21 E-04

7.99E-06

1.85E-05

7.14E-05

5.40E-08

1.85E-08

2.84E-09

1.33E-06

1.59E-09

1.34E-09

3.33E-10

1.62E-11

1.45E-11

7.18E-10

1.35E-1 0

2.62E-08

4.56E-1 0

1.53E-12

4.35E-10

2.87E-09

6.08E-09

5.99E-1 0

8.78E-11

5.91 E-11

2.85E-09

5.22E-1 1

3.90E-08

5.38E-08

7.87E-09

1.71 E-09

5.86E-09

6.40E-08

3.46E-10

1.42E-08

3.01 E-08

THYROID

1.90E-05

3.63E-04

4.99E-06

7.65E-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

4.31 E-06

4.58E-07

1.86E-06

0.

0.

0.

0.

0.

0.

0.

2.43E-08

4.79E-05

6.81 E-06

1.43E-05

3.70E-05

8.01 E-08

4.07E-08

6.46E-1 1

8.67E-09

3.31 E-11

1.85E-1 I

0.

0.

0.

2.94E-09

5.37E-1 0

1.21 E-07

2.13E-09

7.05E-12

4.25E-09

1.34E-08

1.20E-08

2.25E-09

4.06E-10

2.09E-1 0

1.33E-08

2.31 E-1 0

2.75E-07

3.62E-07

5.63E-08

7.08E-09

1.94E-08

1.26E-07

0.

0.

0.

LUNG

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

3.83E-09

1.59E-05

2.04E-06

1.96E-06

1.23E-05

7.91 E-09

3.70E-09

3.92E-11

1.46E-08

2.02E-1 1

1.24E-11

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.

GI-LLI

1.02E-07

2.22E-06

2.51 E-10

1.31 E-06

0.

0.

0.

0.

0.

0.

0.

1.5BE-08

2.59E-06

4.21 E-07

2.92E-06

2.11E-06

4.65E-13

1.1OE-30

1.72E-07

4.1 BE-05

2.22E-17

3.00E-26

9.25E-05

1.1 BE-05

4.25E-07

2.42E-05

4.55E-05

1.65E-04

4.03E-05

4.33E-18

3.49E-05

8.93E-06

6.7 4E-05

9.3 5E-05

4.03E-05

3.2.2E-05

5.2 5E-06

2.55E-05

2.53E-05

5.43E-05

9.6')E-06

7.23E-05

4.3:3E-05

0.

3.6;3E-07

1 .563E-05

2.8:2E-05

94
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.1

ADIJLT INGESTION DOSE COMMITMENT FACTORS (MREM/50Y PER PCI INGESTED IN FIRST YR)

ISOTOPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI

PB21I0+D 1.53E-02 4.37E-03 5.44E-04 0. 1.23E-02 0. 5.Z.2E-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. 6.86E-05

RN22.2+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.C6E-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

AC22,'+D 1.87E-03 2.48E-04 1.11E-04 0. 8.00E-05 0. 8.19E-05

TH22.+D ) 1.37E-05 2.48E-07 3.95E-07 0. 1.41 E-06 0. 5.40E-04

TH22£+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.OOE-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 4.1OE-03 1.54E-04 1.59E-04 0. 8.64E-04 0. 7.17E-05

PA233 5.26E-09 1.06E-09 9.12E-10 0. 3.99E-09 0. 1.64E-05

U232+D 4.13E-03 0. 2.95E-04 0. 4.47E-04 0. 6.7.3E-05

U233+D 8.71 E-04 0. 5.28E-05 0. 2.03E-04 0. 6.27E-05

U234 8.36E-04 0. 5.17E-05 0. 1.99E-04 0. 6.14E-05

U235+D 8.01 E-04 0. 4.86E-05 0. 1.87E-04 0. 7.81 E-05

U236 8.01E-04 0. 4.96E-05 0. 1.91E-04 0. 5.713E-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 1.71 E-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

PU241fD 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. 7.81 E-05 0. 6.5'iE-05

PU244 8.52E-04 1.17E-04 2.11E-05 0. 8.95E-05 0. 9X7'IE-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. 9.34 E-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. 7.55.E-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

95
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.2

PALISADES

Liquid Effluent

Design Obiective Annual Quantity

Nuclidce Half-Life

Dose Conversion

Factors (mrem/Ci)

Design Objectiva

Annual Quantity

Individual/Organ (Curies)

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

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

1.75E-06

5.44E-03

2.02E-02

1.56E-03

3.50E-02

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

2.71 E-00

1.16E-03

1.51 E-03

2.69E-04

7.24E+00

6.17E-03

6.95E-04

AdulVtTB

Teen/TB

Teen/TB

AdultVGI (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

TeenlTB

1.71 E+OE

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

Zr-97

Mo-99

Tc-99m

Ru-1 03

Ag-11(1m

17 h

66.7 h

6.05 h

39.5 d

255 d

9.28E-04

1.11E-03

1.42E-04

2.74E-03

7.75E-02

Teen/TB

Teen/Kidney

Teen/TB

TeenlTB

Teen/TB

3,232.8

9,009.0

21,126.8

1,094.9

38.7

96
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

TABLE 2.2 (continued)

PALISADES

Liquid Effluent

Design Obiective Annual Quantity

Design Objective

Dose Conversion Annual Quantity Nuclide Half-Life Factors (mrem/Ci) Individual/Organ (Curies)

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-123m 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 Teen/TB 94,339.0

Te-132 77.7 h 2.93E-01 Adult/GI (LLI) 34.1

1-133 20.3 h 3.94E-02 Child/Thyroid 253.8

Cs-134 2 yr 2.86E+00 AdulVtTB 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-133 13.7 d 4.13E-01 AdulVtTB 7.26

Cs-137 30 yr 1.71E+00 Adult/TB 1.75

Cs-133 32.2 mo 2.31E-03 Teen/TB 1,298.0

Ba-133 82.9 mo 4.66E-05 Teen/TB 64,377.0

Ba-141) 12.8 d 7.96E-04 Teen/TB 3,768.0

La-14() 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-15:2 12.7 yr 3.24E-01 Teen/TB 9.25

W-187 23.9 h 1.98E-01 Adult/GI (LLI) 50.5

Np-233 2.346 d 2.26E-03 Adult/GI (LLI) 4,424.0

97
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

Ill. URANIUM FUEL CYCLE DOSE

A. SPECIFICATION

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

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

limit of Appendix A, Sections III.C.1, III.D.1, or Il.H.1, then the cumulative dose

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

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

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

combined sources.

B. ASSUMPTIONS

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

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

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

Sections II.C.2.1 and Il.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.

98
PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

Revision 20

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:

D40 40 CFR 190 dose (mrem).

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

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

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

adjacent to Plant site (mrem/hr).

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

IV. 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 Plant Review Committee.

99
Proc No ODCM

Attachment I

Revision 20

Page 1 of 4

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

Description:

Provide a brief description of the change.

1.

2. Evaluation:

Provide sufficient information to support the change, with appropriate analyses or

evaluations justifying the change if needed.

3. 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.)

L Yes

n No
Proc No ODCM

Attachment I

Revision 20

Page 2 of 4

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

b. Does the proposed 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.)

LI Yes

EJ No

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.)

LI Yes

LI 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.)

EL Yes

LI|No
Proc No ODCM

Attachment I

Revision 20

Page 3 of 4

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

e. Does the proposed change adversely impact the accuracy or reliabilityof

effluent calculations?

El Yes

[E No

f. Does the proposed chanae adversely impact the accuracy or reliabiit'Lof

dose calculations?

El Yes

El No

9. Does the proposed change adversely impact the accuracy or reliability of

setpoint calculations?

El Yes

El No
Proc No ODCM

Attachment I

Revision 20

Page 4 o14

OFFSITE DOSE CALCULATION MANUAL CHANGE REVIEWS

4. 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
ODCM

Appendix A

Revision 11

Issued Date 3118104

PALISADES NUCLEAR PLANT

OFFSITE DOSE CALCULATION MANUAL

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

MLC;rogan I 3/17/04

Procedure Sponsor Date

JLBeer / 12/4/03

Technical Reviewer Date

WWDoolittle / 12/2/03

Useir Reviewer Date

RRemus I 1/12/04

Plant Manager Date
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 11

Page i

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

INTRODUCTION ...

DEFINITIONS.................................................................................................................I

A. CHANNEL CALIBRATION .I

B. CHANNEL CHECK .I

C. CHANNEL FUNCTIONAL TEST .2

D. SOURCE CHECK .. 2

E. OFFSITE DOSE CALCULATION MANUAL . . 2

F. GASEOUS RADWASTE TREATMENT SYSTEM .2

G. MEMBERS OF THE PUBLIC .2

H. PROCESS CONTROL PROGRAM (PCP) . . 3

I. SITE BOUNDARY .. 3

J. UNRESTRICTED AREA .. 3

K. VENTILATION EXHAUST TREATMENT SYSTEM . . 3

III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES . 4

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING

INSTRUMENTATION .. 4

1. Requirement .4

2. Action .4

3. Surveillance Requirements .4

4. Bases .5

B. GASEOUS EFFLUENTS DOSE RATE . .10

1. Requirement .10

2. Action .10

3. Surveillance Requirements .10

4. Bases .11
PALISADES NUCLEAR PLANT ODCM

OFFSITE DOSE CALCULATION MANUAL Appendix A

Revision 11

Page ii

TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table of Contents

C. NOBLE GASES DOSE .................................. 12

1. Requirement .................................. 12

2. Action .................................. 12

3. Surveillance Requirements .................................. 12

4. Bases .................................. 13

D. 1-131,1-133, TRITIUM, AND PARTICULATES .................................. 14

1. Requirement .................................. 14

2. Action .................................. 14

3. Surveillance Requirements .................................. 14

4. Bases .................................. 15

E. GASEOUS WASTE TREATMENT SYSTEM . ............................. 18

1. Requirement .................................. 18

2. Action .................................. 18

3. Surveillance Requirements .................................. 18

4. Bases .................................. 19

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 19

1. Requirement ............................... 19

2. Action ............................... 20

3. Surveillance Requirements ............................... 20

4. Bases ............................... 20

G. LIQUID EFFLUENTS CONCENTRATION ............................... 25

1. Requirement ............................... 25

2. Action ............................... 25

3. Surveillance Requirements ............................... 25

4. Bases ... 26
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Table of Contents

H. LIQUID EFFLUENT DOSE ........................................ 29

1. Requirement ........................................ 29

2. Action ........................................ 29

3. Surveillance Requirements ......................................... 29

4. Bases ........................................ 30

. T OTAL DOSE ......................................... 31

1. Requirement ........................................ 31

2. Action ......................................... 31

3. Surveillance Requirements ........................................ 32

4. Bases ........................................ 33

J. RADIOLOGICAL ENVIRONMENTAL MONITORING . ................................ 34

1. Requirement ......................................... 34

2. Action ........................................ 34

3. Surveillance Requirements ........................................ 35

4. Bases ........................................ 36

K. SIRW OR TEMPORARY LIQUID STORAGE TANK . .................................. 46

1. Requirement ........................................ 46

2. Action ........................................ 46

3. Surveillance Requirement ........................................ 46

4. Bases ......................................... 47

L. SURVEILLANCE REQUIREMENT TIME INTERVALS . .............................. 47

1. Requirement ........................................ 47

2. Action ........................................ 47

3. Surveillance Requirements ........................................ 48

4. Bases ... 48
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M. SEALED SOURCE CONTAMINATION ................................... 48

1. Requirement ..................................... 48

2. Action ..................................... 48

3. Surveillance Requirements ..................................... 49

4. Bases ..................................... 50

IV. REPORTING REQUIREMENTS ... ................... 50

A. RADIOLOGICAL EFFLUENT RELEASE REPORT . ......................... 50

1. Supplemental Information .................... 51

2. Gaseous Effluents .................... 51

3. Liquid Effluents .................... 53

4. Radiological Impact on Man .................... 54

5. ODCM Changes .................... 55

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT .. 55

C. NONROUTINE REPORTS ............................................. 56

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS . . . 58

A. LICENSEE MODIFICATIONS .. 58

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION . 58

TABLES

A-1 Radioactive Gaseous Effluent Monitoring Instrumentation

A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance

Requirements

B-1 Radioactive Gaseous Waste Sampling and Analysis Program

C-1 Radioactive Liquid Effluent Monitoring Instrumentation

C-2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

D-1 Radioactive Liquid Waste Sampling and Analysis Program

E-1 Radiological Environmental Monitoring Program

E-2 Reporting Levels for Radioactivity Concentrations in Environmental Samples

E-3 Detection Capabilities for Environmental Sample Analysis

F-1 Environmental Radiological Monitoring Program Summary
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INTRODUCTION

The NRC, through 10CFR50.36a, requires implementation of Technical

Specifications on effluents from nuclear power plants. NRC Generic Letter 89-01,

dated January 31, 1989, allowed relocation of the existing procedural

requirements from the Technical Specifications (implemented in Amendment 85,

November 9, 1984). The relocated procedural requirements related to gaseous and

liquid effluents, total dose, environmental monitoring program, and associated

procedural reporting requirements follow below. Programmatic controls are retained

in the Administrative Controls section of the Technical Specification to satisfy the

regulatory requirements of 1OCFR50.36a. The Technical Specifications

programmatic controls include requirements for the establishment, implementation,

maintenance, and changes to the Offsite Dose Calculation Manual (ODCM) as well

as record retention and reporting requirements.

DEFINITIONS

A. CHANNEL CALIBRATION

- a Channel Calibration shall be the adjustment, as necessary, of the channel

output such that it responds with the necessary range and accuracy to known

values of the parameter which the channel monitors. The Channel

Calibration shall encompass the entire channel including the sensor and

alarm and/or trip functions, and shall include the Channel Function Test.

The Channel Calibration may be performed by any series of sequential,

overlapping, or total channel steps such that the entire channel is calibrated.

B. CHANNEL CHECK - a Channel Check shall be the qualitative assessment of channel behavior

during operation by observation. This determination shall include, where

possible, comparison of the channel indication and/or status with other

indications and/or status derived from independent instrumentation channels

measuring the same parameter.
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C. CHANNEL FUNCTIONAL TEST

- a Channel Functional Test shall be:

1. Analog channels - the injection of a simulated signal into the channel

as close to the sensor as practicable to verify operability including

alarm and/or trip functions.

2. Bistable channels - the injection of a simulated signal into the sensor to

verify operability including alarm and/or trip functions.

D. SOURCE CHECK

- a source check shall be the qualitative assessment of channel response

when the channel sensor is exposed to a radioactive source.

E. OFFSITE DOSE CALCULATION MANUAL

- (per Plant Technical Specifications) - the Offsite Dose Calculation Manual

(ODCM) shall contain the methodology and parameters used in the

calculation of offsite doses resulting from radioactive gaseous and liquid

effluents, in the calculation of gaseous and liquid effluent monitoring alarm/trip

setpoints, and in the conduct of the Radiological Environmental Monitoring

Program. The ODCM shall also contain: 1) the Radioactive Effluent Controls

and Radiological Environmental Monitoring Programs required by the

Technical Specifications, and 2) descriptions of the information that should be

included in the Annual Radiological Environmental Operating and Raclioactive

Effluent Release Reports required by the Technical Specifications.

F. GASEOUS RADWASTE TREATMENT SYSTEM - any system designed and installed to reduce radioactive gaseous effluents

by collecting primary coolant system off gases from the primary system and

providing for delay or holdup for the purpose of reducing the total radioactivity

prior to release to the environment.

G. MEMBERS OF THE PUBLIC

- all persons who are not occupationally associated with the Plant. This

category does not include employees of the utility, its contractors, or vendors.

Also excluded from this category are persons who enter the site to service

equipment or to make deliveries.
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NRC GENERIC LETTER 89-01 (TAC NO 75060)

H. PROCESS CONTROL PROGRAM (PCP)

- shall contain the current formula, sampling, analyses, tests, and

determinations to be made to ensure that the processing and packaging of

solid radioactive wastes based on demonstrated processing of actual or

simulated wet solid wastes will be accomplished in such a way as to assure

compliance with 1OCFR Part 20, 1OCFR Part 71 and Federal and Stale

regulations and other requirements governing the disposal of the radioactive

waste.

I. SITE BOUNDARY

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

the licensee.

J. UNRESTRICTED AREA

- any area at or beyond the Site Boundary access which is not controlled by

the licensee for purposes of protection of individuals from exposure to

radiation and radioactive materials or, any area within the Site Boundary used

for residential quarters or for industrial, commercial, institutional, and/or

recreational purposes.

K. VENTILATION EXHAUST TREATMENT SYSTEM

- any system designed and installed to reduce gaseous radioiodine or

radioactive material in particulate form in effluents by passing ventilation or

vent exhaust gases through charcoal absorbers and/or HEPA filters for the

purpose of removing iodines or particulates from the gaseous exhaust stream

prior to the release to the environment. Such a system is not considered to

have any effect on noble gas effluents. Engineered Safety Feature (EiSF) atmospheric cleanup systems are not considered to be ventilation exhaust

treatment system components.
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III. PROCEDURAL AND SURVEILLANCE REQUIREMENTS AND BASES

A. RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

1. Requirement

The radioactive gaseous effluent monitoring instrumentation channels

shown in Table A-1 shall be operable with their alarm/trip setpoints set

to ensure that the limits of requirement lll.B.1 are not exceeded. The

alarm/trip setpoints of these channels shall be determined and

adjusted in accordance with the methodology and parameters in the

ODCM.

2. Action

a. With a radioactive gaseous effluent monitoring instrumentation

channel alarm/trip setpoint less conservative than required by

the above requirement, without delay, suspend the release of

radioactive gaseous effluents monitored by the affected channel

or declare the channel inoperable or change the setpoint so it is

acceptably conservative.

b. With less than the minimum number of radioactive gaseous

effluent monitoring instrumentation channels operable, take the

action shown in Table A-1. Exert best efforts to return the

instruments to operable status within 30 days and, if

unsuccessful, explain in the next Radioactive Effluent Release

Report why the inoperability was not corrected in a timely

manner.

3. Surveillance Requirements

Each radioactive gaseous effluent monitoring instrumentation channel

shall be demonstrated operable by performance of the Channel Check,

Source Check, Channel Calibration, and Channel Functional Test

operations at the frequencies shown in Table A-2.
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4. Bases

The radioactive gaseous effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

gaseous effluents during actual or potential releases of gaseous

effluents. The alarm/trip setpoints for these instruments shall be

calculated and adjusted in accordance with the methodology and

parameters in the ODCM to ensure that the alarm/trip will occur prior to

exceeding the limits of I OCFR Part 20.

The operability and use of this instrumentation is consistent wi':h the

requirements of General Design Criteria 60, 63, and 64 of Appendix A

to 1OCFR Part 50.
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ODCM

Appendix A

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Table A-1

Radioactive Gaseous Effluent Monitoring Instrumentation

Minimum

Instrument Operable Applicability Action

Channels

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor (RIA 1113) Providing

Alarm and Automatic Termination of Release (1) At All Times 1

2. CONDENSER EVACUATION SYSTEM (RIA 0631)

a. Noble Gas Activity Monitor (1) Above 210OF 3

Modes 1, 2, 3, 4

Above 2100 F

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

3. STACK GAS EFFLUENT SYSTEM

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

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

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

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

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM

a. Noble Gas Activity Monitor (RIA 2320) (1) Above 210OF 3

Modes 1, 2, 3, 4

l5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE

a. Gross Gamma Activity Monitor* 1 per Main Above 3250F 4

(RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor ** 1 per Room Above 210OF 5

(RIA 1810 and 1811) Modes1 2, 3, 4

* Setpoints for these instruments are exempted from IIl.B.1 limits, but are governed by

Emergency Implementing Procedures or Operating procedures.

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

*** Documentation of operability not required.
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Table A-1 (Cont'd)

TABLE NOTATION - ACTION STATEMENTS

ACTION 1 - With the number of channels operable less than required by the Minimum Operable Channels

requirements, the contents of the tank(s) may be released to the environment provided that

prior to initiating the release:

a. At least two independent samples of the tank's contents are analyzed, and

b. At least two technically qualified members of the facility staff independently verify the

release rate calculations and discharge valve line up;

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2 -

ACTION 3 -

ACTION 4 -

With the number of channels operable less than required by the Minimum Operable Channels

requirement, effluent releases via this pathway may continue provided the flow rate is

estimated at least once per 24 hours.

With the number of channels operable less than required by the Minimum Operable! Channels

requirement, effluent releases via this pathway may continue provided grab samples are

taken at least once per 12 hours and these samples are analyzed for gross activity within

24 hours.

With the number of operable channels less than required by the Minimum Operable Channels

requirements, initiate the preplanned alternate method of monitoring the appropriate

parameter(s), within 72 hours, and:

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

or

b. Prepare and submit a Special Report to the NRC within 30 days following the event

outlining the actions taken, the cause of the inoperability, and the plans ancd schedule

for restoring the system to operable status.

ACTION 5 - If either channel fails low or is otherwise inoperable, the ventilation dampers associated with

that channel shall be closed immediately and action shall be taken to have the affected

channel repaired. The dampers associated with the channel shall not be opened until the

affected channel has been declared operable.

(Reference Technical Specifications LCO 3.3.10.) I
PALISADES NUCLEAR PLANT

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TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER

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ODCM

Appendix A

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Table A-2

Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements

Instrument IntuetChannel Source Channel Channel Modes in Which Chec Calibration Functional Surveillance

1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor-Providing Alarm and D(4) P R(3) Q(1)(2) * Automatic Termination of Release

2. CONDENSER EVACUATION SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2) Above 21 0F b. Evacuation Flow Indicator (FI-0632) or *** *** *** *** Modes 1, 2, 3, 4

c. Evacuation Flow Indicator (FI-0631) *** ***

3. STACK GAS EFFLUENT SYSTEM

a. Noble Gas Activity Monitor D M R(3) Q(2) * b. Iodine Particulate Sampler/Monitor W M** R(3)** NA * c. Sampler Flow Rate Monitor D NA R NA * d. Hi Range Noble Gas D M R(3) Q(2) Above 210F

l__ _Modes 1, 2, 3, 4

4. STEAM GENERATOR BLOWDOWN VENT SYSTEM Above 21 OOF

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

5. MAIN STEAM SAFETY AND DUMP VALVE

DISCHARGE LINE Above 3250F

0 M R(3) 0(2) Modes 1, 2, 3 a. Gross Gamma Activity Monitor D ___________ Modes____2__3 6. ENGINEERED SAFEGUARDS PUMP ROOM

VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours 31 days 18 months (3) 31 days(1)(2) Above 2100F (Technical Specifications SR 3.3.10 and Modes 1, 2, 3, 4 SR 3.7.-3.iJ )

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

** Sampler not applicable *** This type of Flowmeter doesn't have any surveillance requirements.

I

11
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Table A-2 (Cont'd)

Table Notation

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates

measured levels above the alarm/trip setpoint.

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

conditions exists.

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

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National

Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in

measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended

range of energy and measurement range.

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

(4) Channel Check shall be made at least once per 24 hours on days on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION

S At least once per 12 hours

D At least once per 24 hours

M At least once per 31 days

P Prior to rndiinctivp hatrh release

Q At least once per 92 days

R At least once per 18 months

W At least once per week
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B. GASEOUS EFFLUENTS DOSE RATE

1. Requirement

The dose rate due to radioactive materials released in gaseous

effluents from the site to areas at and beyond the Site Boundary

(see Figure 2-1) shall be limited to the following:

a. For noble gases: Less than or equal to 500mrems/yr to the total

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

b. For lodine-1 31, For lodine-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.

2. Action

With the dose rate(s) averaged over a period of one hour exceeding

the above limits, without delay, restore the release rate to within the

above limit(s).

3. Surveillance Requirements

a. The dose rate due to noble gases in gaseous effluents shall be

determined to be within the limits of B.1.a in accordance with

the methodology and parameters in the ODCM.

b. The dose rate due to lodine-131, lodine-133, tritium, and all

radionuclides in particulate form with half-lives greater than

8 days in gaseous effluents shall be determined to be within the

limits of B.1.b in accordance with the methodology and

parameters in the ODCM by obtaining representative samples

and performing analyses in accordance with the sampling and

analysis program specified in Table B-1.
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4. Bases

This is provided to ensure that the dose at any time at and beyond the

Site Boundary from gaseous effluents from all units on the site will be

within 10 times the annual dose limits of 1 OCFR Part 20 to Unrestricted

Areas. The annual dose limits are the doses associated with the

concentrations of 10 times 10CFR Part 20, Appendix B, Table :2,

Column 1. These restrictions provide reasonable assurance that

radioactive material discharged in gaseous effluents will not result in

the exposure of a Member of the Public in an Unrestricted Area, either

within or outside the Site Boundary, to annual exposure greater than

design objectives of 10CFR 50, Appendix I, Section ll.B.1. For

Members of the Public who may at times be within the Site Boundary,

the occupancy of the Member of the Public will usually be sufficiently

low to compensate for any increase in the atmospheric diffusion factor

above that for the Site Boundary. Examples of calculations for such

Members of the Public, with the appropriate occupancy factors, shall

be given in the ODCM. The specified release rate limits restrict, at all

times, the corresponding dose rate above background to a Member of

the Public at or beyond the Site Boundary to less than or equal to

500 mrems/yr to the total body.

The required detection capabilities for radioactive materials in gaseous

waste samples are tabulated in terms of the lower limits of detection

(LLDs). Detailed discussion of the LLD and other detection limits can

be found in HASL Procedures Manual, HASL-300, Currie, L A, "Limits

for Qualitative Detection and Quantitative Determination - Application

to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK,

"Detection Limits for Radjoanalytical Counting Techniques," Atlantic

Richfield Hanford Company Report ARH-SA-215 (June 1975).
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C. NOBLE GASES DOSE

1. Requirement

The air dose due to noble gases released in gaseous effluents to areas

at and beyond the Site Boundary (see Figure 2-1) shall be limited to

the following:

a. During any calendar quarter: Less than or equal to 5 mrads for

gamma radiation and less than or equal to 10 mrads for beta

radiation, and

b. During any calendar year: Less than or equal to 10 mrads for

gamma radiation and less than or equal to 20 mrads for beta

radiation.

2. Action

With the calculated air dose from radioactive noble gases in gaseous

effluents exceeding any of the above limits, prepare and submit to the

NRC within 30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for noble gases shall be determined in

accordance with the methodology and parameters in the ODCIM at

least once per 31 days.
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4. Bases

This requirement is provided to implement the requirements of

Sections lI.B, 1Il.A, and IV.A of Appendix I, 1OCFR Part 50. The

limiting Condition for Operation implements the guides set forth in

Section ll.B of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in gaseous effluents to Unrestricted Areas will be

kept "as low as is reasonably achievable." The Surveillance

Requirements implement the requirements in Section II.A of

Appendix I that conformance with the guides of Appendix I be shown

by calculational procedures based on models and data such that the

actual exposure of a Member of the Public through appropriate

pathways is unlikely to be substantially underestimated. The dDse

calculation methodology and parameters established in the ODCM for

calculating the doses due to the actual release rates of radioactive

noble gases in gaseous effluents are consistent with the methodology

provided in Regulatory Guide 1.109, "Calculation of Annual Doses to

Man from Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1,

October 1977 and Regulatory Guide 1.11 1, "Methods for Estimating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

The ODCM equations provided for determining the air doses at and

beyond the Site Boundary are based upon the historical average

atmospheric conditions.
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D. 1-131, 1-133, TRITIUM, AND PARTICULATES

1. Requirement

The dose to a Member of the Public from lodine-1 31, lodine-1 33,

tritium, and all radionuclides in particulate form with half-lives g eater

than 8 days in gaseous effluents released, from each reactor unit, to

areas at and beyond the Site Boundary (see Figure 2-1) shall be

limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 rnrems

to any organ, and

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

any organ.

2. Action

With the calculated dose from the release of Iodine-131, Iodine-133,

tritium, and radionuclides in particulate form with half-lives greater than

8 days, in gaseous effluents exceeding any of the above limits, prepare

and submit to the NRC within 30 days a Special Report that identifies

the cause(s) for exceeding the limit and define(s) the corrective actions

that have been taken to reduce the releases and the proposed

corrective actions to be taken to assure that subsequent releases will

be in compliance with the above limits.

3. Surveillance Requirements

Cumulative dose contributions for the current calendar quarter and

current calendar year for lodine-131, lodine-133, tritium, and

radionuclides in particulate form with half-lives greater than 8 days

shall be determined in accordance with the methodology and

parameters in the ODCM at least once per 31 days.
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4. Bases

This requirement is provided to implement the requirements of

Sections Il.C, Il.A, and IV.A of Appendix I, 10CFR Part 50. The

requirements are the guides set forth in Section ll.C of Appencix I.

The Action statements provide the required operating flexibility and at

the same time implement the guides set forth in Section IV.A of

Appendix I to assure that the releases of radioactive materials in

gaseous effluents to Unrestricted Areas will be kept "as low as is

reasonably achievable." The ODCM calculational methods specified in

the Surveillance Requirements implement the requirements in

Section ll.A of Appendix I that conformance with the guides of

Appendix I be shown by calculational procedures based on models

and data, such that the actual exposure of a Member of the Public

through appropriate pathways is unlikely to be substantially

underestimated. The ODCM calculational methodology and

parameters for calculating the doses due to the actual release rates

of the subject materials are consistent with the methodology provided

in Regulatory Guide 1.109, "Calculation of Annual Doses to Man

From Routine Releases of Reactor Effluents for the Purpose of

Evaluating Compliance with 10CFR Part 50, Appendix I," Revision 1,

October 1977 and Regulatory Guide 1.1 11, "Methods for Estimnating

Atmospheric Transport and Dispersion of Gaseous Effluents in Routine

Releases From Light-Water-Cooled Reactors," Revision 1, July 1977.

These equations also provide for determining the actual doses based

upon the historical average atmospheric conditions. The release rate

requirements for lodine-131, Iodine-133, tritium, and radionuclides in

particulate form with half-lives greater than 8 days are dependent upon

the existing radionuclide pathways to man, in areas at and beyond the

Site Boundary. The pathways that were examined in the development

of these calculations were: 1) individual inhalation of airborne

radionuclides, 2) deposition of radionuclides onto green leafy

vegetation with subsequent consumption by man, 3) deposition onto

grassy areas where milk animals and meat producing animals graze

with consumption of the milk and meat by man, and 4) deposition on

the ground with subsequent exposure of man.
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Table B-1

Radioactive Gaseous Waste Sampling and Analysis Program

Gaseous Release Type Sampling Minimum Type of Lower Limit

Frequency Analysis Activity Analysis Detection (LLD)a _ _ Frequency (PCi/ml)

A. Waste Gas Storage Tank P

Each Tank P

Grab Sample Each Tank Principal Gamma Emittersb 1 x 104

B. Containment PURGE P

Each PURGE P

Grab Sample Each PURGE Principal Gamma Emittersb 1 x 104

C. Stack Gas Effluent Wd,e

ContinuousC Charcoal 1-131, 1-133 1 x 10-12

l__ _ Sample l

Wde

Continuousc Particulate Principal Gamma Emittersb 1 x 10 11

Sample (1-131, Others) l

Q

Continuousc Composite Sr-89, Sr-90, and 1 x 10

Particulate Gross Alpha

Sample

Noble Gas Noble Gases 1 E-06

CuriiinuousC AI uliLoC __ _ r __ _r r-.-- %.:__ s D Ld Gt ar - I i dii _ _ _ _ _ _ _ _ _J
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Table B-1 (Cont'd)

Table Notation

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

b The principal gamma emitters for which the LLD specification applies exclusively are

the following radionuclides: Kr-87, Kr-88, Xe-1 33, Xe-1 33m, Xe-1 35, and Xe-i 38 for

gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99*, Cs-1 34,

Cs-137, Ce-141, and Ce-144* for particulate emissions. This list does not mean that

only these nuclides are to be considered. Other gamma peaks that are identifiable,

together with those of the above nuclides, shall also be analyzed and reported in the

Radioactive Effluent Release Report.

*Ten times the LLD because of low gamma yields.

C The ratio of the sample flow rate to the sample stream flow rate shall be known for

the time period covered by each dose or dose rate calculation made in accordance

with requirements IIl.B.1, 111.C.1, and III.D.I.

d Samples shall be changed at least once per 7 days and analyses shall be completed

within 48 hours after changing or after removal from sampler.

e With channels operable on iodine monitor RIA 2325 less than required per 11I.A.1,

sampling shall also be performed at least once per 24 hours for at least 7 days

following each shutdown, start-up or Thermal Power change exceeding 15 percent

of Rated Thermal Power in one hour and analyses shall be completed within

48 hours of changing. When samples collected for 24 hours are analyzed, the

corresponding LLDs may be increased by a factor of 10. This requirement does not

apply if, 1) analysis shows that the Dose Equivalent 1-131 concentration in the

primary coolant has not increased more than a factor of 3, and 2) the noble gas

monitor shows that effluent activity has not increased more than a factor of 3.
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E. GASEOUS WASTE TREATMENT SYSTEM

1. Requirement

When gaseous waste exceeds a Xe-133 concentration of

1 E-05 pCi/cc, the Waste Gas Decay Tank System shall be used to

reduce radioactive gaseous effluents by holding gaseous waste

collected by the system for a minimum of 15 days up to 60 days.

2. Action

a. If a waste gas decay tank is required to be released with less

than 60 days holdup time, the system waste gas tank contents

shall be evaluated and the waste gas decay tank with the lowest

Xe-133 content shall be released.

b. Gaseous waste may be discharged directly from the waste gas

surge tank through a high-efficiency filter or from a waste gas

decay tank with less than 15 days of holdup directly to the

stack for a period not to exceed 7 days if the holdup system

equipment is not available and the release rates meet

requirements lll.B, C, and D.

3. Surveillance Requirements

Not Applicable.
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4. Bases

The requirement that the appropriate portions of these systems be

used, when specified, provides reasonable assurance that the releases

of radioactive materials in gaseous effluents will be kept "as lowv as is

reasonably achievable" by meeting the design objectives given in

Section Il.D of Appendix I to 10CFR50.

It is expected that releases of radioactive materials in effluents shall be

kept at small fractions of the limits specified in 20.1302 of 10CFR20.

At the same time the licensee is permitted the flexibility of operation,

compatible with considerations of health and safety, to assure that the

public is provided a dependable source of power even under unusual

operating conditions which may temporarily result in releases higher

than such small fractions, but still within the limits specified in III.B, C,

and D.

F. RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

1. Requirement

The radioactive liquid effluent monitoring instrumentation channels

shown in Table C-1 shall be operable with their alarm/trip setpoints

set to ensure that the limits of III.G are not exceeded. The alarm/trip

setpoints of these channels shall be determined and adjusted in

accordance with the methodology and parameters in the Offsite Dose

Calculation Manual (ODCM).
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2. Action

a. With a radioactive liquid effluent monitoring instrumentation

channel alarm/trip setpoint less conservative than required by

the above specification, without delay suspend the release of

radioactive liquid effluents monitored by the affected channel or

declare the channel inoperable, or change the setpoint so it is

acceptably conservative.

b. With less than the minimum number of radioactive liquid effluent

monitoring instrumentation channels Operable, take the Action

shown in Table C-1. Exert best efforts to return the instruments

to Operable status within 30 days and, if unsuccessful, explain

in the next Radioactive Effluent Release Report why the

inoperability was not corrected in a timely manner.

3. Surveillance Requirements

Each radioactive liquid effluent monitoring instrumentation channel

shall be demonstrated Operable by performance of the Channel

Check, Source Check, Channel Calibration, and Channel Functional

Test operations at the frequencies shown in Table C-2.

4. Bases

The radioactive liquid effluent instrumentation is provided to monitor

and control, as applicable, the releases of radioactive materials in

liquid effluents during actual or potential releases of liquid effluents.

The alarm/trip setpoints for these instruments shall be calculated and

adjusted in accordance with the methodology and parameters in the

ODCM to ensure that the alarm/trip will occur prior to exceeding the

limits of 1 OCFR Part 20. The Operability and use of this

instrumentation is consistent with the requirements of General Design

Criteria 60, 63, and 64 of Appendix A to 1OCFR Part 50.
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Table C-1

Radioactive Liquid Effluent Monitorinq Instrumentation

Minimum

Instrument Operable Applicability Action

Channels

1. GROSS RADIOACTIVITY MONITORS PROVIDING

ALARM AND AUTOMATIC TERMINATION OF

RELEASE

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

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

(RIA 0707)

2. GROSS BETA OR GAMMA RADIOACTIVE

MONITORS PROVIDING ALARM BUT NOT

PROVIDING AUTOMATIC TERMINATION OF

RELEASE

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

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

Line (RIA 5211) _1

3. FLOW RATE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line (FIC 1051 or (1) For Effluent Release; 4

1050)

4. CONTINUOUS COMPOSITE SAMPLERS (Alarm/Trip

Setpoints are not applicable)

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

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

c. Steam Generator Blowdown Effluent (1) For Effluent Releases 3
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Table C-1 (Cont'd)

TABLE NOTATION

ACTION 1 - With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases may continue provided that

prior to initiating a release:

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

requirements and

b. At least two technically qualified members of the Facility Staff

independently verify the release rate calculations and discharge line

valving;

Otherwise, suspend release of radioactive effluents via this pathway.

ACTION 2- With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided grab samples are analyzed for radioactivity at a lower limit

of detection as specified in Table D-1 for principle gamma emitters and 1-131

at least once per 12 hours.

NOTE: The Steam Generator blowdown monitor is normally used in a clean up closed loop

system instead of as an effluent monitor. The action statement only applies when

the monitor is used as an effluent monitor.

ACTION 3 -

ACTION 4 -

With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided that, at least once per 24 hours, grab samples are

collected and analyzed for radioactivity at a lower limit of detection as

specified in Table D-1 for principle gamma emitters and 1-131.

With the number of channels operable less than required by the Minimum

Operable Channels requirement, effluent releases via this pathway may

continue provided the flow rate is estimated at least once per 4 hours during

actual releases. Pump performance curves or tank levels may be used to

estimate flow.
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Table C-2

Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements

Instrument Channel Source Channel Functional IntuetCheck Check Calibration Tsctioa

1. GROSS RADIOACTIVITY MONITORS PROVIDING ALARM AND

AUTOMATIC TERMINATION OF RELEASE

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

b. Steam Generator Blowdown Effluent Line (RIA 0707) D M R(3) Q(1)(2)

2. GROSS GAMMA OR GAMMA RADIOACTIVITY MONITORS

PROVIDING ALARM BUT NOT PROVIDING AUTOMATIC

TERMINATION OF RELEASE

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

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

3. FLOW RATE MEASUREMENT DEVICES (5)

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

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

5I . STEAM NEER' ~.~¶II.~VYI~¶ ATOR BLOW II r~~I WSNSI .,JVMIA% COMPO ELUENT o~~L~~I_____ SAITLERZ () N ANA P.dIA NA I

16. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER |D(4) |NA | NA | N~A~
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Table C-2 (Cont'd)

TABLE NOTATION

(1) The Channel Functional Test shall also demonstrate that automatic isolation of this pathway occurs if instrument indicates

measured levels above the alarm/trip setpoint.

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

conditions exists:

a. Instrument indicates measured levels above the alarm setpoint.

b. Circuit failure.

(3) a. The Channel Calibration shall be performed using one or more of the reference standards traceable to the National

Institute of Standards and Technology or using standards that have been obtained from suppliers that participate in

measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended

range of energy and measurement range.

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

(4) Channel Check shall consist of verifying indication of flow during periods of releases. Channel Check shall be made at

least once per 24 hours on days on which continuous or batch releases are made.

(5) Turbine Sump Discharge Flow Meter FQI-5210 was calibrated at factory and doesn't require recalibration.

TABLE FREQUENCY NOTATION

D At least once per 24 hours

M At least once per 31 days

P Prior to radioactive batch release

Q At least once per 92 days

R At least once per 18 months

W At least once per week
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G. LIQUID EFFLUENTS CONCENTRATION

1. Requirement

The concentration of radioactive material released in liquid effluents to

Unrestricted Areas shall be limited to 10 times the concentrations

specified in 10CFR Part 20, Appendix B, Table 2, Column 2 for

radionuclides other than dissolved or entrained noble gases. For

dissolved or entrained noble gases, the concentration shall be limited

to 2 x 10-4 microcuries/ml total activity.

2. Action

With the concentration of radioactive material released in liquid

effluents to Unrestricted Areas exceeding the above limits, without

delay, restore the concentration to within the above limits.

3. Surveillance Requirements

a. Radioactive liquid wastes shall be sampled and analyzed

according to the sampling and analysis program of Tabla D-1.

b. The results of the radioactivity analysis shall be used in

accordance with the methodology and parameters in the ODCM

to assure that the concentrations at the point of release are

maintained within the limits of G.1 above.
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4. Bases

This requirement is provided to ensure that the concentration of

radioactive materials released in liquid waste effluents to Unrestricted

Areas will be less than 10 times the concentration levels specified in

10CFR Part 20, Appendix B, Table 2, Column 2. This limitation

provides additional assurance that the levels of radioactive materials in

bodies of water in Unrestricted Areas will result in exposures within the

Section ll.A design objectives of Appendix I, 10CFR Part 50, to a

Member of the Public. The concentration limit for dissolved or

entrained noble gases is based upon the assumption that Xe-135 is

the controlling radioisotope and 10 times the effluent concentration in

air (submersion) was converted to an equivalent concentration in water

using the methods described in International Commission on

Radiological Protection (ICRP) Publication 2.

The required detection capabilities for radioactive materials in liquid

waste samples are tabulated in terms of the lower limits of detection

(LLDs). Detailed discussion of the LLD and other detection limits can

be found in HASL Procedures Manual, HASL-300, Currie, LA, "Limits

for Qualitative Detection and Quantitative Determination - Application

to Radiochemistry," Anal Chem 40, 586-93 (1968), and Hartwell, JK,

"Detection Limits for Radioanalytical Counting Techniques," Atlantic

Richfield Hanford Company Report ARH-SA-215 (June 1975).
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Table D-1

Radioactive Liauid Waste Samnlina and Analvsis Proaram

Liquid Release Type Sampling Minimum Type of Lower Limit

Frequency Analysis Activity Analysis Detection (LLD)a Frequency (PCiml)

A. Batch Waste Release Tanksb P p Principal Gamma Emittersc 5 x 10'7

Each Batch Each Batch 1-131 1 x 104

P M Dissolved and Entrained Gases 1 x 105|

One Batch/M (Gamma Emitters)

P M H-3 1 x 10oEach Batch Composited Gross Alpha 1 x 10 '

P Q Sr-89, Sr-90 5 x 10l

Each Batch Composited .

B. Continuous Releases" Continuousf W Principal Gamma Emittersc 5 x 10i7

(Turbine Sump, Steam Generator Compositef 1-131 1 x 104

6

Blowdown, and Service Water)

M M Dissolved and Entrained Gases

Grab Sample (Gamma Emitters) 1 x l0o5

Continuousf M H-3 1 x 10o-

. Compositef Gross Alpha I x 10'T

Continuousf Q Sr-89, Sr-90 5 x 1048

._ Compositef

Frequency Notation

P Prior to batch reiease

M Calendar month

Q Calendar quarter

W Calendar week
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Table D-1 (Cont'd)

TABLE NOTATION

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

b A batch release is the discharge of liquid wastes of a discrete volume. Prior to

sampling for analyses, each batch shall be isolated and then thoroughly mixed to

assure representative sampling.

C The principal gamma emitters for which the LLD specification applies exclusively are

the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99*, Cs-134,

Cs-137, Ce-141, and Ce-144*. This list does not mean that only these nuclides are

to be considered. Other gamma peaks that are identifiable, together with those of

the above nuclides, shall also be analyzed and reported in the Radioactive Effluent

Release Report.

*LLD - 5E-06 because of low gamma yields.

d A composite sample is one in which the quantity of liquid sampled is proportional to

the quantity of liquid waste discharged and in which the method of sampling

employed results in a specimen that is representative of the liquids released.

e A continuous release is the discharge of liquid wastes of a nondiscrete volume;

eg, from a volume of a system that has an input flow during the continuous release.

To be representative of the quantities and concentrations of radioactive materials in

liquid effluents, samples shall be collected in a series of aliquots of constant volume

collected at regular time intervals and combined to form a single sample. Prior to

analyses, all samples taken for the composite shall be thoroughly mixed in order for

the composite sample to be representative of the effluent release.
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H. LIQUID EFFLUENT DOSE

1. Requirement

The dose or dose commitment to a Member of the Public from

radioactive materials in liquid effluents released from each reactor unit

to Unrestricted Areas shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems

to the total body and to less than or equal to 5 mrems to any

organ, and

b. During any calendar year to less than or equal to 3 mrerns to

the total body and to less than or equal to 10 mrems to any

organ.

2. Action

With the calculated dose from the release of radioactive materials in

liquid effluents exceeding any of the above limits, prepare and submit

to the NRC within 30 days a Special Report that identifies the cause(s)

for exceeding the limit(s) and defines the corrective actions that have

been taken to reduce the releases and the proposed corrective actions

to be taken to assure that subsequent releases will be in compliance

with the above limits. This Special Report shall also include the results

of radiological analyses of the drinking water source.

3. Surveillance Requirements

Cumulative dose contributions from liquid effluents for the current

calendar quarter and the current calendar year shall be determined in

accordance with the methodology and parameters in the ODClM at

least once every 31 days.
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4. Bases

This requirement is provided to implement the requirements of

Sections IL.A, Il.A, and IV.A of Appendix I, 10CFR Part 50. The

Limiting Condition for Operation implements the guides set forth in

Section I.A of Appendix I. The Action statements provide the required

operating flexibility and at the same time implement the guides set

forth in Section IV.A of Appendix I to assure that the releases of

radioactive material in liquid effluents to Unrestricted Areas will be kept

"as low as is reasonably achievable." Also, for freshwater sites, with

drinking water supplies that can be potentially affected by Plant:

operations, there is reasonable assurance that the operation of the

facility will not result in radionuclide concentrations in the finished

drinking water that are in excess of the requirements of 40CFR

Part 141. The dose calculation methodology and parameters in the

ODCM implement the requirements in Section 1ll.A of Appendix I that

conformance with the guides of Appendix I be shown by calculational

procedures based on models and data, such that the actual exposure

of a Member of the Public through appropriate pathways is unlikely

to be substantially underestimated. The equations specified in the

ODCM for calculating the doses due to the actual release rates of

radioactive materials in liquid effluents are consistent with the

methodology provided in Regulatory Guide 1.109, "Calculation of

Annual Doses to Man From Routine Releases of Reactor Effluents

for the Purpose of Evaluating Compliance with 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.
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TOTAL DOSE

1. Requirement

The annual (calendar year) dose or dose commitment to any Member

of the Public due to releases of radioactivity and to radiation from

uranium fuel cycle sources shall be limited to less than or equal to

25 mrems to the total body or any organ, except the thyroid, which

shall be limited to less than or equal to 75 mrems.

2. Action

With the calculated doses from the release of radioactive materials in

liquid or gaseous effluents exceeding twice the limits of III.C.1.a,

IlI.C.1.b, IlI.D.1.a, IlI.D.1.b, 11l.H.1.a, or 1ll.H.1.b, calculations should be

made including direct radiation contributions from the reactor units and

from outside storage tanks to determine whether the above limits of

111.1.1 have been exceeded. If such is the case, prepare and submit to

the NRC within 30 days a Special Report that defines the corrective

action to be taken to reduce subsequent releases to prevent

recurrence of exceeding the above limits and includes the schedule for

achieving conformance with the above limits. This Special Report, as

defined in 1 OCFR Part 20.2203, shall include an analysis that

estimates the radiation exposure (dose) to a Member of the Public

from uranium fuel cycle sources, including all effluent pathways and

direct radiation, for the calendar year that includes the release(s)

covered by this report. It shall also describe levels of radiation and

concentrations of radioactive material involved and the cause of the

exposure levels or concentrations. If the estimated dose(s) exceeds

the above limits, and if the release condition resulting in violation of

40CFR Part 190 has not already been corrected, the Special Report

shall include a request for a variance in accordance with the provisions

of 40CFR Part 190. Submittal of the report is considered a timely

request and a variance is granted until staff action on the request is

complete.
1, _ "_

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3. Surveillance Requirements

a. Cumulative dose contributions from liquid and gaseous effluents

shall be determined in accordance with III.C.1, Il.D.1, and

lll.H.1 and in accordance with the methodology and parameters

in the ODCM.

b. Cumulative dose contributions from direct radiation from the

reactor units and from radwaste storage tanks shall be

determined in accordance with the methodology and

parameters in the ODCM. This requirement is applicable only

under conditions set forth in Action 1.2 above.
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4. Bases

This requirement is provided to meet the dose limitations of

40CFR Part 190 that have been incorporated into 1 OCR Part :20 by

46 FR 18525. It also requires the preparation and submittal of a

Special Report whenever the calculated doses from Plant generated

radioactive effluents and direct radiation exceed 25 mrems to the total

body or any organ, except for thyroid, which shall be limited to less

than or equal to 75 mrems. For sites containing up to 4 reactors, it is

highly unlikely that the resultant dose to a Member of the Public will

exceed the dose limits of 40CFR Part 190 if the individual reactors

remain within twice the dose design objectives of Appendix I arid if

direct radiation doses from the reactor units and outside storage tanks

are kept small. The Special Report will describe a course of action that

should result in the limitation of the annual dose to a Member of the

Public to within the 40CFR Part 190 limits. For the purposes of the

Special Report, it may be assumed that the dose commitment to the

Member of the Public from other uranium fuel cycle sources is

negligible, with the exception that dose contributions from other

nuclear fuel cycle facilities at the same site or within a radius of 8 km

must be considered. If the dose to any Member of the Public is

estimated to exceed the requirements of 40CFR Part 190, the Special

Report with a request for a variance (provided the release conditions

resulting in violation of 40CFR Part 190 have not already been

corrected), in accordance with the provisions of 40CFR Part 190.11

and 1 OUR Part 20.2203, is considered to be a timely request and

fulfills the requirements of 40CFR Part 190 until NRC staff action is

completed. The variance only relates to the limits of 40CFR Part 190

and does not apply in any way to the other requirements for dose

limitation of 10CFR Part 20. An individual is not considered a Member

of the Public during any period in which he/she is engaged in carrying

out any operation that is part of the nuclear fuel cycle.
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J. RADIOLOGICAL ENVIRONMENTAL MONITORING

1. Requirement

The radiological environmental monitoring program shall be conducted

as specified in Table E-1.

2. Action

a. With the radiological environmental monitoring program not

being conducted as specified in Table E-1, prepare and submit

to the NRC, in the Annual Radiological Environmental Operating

Report a description of the reasons for not conducting the

program as required and the plans for preventing a recurrence.

b. With the level of radioactivity as the result of Plant effluents in

an environmental sampling medium at a specified location

exceeding the reporting levels of Table E-2 when averaged over

any calendar quarter, prepare and submit to the NRC within

30 days a Special Report that identifies the cause(s) for

exceeding the limit(s) and defines the corrective actions to be

taken to reduce radioactive effluents. When more than one of

the radionuclides in Table E-2 are detected in the sampling

medium, this report shall be submitted if:

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

Reporting Level (1) Reporting Level (2)

When radionuclides other than those in Table E-2 are detected

and are the result of Plant effluents, this report shall be

submitted if the potential annual dose to a Member of the Public

is equal to or greater than the calendar year limits of 111.C.1,

III.D.1, and lll.H.1. This report is not required if the measured

level of radioactivity was not the result of Plant effluents;

however, in such an event, the condition shall be reported and

described in the Annual Radiological Environmental Operating

Report.
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c. With milk or fresh leafy vegetable samples unavailable from one

or more of the sample locations required by Table E-1, identify

locations for obtaining replacement samples and add them to

the radiological environmental monitoring program within

30 days. The specific locations from which samples were

unavailable may then be deleted from the monitoring program.

Identify the cause of the unavailability of samples and identify

the new location(s) for obtaining replacement samples ill the

next Annual Radiological Environmental Report.

3. Surveillance Requirements

a. The radiological environmental monitoring samples shall be

collected pursuant to Table E-1 and shall be analyzed pursuant

to the requirements of Table E-1 and the detection capabilities

required by Table E-3.

b. A land use census shall be conducted and shall identify within a

distance of 8 km (5 miles) the location in each of the 9 overland

meteorological sectors of the nearest milk animal, the nearest

residence and the nearest garden of greater than 50 m2 (500 ft2)

producing broad leaf vegetation.

c. The land use census shall be conducted during the growing

season at least once per 12 months using that information that

will provide the best results, such as by a door-to-door survey,

aerial survey, or by consulting local agriculture authorities. The

results of the land use census shall be included in the Annual

Radiological Environmental Operating Report and shall be

included in a revision of the ODCM for use in the following

calendar year.

d. Analyses shall be performed on radioactive materials supplied

as part of an Interlaboratory Comparison Program that has been

approved by the NRC.
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e. A summary of the results obtained as part of the above required

Interlaboratory Comparison Program shall be included in the

Annual Radiological Environmental Operating Report.

f. The environmental air samplers shall be operationally cfecked

monthly and airflow verified annually.

4. Bases

a. Monitoring Program

The radiological environmental monitoring program provides

representative measurements of radiation and of radioactive

materials in those exposure pathways and for those

radionuclides that lead to the highest potential radiation

exposures of Members of the Public resulting from the station

operation. This monitoring program implements Section IV.B.2

of Appendix I to 10CFR Part 50 and thereby supplements the

radiological effluent monitoring program by verifying that the

measurable concentrations of radioactive materials and levels of

radiation are not higher than expected on the basis of the

effluent measurements and the modeling of the environmental

exposure pathways. Guidance for this monitoring program is

provided by the Radiological Assessment Branch Technical

Position on Environmental Monitoring. The initially specified

monitoring program will be effective for at least the first

three years of commercial operation. Following this period,

program changes may be initiated based on operational

experience.

The required detection capabilities for environmental sample

analyses are tabulated in terms of the lower limits of detection

(LLDs). The LLDs required by Table E-3 are considered

optimum for routine environmental measurements in industrial

laboratories.

Detailed discussion of the LLD, and other detection limits, can

be found in HASL Procedures Manual, HASL-300, Currie, LA,

"Limits for Qualitative Detection and Quantitative

Determination - Application to Radiochemistry," Anal Cham 40,

586-92 (1968), and Hartwell, JK, "Detection Limits for

Radioanalytical Counting Techniques," Atlantic Richfield

Hanford Company Report ARH-SA-1 5 (June 1975).
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b. Land Use Census:

This requirement is provided to ensure that changes in the use

of areas at and beyond the site boundary are identified and that

modifications to the radiological environmental monitoring

program are made if required by results of this census. The

best information from the door-to-door survey, from aerial

survey or from consulting with local agricultural authorities shall

be used. This census satisfies the requirements of

Section IV.B.3 of Appendix I to 10CFR Part 50. Restricting the

census to gardens of greater than 50 m2 provides assurance

that significant exposure pathways via leafy vegetables will be

identified and monitored since a garden of this size is the

minimum required to produce the quantity (16 kg/yr) of leafy

vegetables assumed in Regulatory Guide 1.109 for consumption

by a child.

To determine this minimum garden size, the following

assumptions were made: (1) 20% of the garden was used

for growing broad leaf vegetation (ie, similar to lettuce and

cabbage), and (2) a vegetation yield of 2 kg/M2.

c. Interlaboratory Comparison Program:

The requirement for participation in an approved Interlaboratory

Comparison Program is provided to ensure that independent

checks on the precision and accuracy of the measurements of

radioactive material in environmental sample matrices are

performed as part of the quality assurance program for

environmental monitoring in order to demonstrate that the

results are valid for the purposes of Section IV.B.2 of Appendix I

to 1OCFR Part 50.
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Table E-1

Radiological Environmental Monitoring Program

Exposure Pathway Number of Representative Sampling and Type of Frequency

and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis

1. DIRECT RADIATIONb 21 routine monitoring stations either with two or Quarterly Gamma dose quarterly

more dosimeters or with one instrument for

measuring and recording dose rate continuously,

placed as follows:

An inner ring of stations, one in each overland

meteorological sector (9) in the general area of

the Site Boundary.

An outer ring of stations, one in each overland

meteorological sector (9) within the 12 km range

from the site.

The balance of the stations (3) to be placed to

serve as control stations.
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Exposure Pathway Number of Representative Sampling and Type of Frequency and/or Sample Samples and Sample Locations' Collection Frequency of Analysis

2. AIRBORNE

Radioiodine and Samples from 5 locations. Continuous sample Radioiodine Canister:

Particulates operation with sample 1-131 analysis weekly for

3 samples from within 6 km of the Site Boundary collection weekly or more each filter change. in different sectors (2.4 km-SSW, 5.6 km-ESE, frequently if required by

and 1.6 km-N). dust loading. Particulate Sampler:

Gross beta radioactivity 1 sample from the vicinity of a community having analysis following filter

the highest calculated annual average ground change d. Gamma isotopic level D/Q (Covert-5.6 km-SE). analysis if gross beta

>1.0 pCi/m . 1 sample from a control location in the least

prevalent wind directionc (Grand Rapids

89 km-NNE).

3. WATERBORNE

a. Lake (surface) Plant lake water inlet. Composite sample over Gross beta (>10 pCi/I

1-month period'. requires gamma) and tritium

monthly.

b. Lake (drinking) 1 sample of South Haven drinking water supply. Composite sample over Gross beta (>10 pCi/I

1-month period'. requires gamma) and tritium

monthly.

c. Sediment from 1 sample from between north boundary and Van Semiannually Gamma isotopic analysis shoreline Buren State Park beach, approximately Y2 mile semiannually.

north of the Plant discharge. l

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Exposure Pathway Number of Representative Sampling and Type of Frequency

and/or Sample Samples and Sample Locationsa Collection Frequency of Analysis

4. INGESTION NOTE: Currently there are no dairy farms within a

distance of 5-8 km from the Plant; however, milk

samples will be obtained at 3 locations within a

distance of 15 km whenever available. When milk

samples are collected, broad leaf vegetation

sampling is not required.

a. Milk Samples from milking animals in 3 locations Monthly Gamma isotopic0 and 1-131

between 5-8 km distance. analysis monthly.

1 sample from milking animals at a control location,

15-30 km distance.

NOTE: Samples of 3 different kinds of broad leaf Sample in season or Gamma isotopic0 and 1-131

vegetation grown nearest each of two different semiannually if they are analysis.

offsite locations of highest predicted annual average not seasonal.

ground level D/Q if milk sample is not performed.

(SE or SSE sectors near site.)

1 sample of each of the similar broad leaf vegetation Monthly when available Gamma isotopic and 1-131

grown 15-30 km distance in the least prevalent wind analysis.

direction if milk sampling is not performed. (SSW or

S sectors.)

b. Fish Sample 2 species of commercially and/or Sample in season or Gamma isotopic analysis' on

recreationally important species in vicinity of Plant semiannually if they are edible portions.

discharge area. 1 sample of same species in areas not seasonal.

not influence by Plant discharge.

Food Products 1 sample each of two principal fruit crops At time of harvest Gamma Isotopic! and 1-131

c (blueberries and apples). analysis. I
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Table E-1 (Cont'd)

Table Notation

a Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability,

malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction,

every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be

documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to

obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosen for

the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program.

One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place, or in addition to,

integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors or

phosphor readout zones in a packet are considered as two or more dosimeters.

C The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind

direction criteria, other sites that provide valid background data may be substituted.

d Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours or more after sampling to allow for radon and thoron daughter

decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be

performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the

facility.

A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of

sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet this

criteria are acceptable).

9 If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
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Table E-2

Reporting Levels for Radioactivity Concentrations in Environmental Samples

Reporting Levels

Analysis Water Airborne Particulates Fish Milk Food Products

(pCi/l) or Gases (pCi/m3) (pCi/kg, Wet) (pCi/i) (pCi/kg, Wet)

H-3 20,000*

Mn-54 1,000 30,000

Fe-59 400 _ 10,000 l

Co-58 1,000 30,000 ._l

Co-60 300 10,000

Zn-65 300 20,000

Zr-Nb-95 400

1-131 2 0.9 3 100

Cs-134 30 10 1,000 60 1,000

Cs-1 37 50 20 2,000 70 2,000

Ba-La-140 200 300 _

* For drinking water samples.

be used.

This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may
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Table E-3

Detection Capabilities for Environmental Sample Analysisa

Lower Limit of Detection (LLD)bc

Water Airborne Particulates Fish Milk Food Products Sediment

Analysis (pCiIl) or Gases (pCi/m 3 ) (pCi/kg, Wet) (pCi/1) (pCi/kg, Wet) (pCi/kg, Dry)

Gross Beta 4 0.01 X

H-3 2,000* _

Mn-54 15 130

Fe-59 30 260 l

Co-58, 60 15 130 l

Zn-65 30 260 l

Zr-Nb-95 15 . ____l

1-131 1d 0.07 1 60

Cs-134 15 0.05 130 15 60 150

Cs-137 18 0.06 150 18 80 180

Ba-La-140 1 15 1 | j l _

* If no drinking water pathway exists, a value of 3,000 pCi/l may be used.

I
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Table E-3 (Cont'd)

TABLE NOTATION

a This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also

be analyzed and reported in the Annual Radiological Environmental Operating Report.

b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements are given in Regulatory Guide 4.13.

C The LLD is defined as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be

detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system, which may include radiochemical separation:

LLD = 4.66.

b

E V 2.22 Y Exp (-AAt)

Where:

LLD is the "a priori" lower limit of detection as defined above, as picocuries per unit mass or volume.

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, as counts per minute.

E is the counting efficiency, as counts per disintegration.

V is the sample size in units of mass or volume.

2.22 is the number of disintegrations per minute per picocurie.

Y is the fractional radiochemical yield, when applicable.

i fk n rdi-active deca- constant for the -anri,,,6r rndioneiu.ida

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.
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Table E-3 (Cont'd)

Table Notation

It should be recognized that the LLD is defined as an "a priori" (before the fact) limit representing the capability of a measurement system and not as an

"a posteriori" (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine

conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may

render these LLDs unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating

Report.

d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
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K. SIRW OR TEMPORARY LIQUID STORAGE TANK

1. Requirement

The concentration of radioactive material contained in the SIRW tank

or any unprotected outside temporary tank* shall be limited such that

the mixture radionuclides do not exceed 1,000 times the effluent

concentration (EC) as listed in 1 OCFR Part 20, Appendix B, Table 2,

Column 2.

Ca + Ctb...+gi = <1000

ECa ECb EC1

2. Action

With the quantity of radioactive material in any of the above listed

tanks exceeding the above concentration, immediately suspend all

additions of radioactive material to the tank, within 48 hours reduce the

tank contents to within the limit, and describe the events leading to this

condition in the next Radiological Effluent Release Report.

3. Surveillance Requirement

The concentration of radioactive material contained in each of the

above listed tanks shall be determined to be within the above limit by

analyzing a representative sample of the tank's contents at least once

per 7 days when radioactive materials are being added to the tank.

or

A calculational methodology performed prior to the material being

transferred may be used to show compliance with the requirement of

this section if a representative sample cannot be obtained at least once

per seven days. A representative sample of the radioactive material to

be added to the SIRW or Temporary Liquid Storage Tank shall be

analyzed and a calculation performed to show compliance with the

1000 EC limit.
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4. Bases

This requirement will provide reasonable assurance that in the event

of an uncontrolled release of the tanks' contents, the resulting

concentrations would be less than the limits of 1OCFR Part 20,

Appendix B, Table 2, Column 2, at the nearest potable water

supply and the nearest surface water supply in an Unrestricted Area.

(The dilution between Palisades and the South Haven drinking water

supply has been established as 1000.)

*Tanks included in this specification are those outdoor tanks that are riot

surrounded by liners, dikes, or walls capable of holding the tank contents and

that do not have tank overflows and surrounding area drains connected to the

liquid radwaste treatment system.

NOTE: The limit for the SIRW Tank may be exceeded for operational flexibility if the

conditions of this section are met.

L. SURVEILLANCE REQUIREMENT TIME INTERVALS

1. Requirement

Each Surveillance Requirement shall be performed within the specified

surveillance interval with a maximum allowable extension not to

exceed 25 percent of the specified surveillance interval.

2. Action

Failure to perform a Surveillance Requirement within the allowed

surveillance interval shall constitute noncompliance with the operability

requirements. The time limits of the action requirements are applicable

at the time it is identified that a Surveillance Requirement has riot been

performed. The action requirements may be delayed for up to

24 hours to permit the completion of the surveillance when the allowed

outage time limits of the action requirements are less than 24 hours.

Surveillance Requirements do not have to be performed on inoperable

equipment.
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3. Surveillance Requirements

The applicable surveillance interval frequencies are specified in

Tables A-2 and C-2. The applicable sampling and/or analysis

frequencies are specified in Tables A-1, B-1, C-1, D-1, and E-1.

Extendable surveillance requirements are limited to Channel Checks,

Source Checks, Channel Calibrations, Channel Functional Checks,

sampling frequencies and/or analysis frequencies.

4. Bases

The maximum allowable extension for a surveillance interval is

consistent with the surveillance requirements specified in the Technical

Specifications, Section 4.0. Until relocated in the ODCM, all of the

effluent surveillances were subject to these same requirements.

M. SEALED SOURCE CONTAMINATION

1. Requirement

Each sealed source containing radioactive material either in excess

of 100 microcuries of beta and/or gamma emitting material or

5 microcuries of alpha emitting material shall be free of greater than

or equal to 0.005 microcuries of removable contamination.

2. Action

a. With a sealed source having removable contamination in excess

of 0.005 microcuries, immediately withdraw the sealed source

from use and either:

(1) Decontaminate and repair the sealed source, or

(2) Dispose of the sealed source in accordance with

applicable regulations.

b. A report shall be prepared and submitted to the Commission on

an annual basis if sealed source leakage tests reveal the

presence of greater than or equal to 0.005 microcuries of

removable contamination.
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3. Surveillance Requirements

a. Each category of sealed sources as described in the

requirement with a half-life greater than 30 days (excluding

Hydrogen-3), and in any other form than gas, shall be tested for

leakage and/or contamination at intervals not to exceed

6 months.

b. The test shall be performed by the licensee or by other persons

specifically authorized by the Commission or an Agreement

State. The test method shall have a detection sensitivity of at

least 0.005 microcuries per test sample.

c. The test sample shall be taken from the sealed source or, in the

case of permanently mounted sources, from the surfaces of the

mounting device on which contamination would be expected to

accumulate.

d. The periodic leak test does not apply to sealed sources that are

stored and not being used. These sources shall be tested prior

to use or transfer to another licensee, unless tested within the

previous 6 months. Sealed sources which are continuously

enclosed within a shielded mechanism (ie, sealed sources

within radiation monitoring or boron measuring devices) are

considered to be stored and need not be tested unless they are

removed from the shielded mechanism.

e. Sealed sources transferred without a certificate indicating the

last test date shall be tested prior to being placed in use.
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4. Bases

The requirement, actions, and surveillance requirements are the same

as contained in the Technical Specifications 6.21 prior to relocation to

the ODCM and will provide assurance that sealed sources are tested

to demonstrate that source integrity is being maintained.

IV. REPORTING REQUIREMENTS

A. RADIOLOGICAL EFFLUENT RELEASE REPORT

The Radioactive Effluent Release Report shall be submitted in accordance

with 10CFR 50.36a by March 31 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 10CFR 50.36a and Section WV.E.1 of

Appendix I to 10CFR 50.

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.

These estimates 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 gaseous waste tank and from a minimum of one

typical liquid waste tank. For noble gases released to the atmosphere from

other than the waste gas system the error term will be estimated (and

weight-averaged with the waste gas tank error) based on a statistical analysis

of a series of sample results taken once a year (or the stack gas monitor

counting statistics taken over one release per year) from each source

contributing more than 10% of the total annual release.

The error term for iodine and particulates released to the atmosphere will be

based on the counting statistics for one stack gas sample taken during the

year.
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The report shall include an estimate of the lower level of detection (in pCilml)

if the unidentified portion of the release exceeds 10% of the total annual

releases. This estimate of the lower level of detection will be made for those

gamma emitting isotopes listed in Appendix B of Regulatory Guide 1.21

(June 1974) and will be provided based on a typical background gamma

spectrum.

The report shall provide the following specific terms:

1. Supplemental Information

a. Batch Releases:

The report should provide information relating to batch releases

of liquid and gaseous effluents which are discharged to the

environment. This information should include the number of

releases, total time period for batch releases, and the maximum,

mean, and minimum time period of release.

b. Abnormal Releases

The number of abnormal releases of radioactive material to the

environment should be reported. The total curies of radioactive

materials released as a result of abnormal releases should be

included.

2. Gaseous Effluents

a. Gases

(1) Total curies of fission and activation gases releases.

(2) Average release rates (pCi/s) of fission and activation

gases for the quarterly periods covered by the report.

(3) Percent of limit for releases of fission and activation

gases.

(4) Quarterly sums of total curies for each of the

radionuclides determined to be released, based con

analyses of fission and activation gases.
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b. lodines

(1) Total curies of each of the isotopes, Iodine-131,

lodine-133, and Iodine-135 determined to be released.

(2) Average release rate (pCi/s) of lodine-131/133.

(3) Percent of limit for lodine-131/133.

C. Particulates

(1) Total curies of radioactive material in particulate form

with half-lives greater than 8 days determined to be

released.

(2) Average release rate (pCi/s) of radioactive material in

particulate form with half-lives greater than 8 days.

(3) Percent of limit for radioactive material in particulate form

with half-lives greater than 8 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 determined to be

released.

d. Tritium

(1) Total curies of tritium determined to be released in

gaseous effluents.

(2) Average release rate (pCils) of tritium.

(3) Percent of applicable limits for tritium.
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3. 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-emilting

material).

(2) Average concentrations (pCi/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 (pCi/ml) of tritium released in

liquid effluents 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

(1) Total curies of gaseous radioactive material determined

to be released in liquid effluents.

(2) Average concentrations (pCi/ml) of dissolved and/or

entrained gaseous radioactive material released to

unrestricted areas, averaged over the quarterly periods

covered by the report.
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(3) Percent of applicable limit of average concentrations

released to unrestricted areas.

(4) Total curies for each of the radionuclides determined to

be released as dissolved and/or entrained gases in liquid

effluents.

d. Alpha Radioactivity

Total curies of gross alpha-emitting material determined to be

released in liquid effluents.

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.

4. 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 in

the ODCM.

a. Total body and significant organ doses (greater than 1 millirem

to individuals in unrestricted areas from receiving water-related

exposure pathways.

b. The maximum offsite air doses (greater than 1 millirad) due to

beta and gamma radiation at locations near ground level from

gaseous effluents.

c. Organ doses (greater than 1 millirem) to individuals in

unrestricted areas from radioactive iodine and radioactive

material in particulate form from the major pathways of

exposure.
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d. Total body doses (greater than 1 manrem) to the population and

average doses (greater than 1 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 1 manrem) to the population and

average doses (greater than 1 millirem) to individuals in the

population from gaseous effluents to a distance of 50 miles from

the site.

5. ODCM Changes

The Radiological Effluent Release Report shall include any changes

made during the reporting period to the Offsite Dose Calculation

Manual (ODCM), as well as a listing of new locations for dose

calculations and/or environmental monitoring identified by the land use

census pursuant to IlI.J.3.c.

B. RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

The Radiological Environmental Operating Report covering the operation of

the unit during the previous calendar year shall be submitted before May 1 of

each year. The report shall include summaries, interpretations, and analysis

of trends of the results of the Radiological Environmental Monitoring F'rogram

for the reporting period. The material provided shall be consistent with the

objectives outlined in: (1) the ODCM, and (2) Sections IV.B.2, IV.B.3, and

IV.C of Appendix 1 to 10CFR50.

The Annual Radiological Environmental Operating Reports shall include

summaries, interpretation and statistical evaluation of the results of the

radiological environmental surveillance activities for the report period,

including a comparison with preoperational studies, operational controls

(as appropriate), and previous environmental surveillance reports and an

assessment of the observed impacts of the Plant operation on the

environment. The reports shall also include the results of land use census

pursuant to IlI.J.3.c.
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The Annual Radiological Environmental Operating Reports shall include

summarized and tabulated results in the format of Table F-1 of all radiological

environmental samples taken during the report period. In the event that some

results are not available for inclusion with the report, the report shall be

submitted noting and explaining the reasons for the missing results. The

missing data shall be submitted as soon as possible in a supplementary

report.

The reports shall also include the following; a summary description of the

radiological environmental monitoring program, including sampling methods

for each sample type, a map of all sampling locations keyed to a table giving

distances and directions from the reactor and the results of land use census

required by lIl.J.3.c and results of the Interlaboratory Comparison Program

required by IlI.J.3.e.

C. NONROUTINE REPORTS

A report shall be submitted to the NRC in the event that: 1) the Radiological

Environmental Monitoring Programs are not substantially conducted as

described in Section lll.J, or 2) an unusual or important event occurs from

Plant operation that causes a significant environmental impact or affects a

potential environmental impact. Reports shall be submitted within 30 days.
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Table F-1

Environmental Radiological Monitoring Program Summary

Name of Facility Docket No

Location of Facility

(Conntv- State) Reporting Period_

Medium or Pathway Type/Total Lower Limit All Indicator b Control Locations Number of

| (Unit of Measure) | NDeutectifon | Mean Distance & Direction Range Rang-e OCCR EN

SaitofMpedsre Performed Anlss DtRin (LLD) Range ea aeMa ~ Mangel REO RTABLENE ________ _______

Air Particulates Gross 13 416 0.003 0.08 Middletown 0.10 (5/52) 0.08 (8/104- 1

(pCi/M3) (200/312) 5 miles 3400 (0.08-2.0) (0.05-1.40)

y-Spec 32 (0.05-2.0)

Cs-137 0.003 0.05 (4/24) Smithville 0.08 (2/4) <LLD 4

(0.03-0.13) 2.5 miles 1600 (0.03-0.13)

Ba-140 0.003 0.03 (2/24) Podunk 0.05 (2/4) 0.02 (1/8) 1

(0.01-0.08) 4 miles 2700 (0.01-0.08)

Sr-89 40 0.002 <LLD <LLD 0

Sr-90 40 0.0003 <LLD _ <LLD 0

Fish y-Spec 8

pCi/kg (dry weight) <LLD

lCs-137 80 <LD_<LLD 90 (1/4) 0

<LLD

Cs-134 80 1 <LLD <LLD 0

120 (314)

Co-60 80 (90-200) River Mile 35 See <LLD 0

Podunk River Column 4

a Nominal Lower Limit of Detection (LLU) as defined in table notation c of Table E-3.

b Mean and range based upon detectable measurements only. Fraction of detectable measurements at specific locations is indicated in parentheses (f).

NOTE: The example data are provided for illustrative purposes only.
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V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE

TREATMENT SYSTEMS

A. LICENSEE MODIFICATIONS

Licensee initiated major modifications to the radioactive liquid and gaseous

waste systems.

1. Shall be reported to the NRC pursuant to 1OCFR 50.59. The

discussion of each modification shall contain:

a. A summary of the evaluation that led to the determination that

the modification could be made in accordance with

IOCFR Part 50.59.

b. A description of the equipment, components and processes

involved, and the interfaces with other Plant systems.

c. Documentation of the fact that the modification was reviewed

and found acceptable by the PRC.

2. Shall become effective upon review and acceptance by the Plant

General Manager.

B. DEFINITION OF MAJOR RADWASTE SYSTEM MODIFICATION

1. Purpose:

The purpose of this definition is to assure that this requirement will be

satisfied under clearly identifiable circumstances, and with the

objective that current radwaste system capabilities are not jeopardized.
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2. Definition:

A major radwaste system modification is a modification which would

remove (either by bypassing for greater than 7 days or physical

removal) or replace with less efficient equipment, any components of

the radwaste system:

a. Letdown filters or demineralizers.

b. Vacuum degassifier (not applicable when the reactor is i'n cold

shutdown and depressurized).

c. Miscellaneous or clean waste evaporators.

d. The present waste gas compressor/decay tank system.

e. Fuel Pool filters/demineralizers.

f. Radwaste polishing demineralizers.

g. Radwaste Solidification system.

Improvements or additions to improve efficiency will not be

considered major modifications unless a complete substitution

of equipment or systems is made with equipment of unrelated

design. Examples would be: 1) replacement of mechanical

degassifier with steam, jet degassifier, 2) replacement of waste

gas system with cryogenic system, 3) replacement of asphalt

solidification with cement system, and 4) change from deep

bead resins to Powdex, etc.