Text

2005 Annual Radioactive Effluent Release and Waste Disposal Report, Palisades
	ML060960466
Person / Time
Site:	Palisades
Issue date:	03/29/2006
From:	Harden P; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	FOIA/PA-2010-0209
	Download: ML060960466 (200)
	v • d • e

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.

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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 - 2.38E-05 millirad beta and 8.32E-06 millirad gamma Second Quarter - 4.51 E-05 millirad beta and 1.55E-05 millirad gamma Third Quarter - 5.79E-05 millirad beta and 1.98E-05 millirad gamma Fourth Quarter - 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 - 3.97E-02 millirem (child thyroid)

Second Quarter - 1.98E-02 millirem (child thyroid)

Third Quarter 2.21 E-02 millirem (child thyroid)

Fourth Quarter - 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 - 1.49E-01 person-rem and 1.13E-04 millirem Second Quarter- 7.30E-02 person-rem and 5.53E-05 millirem Third Quarter - 8.18E-02 person-rem and 6.20E-05 millirem Fourth Quarter - 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 - 1.42E-04 millirem (teen)

Second Quarter- 3.36E-04 millirem (adult)

Third Quarter - 1.09E-03 millirem (teen)

Fourth Quarter - 1.63E-03 millirem (teen)

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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.

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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. also contains the ODCM, Appendix A, Revision 11. There were no changes to Appendix A during 2005.

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ATTACHMENT 1 RADIOACTIVE EFFLUENT RELEASE REPORT BATCH RELEASES JANUARY - DECEMBER 2005 TABLE HP 10.5-1 GASEOUS Units 1st Otr 2nd Qtr 3rd Qtr 4 th 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 1st Qtr 2nd Qtr 3rd Qtr l 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 _ _% l 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 l _l_% l 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 3 rd 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 3 rd Qtr 4 th 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 1 st 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.

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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 l 7.68E-07 I 3.48E-03 l 5.46E-1t E. Volume of Waste Released (prior to dilution) R liters 1.42E+05 1.67E+05 l 2.70E+05 l 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 2 nd 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, Ni-63, Sr-90, Nb-95, Ag-1 1Om, 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 1Om, 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 102.72m 3 346.83 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 ODCM Required Gasemus Effluents Nuclide MDA (uCi/cc) LLD (uCi/c).

Mn-54 4.68E-14 1E-11 Co-58 2.03E-14 1E-11 Fe-59 5.66E-14 1E-11 Co-60 8.73E-1 4 1E-11 05-014-ST Zn-65 6.73E-14 1E-11 05-044-G Zr-95 4.48E-14 1E-11 Mo-99 1.29E-13 1E-11 1-131 2.07E-14 1E-12 1-133 2.23E-14 1E-12 Cs-134 3.85E-14 1E-11 Cs-137 5.53E-14 1E-11 Ce-1 41 2.69E-14 1E-11 Ce-1 44 1.16E-13 1E-11 Kr-87 8.63E-07 I E-04 Kr-88 1.25E-06 1E-04 Xe-133 5.21 E-07 1E-04 Xe-133m 2.OOE-06 1E-04 Xe-135 4.06E-07 1E-04 Xe-138 2.12E-06 1E-04 ODCM Required Liquid Effluents Nuclide MDA (uCi/ml) LLD uCi/ml Mn-54 4.08E-08 5E-07 Co-58 1.03E-07 5E-07 Fe-59 1.34E-07 5E-07 Co-60 1.87E-07 5E-07 Liquid Batch Release Zn-65 1.51 E-07 5E-07 05-032-R Mo-99 3.22E-07 5E-07 1-131 6.96E-07 1E-06 Cs-134 1.18E-07 5E-07 Cs-137 1.33E-07 5E-07 Ce-1 41 1.1 OE-07 5E-07 Ce-144 5.03E-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 ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCiicc microCiicc ANALY iCS RESOLUTiON COMPARiSON Al 9496-66 Ce-141 2.83E-05 2.77E-05 1.02 20 AGREEMENT SOLID Cr-51 1.06E-04 1.OOE-04 1.06 20 AGREEMENT 1 Liter Cs-134 1.66E-05 1.64E-05 1.01 20 AGREEMENT Vol. Cs-i 37 3.38E-05 3.18E-05 1.06 20 AGREEMENT 1000 mL Mn-54 2.29E-05 2.24E-05 1.02 20 AGREEMENT DET. 1 Fe-59 1.74E-05 1.64E-05 1.06 20 AGREEMENT Zn-65 2.82E-05 2.82E-05 1.00 20 AGREEMENT Co-60 2.43E-05 2.46E-05 0.99 20 AGREEMENT Co-58 1.40E-06 1.16E-06 1.21 20 AGREEMENT A19496-66 Ce-I141 2.81 E-05 2.77E-05 1.02 20 AGREEMENT SOLID Cr-51 1.31 E-04 1.OOE-04 1.31 20 AGREEMENT I Liter Cs-i 34 1.67E-05 1.64E-05 1.02 20 AGREEMENT Vol. Cs-I 37 3.34E-05 3.18E-05 1.05 20 AGREEMENT 1000 mL Mn-54 2.36E-05 2.24E-05 1.06 20 AGREEMENT DET. 2 Fe-59 1.62E-05 1.64E-05 0.99 20 AGREEMENT Zn-65 2.89E-05 2.82E-05 1.03 20 AGREEMENT Co-60 2.40E-05 2.46E-05 0.98 20 AGREEMENT Co-58 <1.92E-06 1.16E-06 20 Al 9496-66 Ce-141 2.75E-05 2.77E-05 0.99 20 AGREEMENT SOLID Cr-51 1.06E-04 1.OOE-04 1.06 20 AGREEMENT 1 Liter Cs-i 34 1.61 E-05 1.64E-05 0.98 20 AGREEMENT Vol. Cs-i 37 3.40E-05 3.18E-05 1.07 20 AGREEMENT 1000 mL Mn-54 2.25E-05 2.24E-05 1.01 20 AGREEMENT DET. 3 Fe-59 1.79E-05 1.64E-05 1.09 20 AGREEMENT

- .o't-u05 n on-L.ULL.U.J fC .4 A4 ~

A f- M C Ci At KM 1.01 Co-60 2.46E-05 2.46E-05 1.00 20 AGREEMENT Co-58 <1.62E-06 1.16E-06 20 2ND QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE ANALYSiS IIliui1UCix; *-,G uib so'dr1¶ALI, TI1,C e I MC70ni I I-Tlr~kl

. .v v II IJ fonlk DA DI Qr)

- - - - kk******************************************************.

A19497-66 Ce-141 2.86E-05 2.77E-05 1.03 20 AGREEMENT SIMULATED Cr-51 1.OOE-04 11.OOE-04 1.00 20 AGREEMENT I Liter Cs-I 34 1.66E-05 1.64E-05 1.01 20 AGREEMENT Vol. Cs-1 37 3.27E-05 3.1 9E-05 1.03 20 AGREEMENT 1000 cc Mn-54 2.36E-05 2.24E-05 1.05 20 AGREEMENT DET. 1 Fe-59 2.12E-05 1.64E-05 1.29 20 AGREEMENT Zn-65 2.29E-05 2.82E-05 0.81 20 AGREEMENT Co-60 2.68E-05 2.46E-05 1.09 20 AGREEMENT Co-58 1.30E-06 1.16E-06 1.12 20 AGREEMENT Al 9497-66 Ce-141 2.86E-05 2.77E-05 1.03 20 AGREEMENT SIMULATED Cr-51 1.14E-04 1.OOE-04 1.14 20 AGREEMENT 1 Liter Cs-134 1.57E-05 1.64E-05 0.96 20 AGREEMENT Vol. Cs-I 37 3.21 E-05 3.19E-05 1.01 20 AGREEMENT 1000 cc Mn-54 2.20E-05 2.24E-05 0.98 20 AGREEMENT DET. 2 Fe-59 2.08E-05 1.64E-05 1.27 20 AGREEMENT Zn-65 3.OOE-05 2.82E-05 1.06 20 AGREEMENT Co-60 2.37E-05 2.46E-05 0.96 20 AGREEMENT Co-58 <1.65E-06 1.16E-06 20 Al 9497-66 Ce-141 2.94E-05 2.77E-05 1.06 20 AGREEMENT SIMULATED Cr-51 1.09E-04 1.OOE-04 1.09 20 AGREEMENT I Liter Cs-1 34 1.64E-05 1.64E-05 1.00 20 AGREEMENT Vol. Cs-1 37 3.30E-05 3.19E-05 1.03 20 AGREEMENT 1000 cc Mn-54 2.38E-05 2.24E-05 1.06 20 AGREEMENT DET. 3 Fe-59 2.01 E-05 1.64E-05 1.23 20 AGREEMENT 2n-65 ') 1 14nV 92,9E-0j5 1.03 20 AGREEMENT Co-60 2.47E-05 2.46E-05 1.00 20 AGREEMENT Co-58 1.45E-06 1.16E-06 1.25 20 AGREEMENT 2ND QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

CARA.1 If A IAlI %fleIf*

1-4rL- I 0 nicroCiicc microClIcc ANALYTICS RESOLUTION COMPARISON A19498-66 Ce-141 4.56E-04 4.48E-04 1.02 20 AGREEMENT SOLID Cr-51 1.87E-03 0.002 1.15E+00 20 AGREEMENT Vol. Cs-1 34 2.41 E-04 0.000 9.07E-01 20 AGREEMENT 50 mL Cs-137 5.19E-04 5.16E-04 1.01 E+00 20 AGREEMENT DET. 1 Mn-54 3.59E-04 3.62E-04 0.99 20 AGREEMENT Fe-59 3.24E-04 0.000 1.22E+00 20 AGREEMENT Zn-65 4.45E-04 0.000 9.75E-01 20 AGREEMENT Co-60 3.62E-04 3.98E-04 9.09E-01 20 AGREEMENT Co-58 2.30E-05 1.88E-05 1.22 20 AGREEMENT Al 9498-66 Ce-141 4.43E-04 0.000 9.88E-01 20 AGREEMENT SOLID Cr-51 1.52E-03 1.62E-03 9.38E-01 20 AGREEMENT Vol. Cs-1 34 0.000 0.000 0.911 20.000 AGREEMENT 50 mL Cs-1 37 0.001 0.001 1.010 20.000 AGREEMENT DET. 2 Mn-54 0.000 0.000 0.983 20.000 AGREEMENT Fe-59 0.000 0.000 1.018 20.000 AGREEMENT Zn-65 0.000 0.000 0.988 20.000 AGREEMENT Co-60 0.000 0.000 0.914 20.000 AGREEMENT Co-58 0.000 0.000 0.914 20.000 AGREEMENT Al 9498-66 Ce-141 0.000 0.000 1.015 20.000 AGREEMENT SOLID Cr-51 0.002 0.002 0.962 20.000 AGREEMENT Vol. Cs-1 34 0.000 0.000 0.945 20.000 AGREEMENT 50 mL Cs-I 37 0.001 0.001 1.006 20.000 AGREEMENT DET. 3 Mn-54 0.000 0.000 0.997 20.000 AGREEMENT Fe-59 0.000 0.000 0.965 20.000 AGREEMENT 7n-65 A Ann 0.979 20.000 AGRtEMENT Co-60 0.000 0.000 0.939 20.000 AGREEMENT Co-58 0.000 0.000 1.106 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 ANALYTICS RATIO VALUE VALUE PALISADES:

CARADI C AKOAL'.e'SeO

_, ..... r1%114%L. I 131IQ ir1ruCi icc micro(;i /cc ANALYTICS RESOLUTION COMPARISON Al 9500-66 Ce-141 6.39E-02 6.34E-02 1.01 20 AGREEMENT CARTRIDGE Cr-51 1.OOE-01 1.02E-01 0.98 20 AGREEMENT DET. 1 Cs-1 34 1.77E-02 1.91 E-02 0.92 20 AGREEMENT SAIC Cs-1 37 3.16E-02 2.98E-02 1.06 20 AGREEMENT BG-300 Co-58 1.27E-02 1.26E-02 1.01 20 AGREEMENT Vol. 1 cc Mn-54 1.62E-02 1.49E-02 1.08 20 AGREEMENT Fe-59 1.52E-02 1.42E-02 1.07 20 AGREEMENT Zn-65 2.21 E-02 2.04E-02 1.09 20 AGREEMENT Co-60 2.53E-02 2.58E-02 0.98 20 AGREEMENT Al 9500-66 Ce-141 6.49E-02 6.34E-02 1.02 20 AGREEMENT CARTRIDGE Cr-51 1.01 E-01 1.02E-01 0.99 20 AGREEMENT DET. 2 Cs-1 34 1.88E-02 1.91 E-02 0.98 20 AGREEMENT SAIC Cs-137 3.32E-02 2.98E-02 1.11 20 AGREEMENT BG-300 Co-58 1.33E-02 1.26E-02 1.05 20 AGREEMENT Vol. 1 cc Mn-54 1.68E-02 1.49E-02 1.12 20 AGREEMENT Fe-59 1.58E-02 1.42E-02 1.11 20 AGREEMENT Zn-65 2.30E-02 2.04E-02 1.13 20 AGREEMENT Co-60 2.67E-02 2.58E-02 1.03 20 AGREEMENT Al 9500-66 Ce-141 6.74E-02 6.34E-02 1.06 20 AGREEMENT CARTRIDGE Cr-51 1.04E-01 1.02E-01 1.02 20 AGREEMENT DET. 3 Cs-134 1.83E-02 1.91 E-02 0.96 20 AGREEMENT SAIC Cs-1 37 3.28E-02 2.98E-02 1.10 20 AGREEMENT BG-300 Co-58 1.32E-02 1.26E-02 1.05 20 AGREEMENT Vol. 1 cc Mn-54 1.71 E-02 1.49E-02 1.14 20 AGREEMENT Fe-.59 .1 QAC A) AI A flI fP I.16 2U AGREEMENT Zn-65 2.34E-02 2.04E-02 1.15 20 AGREEMENT Co-60 2.66E-02 2.58E-02 1.03 20 AGREEMENT 3RD QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

SAML _ A1d41LL I0 10 i, ,itic uCi U ,,,-isouwi t;us A N ALT ii 1 S IM-OULU I UIVN CuMPARiSOuN Al 9501-66 Ce-1 41 1.12E-03 1.07E-03 1.05 20 AGREEMENT SIMULATED Cr-51 1.70E-03 1.71 E-03 1.00 20 AGREEMENT GAS Cs-i 34 3.06E-04 3.22E-04 0.95 20 AGREEMENT 25 cc Cs-i 37 5.49E-04 5.01 E-04 1.10 20 AGREEMENT VOL. 25cc Co-58 2.15E-04 2.12E-04 1.01 20 AGREEMENT DET. 1 Mn-54 2.73E-04 2.51 E-04 1.09 20 AGREEMENT Fe-59 2.54E-04 2.39E-04 1.06 20 AGREEMENT Zn-65 3.76E-04 3.42E-04 1.10 20 AGREEMENT Co-60 4.31 E-04 4.34E-04 0.99 20 AGREEMENT Al 9501-66 Ce-1 41 1.13E-03 1.07E-03 1.06 20 AGREEMENT SIMULATED Cr-51 1.76E-03 1.71 E-03 1.03 20 AGREEMENT GAS Cs-I 34 3.21 E-04 3.22E-04 1.00 20 AGREEMENT 25 cc Cs-I 37 5.59E-04 5.01 E-04 1.12 20 AGREEMENT VOL. 25cc Co-58 2.43E-04 2.12E-04 1.15 20 AGREEMENT DET. 2 Mn-54 2.91 E-04 2.51 E-04 1.16 20 AGREEMENT Fe-59 2.89E-04 2.39E-04 1.21 20 AGREEMENT Zn-65 3.93E-04 3.42E-04 1.15 20 AGREEMENT Co-60 4.61 E-04 4.34E-04 1.06 20 AGREEMENT Al 9501-66 Ce-141 1.14E-03 1.07E-03 1.07 20 AGREEMENT SIMULATED Cr-51 1.81 E-03 1.71 E-03 1.06 20 AGREEMENT GAS Cs-134 3.14E-04 3.22E-04 0.98 20 AGREEMENT 25cc Cs-i 37 5.63E-04 5.01 E-04 1.12 20 AGREEMENT VOL. 25cc Co-58 2.35E-04 2.12E-04 1.11 20 AGREEMENT DET. 3 Mn-54 2.91 E-04 2.51 E-04 1.16 20 AGREEMENT Fe-.59 2.66E-4A 2.39E-0fl '1 *11 O' A fl D C C KA C ITr Zn-65 3.85E-04 3.42E-04 1.12 20 AGREEMENT Co-60 4.57E-04 4.34E-04 1.05 20 AGREEMENT 3RD QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE ANALYSiS microCi icc microCi icc ANALYTi CS RESOLUTiON COMPARiSON Al 9502-66 Ce-141 6.47E-05 6.07E-05 1.07 20 AGREEMENT SAND Cr-51 1.OOE-04 0.000 1.03E+00 20 AGREEMENT 1 LITER Cs-I 34 1.91 E-05 0.000 1.04E+00 20 AGREEMENT VOL. Cs-I 37 3.20E-05 2.85E-05 1.12E+00 20 AGREEMENT 1i0Og Co-58 1.41 E-05 1.21 E-05 1.17 20 AGREEMENT DET. 1 Mn-54 1.61 E-05 0.000 1.13E+00 20 AGREEMENT Fe-59 1.30E-05 0.000 9.57E-01 20 AGREEMENT Zn-65 2.21 E-05 1.95E-05 1.13E+00 20 AGREEMENT Co-60 2.53E-05 2.47E-05 1.02 20 AGREEMENT Al 9502-66 Ce-141 6.41 E-05 0.000 1.06E+00 20 AGREEMENT SAND Cr-51 1.03E-04 9.72E-05 1.06E+00 20 AGREEMENT 1 LITER Cs-i 34 0.000 0.000 1.021 20.000 AGREEMENT VOL. Cs-i 37 0.000 0.000 1.055 20.000 AGREEMENT 1OOOg Co-58 0.000 0.000 1.060 20.000 AGREEMENT DET. 2 Mn-54 0.000 0.000 1.133 20.000 AGREEMENT Fe-59 0.000 0.000 0.957 20.000 AGREEMENT Zn-65 0.000 0.000 1.118 20.000 AGREEMENT Co-60 0.000 0.000 1.056 20.000 AGREEMENT Al 9502-66 Ce-141 0.000 0.000 1.036 20.000 AGREEMENT SAND Cr-51 0.000 0.000 1.060 20.000 AGREEMENT 1 LITER Cs-I 34 0.000 0.000 1.004 20.000 AGREEMENT VOL. Cs-i 37 0.000 0.000 1.087 20.000 AGREEMENT I OOOg Co-58 0.000 0.000 1.077 20.000 AGREEMENT DET. 3 Mn-54 0.000 0.000 1.119 20.000 AGREEMENT C rn A AAA 1 AO A - D1 I MC A CN IT vJ.vvvu Zn-65 0.000 0.000 1.047 20.000 AGREEMENT Co-60 0.000 0.000 1.020 20.000 AGREEMENT 3RD QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

QAKA,2. D!= AKA,

.% V,5.

X/LIL 1... Il micr.Ci I'c Inicroci icc ANALY-i IuS RESOLUTION COMPARISON AtADI CU CL.S Al 9503-66 Ce-141 0.063 0.062 1.017 20.000 AGREEMENT CARTRIDGE Cr-51 0.096 0.099 0.972 20.000 AGREEMENT DE-500 Cs-I 34 0.017 0.019 0.921 20.000 AGREEMENT LAPEL Cs-137 0.032 0.029 1.090 20.000 AGREEMENT VOL. Co-58 0.013 0.012 1.032 20.000 AGREEMENT I cc Mn-54 0.016 0.015 1.118 20.000 AGREEMENT DET. 1 Fe-59 0.014 0.014 1.033 20.000 AGREEMENT Zn-65 0.022 0.020 1.082 20.000 AGREEMENT Co-60 0.025 0.025 1.009 20.000 AGREEMENT Al 9503-66 Ce-141 0.064 0.062 1.038 20.000 AGREEMENT CARTRIDGE Cr-51 0.100 0.099 1.006 20.000 AGREEMENT SOLID Cs-1 34 0.018 0.019 0.953 20.000 AGREEMENT DE-500 Cs-1 37 0.032 0.029 1.111 20.000 AGREEMENT LAPEL Co-58 0.013 0.012 1.089 20.000 AGREEMENT VOL. Mn-54 0.017 0.015 1.139 20.000 AGREEMENT 1 cc Fe-59 0.017 0.014 1.199 20.000 AGREEMENT DET. 2 Zn-65 0.022 0.020 1.127 20.000 AGREEMENT Co-60 0.026 0.025 1.032 20.000 AGREEMENT Al 9503-66 Ce-1 41 0.065 0.062 1.057 20.000 AGREEMENT CARTRIDGE Cr-51 0.102 0.099 1.030 20.000 AGREEMENT SOLID Cs-134 0.018 0.019 0.953 20.000 AGREEMENT DE-500 Cs-137 0.033 0.029 1.121 20.000 AGREEMENT LAPEL Co-58 0.013 0.012 1.064 20.000 AGREEMENT VOL. Mn-54 0.017 0.015 1.160 20.000 AGREEMENT 1 cc Fe-59 A A1c n n4 A A.A 4fl 20.000 AGREEMEN DET. 3 Zn-65 0.023 0.020 1.132 20.000 AGREEMENT Co-60 0.026 0.025 1.036 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 ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE ANALYSIS microCi . jj j.;fo AIIAU trle>L

,',-L I ICS RE SO LUT!01,1 COMPARISON A19880-66 Ce-1 41 1.62E-03 1.71 E-03 0.95 20 AGREEMENT

.SOLID Cr-51 1.60E-03 1.63E-03 0.98 20 AGREEMENT 7.2 mL Cs-1 34 4.02E-04 3.84E-04 1.05 20 AGREEMENT BOMB Cs-1 37 8.23E-04 8.12E-04 1.01 20 AGREEMENT Co-58 4.41 E-04 4.33E-04 1.02 20 AGREEMENT DET. 1 Mn-54 6.95E-04 6.93E-04 1.00 20 AGREEMENT Fe-59 5.81 E-04 5.37E-04 1.08 20 AGREEMENT Zn-65 7.27E-04 7.12E-04 1.02 20 AGREEMENT Co-60 4.67E-04 4.78E-04 0.98 20 AGREEMENT A19880-66 Ce-141 1.67E-03 1.71 E-03 0.98 20 AGREEMENT SOLID Cr-51 1.84E-03 1.63E-03 1.13 20 AGREEMENT 7.2 mL Cs-134 4.29E-04 3.84E-04 1.12 20 AGREEMENT BOMB Cs-137 8.63E-04 8.12E-04 1.06 20 AGREEMENT Co-58 4.40E-04 4.33E-04 1.02 20 AGREEMENT DET. 2 Mn-54 7.29E-04 6.93E-04 1.05 20 AGREEMENT Fe-59 5.60E-04 5.37E-04 1.04 20 AGREEMENT Zn-65 7.12E-04 7.12E-04 1.00 20 AGREEMENT Co-60 4.35E-04 4.78E-04 0.91 20 AGREEMENT Al 9880-66 Ce-141 1.79E-03 1.71 E-03 1.05 20 AGREEMENT SOLID Cr-51 1.62E-03 1.63E-03 1.00 20 AGREEMENT 7.2 mL Cs-134 3.78E-04 3.84E-04 0.99 20 AGREEMENT BOMB Cs-137 8.41 E-04 8.12E-04 1.04 20 AGREEMENT Co-58 4.06E-04 4.33E-04 0.94 20 AGREEMENT DET. 3 Mn-54 7.16E-04 6.93E-04 1.03 20 AGREEMENT r- 5.37E n4 A A 1E-nA 0.82 20 AGREEMENT Zn-65 6.88E-04 7.12E-04 0.97 20 AGREEMENT Co-60 4.97E-04 4.78E-04 1.04 20 AGREEMENT 14TH QUARTER 2005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE ANALYSIS m~i'r^Ci --

'cro'i ANALYT iCS RESOLu I ION COMPARISON

- - - - .*********************************I*4.****4h**************************

A19879-66 Ce-141 7.61 E-02 6.63E-02 1.15 20 AGREEMENT CARTRIDGE Cr-51 7.08E-02 6.32E-02 1.12 20 AGREEMENT RGEM Cs-134 1.53E-02 1.49E-02 1.03 20 AGREEMENT DET. 1 Cs-137 3.80E-02 3.16E-02 1.20 20 AGREEMENT Co-58 1.95E-02 1.68E-02 1.16 20 AGREEMENT Mn-54 3.37E-02 2.69E-02 1.25 20 AGREEMENT Fe-59 2.51 E-02 2.09E-02 1.20 20 AGREEMENT Zn-65 3.36E-02 2.77E-02 1.21 20 AGREEMENT Co-60 2.04E-02 1.86E-02 1.10 20 AGREEMENT Al 9879-66 Ce-141 6.91 E-02 6.63E-02 1.04 20 AGREEMENT CARTRIDGE Cr-51 6.41 E-02 6.32E-02 1.01 20 AGREEMENT RGEM Cs-I 34 1.47E-02 1.49E-02 0.99 20 AGREEMENT DET. 2 Cs-1 37 3.55E-02 3.16E-02 1.13 20 AGREEMENT Co-58 1.84E-02 1.68E-02 1.09 20 AGREEMENT Mn-54 3.1 OE-02 2.69E-02 1.15 20 AGREEMENT Fe-59 2.36E-02 2.09E-02 1.13 20 AGREEMENT Zn-65 3.09E-02 2.77E-02 1.12 20 AGREEMENT Co-60 1.89E-02 1.86E-02 1.02 20 AGREEMENT A19879-66 Ce-141 7.20E-02 6.63E-02 1.09 20 AGREEMENT CARTRIDGE Cr-51 6.76E-02 6.32E-02 1.07 20 AGREEMENT RGEM Cs-1 34 1.51 E-02 1.49E-02 1.01 20 AGREEMENT DET. 3 Cs-I 37 3.69E-02 3.16E-02 1.17 20 AGREEMENT Co-58 1.92E-02 1.68E-02 1.14 20 AGREEMENT Mn-54 3.29E-02 2.69E-02 1.22 20 AGREEMENT Fe-59 2.51 E-02 2,09F-02 1.20 1AD AGREEMENT Zn-65 3.23E-02 2.77E-02 1.17 20 AGREEMENT Co-60 1.98E-02 1.86E-02 1.07 20 AGREEMENT

- - - - *******************************************2*********************************************

4 Tl QUARTER 2 d005

PALISADES ANALYTICS RATIO VALUE VALUE PALISADES:

SAMPLE AKIAI VQIQ .** .. o*.j riIr, U2jICI,, ANALYTICS REISLUTi ION COMPARISON A19882-66 Tritium 8.28E-04 7.86E-04 1.05 12.5 AGREEMENT LIQUID PACKARD TRICARB COUNT 1 Al 9882-66 Tritium 8.30E-04 7.86E-04 1.06 12.5 AGREEMENT LIQUID PACKARD TRICARB COUNT 2 A19882-66 Tritium 8.29E-04 7.86E-04 1.05 12.5 AGREEMENT LIQUID PACKARD TRICARB 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 , "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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 (1.1)

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 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 C1.3) where:

Xi = Air concentration of radionuclide i, pCi/M 3.

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

Qi = Average release rate of radionuclide i, pCi/s.

p = Fraction of radionuclide remaining in plume.

7zk = Vertical dispersion coefficient for stability class k (m).

Uj

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

x = Downwind distance, m.

n = Number of sectors, 16.

= Radioactive decay coefficient of radionuclide i, s 1 .

27rx/n - 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/M 3.

DFB1 = Total body dose factor due to gamma radiation, mrem/y per pCi/M 3 (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 = Ground2 concentration of radionuclide i, pCi/M .

k = Stability class.

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

Q = Average release rate of radionuclide 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 w

E 4c cc 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 = Ground2 concentration of radionuclide i, tCi/m .

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, 1.31x10 5 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 hours0.00185 days 0.0444 hours 2.645503e-4 weeks 6.088e-5 months for stored food).

13

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 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/m 3 .

1x10 3 = 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.

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

1x103 = g/kg conversion factor.

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, mrrem/y.

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

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

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

17

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 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 1E-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

C-In C

m C/

z 0,

C) m '1 en rn m

ui Cl

-4 m K, CD C)

_. z Uj)z

0. oC m

LI m

C) :D r-

-0 z

-I asT

- UJ.4Y "i l FLO sytt MGD P1mw WJw 1JUD g.

5 NOT IIWMIWAT r

OmFa Cx 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 Gaseous(2) Liquid(2)

H-3 5.5 159 Kr-85 4.1 NA Kr-85m 0.12 NA Kr-87 8.4E-02 NA Kr-88 2.1 E-01 NA Ar-41 3.1 E-02 NA Xe-131m 2.2 NA Xe-1 33 1493 NA Xe-1 33m 0.43 NA Xe-1 35 1.11 NA Xe-135m 0.3 NA 1-131 0.025 3.21 E-03 1-132 2.91 E-03 NA 1-133 6.5E-03 4.7E-05 1-134 4.8E-04 NA 1-135 1.84E-02 NA Na-24 1.5E-06 NA Cr-51 2.5E-04 3.9E-03 Mn-54 4.1 E-04 7.8E-03 Co-57 2.1 E-06 3.2E-05 Co-58 8.6E-04 2.9E-02 Fe-59 6.6E-06 4.1 E-04 Co-60 1.1 E-03 1.24E-02 Se-75 3.7E-06 NA Nb-95 2.4E-05 4.53E-04 Zr-95 4.7E-06 1.79E-04 Mo-99 1.5E-07 NA Ru-103 0.3E-07 0.1 E-05 Sb-1 27 NA 3.5E-05 Cs-134 4.5E-05 0.7 Cs-136 NA 1.8E-06 Cs-137 2.6E-04 1.36E-02 Ba-140 2.8E-07 NA La-140 7.5E-07 1.1 E-04 Unidentified beta 3.9E-04 3.3E-03 (1) Data derived from taking the effluents released during July-December 1978 through January-June 1982 and dividing by 4.

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

29

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.2 BASIC RADIONUCLIDE DATA NUCLIDE HALF-LIFE LAMBDA BETA' GAMMA 1 (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 BETA 1 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 .4i 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 SESMENT BOUNDARIES IN MILES FROM THE SITE DIREToION .5-1 1-2 2-3 3-4 4-S 5-10 10-20 20-30 30-40 40-50 FROM SITE S 7.808E-07 2.856e-07 1.351E-07 8.334E-08 5.828E-08 2.904E-08 1.110E-08 5.448E-09 3.445E-09 2.454E-09 SSW 6.085E-07 2.219E-07 1.057E-07 6.555E-08 4.602E-08 2.308E-08 8.912E-09 4.409E-09 2.802E-09 2.004E-09 SW 6.883E-07 2.484E-07 1.193e-07 7.468E-08 5.279E-08 2.681E-08 1.057E-08 5.316E-09 3.415E-09 2.462E-09 WSW 7.038E-07 2.527E-07 1.224E-07 7.721E-08 5.4893-08 2.815E-08 1.126E-08 5.725E-09 3.703E-09 2.683E-09 W 9.666E-07 3.457E-07 1.669E-07 1.051E-07 7.463E-08 3.821E-08 1.525E-08 7.749E-09 5.010E-09 3.629E-09 WNW 1.292E-06 4.630E-07 2.232E-07 1.404E-07 9.958E-08 5.089E-08 2.025E-08 1.026E-08 6.625E-09 4.793E-09 NW 1.627E-06 S.800E-07 2.819E-07 1.787E-07 1.276E-07 6.587E-08 2.662E-08 1.366E-08 8.879E-09 6.458E-09 NNW 2.159E-06 7.695E-07 3.765E-07 2.399E-07 1.718E-07 8.923E-08 3.636E-08 1.877E-08 1.224E-08 8.s92E-09 0 N 1.829E-06 6.557E-07 3.212E-07 2.046E-07 1.465E-07 7.604E-08 3.093E-08 1.594E-08 1.039E-08 7.569E-09 -n NNE 9.521E-07 3.454E-07 1.676E-07 '1 NE 1.017E-06 3.678E-07 1.720E-07 1.057E-07 1.054E-07 7.516E-08 7.332E-08 3.854E-08 3.627E-08 1.540E-08 1.374E-08 7.825E-09 6.704E-09 5.056E-09 4.227E-09 3.660E-09 3.006E-09 cn ENE 7.724E-07 2.773E-07 1.294E-07 7.922E-08 5.511E-08 2.731E-08 1.038E-08 5.092E-09 3.222E-09 2.298E-09 m E 8.592E-07 3.076S-07 1.426E-07 8.686E-08 6.020E-08 2.958E-08 1.109E-08 5.378E-09 3.378E-09 2.397E-09 I-ESE 8.271E-07 2.934E-07 1.351E-07 8.193E-08 5.661E-08 2.770E-08 1.033E-08 4.986E-09 3.126E-09 2.214E-09 cn SE 9.353E-07 3.305E-07 1.524E-07 9.262E-08 6.411E-08 3.149E-08 1.182E-08 5.745E-09 3. 617E-09 2.571E-09 0

SSE 1.123E-06 4.016E-07 1.863E-07 1.136E-07 7.881E-08 3.882E-08 1.462E-08 7.116E-09 4. 482E-09 3.186E-09 CO)

CA) 0 mm Cw co) r- (n z C) c 0.

mn I-. I-(Ai Q I- m 0

-I 0

z z

z -I c

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) DISTANCE IN MILES FRCH 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 4.205E-06 1.379E-06 7.540E-07 4.979E-07 2.769E-07 1.831E-07 1.330E-07 1.024E 07 8.212E-08 6.785E-08 5.735E-08 3.327E-06 1.084E-06 5.842E-07 3.8586-07 2.150E-07 1.428E-07 1.040E-07 8.032E-08 6.457E-08 5.346E-08 4.526E-08 WSW 3.887E-06 1.240E-06 6.575E-07 4.319E-07 2.402E-07 1.604E-07 1.175E-07 9.117E-08 7.359E-08 6.114E-08 5.193E-08 4.057E-06 1.277E-06 6.699E-07 4.388E-07 2.439E-07 1.637E-07 1.206E-07 9.394E-08 7.609E-08 6.341E-08 5.400E-08 W 5.550E-06 1.757E-06 9.203E-07 6.016E-07 3.334E-07 2.235E-07 1.644E-07 1.280E-07 1.036E-07 8.628E-08 7.344E-08 WSW 7.373E-06 2.343E-06 1.232E-06 8.062E-07 4.468E-07 2.993E-07 2.200E-07 1.712E-07 1.385E-07 1.153E-07 9.810E-08 NW 9.524E-06 2.969E-06 1.547E-06 1.009E-06 5.58SE-07 3.761E-07 2.779E-07 2.171E-07 1.762E-07 1.472E-07 1.256E-07 NW 1.285E-05 3.953E-06 2.047E-06 1.335E-06 7.408E-07 5.008E-07 3.712E-07 2.907E-07 2.365E-07 1.979E-07 1.691E-07 0

'1 N 1.087E-05 3.341E-06 1.735E-06 1.134E-06 6.316E-07 4.271E-07 3.165E-07 2.478E-07 2.016E-07 1.686E-07 1.440E-07 -n NNE 5.483E-06 1.714E-06 9.099E-07 5.982E-07 3.338E-07 2.242E-07 1.652E-07 1.287E-07 1.042E-07 8.687E-08 7.398E-08 U)

NE 5.447E-06 1.800E-06 9.837E-07 6.458E-07 3.563E-07 2.343E-07 1.693E-07 1.299E-07 1.039E-07 8.564E-08 7.223E-08 ENE 4.255E-06 1.377E-06 7.44BE-07 4.872E-07 2.685E-07 1.763E-07 1.273E-07 9.763E-08 7.804E-08 6.431E-08 5.423E-08 m cn I-E 4.615E-06 1.528E-06 8.303E-07 5.423E-07 2.977E-07 1.948E-07 1.403E-07 1.073E-07 8.559E-08 7.039E-08 5.925E-08 a ESE 4.433E-06 1.477E-06 7.992E-07 5.196E-07 2.837E-07 1.850E-07 1.328E-07 1.014E-07 8.075E-08 6.631E-08 5.575E-08 0 SE 5.088E-06 1.676E-06 9.026E-07 5.856E-07 3.194E-07 2.085E-07 1.499E-07 1.145E-07 9.128E-08 7.502E-08 6.312E-08 U) 0 SSE 6.040E-06 1.997E-06 1.086E-06 7.087E-07 3.885E-07 2.543E-07 1.833E-07 1.403E-07 1.120E-07 9.213E-08 7.760E-08 CD mm Ir Cn C) z ANMIAL AVEPAGS CHIQ (SEC/MRTER CUBED)

SECTOR 5.000 7.500 10.000 15.000 DISTANCE IN MILES FROM THE SITE 20.000 25.000 30.000 35.000 40.000 45.000 50.000 I-m W a S 4.936E-08 2.774E-08 1.845E-08 1.039E-08 6.911E-09 5.029E-09 3.874E-09 3.103E-09 2.557E-09 2.153E-09 1.844E-09 I-0

.1 0 m SSW 3.901E-08 2.204E-08 1.472E-08 8.327E-09 5.55SE-09 4.051E-09 3.126E-09 2.506E-09 2.067E-09 1.742E-09 1.492E-09 SW 4.489E-08 2.566E-08 1.727E-08 9.893E-09 6.657E-09 4.889E-09 3.793E-09 3.056E-09 2.531E-09 2.140E-09 1.840E-09 -4 0

WSW 4.678E-08 2.698E-08 1.827E-08 1.05SE-08 7.141E-09 5.267E-09 4.101E-09 3.314E-09 2.751E-09 2.332E-09 2.009E-09 0 I-W 6.361E-08 3.664E-08 2.480E-08 1.431E-08 9.688E-09 7.147E-09 5.566E-09 4.500E-09 3.738E-09 3.170E-09 2.732E-09 z WmW 8.494E-08 4.886E-08 3.304E-08 1.90SE-08 1.289E-08 9.508E-09 7.405E-09 5.987E-09 4.975E-09 4.220E-09 3.639E-09 NW 1.0903-07 6.323E-08 4.301E-08 2.500E-08 1.700E-08 1.259E-08 9.836E-09 7.972E-09 6.638E-09 5.641E-09 4.872E-09 z NNW 1.469E-07 8.570E-08 5.851E-08 3.417E-08 2.331E-08 1.730E-08 1.354E-08 1.099E-08 9.164E-09 7.796E-09 6.739E-09 z -i1 N 1.251E-07 7.285E-08 4.966E-08 2.893E-08 1.9693-08 1.458E-08 1.139E-08 9.223E-09 7.6743-09 6.5163-09 5.622E-09 c NNE 6.410E-08 3.697E-08 2.504E-08 1.446E-08 9.7863-09 7.218E-09 5.620E-09 4.541E-09 3.771E-09 3.196E-09 2.754E-09 NE 6.206E-08 3.468E-08 2.298E-08 1.289E-08 8.558E-09 6.223E-09 4.791E-09 3.836E-09 3.160E-09 2.662E-09 2.280E-09 I-ENE 4.659E-08 2.607E-08 1.729E-08 9.711E-09 6.459E-09 4.702E-09 3.624E-09 2.904E-09 2.395E-09 2.0183-09 1.730E-09 E 5.082E-08 2.822E-08 1.861E-08 1.037E-08 6.861E-09 4.973E-09 3.819E-09 3.051E-09 2.509E-09 2.110E-09 1.805E-09 ESE 4.776E-08 2.643E-08 1.739E-08 9.664E-09 6.380E-09 4.619E-09 3.544E-09 2.830E-09 2.327E-09 1.956E-09 1.673E-09 SE 5.413E-08 3.005E-08 1.9833E-08 1.106E-08 7.329E-09 5.320E-09 4.091E-09 3.273E-09 2.695E-09 2.268E-09 1.943E-09 SSE 6.659E-08 3.7063-08 2.449E-08 1.369E-08 9.073E-09 6.588E-09 5.066E-09 4.053E-09 3.337E-09 2.808E-09 2.404E-09 VENT AND BUILDING PARAMETERS:

RELEASE HEIGHT (MErERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (HETERS) 0.00 BUILDING HEIGHT (HETERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG .HIN.CRS . SEC. AREA tSQ.ETrERs) 2000.0 HEAT EMISSION RATE (CAL/SEC)8 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 20-30 30-40 40-50 FROM SITE S 7.791E-07 2.843E-07 1.341E-07 8.248E-08 5.7soE-08 2.842E-08 1.064E-08 5.069E-09 3.115E-09 2.158E-09 ssw 6.072E-07 2.209E-07 1.049E-07 6.484E-08 4.537E-08 2.256E-08 8.515E-09 4.082E-09 2.516E-09 1.746E-09 sW 6.867E-07 2.473E-07 1.184E-07 7.387E-08 5.20SE-08 2.621E-08 1.010E-08 4.922E-09 3.066E-09 2.145E-09 WSW 7.022E-07 2.516E-07 1.214E-07 7.636E-08 5.412E-08 2.751E-08 1.075E-08 5.300E-09 3.324E-09 2.337E-09 W 9.64SE-07 3.441E-07 1.656E-07 1.040E-07 7.360E-08 3.737E-08 1.459e-08 7.192E-09 4.514E-09 3.176E-09 hN4 1.290E-06 4.611E-07 2.216E-07 1.390E-07 9.832E-08 4.985E-08 1.942E-08 9.569E-09 6.007E-09 4.229E-09 NW 1.624E-06 5.775E-07 2.798E-07 1.768E-07 1.258E-07 6.441E-08 2.545E-08 1.267E-08 7.996E-09 5.651E-09 NNW 2.154E-06 7.661E-07 3.736E-07 2.373E-07 1.694E-07 8.722E-08 3.47SE-08 1.740E-09 1.102E-08 7.810E-09 0 N 1.825E-D6 6.524z-07 3.18sE-07 2.022E-07 1.443E-07 7.415E-08 2.943E-08 1.466E-08 9.251E-09 6.52SE-09 11 NNE 9.5DOE-07 3.438E-07 1.663E-07 1.046E-07 7.414E-08 3.770E-08 1.473E-08 7.263E-09 4.556E-09 3.203E-09 NE 1.015E-06 3.664E-07 1.709E-07 1.044E-07 7.244E-08 3.557E-08 1.321E-08 6.272E-09 3.851E-09 2.66SE-09 rn MEN 7.708E-07 2.761E-07 1.2858-07 7.840E-08 5.439E-08 2.673e-08 9.950E-09 4.739E-09 2.916E-09 2.023E-09 E 8.574E-07 3.063E-07 1.416E-07 8.600E-08 5.943E-08 2.897E-08 1.064E-08 5.015E-09 3.064E-09 2.115E-09 C ESE 8.255E-07 2.922E-07 1.342E-07 8.115E-08 5.592E-08 2.715E-08 9.921E-09 4.659E-09 2.842E-09 1.961E-09 0 SE 9.33SE-07 3.292E-07 1.514E-07 9.173E-08 6.332E-08 3.086E-08 1. 13sE-08 5.364E-09 3.286E-09 2.274E-09 in SSE 1.121E-06 4.000E-07 1.850E-07 1.125E-07 7.783E-08 3.804E-08 1.404E-08 6.642E-09 4.070E-09 2.815E-09 v iu 0n Ca z r 0. a m 0 r- I-m CA) 0 rl

a z z I: -41

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 FROM4THE 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 - Crm 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 AIDMBUILDING PARAHETERS:

RELEASE HEIGNt (METERS) 58.10 REP. WIND HEIGTr hMErERSl 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 10-20 20-30 30-40 40-50 FEO14 SrTE S 6.986E-07 2.434E-07 1.094E-07 6.492E-08 4.393E-08 2.052E-08 6.907E-09 2.969E-09 1.695E-09 1. 106E-09 SSW 5.445E-07 1.391E-07 8.560E-08 5.105E-08 3.468E-08 1.630E-08 5.540E-09 2.399E-09 1.3765-09 9.011E-10 SW 6.160E-07 2.117E-07 9.664E-08 5.816E-08 3.979E-08 1.893E-08 6.565E-09 2.892E-09 1.677E-09 1.107E-09 WSW 6.299e-07 2.153E-07 9.911E-08 6.013E-08 4.137e-08 1.987E-08 6.991E-09 3.114E-09 1.81SE-09 1.206E-09 W 8.653E-07 2.946E-07 1.351E-07 8.194E-08 5.625E-08 2.697E-508 947SE-09 4.218E-09 2.462E-09 1.634E-09 WNW 1.157E-06 3.946E-07 1.808E-07 1.094E-07 7.508E-08 3.594e-08 1.259E-08 5.594E-09 3.261E-09 2.162E-09 NW 1.457S-06 4.943E-07 2.283E-07 1.392E-07 9.614E-08 4.64se-08 1.653E-08 7.429e-09 4.359E-09 2.904E-09 0 NNW 1.932E-06 6.557E-07 3.049E-07 1.868E-07 1.295E-07 6.295E-08 2.257E-08 1.021E-08 6.012E-09 4.016E-09 *n N 1.637E-06 5.5S6E-07 2.601E-07 1.593E-07 1.104E-07 5.361E-08 1.918E-08 8.652E-09 S.085E-09 3.391E-09 NNE 8.521E-07 2.943E-07 1.357E-07 8.234E-08 5.66SE-08 2.721E-08 9.569e-09 4.260E-09 2.48SE-09

('3I 1.648E-09 NE 9.101E-07 3.136E-07 1.394E-07 8.21oE-os 5.529E-08 2.565E-08 8.556E-09 3.659E-09 2.084E-09 1.359E-09 mi U)

ENE 6.913E-07 2.364E-07 1.049E-07 6.171E-08 4.155E-08 1.93OR-08 6.461E-09 2.77sE-09 1.585E-09 1.036E-09 E 7.689E-07 2.622E-07 1.156E-07 6.768E-08 4.539E-08 2.0915-08 6.90SE-09 2.932E-09 1.663E-09 1.01E-09 0 5EE 7.403E-07 2.502E-07 1.095E-07 6.384E-08 4.269E-08 1.959E-08 6.434E-09 2.721E-09 1.540E-09 1.OOOE-09 CD i SE 8.371E-07 2.818E-07 1.235E-07 7.217E-08 4.834E-08 2.226E-08 7.362E-09 3.134E-09 1.782E-09 1.161E-09 iU m

-4 SSE 1.OOSE-06 3.424E-07 1.510E-07 8.852E-08 5.943E-08 2.74se-08 9.106E-09 3.882E-09 2.20SE-09 1.438E-09 -I MI- V)

S. z C)I- c tn CD m 0.

I-o m CA 0 0 -a z

C z -4 O-z

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.NDSDTIORS ********..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 0 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 tqn 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 SE 4.148E-08 4.9193-08 1.403E-08 1.663E-08 7.202E-09 8.5403-09 4.423E-09 5.244E-09 2.20SE-09 2.614E-09 1.337E-09 1.586E-09 9.041E-10 1.072E-09 6.552E-10 7.769E-10 4.982E-10 5.907E-10 3.9253-10 4.654E-10 3.177E-10 3.768E-10 V) cn

'a E)

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 m-I DIRECTIONI DISTAN4ES IN HILES m m CA FROM SITE 5.00 7.50 10.00 15.00 20.00 25.00 30.00 35.00 40.00 45.00 50.00 -I U) 00 S

SSW 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 CD 0 z 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 I- 0 C, SW 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 m K) z)

I-WSW 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 N 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 -.

-W z:D m 14NW 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 0 C NW4 mm4 3.071E-10 3.736E-10 1.505E-10 1.831E-10 9.443E-11 1.149E-10 4.773E-11 5.807E-11 2.889E-l1 3.515E-11 1.937E-11 2.357E-11 1.388E-11 1.689E-11 1.042E-11 1.268E-11 8.103E-12 9.859E-12 6.473E-12 7.87SE-12 5.283E-12 6.428E-12 I- >

N 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 NNE3 NE 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 z 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 -4 DEN 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 E 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 ESE 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 SE 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 SSE 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

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

"***** RELATIVE DEPOSITIoN PER UNIT AREA (m**-2) BY DOWNWIND SECrORS SSGMETr BOUNDARIES IN MILES DIRECTIO*N .5-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 30-40 40-50 FRROK SITE S 4.691E-09 1.449e-09 5.768e-10 3.152E-10 2.003E-10 8.604E-11 2.668E-11 1.057E-11 5.647E-12 3.495E-12 SSW 3.1222-09 9.645E-10 3.838E-10 2.097E-10 1.333E-10 5.726E-11 1.776E-11 7.037E-12 3.758E-12 2.326E-12 SW 3.366E-09 1.040E-09 4.138E-10 2.261E-10 1.437E-10 6.173E-11 1.914E-11 7.587E-12 4.051E-12 2.508E-12 WSW 3.299E-09 1.019E-09 4.055E-10 2.216E-10 1.409E-10 6.050E-11 1. 876E-11 7.436E-12 3.971E-12 2.458E-12 w 4.823e-09 1.490E-09 5.929E-10 3.240E-10 2.059E-10 8.845E-11 2.743E-11 1.087E-11 5.805E-12 3.593E-12 WNW 7.472E-09 2.308E-09 9.186E-10 5.020E-10 3.190E-10 1.370E-10 4.249E-11 1.684E-1l 8.994E-12 5.567E-12 NW 8.745E-09 2.702E-09 1.075e-09 5.875E-10 3.734E-10 1.604E-10 4.974E-11 1.971E-11 1.053E-11 6.516E-12 NR1 1.064E-08 3.287E-09 1.308E-09 7.147E-10 4.543E-10 1.951E-10 6.051E-11 2.3988-11 1.281E-11 7.927E-12 0 N 7.527E-09 2.325E-09 9.253E-10 5.057E-10 3.214g-10 1.380E-10 4.281E-11 1.697E-11 '1 9.060E-12 5.608E-12 '1 NWE 4.371E-09 1.351E-09 5.374E-10 2.937E-10 1.866E-10 8.017E-11 2.4868-11 9.853E-12 5.262E-12 3.257E-12 co NE 7.591E-09 2.345E-09 9.333E-10 5.100E-10 3.241E-10 1.392E-10 4.317E-11 1.711E-11 9.138E-12 5.656E-12 ENE 6.110E-09 1.888s-09 7.512E-10 4.105E-10 2.609E-10 1.121E-10 3.475E-11 1.377E-11 7.355E-12 4.552E-12 m E 7.082E-09 2.188E-09 8.707E-10 4.758E-10 3.024E-10 1.299E-10 4.028E-11 1.596E-11 8.525E-12 5.271E-12 0 Co ESE 7.484E-09 2.312E-09 9.200E-10 5.029E-10 3.195E-10 1. 373E-10 4.256E-11 1.687E-11 9.008E-12 5.576E-12 SE 8.874E-09 2.742E-09 tn 1.091E-09 5.962E-10 3.789B-10 1.628E-10 5.047E-11 2.000E-11 1.068E-11 6.612E-12 SSE 9.261E-09 2.861E-09 1.139E-09 6.222E-10 3.954E-10 1.699E-10 5.267E-11 2.088E-11 1.115E-11 6.900E-12 -I m m (0 Co CD 0 VENr AND BUILDIiG PARAMETERS:

RELEASE MEIGHT (METERS) 58.10 REP. WIND HEIGHT w

I-

5. Co z c

(METERS) 10.0 tJ)

DILMETER (MTERS) 0.00 BUILDING HEI5GT (METERS) 58.1 m C EXIT VELOC1TY (METERS) 0.00 WXG.MHN.-CRS-S..AREA (SQ.METES) 2000.0 HEAT EMISSIOTN RATE (cAL/SW) 0.0 CA) 0 0 tI-ALL GRONlD LEVEL RELEES. ZI a

I-0 z

r -4

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:mS`AJCE X/Q X/Q X/Q D/Q ID LOCATION FROM SITE (MILES) (METERS) (SEC/CUD.NETER) (SEC/CUB.WETER) (SEC/CUB.METER) (PER SQ.METER)

NO DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED DEPLErED A SITE BOUnDARY 0.50 805. 1.72E-06 1.71E-06 1.57E-06 8.19E-09 A

NNE SITE BOUNDARY 0.65 1046. 1.22E-06 1.22E-06 1.10e-06 9.30E-09 A SITE BOUNDARY DEN 0.87 1400. 5.99E-07 5.98E-07 5.29e-07 4.58E-09 A SITE BOUNDARY 0.82 1320. 7.28E-07 7.27E-07 6.45E-07 5.86E-09 A SITE BOUNDARY ES 0.76 1223. 7.85E-07 7.83E-07 6.98e-07 7.04E-09 A SITE BOUNDARY ESE 0 0.63 1014. 1.18E-06 1.18E-06 1.06E-06 1.14E-08 A SITE BOUNDARY SE 0.48 772. 2.13E-06 2.12E-06 1.95E-06 A SITE BOUNDARY SSE 0.42 1.86E-08 -n 676. 1.78E-06 1.78E-06 1.64E-06 1.16E-08 A SITE BOUNDARY 0.48 772. 1.16E-06 1.15E-06 1.06E-06 6.26E-09 m i A GARDEN 1.60 2575. 3.06E-07 3.04E-07 2.58E-07 1.15E-09 m I-A GARDEN SS 1.20 1931. 4.96E-07 4.95E-07 4.28E-07 3.29E-09 0 cn A GARDEN 2.70 4345. 1.15E-07 1.14E-07 9.20E-08 6.45e-10 0 A GARDeN NE 2.20 3541. 1.69E-07 (n A GARDEN 2.30 3701.

1.70E-07 1.51E-07 1.50E-07 1.40E-07 1.23E-07 1.07e-09

5. mm 1.05E-09 0 A GARDEN ENE 1.80 0 cn DE 1.60 2897.

2575.

2.45E-07 3.55E-07 2.44E-07 3.53E-07 2.04E-07 2.99E-07 1.91E-09 2.44E-09 Ir-z

0. 1C A GARDEN SE 1.50 2414. 2.78e-07 2.77E-07 2.36E-07 1.38E-09 m C)

A BEEF CoW 2.90 4667. 1.385-07 1.36E-07 K) I-A BEEF COW SSE 4.00 6437. 6.51E-08 6.43E-08 1.09E-07 4.98E-08 7.06E-10 3.20e-10 -. 0CD 0 m A RR COW 3.50 5633. 8.64e-08 8.56E-08 6.73E-08 4.71E-10 X3 A BEEF COW 4.00 6437. 6.70E-08 6.63E-08 5.13E-08 3.93E-10 A BEFD OOW ENE 55 3.00 4828. 1.415-07 1.40E-07 1.12E-07 8.11E-10 z r-A DAIRY COW 4.30 6920. 6.83E-08 6.75e-08 5.18E-08 A GOAT 3.20 4.09E-10 z

A GOAT 3.00 5150.

4828.

1.19E-07 1.02E-07 1.18E-07 1.01e-07 9.39E-08 8.10e-08 5.93E-10 6 .s5E-10 zi -I a

VENT AND BUILDING PARAME1DS: I-RELEASE HEIGHT (METERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERSl 0.00 BUILDING HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 LDG. MICS.SEX.AREA (SQ.NMEERS) 2000.0 HEAT EHISSIONI RATE (CAL/SEC) 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 DISTANCE X/Q X/Q X/Q D/Q ID LOCATION FROM SITE (ILES) (METERS) (SEC/CUB.METER) (SEC/CUB.METER) (SEC/CUB.METER) (PER SQ.WETER)

NQ DECAY 2.260 DAY DECAY 8.000 DAY DECAY UNDEPLETED UNDEPLETED DEPLETED A SITE BOUNDARY NNE 0.50 805. 1.72E-06 1.71E-06 1.57E-06 8.19E-09 A SITE BOUNDARY NE 0.65 1046. 1.22E-06 1.22E-06 1.10E-06 9.30E-09 A SITE BOUNDARY ENE 0.87 1400. 5.99E-07 5.98E-07 5.29E-07 4.58E-09 A SITE BOUNDARY E 0.82 1320. 7.28E-07 7.27E-07 6.45E-07 5.86E-09 A SITE BOUNDARY ESE 0.76 1223. 7.85E-07 7.83E-07 6.98E-07 7.04E-09 0 A SITE BOUNDARY SE 0.63 1014. 1.18E-06 1.18E-06 1.06E-06 1.14E-08 A SITE BOUNDARY SSE 0.48 772. 2.13E-06 2.12E-06 1.95E-06 1.86E-08 A SITE BOUNDARY S 0.42 676. 1.78E-06 cn 1.78E-06 1.64E-06 1.16E-08 A SITE BOUNDARY SSW 0.48 772. 1.16E-06 1.15E-06 1.06E-06 6.26E-09 m E-A RESIDENCE NNE 1.10 1770. 5.23E-07 5.21E-07 4.55E-07 2.20E-09 A RESIDENCE NE 1.20 1931. 4.96E-07 4.95E-07 4.28E-07 3.29E-09 0 C,)

A RESIDENCE ENE 1.30 2092. 3.33E-07 3.3lE-07 2.85E-07 2.30E-09 A RESIDENCE E 1.00 1609. 5.44E-07 5.42E-07 4.76E-07 4.19E-09 m m A RESIDENCE ESE 1.00 1609. 5.21E-07 5.20E-07 4.56E-07 4.42E-09 C) CO)

A RESIDIRCE 1.00 1609. 5.87E-07 5.86E-07 5.14E-07 5.25E-09 z A RESIDENCE SSE 0.70 1127. 1.21E-06 1.20E-06 1.08E-06 1.00E-08 rI 0.

I- C A RESIDENCE S 0.50 SOS. 1.38E-06 1.38E-06 1.26E-06 8.79E-09 m CD. r-A RESIDENCE SSW 0.70 1127. 6.SOE-07 6.49E-07 5.81E-07 3.37E-09 7A m

A BEEF COW NE 2.90 4667. 1.38E-07 1.36E-07 1.09E-07 7.06E-10 A BEEF COW ENE -4 M 4.00 6437. 6.51E-08 6.43E-08 4.98E-08 3.20E-10 A BEEF COW E 3.50 5633. 8.64E-08 8.56E-08 6.73E-08 4.71E-10 0 A r, BEEF COW ESE 4.00 6437. 6.70E-08 6.63E-08 5.13E-08 3.93E-10 z zi z-q A BEEF Cow SSE 3.00 4828. 1.41E-07 1.40E-07 1.12E-07 8.11E-10 A DAIRY COW SE 4.30 6920. 6.83E-08 6.75E-08 5. 18E-08 4.09E-10 A GOAT NE 3.20 5150. 1.19E-07 1.18E-07 9.39E-08 5.93E-10 C A GOAT ESE 3.00 4828. 1.02E-07 1.01E-07 8.10E-08 6.55E-10 a-VErT AND BUILDINlG PARAMETERS:

RELEASE HEIGHT (MLrERS) 58.10 REP. WIND HEIGHT (METERS) 10.0 DIAMETER (METERS) 0.00 BUILDING HEIGHT (METERS) 58.1 EXIT VELOCITY (METERS) 0.00 BLDG . HIN . CRS . SEC . AREA (SQ.MErERS) 2000.0 HEAT MISSION RATE (CAL/SEC) 0.0 ALL GROUND LEVL RELEASES.

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.4 2004 PALISADES LAND USE CENSUS I Distance to the nearest residence, garden, dairy/beef cattle, and goat in each sector.

SECTOR RESIDENCE GARDEN BEEF CATTLE DAIRY COW GOAT NNE 1.1 mi 1.7 mi >5 mi >5 ml >5 ml NE 1.2 mi 1.2 mi >5 mi >5 mi >5 ml ENE 1.3 ml 1.6 mi 4.0 ml >5 ml 1.8 ml E 1.0 mi 2.1 mi >5 mi >5 ml 3.5 ml ESE 1.0 mi *1.0 mi >5 ml >5 ml >5 ml SE 1.0 mi *1.0 mi 1.9 ml 4.3 mi 1.9 ml I

,SSE 0.7 mi 1.6 ml >5 ml >5 ml 4.8 ml I S 0.5 mi 4.0 ml >5 mi >5 mi 4.7 ml SSW 0.7 mi >5.0 mi >5 mi >5 mi >5 ml 42

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.4a 2004 PALISADES LAND USE CENSUS Critical Receptor Items Distance Sector Miles Location/Description Item *X/Q (sec/m 3 )

SSE: 0.48 Site Boundary N/A 2.13E-06 S 0.50 Residence, Palisades Park; Residence 1.38E-06 1/2 mile west of 2 9 th Avenue and Blue Star intersection SE 1.0 77550 2 8 th Avenue Garden 5.87E-07 I

SE 1.9 SE corner of 76"' Street & 30 "' Beef Cattle 2.32E-07 SE 4.3 72401 3 6 th Ave Dairy Cow 6.83E-08 SE 1.9 SE corner of 76 th Street & 3 0 th Goat 2.32E-07 I

Base(d on Palisades 5-year composite meteorological data, 1992 - 1996.

43

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.5 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES*

DFR 1 DFy 2 DFS1 DFB2 Kr-85m 1.17(+3)3 1.23(+3) 1.46(+3) 1.97(+3)

Kr-85 1.61(+1) 1.72(+1) 1.34(+3) 1.95(+3)

Kr-87 5.92(+3) 6.17(+3) 9.73(+3) 1.03(+4)

Kr-88 1.47(+4) 1.52(+4) 2.37(+3) 2.93(+3)

Kr-89 1.66(+4) 1.73(+4) 1.01 (+4) 1.06(+4)

Xe- 131 m 9.15(+1) 1.56(+2) 4.76(+2) 1.11 (+3)

Xe- 133m 2.51 (+2) 3.27(-+2) 9.94(+2) 1.48(+3)

Xe-i 33 2.94(+2) 3.53(+2) 3.06(+2) 1.05(+3)

Xe- 135m 3.12(+3) 3.36(+3) 7.11(+2) 7.39(+3)

Xe-135 1.81 (+3) 1.92(+3) 1.86(+3) 2.46(+3)

Xe-137 1.42(+3) 1.51(+3) 1.22(+4) 1.27(+4)

Xe-'138 8.83(+3) 9.21 (+3) 4.13(+3) 4.75(+3)

Ar-41 8.84(+3) 9.30(+3) 2.69(+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 Fm - MILK (COW) Fm- MILK (GOAT) F.- MEAT ELEMENT (DAYS/L) (DAYS/L) (DAYS/KG) (VEG/SOQI H 1.OE-02 1.7E-01 1.2E-02 4.8E-OO C 1.2E-02 1.OE-01 3.1 E-02 5.5E-OO Na 4.OE-02 4.OE-02 3.OE-02 5.2E-02 p 2.5E-02 2.5E-01 4.6E-02 1.IE-O0 Cl. 2.2E-03 2.2E-03 2.4E-03 2.5E-04 Mn 2.5E-04 2.5E-04 8.0E-04 2.9E-02 Fe 1.2E-03 1.3E-04 4.OE-02 6.6E-04 Co 1.OE-03 1.OE-03 1.3E-02 9.4E-03 Ni 6.7E-03 6.7E-03 5.3E-02 1.9E-02 Ci 1.4E-02 1.3E-02 8.OE-03 1.2E-01 Zn 3.9E-02 3.9E-02 3.OE-02 4.OE-01 Rb 3.OE-02 3.0E-02 3.1 E-02 1.3E-01 Sr 8.OE-04 1.4E-02 6.OE-04 1.7E-02 y 1.OE-05 1.OE-05 4.6E-03 2.6E-03 Zr 5.OE-06 5.OE-06 3.4E-02 1.7E-04 Nb 2.5E-03 2.5E-03 2.8E-01 9.4E-03 MD) 7.5E-03 7.5E-03 8.OE-03 1.2E-01 Tc 2.5E-02 2.5E-02 4.OE-01 2.5E-01 Ru 1.OE-06 1.OE-06 4.OE-01 5.OE-02 Rh 1.OE-02 1.OE-02 1.5E-03 1.3E+01 Ag 5.OE-02 5.OE-02 1.7E-02 1.5E-01 Tio 1.OE-03 1.OE-03 7.7E-02 1.3E-OO 6.OE-03 6.OE-02 2.9E-03 2.OE-02 Cs 1.2E-02 3.OE-01 4.OE-03 1.OE-02 Ba 4.OE-04 4.OE-04 3.2E-03 5.OE-03 La 5.OE-06 5.OE-06 2.OE-04 2.5E-03 CeI 1.OE-04 1.OE-04 1.2E-03 2.5E-03 Pl 5.OE-06 5.OE-06 4.7E-03 2.5E-03 Nd 5.OE-06 5.OE-06 3.3E-03 2.4E-03 W 5.OE-04 5.OE-04 1.3E-03 1.8E-02 Np 5.OE-06 5.OE-06 2.OE-04 2.5E-03 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.35E-06 0. 6.30E-08 0. 0. 1.92E-04 7.43E-05 Y91M-D 2.91 E-10 0. 9.90E-12 0. 0. 1.99E-06 1.68E-06 Y91 4.20E-04 0. 1.12E-05 0. 0. 1.75E-03 5.02E-05 Y92 1.17E-08 0. 3.29E-1 0 0. 0. 1.75E-05 9.04E-05 Y93 1.07E-07 0. 2.91 E-09 0. 0. 5.46E-05 1.1 9E-04 ZR93d-D 2.24E-04 9.51 E-05 6.18E-05 0. 3.19E-04 1.37E-03 1.48E-05 ZR95-i D 8.24E-05 1.99E-05 1.45E-05 0. 2.22E-05 1.25E-03 1.55E-05 ZR974 D 1.07E-07 1.83E-08 8.36E-09 0. 1.85E-08 7.88E-05 1.OOE-04 NB93M 1.38E-04 3.59E-05 1.15E-05 0. 3.68E-05 2.09E-04 2.47E-06 NB95 1.12E-05 4.59E-06 2.70E-06 0. 3.37E-06 3.42E-04 9.05E-06 NB97 2.44E-10 5.21E-11 1.88E-11 0. 4.07E-1 1 2.37E-06 1.92E-05 M093 0. 6.46E-06 2.22E-07 0. 1.54E-06 3.40E-04 3.76E-06 M099 FD 0. 1.18E-07 2.31 E-08 0. 1.89E-07 9.63E-05 3.48E-05 TC99M 9.98E-13 2.06E-12 2.66E-1 1 0. 2.22E-1 1 5.79E-07 1.45E-06 TC99 2.09E-07 2.68E-07 8.85E-08 0. 2.49E-06 6.77E-04 7.82E-06 TC101 4.65E-14 5.88E-14 5.80E-13 0. 6.99E-13 4.17E-07 6.03E-07 RU103+D 1.44E-06 0. 4.85E-07 0. 3.03E-06 3.94E-04 1.15E-05 RU10'i+D 8.74E-1 0 0. 2.93E-1 0 0. 6.42E-10 1.12E-05 3.46E-05 RU1 06+D 6.20E-05 0. 7.77E-06 0. 7.61 E-05 8.26E-03 1.17E-04 RH105 8.26E-09 5.41 E-09 3.63E-09 0. 1.50E-08 2.08E-05 1.37E-05 PD107' 0. 4.92E-07 4.11E-08 0. 2.75E-06 6.34E-05 7.33E-07 PD109 0. 3.92E-09 1.05E-09 0. 1.28E-08 1.68E-05 2.85E-05 AG110M+D 7.13E-06 5.16E-06 3.57E-06 0. 7.80E-06 2.62E-03 2.36E-05 AG 11 3.75E-07 1.45E-07 7.75E-08 0. 3.05E-07 2.06E-04 3.02E-05 CD113M 0. 6.67E-04 2.64E-05 0. 5.80E-04 1.40E-03 1.65E-05 CD11iM 0. 1.73E-04 6.19E-06 0. 9.41 E-05 1.47E-03 5.02E-05 SN123 2.09E-04 4.21 E-06 7.28E-06 4.27E-06 0. 2.22E-03 4.08E-05 SN125+D 1.01 E-05 2.51 E-07 6.OOE-07 2.47E-07 0. 6.43E-04 7.26E-05 SN12E6+D 8.30E-04 1.44E-05 3.52E-05 3.84E-06 0. 4.93E-03 1.65E-05 SB124 2.71 E-05 3.97E-07 8.56E-06 7.18E-08 0. 1.89E-03 4.22E-05 SB12E+D 3.69E-05 3.41 E-07 7.78E-06 4.45E-08 0. 1.17E-03 1.05E-05 SB12E 3.08E-06 6.01 E-08 1.11E-06 2.35E-08 0. 6.88E-04 5.33E-05 SB127 2.82E-07 5.04E-09 8.76E-08 3.60E-09 0. 1.54E-04 3.78E-05 TE125M 3.40E-06 1.42E-06 4.70E-07 1.16E-06 0. 3.19E-04 9.22E-06 TE127M+D 1.19E-05 4.93E-06 1.48E-06 3.48E-06 2.68E-05 9.37E-04 1.95E-05 TE127 1.59E-09 6.81 E-10 3.49E-10 1.32E-09 3.47E-09 7.39E-06 1.74E-05 TE129M+D 1.01 E-05 4.35E-06 1.59E-06 3.91 E-06 2.27E-05 1.20E-03 4.93E-05 TE129 5.63E-1 1 2.48E-1 1 1.34E-11 4.82E-11 1.25E-10 2.14E-06 1.88E-05 TE131M+D 7.62E-08 3.93E-08 2.59E-08 6.38E-08 1.89E-07 1.42E-04 8.51 E-05 TE131+D 1.24E-11 5.87E-12 3.57E-12 1.13E-11 2.85E-1 1 1.47E-06 5.87E-06 TE132+D 2.66E-07 1.69E-07 1.26E-07 1.99E-07 7.39E-07 2.43E-04 3.15E-05 TE133M+D 6.13E-11 3.59E-1 I 2.74E-1 1 5.52E-1 1 1.72E-10 3.92E-06 1.59E-05 TE134+D 3.18E-11 2.04E-11 1.68E-11 2.91 E-11 9.59E-1 1 2.93E-06 2.53E-06 1129 2.16E-05 1.59E-05 1.16E-05 1.04E-02 1.88E-05 0. 2.12E-07 1130 4.54E-06 9.91 E-06 3.98E-06 1.14E-03 1.09E-05 0. 1.42E-06 1131+[) 2.71 E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.21 E-06 2.53E-06 8.99E-07 1.21 E-04 2.82E-06 0. 1.36E-06 1133+1) 9.46E-06 1.37E-05 4.OOE-06 2.54E-03 1.60E-05 0. 1.54E-06 1134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0. 9.21 E-07 1135+1) 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0. 1.31 E-06 XE13 zM 0. 0. 0. 0. 0. 6.77E-09 0.

XE1 33M 0. 0. 0. 0. 0. 8.89E-09 0.

XE1 33 0. 0. 0. 0. 0. 7.41 E-09 0.

XE1 35M 0. 0. 0. 0. 0. 8.05E-09 0.

XE13'5 0. 0. 0. 0. 0. 1.80E-08 0.

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

XE1 38+D 0. 0. 0. 0. 0. 9.78E-08 0.

CS1 3'1M+D 1.32E-07 2.10E-07 1.11E-07 0. 8.50E-08 2.00E-08 1.16E-07 CS 134 2.83E-04 5.02E-04 5.32E-05 0. 1.36E-04 5.69E-05 9.53E-07 CS135 1.OOE-04 8.66E-05 4.73E-06 0. 2.58E-05 1.01 E-05 2.18E-07 CS136 3.45E-05 9.61 E-05 3.78E-05 0. 4.03E-05 8.40E-06 1.02E-06 CS1 3'+D 3.92E-04 4.37E-04 3.25E-05 0. 1.23E-04 5.09E-05 9.53E-07 CS138 3.61 E-07 5.58E-07 2.84E-07 0. 2.93E-07 4.67E-08 6.26E-07 CS1 39+D 2.32E-07 3.03E-07 1.22E-07 0. 1.65E-07 2.53E-08 1.33E-08 BA1 39 1.06E-09 7.03E-1 3 3.07E-1 1 0. 4.23E-13 4.25E-06 3.64E-05 BA14tl+D 4.OOE-05 4.OOE-08 2.07E-06 0. 9.59E-09 1.14E-03 2.74E-05 BA141+D 1.12E-10 7.70E-1 4 3.55E-1 2 0. 4.64E-14 2.12E-06 3.39E-06 BA1 42+D 2.84E-1 1 2.36E-1 4 1.40E-12 0. 1.36E-14 1.11E-06 4.95E-07 LA140 3.61 E-07 1.43E-07 3.68E-08 0. 0. 1.20E-04 6.06E-05 LA141 4.85E-09 1.40E-09 2.45E-1 0 0. 0. 1.22E-05 5.95E-05 LA1 42 7.36E-1 0 2.69E-1 0 6.46E-1 1 0. 0. 5.87E-06 4.25E-05 CE14', 1.98E-05 1.19E-05 1.42E-06 0. 3.75E-06 3.69E-04 1.54E-05 CE1 43+D 2.09E-07 1.38E-07 1.58E-08 0. 4.03E-08 8.30E-05 3.55E-05 CE1 44+D 2.28E-03 8.65E-04 1.26E-04 0. 3.84E-04 7.03E-03 1.06E-04 PR143 1.OOE-05 3.74E-06 4.99E-07 0. 1.41 E-06 3.09E-04 2.66E-05 PR144 3.42E-1 1 1.32E-1 1 1.72E-12 0. 4.80E-12 1.15E-06 3.06E-06 ND14;'+D 5.67E-06 5.81 E-06 3.57E-07 0. 2.25E-06 2.30E-04 2.23E-05 PM14.' 3.91 E-04 3.07E-05 1.56E-05 0. 4.93E-05 4.55E-04 5.75E-06 PM14l3M+D 5.OOE-05 1.24E-05 9.94E-06 0. 1.45E-05 1.22E-03 3.37E-05 PM148 3.34E-06 4.82E-07 2.44E-07 0. 5.76E-07 3.20E-04 6.04E-05 PM149 3.10E-07 4.08E-08 1.78E-08 0. 4.96E-08 6.50E-05 3.01 E-05 PM15'1 7.52E-08 1.10E-08 5.55E-09 0. 1.30E-08 3.25E-05 2.58E-05 SM1511 3.38E-04 6.45E-05 1.63E-05 0. 5.24E-05 2.98E-04 3.46E-06 SM153 1.53E-07 1.18E-07 9.06E-09 0. 2.47E-08 3.70E-05 1.93E-05 EU1 52 7.83E-04 1.77E-04 1.72E-04 0. 5.94E-04 1.48E-03 9.88E-06 EU154. 2.96E-03 3.46E-04 2.45E-04 0. 1.14E-03 3.05E-03 2.84E-05 EU155 5.97E-04 5.72E-05 3.46E-05 0. 1.58E-04 5.20E-04 5.19E-05 EU156E 1.56E-05 9.59E-06 1.54E-06 0. 4.48E-06 6.12E-04 4.14E-05 TB160 1.12E-04 0. 1.40E-05 0. 3.20E-05 1.11E-03 2.14E-05 HO1 66M 1.45E-03 3.07E-04 2.51 E-04 0. 4.22E-04 2.05E-03 1.65E-05 W181 4.86E-08 1.46E-08 1.67E-09 0. 0. 1.33E-05 2.63E-07 W1 85 1.57E-06 4.83E-07 5.58E-08 0. 0. 4.48E-04 1.12E-05 W187 9.26E-09 6.44E-09 2.23E-09 0. 0. 2.83E-05 2.54E-05 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.11E-06 0. 2.99E-08 0. 0. 7.07E-05 7.24E-05 Y91M-D 1.37E-10 0. 4.98E-12 0. 0. 7.60E-07 4.64E-07 Y91 2.47E-04 0. 6.59E-06 0. 0. 7.1 OE-04 4.97E-05 Y92 5.50E-09 0. 1.57E-10 0. 0. 6.46E-06 6.46E-05 Y93 5.04E-08 0. 1.38E-09 0. 0. 2.01 E-05 1.05E-04 ZR934 D 2.07E-04 7.80E-05 5.55E-05 0. 3.OOE-04 7.1 OE-04 1.47E-05 ZR954D 5.13E-05 1.13E-05 1.OOE-05 0. 1.61 E-05 6.03E-04 1.65E-05 ZR974D 5.07E-08 7.34E-09 4.32E-09 0. 1.05E-08 3.06E-05 9.49E-05 NB93M 1.27E-04 3.17E-05 1.04E-05 0. 3.44E-05 1.04E-04 2.45E-06 NB95 6.35E-06 2.48E-06 1.77E-06 0. 2.33E-06 1.66E-04 1.OOE-05 NB97 1.16E-10 2.08E-1 1 9.74E-12 0. 2.31 E-11 9.23E-07 7.52E-06 M093 0. 3.76E-06 1.35E-07 0. 1.06E-06 1.70E-04 3.78E-06 MO99-+D 0. 4.66E-08 1.15E-08 0. 1.06E-07 3.66E-05 3.42E-05 TC99M 4.81E-13 9.41 E-13 1.56E-1 1 0. 1.37E-11 2.57E-07 1.30E-06 TC99 1.34E-07 1.49E-07 5.35E-08 0. 1.75E-06 3.37E-04 7.75E-06 TC101 2.19E-14 2.30E-14 2.91 E-13 0. 3.92E-1 3 1.58E-07 4.41 E-09 RU10$+D 7.55E-07 0. 2.90E-07 0. 1.90E-06 1.79E-04 1.21 E-05 RU10'+D 4.13E-10 0. 1.50E-10 0. 3.63E-10 4.30E-06 2.69E-05 RU1O6.+D 3.68E-05 0. 4.57E-06 0. 4.97E-05 3.87E-03 1.16E-04 RH10' 3.91 E-09 2.10E-09 1.79E-09 0. 8.39E-09 7.82E-06 1.33E-05 PD107 0. 2.65E-07 2.51 E-08 0. 1.97E-06 3.16E-05 7.26E-07 PD109 0. 1.48E-09 4.95E-10 0. 7.06E-09 6.16E-06 2.59E-05 AG11CM+D 4.56E-06 3.08E-06 2.47E-06 0. 5.74E-06 1.48E-03 2.71 E-05 AG111 1.81 E-07 5.68E-08 3.75E-08 0. 1.71 E-07 7.73E-05 2.98E-05 CD112M 0. 4.93E-04 2.12E-05 0. 5.13E-04 6.94E-04 1.63E-05 CD11'M 0. 7.88E-05 3.39E-06 0. 5.93E-05 5.86E-04 4.97E-05 SN123 1.29E-04 2.14E-06 4.19E-06 2.27E-06 0. 9.59E-04 4.05E-05 SN125+D 4.95E-06 9.94E-08 2.95E-07 1.03E-07 0. 2.43E-04 7.17E-05 SN 126+D 6.23E-04 1.04E-05 2.36E-05 2.84E-06 0. 3.02E-03 1.63E-05 SB124 1.55E-05 2.OOE-07 5.41 E-06 3.41 E-08 0. 8.76E-04 4.43E-05 SB125+D 2.66E-05 2.05E-07 5.59E-06 2.46E-08 0. 6.27E-04 1.09E-05 SB126 1.72E-06 2.62E-08 6.16E-07 1.OOE-08 0. 2.86E-04 5.67E-05 SB127 1.36E-07 2.09E-09 4.70E-08 1.51E-09 0. 6.17E-05 3.82E-05 TE125M 1.82E-06 6.29E-07 2.47E-07 5.20E-07 0. 1.29E-04 9.13E-06 TE127M+D 6.72E-06 2.31 E-06 8.16E-07 1.64E-06 1.72E-05 4.OOE-04 1.93E-05 TE127 7.49E-10 2.57E-10 1.65E-10 5.30E-1 0 1.91 E-09 2.71 E-06 1.52E-05 TE129M+D 5.19E-06 1.85E-06 8.22E-07 1.71 E-06 1.36E-05 4.76E-04 4.91 E-05 TE129 2.64E-1 1 9.45E-12 6.44E-1 2 1.93E-11 6.94E-1 1 7.93E-07 6.89E-06 TE131 M+D 3.63E-08 1.60E-08 1.37E-08 2.64E-08 1.08E-07 5.56E-05 8.32E-05 TE131 tD 5.87E-12 2.28E-12 1.78E-12 4.59E-12 1.59E-1 I 5.55E-07 3.60E-07 TE132tD 1.30E-07 7.36E-08 7.12E-08 8.58E-08 4.79E-07 1.02E-04 3.72E-05 TE133VM+D 2.93E-1 1 1.51 E-11 1.50E-11 2.32E-1 1 1.01E-10 1.60E-06 4.77E-06 TE134tD 1.53E-11 8.81 E-12 9.40E-12 1.24E-11 5.71 E-11 1.23E-06 4.87E-07 1129 1.05E-05 6.40E-06 5.71 E-06 4.28E-03 1.08E-05 0. 2.15E-07 1130 2.21 E-06 4.43E-06 2.28E-06 4.99E-04 6.61 E-06 0. 1.38E-06 1131+D 1.30E-05 1.30E-05 7.37E-06 4.39E-03 2.13E-05 0. 7.68E-07 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 5.72E-07 1.10E-06 5.07E-07 5.23E-05 1.69E-06 0. 8.65E-07 1133+1) 4.48E-06 5.49E-06 2.08E-06 1.04E-03 9.13E-06 0. 1.48E-06 1134 3.17E-07 5.84E-07 2.69E-07 1.37E-05 8.92E-07 0. 2.58E-07 1135+1) 1.33E-06 2.36E-06 1.12E-06 2.14E-04 3.62E-06 0. 1.20E-06 XE131M 0. 0. 0. 0. 0. 3.30E-09 0.

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

XE13'i 0. 0. 0. 0. 0. 3.66E-09 0.

XE13E5M 0. 0. 0. 0. 0. 4.48E-09 0.

XE13E 0. 0. 0. 0. 0. 9.09E-09 0.

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

XE136+D 0. 0. 0. 0. 0. 5.17E-08 0.

CS13'1M+D 6.33E-08 8.92E-08 6.12E-08 0. 4.94E-08 8.35E-09 7.92E-08 CS13'. 1.76E-04 2.74E-04 6.07E-05 0. 8.93E-05 3.27E-05 1.04E-06 CS135 6.23E-05 4.13E-05 4.45E-06 0. 1.53E-05 5.22E-06 2.17E-07 CS136 1.76E-05 4.62E-05 3.14E-05 0. 2.58E-05 3.93E-06 1.1 3E-06 CS137+D 2.45E-04 2.23E-04 3.47E-05 0. 7.63E-05 2.81 E-05 9.78E-07 CS138 1.71 E-07 2.27E-07 1.50E-07 0. 1.68E-07 1.84E-08 7.29E-08 CS139+D 1.09E-07 1.15E-07 5.80E-08 0. 9.08E-08 9.36E-09 7.23E-12 BA13E9 4.98E-1 0 2.66E-13 1.45E-11 0. 2.33E-13 1.56E-06 1.56E-05 BA140+D 2.OOE-05 1.75E-08 1.17E-06 0. 5.71 E-09 4.71 E-04 2.75E-05 BA141+D 5.29E-1 1 2.95E-14 1.72E-12 0. 2.56E-14 7.89E-07 7.44E-08 BA142+D 1.35E-11 9.73E-15 7.54E-1 3 0. 7.87E-1 5 4.44E-07 7.41 E-10 LA140 1.74E-07 6.08E-08 2.04E-08 0. 0. 4.94E-05 6.10E-05 LA141 2.28E-09 5.31 E-10 1.15E-10 0. 0. 4.48E-06 4.37E-05 LA142 3.50E-10 1.11E-10 3.49E-1 I 0. 0. 2.35E-06 2.05E-05 CE141 1.06E-05 5.28E-06 7.83E-07 0. 2.31 E-06 1.47E-04 1.53E-05 CE143+D 9.89E-08 5.37E-08 7.77E-09 0. 2.26E-08 3.12E-05 3.44E-05 CE144+D 1.83E-03 5.72E-04 9.77E-05 0. 3.17E-04 3.23E-03 1.05E-04 PR143 4.99E-06 1.50E-06 2.47E-07 0. 8.11E-07 1.17E-04 2.63E-05 PR14. 1.61 E-11 4.99E-12 8.10E-13 0. 2.64E-12 4.23E-07 5.32E-08 ND147+D 2.92E-06 2.36E-06 1.84E-07 0. 1.30E-06 8.87E-05 2.22E-05 PM14,' 3.52E-04 2.52E-05 1.36E-05 0. 4.45E-05 2.20E-04 5.70E-06 PM148M+D 3.31 E-05 6.55E-06 6.55E-06 0. 9.74E-06 5.72E-04 3.58E-05 PM148 1.61 E-06 1.94E-07 1.25E-07 0. 3.30E-07 1.24E-04 6.01 E-05 PM149 1.47E-07 1.56E-08 8.45E-09 0. 2.75E-08 2.40E-05 2.92E-05 PM15'1 3.57E-08 4.33E-09 2.82E-09 0. 7.35E-09 1.24E-05 2.50E-05 SM151 3.14E-04 4.75E-05 1.49E-05 0. 4.89E-05 1.48E-04 3.43E-06 SM153 7.24E-08 4.51 E-08 4.35E-09 0. 1.37E-08 1.37E-05 1.87E-05 EU152 7.42E-04 1.37E-04 1.61 E-04 0. 5.73E-04 9.OOE-04 1.14E-05 EU154 2.74E-03 2.49E-04 2.27E-04 0. 1.09E-03 1.66E-03 2.98E-05 EU155 5.60E-04 4.05E-05 3.18E-05 0. 1.51 E-04 2.79E-04 5.39E-05 EU15E 7.89E-06 4.23E-06 8.75E-07 0. 2.72E-06 2.54E-04 4.24E-05 TB160 7.79E-05 0. 9.67E-06 0. 2.32E-05 5.34E-04 2.28E-05 HO166M 1.34E-03 2.81 E-04 2.37E-04 0. 4.01 E-04 1.13E-03 1.63E-05 Wi 81 2.66E-08 6.52E-09 8.99E-10 0. 0. 5.71 E-06 2.61 E-07 W185 8.31 E-07 2.08E-07 2.91 E-08 0. 0. 1.86E-04 1.11E-05 Wi 87 4.41E-09 2.61E-09 1.17E-09 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 3.73E-07 0. 1.OOE-08 0. 0. 3.66E-05 6.99E-05 Y91M+D 4.63E-11 0. 1.77E-12 0. 0. 4.00E-07 3.77E-09 Y91 8.26E-05 0. 2.21E-06 0. 0. 3.67E-04 5.11E-05 Y92 1.84E-09 0. 5.36E-11 0. 0. 3.35E-06 2.06E-05 Y93 1.69E-08 0. 4.65E-10 0. 0. 1.04E-05 7.24E-05 ZR93+D 6.83E-05 3.38E-05 1.84E-05 0. 1.16E-04 3.67E-04 1.60E-05 ZR95i D 1.82E-05 5.73E-06 3.94E-06 0. 8.42E-06 3.36E-04 1.86E-05 ZR97 0 1.72E-08 3.40E-09 1.57E-09 0. 5.15E-09 1.62E-05 7.88E-05 NB93PA 4.14E-05 1.36E-05 3.41E-06 0. 1.59E-05 5.36E-05 2.52E-06 NB95 2.32E-06 1.29E-06 7.08E-07 0. 1.25E-06 9.39E-05 1.21 E-05 NB97 3.92E-11 9.72E-12 3.55E-12 0. 1.14E-11 4.91 E-07 2.71 E-07 M093 0. 1.66E-06 4.52E-08 0. 5.06E-07 8.81 E-05 3.99E-06 M099+D 0. 2.11E-08 4.03E-09 0. 5.14E-08 1.92E-05 3.36E-05 TC99hl 1.73E-13 4.83E-13 6.24E-12 0. 7.20E-12 1.44E-07 7.66E-07 TC99 4.48E-08 6.58E-08 1.79E-08 0. 8.35E-07 1.74E-04 7.99E-06 TC101 7.40E-15 1.05E-14 1.03E-13 0. 1.90E-13 8.34E-08 1.09E-16 RU 103+D 2.63E-07 0. 1.12E-07 0. 9.29E-07 9.79E-05 1.36E-05 RU10'i+D 1.40E-10 0. 5.42E-11 0. 1.76E-10 2.27E-06 1.13E-05 RU106+D 1.23E-05 0. 1.55E-06 0. 2.38E-05 2.01 E-03 1.20E-04 RH105' 1.32E-09 9.48E-10 6.24E-10 0. 4.04E-09 4.09E-06 1.23E-05 PD107 0. 1.17E-07 8.39E-09 0. 9.39E-07 1.63E-05 7.49E-07 PD10' 0. 6.56E-10 1.66E-10 0. 3.36E-09 3.19E-06 1.96E-05 AG110M+D 1.73E-06 1.64E-06 9.99E-07 0. 3.13E-06 8.44E-04 3.41 E-05 AG111 6.07E-08 2.52E-08 1.26E-08 0. 8.17E-08 4.00E-05 3.00E-05 CD11.M 0. 2.17E-04 7.10E-06 0. 2.43E-04 3.59E-04 1.68E-05 CD11M 0. 3.48E-05 1.14E-06 0. 2.82E-05 3.03E-04 5.10E-05 SN123 4.31E-05 9.44E-07 1.40E-06 7.55E-07 0. 4.96E-04 4.16E-05 SN125+D 1.66E-06 4.42E-08 9.99E-08 3.45E-08 0. 1.26E-04 7.29E-05 SN126+D 2.18E-04 5.39E-06 8.24E-06 1.42E-06 0. 1.72E-03 1.68E-05 SB124 5.38E-06 9.92E-08 2.10E-06 1.22E-08 0. 4.81 E-04 4.98E-05 SB125+D 9.23E-06 1.01E-07 2.15E-06 8.80E-09 0. 3.42E-04 1.24E-05 SB126 6.19E-07 1.27E-08 2.23E-07 3.50E-09 0. 1.55E-04 6.01 E-05 SB127 4.64E-08 9.92E-10 1.75E-08 5.21 E-10 0. 3.31 E-05 3.94E-05 TE125M 6.10E-07 2.80E-07 8.34E-08 1.75E-07 0. 6.70E-05 9.38E-06 TE127M+D 2.25E-06 1.02E-06 2.73E-07 5.48E-07 8.17E-06 2.07E-04 1.99E-05 TE127 2.51 E-10 1.14E-10 5.52E-11 1.77E-10 9.10E-10 1.40E-06 1.01 E-05 TE129\M+D 1.74E-06 8.23E-07 2.81E-07 5.72E-07 6.49E-06 2.47E-04 5.06E-05 TE129 8.87E-12 4.22E-12 2.20E-12 6.48E-12 3.32E-11 4.12E-07 2.02E-07 TE1311M+D 1.23E-08 7.51E-09 5.03E-09 9.06E-09 5.49E-08 2.97E-05 7.76E-05 TE131+D 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72E-12 2.92E-07 1.89E-09 TE132+D 4.50E-08 3.63E-08 2.74E-08 3.07E-08 2.44E-07 5.61 E-05 5.79E-05 TE133:M+D 1.01 E-1 1 7.33E-12 5.71E-12 8.18E-12 5.07E-11 8.71 E-07 1.23E-07 TE134 +D 5.31E-12 4.35E-12 3.64E-12 4.46E-12 2.91E-11 6.75E-07 1.37E-09 1129 3.53E-06 2.94E-06 4.90E-06 3.66E-03 5.26E-06 0. 2.29E-07 1130 7.80E-07 2.24E-06 8.96E-07 1.86E-04 3.44E-06 0. 1.14E-06 1131 +ED 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.99E-07 5.47E-07 1.97E-07 1.89E-05 8.65E-07 0. 1.59E-07 1133+D 1.52E-06 2.56E-06 7.78E-07 3.65E-04 4.49E-06 0. 1.29E-06 1134 1.11E-07 2.90E-07 1.05E-07 4.94E-06 4.58E-07 0. 2.55E-09 1135+D 4.62E-07 1.18E-06 4.36E-07 7.76E-05 1.86E-06 0. 8.69E-07 XE13lM 0. 0. 0. 0. 0. 2.70E-09 0.

XE13:3M 0. 0. 0. 0. 0. 3.59E-09 0.

XE13:3 0. 0. 0. 0. 0. 2.99E-09 0.

XE1 3!5M 0. 0. 0. 0. 0. 3.88E-09 0.

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

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

XE1 313+D 0. 0. 0. 0. 0. 4.38E-08 0.

CS1 34M+D 2.20E-08 4.35E-08 2.35E-08 0. 2.54E-08 4.56E-09 2.02E-08 CS131 6.28E-05 1.41 E-04 6.86E-05 0. 4.69E-05 1.83E-05 1.22E-06 CS135 2.08E-05 1.82E-05 4.47E-06 0. 7.30E-06 2.70E-06 2.23E-07 CS13i; 6.44E-06 2.42E-05 1.71 E-05 0. 1.38E-05 2.22E-06 1.36E-06 CS1 3'r+D 8.38E-05 1.06E-04 3.89E-05 0. 3.80E-05 1.51 E-05 1.06E-06 CS1383 5.82E-08 1.07E-07 5.58E-08 0. 8.28E-08 9.84E-09 3.38E-11 CS0139+0 3.65E-08 5.12E-08 1.97E-08 0. 4.34E-08 4.86E-09 1.66E-23 BA139 1.67E-10 1.18E-13 4.87E-12 0. 1.11E-13 8.08E-07 8.06E-07 BA140+D 6.84E-06 8.38E-09 4.40E-07 0. 2.85E-09 2.54E-04 2.86E-05 BA14'1+D 1.78E-1 1 1.32E-14 5.93E-1 3 0. 1.23E-14 4.11E-07 9.33E-14 BA1 42+D 4.62E-1 2 4.63E-15 2.84E-13 0. 3.92E-15 2.39E-07 5.99E-20 LA14C 5.99E-08 2.95E-08 7.82E-09 0. 0. 2.68E-05 6.09E-05 LA141 7.63E-1 0 2.35E-1 0 3.87E-1 1 0. 0. 2.31 E-06 1.54E-05 LA142 1.20E-1 0 5.31 E-11 1.32E-1 1 0. 0. 1.27E-06 1.50E-06 CE14'1 3.55E-06 2.37E-06 2.71 E-07 0. 1.11E-06 7.67E-05 1.58E-05 CE143+D 3.32E-08 2.42E-08 2.70E-09 0. 1.08E-08 1.63E-05 3.19E-05 CE14'1+D 6.11E-04 2.53E-04 3.28E-05 0. 1.51 E-04 1.67E-03 1.08E-04 PR143 1.67E-06 6.64E-07 8.28E-08 0. 3.86E-07 6.04E-05 2.67E-05 PR144 5.37E-12 2.20E-12 2.72E-13 0. 1.26E-12 2.19E-07 2.94E-14 ND14,'+D 9.83E-07 1.07E-06 6.41 E-08 0. 6.28E-07 4.65E-05 2.28E-05 PM14.' 1.15E-04 1.10E-05 4.50E-06 0. 2.10E-05 1.14E-04 5.87E-06 PM1411M+D 1.32E-05 3.35E-06 2.62E-06 0. 5.07E-06 3.20E-04 4.10E-05 PM148 5.44E-07 8.88E-08 4.48E-08 0. 1.60E-07 6.52E-05 6.14E-05 PM149 4.91 E-08 6.89E-09 2.84E-09 0. 1.31 E-08 1.24E-05 2.79E-05 PM151 1 .20E-08 1.99E-09 1.01E-09 0. 3.57E-09 6.56E-06 2.27E-05 SM15', 1.07E-04 2.10E-05 4.86E-06 0. 2.27E-05 7.68E-05 3.53E-06 SM153 2.43E-08 2.01 E-08 1.47E-09 0. 6.56E-09 7.11 E-06 1.77E-05 EU15z 2.96E-04 7.19E-05 6.30E-05 0. 3.34E-04 5.01 E-04 1.35E-05 EU154 9.43E-04 1.23E-04 8.60E-05 0. 5.44E-04 9.12E-04 3.34E-05 EU15E 2.OOE-04 1.96E-05 1.21 E-05 0. 7.65E-05 1.51 E-03 5.97E-05 EU15C 2.70E-06 2.03E-06 3.30E-07 0. 1.36E-06 1.37E-04 4.56E-05 TB160 3.04E-05 0. 3.79E-06 0. 1.20E-05 2.97E-04 2.60E-05 HO1 66M 4.40E-04 1.36E-04 9.87E-05 0. 2.00E-04 6.24E-04 1.68E-05 W181 8.90E-09 2.88E-09 3.01E-10 0. 0. 2.95E-06 2.69E-07 W185 2.78E-07 9.17E-08 9.73E-09 0. 0. 9.60E-05 1.14E-05 W1 87 1.50E-09 1.22E-09 4.29E-10 0. 0. 5.92E-06 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 2.61 E-07 0. 7.01 E-09 0. 0. 2.12E-05 6.32E-05 Y91M+ID 3.26E-1 I 0. 1.27E-1 2 0. 0. 2.40E-07 1.66E-10 Y91 5.78E-05 0. 1.55E-06 0. 0. 2.13E-04 4.81 E-05 Y92 1.29E-09 0. 3.77E-1 1 0. 0. 1.96E-06 9.19E-06 Y93 1.18E-08 0. 3.26E-1 0 0. 0. 6.06E-06 5.27E-05 ZR93+D 5.22E-05 2.92E-06 1.37E-06 0. 1.11 E-05 2.13E-05 1.51 E-06 ZR95+D 1.34E-05 4.30E-06 2.91 E-06 0. 6.77E-06 2.21 E-04 1.88E-05 ZR97+D 1.21 E-08 2.45E-09 1.13E-09 0. 3.71 E-09 9.84E-06 6.54E-05 NB93M 3.10E-05 1.01E-05 2.49E-06 0. 1.16E-05 3.11E-05 2.38E-06 NB95 1.76E-06 9.77E-07 5.26E-07 0. 9.67E-07 6.31 E-05 1.30E-05 NB97 2.78E-1 1 7.03E-1 2 2.56E-1 2 0. 8.18E-12 3.OOE-07 3.02E-08 M093 0. 1.17E-06 3.17E-08 0. 3.55E-07 5.11E-05 3.79E-06 M099--D 0. 1.51 E-08 2.87E-09 0. 3.64E-08 1.14E-05 3.10E-05 TC99M 1.29E-13 3.64E-1 3 4.63E-1 2 0. 5.52E-12 9.55E-08 5.20E-07 TC99 3.13E-08 4.64E-08 1.25E-08 0. 5.85E-07 1.01 E-04 7.54E-06 TC1 01 5.22E-1 5 7.52E-1 5 7.38E-1 4 0. 1.35E-13 4.99E-08 1.36E-21 RU103+D 1.91 E-07 0. 8.23E-08 0. 7.29E-07 6.31 E-05 1.38E-05 RU105+D 9.88E-1 I 0. 3.89E-1 1 0. 1.27E-10 1.37E-06 6.02E-06 RU106+D 8.64E-06 0. 1.09E-06 0. 1.67E-05 1.17E-03 1.14E-04 RH105 9.24E-1 0 6.73E-1 0 4.43E-1 0 0. 2.86E-09 2.41 E-06 1.09E-05 PD107 0. 8.27E-08 5.87E-09 0. 6.57E-07 9.47E-06 7.06E-07 PD109 0. 4.63E-1 0 1.16E-10 0. 2.35E-09 1.85E-06 1.52E-05 AG11CM+D 1.35E-06 1.25E-06 7.43E-07 0. 2.46E-06 5.79E-04 3.78E-05 AG111 4.25E-08 1.78E-08 8.87E-09 0. 5.74E-08 2.33E-05 2.79E-05 CD113M 0. 1.54E-04 4.97E-06 0. 1.71 E-04 2.08E-04 1.59E-05 CD1 15M 0. 2.46E-05 7.95E-07 0. 1.98E-05 1.76E-04 4.80E-05 SN123 3.02E-05 6.67E-07 9.82E-07 5.67E-07 0. 2.88E-04 3.92E-05 SN 125+D 1.16E-06 3.12E-08 7.03E-08 2.59E-08 0. 7.37E-05 6.81 E-05 SN1 26+D 1 .58E-04 4.1 8E-06 6.OOE-06 1.23E-06 0. 1.17E-03 1.59E-05 SB124 3.90E-06 7.36E-08 1 .55E-06 9.44E-09 0. 3.10E-04 5.08E-05 SB1251-D 6.67E-06 7.44E-08 1 .58E-06 6.75E-09 0. 2.18E-04 1.26E-05 SB126 4.50E-07 9.1 3E-09 1.62E-07 2.75E-09 0. 9.57E-05 6.01 E-05 SB127 3.30E-08 7.22E-1 0 1.27E-08 3.97E-10 0. 2.05E-05 3.77E-05 TE1 25M 4.27E-07 1.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 TE1 27M+D 1.58E-06 7.21 E-07 1.96E-07 4.11E-07 5.72E-06 1.20E-04 1.87E-05 TE127 1.75E-1 0 8.03E-1 1 3.87E-1 1 1.32E-10 6.37E-1 0 8.14E-07 7.17E-06 TE129:M+D 1 .22E-06 5.84E-07 1.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 TE129 6.22E-1 2 2.99E-1 2 1.55E-12 4.87E-12 2.34E-1 1 2.42E-07 1.96E-08 TE131 M+D 8.74E-09 5.45E-09 3.63E-09 6.88E-09 3.86E-08 1.82E-05 6.95E-05 TE131+D 1 .39E-12 7.44E-13 4.49E-1 3 1.17E-12 5.46E-12 1.74E-07 2.30E-09 TE132+D 3.25E-08 2.69E-08 2.02E-08 2.37E-08 1.82E-07 3.60E-05 6.37E-05 TE1 33M+D 7.24E-12 5.40E-1 2 4.17E-12 6.27E-12 3.74E-1 1 5.51 E-07 5.49E-08 TE1 34+D 3.84E-1 2 3.22E-12 1.57E-1 2 3.44E-12 2.18E-11 4.343-07 2.97E-11 1129 2.48E-06 2.11E-06 6.91 E-06 5.54E-03 4.53E-06 0. 2.22E-07 1130 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61 E-06 0. 9.61 E-07 1131 +C 3.1 5E-06 4.47E-06 2.56E-06 1.49E-03 7.66E-06 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.45E-07 4.07E-07 1.45E-07 1.43E-05 6.48E-07 0. 5.08E-08 1133+E) 1.08E-06 1.85E-06 5.65E-07 2.69E-04 3.23E-06 0. 1.11E-06 1134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0. 1.26E-10 1135+D 3.35E-07 8.73E-07 3.21 E-07 5.60E-05 1.39E-06 0. 6.56E-07 XE131M 0. 0. 0. 0. 0. 1.40E-09 0.

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

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

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

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

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

XE138+D 0. 0. 0. 0. 0. 2.44E-08 0.

CS134M+D 1.59E-08 3.20E-08 1.72E-08 0. 1.83E-08 2.93E-09 7.92E-09 CS134 4.66E-05 1.06E-04 9.10E-05 0. 3.59E-05 1.22E-05 1.30E-06 CS135 1.46E-05 1.29E-05 5.99E-06 0. 5.11E-06 1.57E-06 2.11 E-07 CS13E 4.88E-06 1.83E-05 1.38E-05 0. 1.07E-05 1.50E-06 1.46E-06 CS137+D 5.98E-05 7.76E-05 5.35E-05 0. 2.78E-05 9.40E-06 1.05E-06 CS13E 4.14E-08 7.76E-08 4.05E-08 0. 6.OOE-08 6.07E-09 2.33E-1 3 CS139+D 2.56E-08 3.63E-08 1.39E-08 0. 3.05E-08 2.84E-09 5.49E-31 BA1 39 1.17E-10 8.32E-14 3.42E-12 0. 7.78E-14 4.70E-07 1.12E-07 BA140+D 4.88E-06 6.13E-09 3.21 E-07 0. 2.09E-09 1.59E-04 2.73E-05 BA141+D 1.25E-1 1 9.41 E-15 4.20E-13 0. 8.75E-1 5 2.42E-07 1.45E-17 BA142+D 3.29E-12 3.38E-1 5 2.07E-13 0. 2.86E-1 5 1.49E-07 1.96E-26 LA140 4.30E-08 2.17E-08 5.73E-09 0. 0. 1.70E-05 5.73E-05 LA141 5.34E-10 1.66E-10 2.71 E-11 0. 0. 1.35E-06 7.31 E-06 LA142 8.54E-11 3.88E-1 1 9.65E-12 0. 0. 7.91 E-07 2.64E-07 CE141 2.49E-06 1.69E-06 1.91 E-07 0. 7.83E-07 4.52E-05 1.50E-05 CE142+D 2.33E-08 1.72E-08 1.91 E-09 0. 7.60E-09 9.97E-06 2.83E-05 CE144+D 4.29E-04 1.79E-04 2.30E-05 0. 1.06E-04 9.72E-04 1.02E-04 PR142 1.17E-06 4.69E-07 5.80E-08 0. 2.70E-07 3.51 E-05 2.50E-05 PR144 3.76E-12 1.56E-12 1.91 E-13 0. 8.81 E-1 3 1.27E-07 2.69E-18 ND147 +D 6.59E-07 7.62E-07 4.56E-08 0. 4.45E-07 2.76E-05 2.16E-05 PM147 8.37E-05 7.87E-06 3.19E-06 0. 1.49E-05 6.60E-05 5.54E-06 PM14(.M+D 9.82E-06 2.54E-06 1.94E-06 0. 3.85E-06 2.14E-04 4.18E-05 PM14E8 3.84E-07 6.37E-08 3.20E-08 0. 1.20E-07 3.91E-05 5.80E-05 PM149 3.44E-08 4.87E-09 1.99E-09 0. 9.19E-09 7.21 E-06 2.50E-05 PM151 8.50E-09 1.42E-09 7.21 E-1 0 0. 2.55E-09 3.94E-06 2.OOE-05 SM151 8.59E-05 1.48E-05 3.55E-06 0. 1.66E-05 4.45E-05 3.25E-06 SM153 1.70E-08 1.42E-08 1.04E-09 0. 4.59E-09 4.14E-06 1.58E-05 EU 152 2.38E-04 5.41 E-05 4.76E-05 0. 3.35E-04 3.43E-04 1.59E-05 EU154 7.40E-04 9.1 OE-05 6.48E-05 0. 4.36E-04 5.84E-04 3.40E-05 EU155 1.01 E-04 1.43E-05 9.21 E-06 0. 6.59E-05 9.46E-05 5.95E-06 EU156E 1.93E-06 1.48E-06 2.40E-07 0. 9.95E-07 8.56E-05 4.50E-05 TB160 2.21 E-05 0. 2.75E-06 0. 9.10E-06 1.92E-04 2.68E-05 HO166M 3.37E-04 1.05E-04 8.OOE-05 0. 1.57E-04 3.94E-04 1.59E-05 Wi 81 6.23E-09 2.03E-09 2.17E-10 0. 0. 1.71 E-06 2.53E-07 W185 1.95E-07 6.47E-08 6.81 E-09 0. 0. 5.57E-05 1.07E-05 W187 1.06E-09 8.85E-10 3.1 OE-10 0. 0. 3.63E-06 1.94E-05 60

PALISADES NUCLEAR PLANT 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 61

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 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 62

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 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 3.60E-09 4.20E-09 Ru-1 05 4.50E-09 5.1 OE-09 Ru-106 1.50E-09 1.80E-09 Ag-1 Om 1.80E-08 2.1 OE-08 Te-125m 3.50E-11 4.80E-11 Te-127m 1.10E-12 1.30E-12 Te-127 1.OOE-11 1.1 OE-11 Te-129m 7.70E-10 9.OOE-1 0 Te-129 7.1OE-10 8.40E-1 0 Te-131 m 8.40E-09 9.90E-09 Te-131 2.20E-09 2.60E-06 Te-132 1.70E-09 2.OOE-09 1-130 1.40E-08 1.70E-08 1-131 2.80E-09 3.40E-09 1-132 1.70E-08 2.OOE-08 1-133 3.70E-09 4.50E-09 1-134 1.60E-08 1.90E-08 1-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.40E-08 Cs-136 1.50E-08 1.70E-08 Cs-1 37 4.20E-09 4.90E-09 Cs-1 38 2.1 OE-08 2.40E-08 Ba-139 2.40E-09 2.70E-09 Ba-140 2.1 OE-09 2.40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.90E-09 9.OOE-09 La-140 1.50E-08 1.70E-08 La-142 1.50E-08 1.80E-08 Ce-141 5.50E-1 0 6.20E-1 0 Ce-143 2.20E-09 2.50E-09 Ce-144 3.20E-1 0 3.70E-I 0 Pr-143 0.0 0.0 Pr-1 44 2.OOE-1 0 2.30E-1 0 Nd-147 1.OOE-09 1.20E-09 W-187 3.1 OE-09 3.60E-09 Np-239 9.50E-1 0 1.1OE-09 63

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Oraan Mrem/Ci Ci Ac-110m GI-Tract-T 2.13E+00 7.04E+00 Ar*41 Total Body 3.64E - 04 1.37E+04 Ba-139 GI Tract-C 2.97E - 03 5.05E+03 Ba-140 Lung-T 1.26E - 01 1.19E+02 BrP82 total Body-C 4.97E - 03 1.01 E+03 C-14 Bone-C 1.48E - 01 1.01 E+02 CE-141 Gl Tract-T 1.34E - 01 1.12E+02 Ce!-144 Gl Tract-T 3.37E+00 4.45E+00 Cc-57 Gl Tract-T 8.53E - 02 1.76E+02 Cc-58 Gl Tract-T 2.59E - 01 5.79E+01 Cc-60 Gl Tract-T 6.86E+00 2.19E+00 Cr 51 GI Tract-A 3.75E - 03 1.33E+03 Cs-134 Liver-C 8.77E+00 1.71 E+00 Cs-136 Liver-I 5.99E - 01 2.50E+01 Cs-137 Bone-C 9.58E+00 1.57E+00 Cs-1 38 Total body-C 1.OOE - 01 5.OOE+01 Fe-55 Bone-C 2.06E - 01 7.28E+01 Fe-59 Gl Tract-T 3.20E - 01 4.69E+01 H-:3 Total Body-C 2.19E - 04 2.28E+04 1-129 Thyroid-A 3.66E+02 4.1OE - 02 1-1.31 Thyroid-I 2.21 E+01 6.79E - 01 I 1-1:32 Thyroid-C 1.12E - 02 1.34E+03 1-1:33 Thyroid-C 2.46E - 01 6.11E+01 1-1:34 Thyroid-C 2.45E - 03 6.12E+03 1-1:35 Thyroid-C 4.93E - 02 3.04E+02 64

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci Ci Kr-83m Skin 8.82E - 07 1.70E+07 Kr-85 Skin 9.14E - 05 1.64E+05 Kr-85m Total Body 5.22E - 05 9.58E+04 Kr-87 Skin 8.03E - 04 1.87E+04 Kr-88 Total Body 6.35E - 04 7.87E+03 Kr-89 Total Body 5.08E - 04 9.84E+03 La-140 GI Tract-T 3.04E - 02 4.93E+02 Mn-54 GI Tract-T 6.29E - 01 2.38E+01 Mn-56 GI Tract-C 6.91 E - 03 2.17E+03 Mo-99 GI Tract-T 1.66E - 02 9.04E+02 N-13 Total Body-C 3.44E - 06 1.45E+06 Na-24 Total Body-C 4.02E - 03 1.24E+03 Nb-95 GI Tract-A 2.47E - 01 6.07E+01 I Ni -63 Bone-C 1.21 E+01 1.24E+00 Ni.*65 GI Tract-C 4.70E - 03 3.19E+03 Np-239 GI Tract-T 8.13E - 03 1.84E+03 Rb-88 Total Body-C 2.38E - 05 2.1 OE+05 Ru-1 03 GI Tract-A 3.80E - 01 3.95E+01 Ru-1 05 GI Tract-C 5.82E - 03 2.58E+03 St,-124 GI Tract-T 9.47E - 01 1.58E+01 St-125 GI Tract-T 4.35E - 01 3.45E+01 Sr**89 Bone-C 8.98E+00 1.67E+00 Sr-*90 Bone-C 3.73E+02 4.02E - 02 Sr**91 Bone-I 2.46E+00 6.1 OE+00 Sr-*92 GI Tract-C 1.37E - 02 1.09E+03 65

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 1.9 PALISADES GASEOUS DESIGN OBJECTIVE ANNUAL QUANTITIES Design Objective Dose Factor Annual Quantity Nuclide Organ Mrem/Ci Ci Tc-99 GI Tract-T 5.85E - 01 2.62E+01 Tc- 99m GI Tract-T 3.64E - 04 4.12E+04 Tc-*101 GI Tract-T 8.33E - 05 1.80E+05 Te-127 GI Tract-T 4.87E - 03 3.08E+03 Xe-131m Skin 4.03E - 05 3.72E+05 Xe-133 Total Body 1.39E - 05 3.60E+05 Xe-133m Skin 8.39E - 05 1.79E+05 Xe-135 Total Body 8.32E - 05 6.01 E+04 Xe-135m Total Body 9.55E - 05 5.24E+04 Xe-137 Skin 5.85E - 04 2.56E+04 Xe-138 Total body 2.70E - 04 1.85E+04 Zn*-65 Liver-C 9.38E - 01 1.60E+01 Zr-95 GI Tract-T 3.90E - 01 3.85E+01 Pu -238 Bone-T 1.42E+03 1.06E - 02 Pu -239 Bone-T 1.64E+03 9.15E - 03 Pu -241 Bone-T 3.45E+01 4.35E - 01 Arm-241 Bone-T 5.25E+02 2.86E - 02 Cm-242 Lung-T 3.35E+01 4.48E - 01 Cm-244 Bone-T 3.20E+02 4.69E - 02 66

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL 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.

67

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20

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 EC 1 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.

68

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day with a total collection of approximately one gallon per day. A representative sample is collected daily from the compositor and saved for the weekly, monthly analysis requirements of Appendix A, Table D-1. In the event that a compositor is not operational, effluent releases via this pathway may continue provided that grab samples are collected and analyzed for gross beta or gamma radioactivity at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months per Appendix A, Table C-1, Action 3.

69

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20

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.

70

PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20

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.

71

PALISADES NUJCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 (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.

1E06 = 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 Annual released of ith radionuclide, [tCi.

Bi Fish concentration factor of ith radionuclide pCilg n pCi/ml (see Table 2.0).

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

15 = Dispersion factor from discharge to fish exposure point.

d = Dilution water flow for year, ml.

1E09 = Conversion of piCi and Kgm to gross.

Substiltution of Equation 2.9 into Equation 2.6 gives:

DJ =(6.7E07)F E AixBixDCFiMreM (2.10) d i=1 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.

Isfor water ingestion is described by:

I= Ai Vr pCi (2.13) vd and for fish ingestion 11is 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

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PALISADES NUCLEAR PLANT OFFSITE DOSE CALCULATION MANUAL Revision 20 TABLE 2.0 BIOACCUMULATION FACTORS uCi/cm ner uCi/ml FRESHWATER ELEMENT FISH H 9.OE-01 C 4.6E 03 NA 1.OE 02 P I.OE 05 CR 2.OE 02 MN 4.OE 02 FE 1.OE 02 CO 5.OE 01 NI 1.0E 02 CU 5.OE 01 ZN 2.OE 03 BR 4.2E 02 RB 2.OE 03 SR 3.OE 01 y 2.5E 01 ZR 3.3E 00 NB 3.0E 04 MO 1.OE 01 TC 1.5E 01 RU 1.OE 01 RH 1.OE 01 TE 4.OE 02 I 1.5E 01 CS 2.OE 03 BA 4.0E 00 LA 2.5E 01 CE 1.OE 00 PR 2.5E 01 ND 2.5E 01 W 1.2E 03 NP 1.OE 01 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. 2.0 7 E-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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 8.69E-08 0. 2.33E-09 0. 0. 0. 1.20E-04 Y91MfD 8.1OE-10 0. 2.76E-1 1 0. 0. 0. 2.70E-06 Y91 1.13E-06 0. 3.01 E-08 0. 0. 0. 8.1 GE-05 Y92 7.65E-09 0. 2.15E-10 0. 0. 0. 1.46E-04 Y93 2.43E-08 0. 6.62E-10 0. 0. 0. 1.92E-04 ZR93--D 1.93E-07 9.18E-08 5.54E-08 0. 2.71 E-07 0. 2.39E-05 ZR95i-D 2.06E-07 5.02E-08 3.56E-08 0. 5.41 E-08 0. 2.50E-05 ZR97T-D 1.48E-08 2.54E-09 1.16E-09 0. 2.56E-09 0. 1.62E-04 NB93M 1.23E-07 3.33E-08 1.04E-08 0. 3.25E-08 0. 3.98E-06 NB95 4.20E-08 1.73E-08 1.OOE-08 0. 1.24E-08 0. 1.46E-05 NB97 4.59E-1 0 9.79E-11 3.53E-1 I 0. 7.65E-1 1 0. 3.09E-05 M093 0. 5.65E-05 1.82E-06 0. 1.13E-05 0. 1.21 E-06 M099+D 0. 3.40E-05 6.63E-06 0. 5.08E-05 0. 1.12E-05 TC99tA 1.92E-09 3.96E-09 5.10E-08 0. 4.26E-08 2.07E-09 1.15E-06 TC99 1.08E-06 1.46E-06 4.55E-07 0. 1.23E-05 1.42E-07 6.31 E-06 TC100 2.27E-09 2.86E-09 2.83E-08 0. 3.40E-08 1.56E-09 4.86E-07 RU103+D 1.48E-06 0. 4.95E-07 0. 3.08E-06 0. 1.80E-05 RU 10!;+D 1.36E-07 0. 4.58E-08 0. 1.OOE-06 0. 5.41 E-05 RU106+D 2.41 E-05 0. 3.01E-06 0. 2.85E-05 0. 1.83E-04 RH105 1.09E-06 7.13E-07 4.79E-07 0. 1.98E-06 0. 1.77E-05 PD107 0. 1.19E-06 8.45E-08 0. 6.79E-06 0. 9.46E-07 PD10" 0. 1.50E-06 3.62E-07 0. 5.51 E-06 0. 3.68E-05 AG11 (M+D 9.96E-07 7.27E-07 4.81 E-07 0. 1.04E-06 0. 3.77E-05 AG11 l 5.20E-07 2.02E-07 1.07E-07 0. 4.22E-07 0. 4.82E-05 CD113M 0. 1.77E-05 6.52E-07 0. 1.34E-05 0. 2.66E-05 CD116M 0. 1.42E-05 4.93E-07 0. 7.41 E-06 0. 8.09E-05 SN123 2.49E-04 3.89E-06 6.50E-06 3.91 E-06 0. 0. 6.5BE-05 SN12'+D 7.41 E-05 1.38E-06 3.29E-06 1.36E-06 0. 0. 1.11 E-04 SN126+D 5.53E-04 7.26E-06 1.80E-05 1.91E-06 0. 0. 2.52E-05 SB124- 2.14E-05 3.15E-07 6.63E-06 5.68E-08 0. 1.34E-05 6.6DE-05 SB12r +D 1.23E-05 1.1 9E-07 2.53E-06 1.54E-08 0. 7.72E-06 1.64E-05 SB126 8.06E-06 1.58E-07 2.91 E-06 6.19E-08 0. 5.07E-06 8.35E-05 SB127 2.23E-06 3.98E-08 6.90E-07 2.84E-08 0. 1.15E-06 5.91 E-05 TE125M 2.33E-05 7.79E-06 3.15E-06 7.84E-06 0. 0. 1.11E-05 TE127M+D 5.85E-05 1.94E-05 7.08E-06 1.69E-05 1.44E-04 0. 2.35E-05 TE127 1.OOE-06 3.35E-07 2.15E-07 8.14E-07 2.44E-06 0. 2.1 OE-05 TE129M+D 1.OOE-04 3.43E-05 1.54E-05 3.84E-05 2.50E-04 0. 5.97E-05 TE129 2.84E-07 9.79E-08 6.63E-08 2.38E-07 7.07E-07 0. 2.27E-05 TE131M+D 1.52E-05 6.12E-06 5.05E-06 1.24E-05 4.21 E-05 0. 1.03E-04 TE131+D 1.76E-07 6.50E-08 4.94E-08 1.57E-07 4.50E-07 0. 7.11E-06 TE132+D 2.08E-05 1.03E-05 9.61 E-06 1.52E-05 6.44E-05 0. 3.81 E-05 TE133M+D 3.91 E-07 1.79E-07 1.71 E-07 3.45E-07 1.22E-06 0. 1.93E-05 TE134+D 2.67E-07 1.34E-07 1.38E-07 2.39E-07 9.03E-07 0. 3.05E-06 1129 2.86E-05 2.12E-05 1.55E-05 1.36E-02 2.51 E-05 0. 4.24E-07 1130 6.OOE-06 1.32E-05 5.30E-06 1.48E-03 1.45E-05 0. 2.83E-06 1131+C) 3.59E-05 4.23E-05 1.86E-05 1.39E-02 4.94E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 1.66E-06 3.37E-06 1.20E-06 1.58E-04 3.76E-06 0. 2.73E.06 11 33+ED 1.25E-05 1.82E-05 5.33E-06 3.31 E-03 2.14E-05 0. 3.08E-06 1134 8.69E-07 1.78E-06 6.33E-07 4.15E-05 1.99E-06 0. 1.84E-06 1135+ED 3.64E-06 7.24E-06 2.64E-06 6.49E-04 8.07E-06 0. 2.62E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

XE138*D 0. 0. 0. 0. 0. 0. 0.

CS134M+D 1.76E-07 2.93E-07 1.48E-07 0. 1.13E-07 2.60E-08 2.32E-07 CS134 3.77E-04 7.03E-04 7.1 OE-05 0. 1.81 E-04 7.42E-05 1.91 E-06 CS135 1.33E-04 1.21 E-04 6.30E-06 0. 3.44E-05 1.31 E-05 4.37E-07 CS136 4.59E-05 1.35E-04 5.04E-05 0. 5.38E-05 1.10E-05 2.0!5E-06 CS137+D 5.22E-04 6.11E-04 4.33E-05 0. 1.64E-04 6.64E-05 1.91 E-06 CS138 4.81 E-07 7.82E-07 3.79E-07 0. 3.90E-07 6.09E-08 1.25E-06 CS139+D 3.10E-07 4.24E-07 1.62E-07 0. 2.19E-07 3.30E-08 2.66E-08 BA139 8.81 E-07 5.84E-10 2.55E-08 0. 3.51 E-1 0 3.54E-10 5.58E-05 BA140 FD 1.71 E-04 1.71 E-07 8.81 E-06 0. 4.06E-08 1.05E-07 4.20E-05 BA141 fD 4.25E-07 2.91 E-10 1.34E-08 0. 1.75E-10 1.77E-1 0 5.1 9E-06 BA142 .D 1.84E-07 1.53E-10 9.06E-09 0. 8.81 E-11 9.26E-1 1 7.59E-07 LA140 2.11E-08 8.32E-09 2.14E-09 0. 0. 0. 9.7,'E-05 LA141 2.89E-09 8.38E-10 1.46E-10 0. 0. 0. 9.6-1 E-05 LA142 1.10E-09 4.04E-10 9.67E-1 1 0. 0. 0. 6.86E-05 CE141 7.87E-08 4.80E-08 5.65E-09 0. 1.48E-08 0. 2.48E-05 CE143+D 1.48E-08 9.82E-06 1.12E-09 0. 2.86E-09 0. 5.73E-05 CE144 D 2.98E-06 1.22E-06 1.67E-07 0. 4.93E-07 0. 1.7'1E-04 PR143 8.18E-08 3.04E-08 4.03E-09 0. 1.13E-08 0. 4.29E-05 PR144 2.74E-10 1.06E-10 1.38E-11 0. 3.84E-1 1 0. 4.93E-06 ND147+D 5.53E-08 5.68E-08 3.48E-09 0. 2.19E-08 0. 3.60E-05 PM147 3.88E-07 3.27E-08 1.59E-08 0. 4.88E-08 0. 9.27E-06 PM148M+D 1.65E-07 4.18E-08 3.28E-08 0. 4.80E-08 0. 5.4':3-05 PM148 6.32E-08 9.13E-09 4.60E-09 0. 1.09E-08 0. 9.74E-05 PM149 1.38E-08 1.81 E-09 7.90E-1 0 0. 2.20E-09 0. 4.86E-05 PM151 6.18E-09 9.01 E-1 0 4.56E-1 0 0. 1.07E-09 0. 4.1;'E-05 SM151 2.90E-07 6.67E-08 1.44E-08 0. 4.53E-08 0. 5.58E-06 SM153 7.72E-09 5.97E-09 4.58E-1 0 0. 1.25E-09 0. 3.1,2E-05 EU152 6.74E-07 1.79E-07 1.51 E-07 0. 5.02E-07 0. 1.59E-05 EU154 2.64E-06 3.67E-07 2.20E-07 0. 9.95E-07 0. 4.58E-05 EU155 5.42E-07 6.25E-08 3.23E-08 0. 1.40E-07 0. 8.37E-05 EU156 1.14E-07 7.06E-08 1.12E-08 0. 3.26E-08 0. 6.67E-05 TB160 2.59E-07 0. 3.24E-08 0. 7.37E-08 0. 3.45E-05 H0166M 1.25E-06 2.69E-07 2.13E-07 0. 3.57E-07 0. 0.

W181 8.85E-08 2.72E-08 3.04E-09 0. 0. 0. 3.82E-07 W185 3.62E-06 1.13E-06 1.29E-07 0. 0. 0. 1.62E-05 W187 9.03E-07 6.28E-07 2.17E-07 0. 0. 0. 3.69E-05 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 4.11E-08 0. 1.10E-09 0. 0. 0. 1.17E-04 Y91 M+D 3.82E-1 0 0. 1.39E-1 1 0. 0. 0. 7.48E-07 Y91 6.02E-07 0. 1.61 E-08 0. 0. 0. 8.02E-05 Y92 3.60E-09 0. 1.03E-1 0 0. 0. 0. 1.04E-04 Y93 1.14E-08 0. 3.13E-10 0. 0. 0. 1.70E-04 ZR931+D 1.67E-07 6.25E-08 4.45E-08 0. 2.42E-07 0. 2.37E-05 ZR95 D 1.16E-07 2.55E-08 2.27E-08 0. 3.65E-08 0. 2.66E-05 ZR97 0 6.99E-09 1.01 E-09 5.96E-1 0 0. 1.45E-09 0. 1.53E-04 NB93M 1.05E-07 2.62E-08 8.61 E-09 0. 2.83E-08 0. 3.95E-06 NB95 2.25E-08 8.76E-09 6.26E-09 0. 8.23E-09 0. 1.62E-05 NB97 2.17E-10 3.92E-1 1 1.83E-1 1 0. 4.35E-1 1 0. 1.21 E-05 M093 0. 2.41 E-05 8.65E-07 0. 6.35E-06 0. 1.22E-06 M099 FD 0. 1.33E-05 3.29E-06 0. 2.84E-05 0. 1.1OE-05 TC99M 9.23E-1 0 1.81 E-09 3.OOE-08 0. 2.63E-08 9.19E-10 1.03E-06 TC99 5.35E-07 5.96E-07 2.14E-07 0. 7.02E-06 5.27E-08 6.25E-06 TC101 1.07E-09 1.12E-09 1.42E-08 0. 1.91 E-08 5.92E-10 3.55E-09 RU 103+D 7.31 E-07 0. 2.81 E-07 0. 1.84E-06 0. 1.89E-05 RU105+D 6.45E-08 0. 2.34E-08 0. 5.67E-07 0. 4.21 E-05 RU 106+D 1.17E-05 0. 1.46E-06 0. 1.58E-05 0. 1.82E-04 RHI105 5.14E-07 2.76E-07 2.36E-07 0. 1.10E-06 0. 1.71 E-05 PD107 0. 4.72E-07 4.01 E-08 0. 3.95E-06 0. 9.37E-07 PD10S 0. 5.67E-07 1.70E-07 0. 3.04E-06 0. 3.35E-05 AG1 1C0M+D 5.39E-07 3.64E-07 2.91 E-07 0. 6.78E-07 0. 4.33E-05 AG111 2.48E-07 7.76E-08 5.12E-08 0. 2.34E-07 0. 4.7.5E-05 CD1$1 3M 0. 1.02E-05 4.34E-07 0. 1.05E-05 0. 2.63E-05 CD11 M 0. 5.89E-06 2.51 E-07 0. 4.38E-06 0. 8.01 E-05 SN123 1.33E-04 1.65E-06 3.24E-06 1.75E-06 0. 0. 6.5:2E-05 SN125+D 3.55E-05 5.35E-07 1.59E-06 5.55E-07 0. 0. 1.10E-04 SN126+D 3.33E-04 4.15E-06 9.46E-06 1.14E-06 0. 0. 2.50E-05 SB124 1.11 E-05 1.44E-07 3.89E-06 2.45E-08 0. 6.16E-06 6.94E-05 SB125+D 7.16E-06 5.52E-08 1.50E-06 6.63E-09 0. 3.99E-06 1.71 E-05 SB126 4.40E-06 6.73E-08 1.58E-06 2.58E-08 0. 2.10E-06 8.8.7E-05 SB127 1.06E-06 1.64E-08 3.68E-07 1.18E-08 0. 4.60E-07 5.97E-05 TE125M 1.14E-05 3.09E-06 1.52E-06 3.20E-06 0. 0. 1.10E-05 TE127M+D 2.89E-05 7.78E-06 3.43E-06 6.91 E-06 8.24E-05 0. 2.34E-05 TE127 4.71 E-07 1.27E-07 1.01 E-07 3.26E-07 1.34E-06 0. 1.84E-05 TE129M+D 4.87E-05 1.36E-05 7.56E-06 1.57E-05 1.43E-04 0. 5.94E-05 TE129 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0. 8.34E-06 TE131 M+D 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.41 E-05 0. 1.0 IE-04 TE131 +D 8.30E-08 2.53E-08 2.47E-08 6.35E-08 2.51 E-07 0. 4.31jE-07 TE132tD 1.01 E-05 4.47E-06 5.40E-06 6.51 E-06 4.15E-05 0. 4.50E-05 TE133VM+D 1.87E-07 7.56E-08 9.37E-08 1.45E-07 7.18E-07 0. 5.7.7E-06 TE134tD 1.29E-07 5.80E-08 7.74E-08 1.02E-07 5.37E-07 0. 5.8!3E-07 1129 1.39E-05 8.53E-06 7.62E-06 5.58E-03 1.44E-05 0. 4.29E-07 1130 2.92E-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0. 2.76E-06 1131 +D 1.72E-05 1.73E-05 9.83E-06 5.72E-03 2.84E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 8.OOE-07 1.47E-06 6.76E-07 6.82E-05 2.25E-06 0. 1.73E-06 1133+[) 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.22E-05 0. 2.95E-06 1134 4.1 9E-07 7.78E-07 3.58E-07 1.79E-05 1.19E-06 0. 5.16E-07 1135+1) 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0. 2.40E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

XE1 3lM 0. 0. 0. 0. 0. 0. 0.

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

XE1 35M 0. 0. 0. 0. 0. 0. 0.

XE13t; 0. 0. 0. 0. 0. 0. 0.

XE137' 0. 0. 0. 0. 0. 0. 0.

XE138+D 0. 0. 0. 0. 0. 0. 0.

CS13LM+D 8.44E-08 1.25E-07 8.1 6E-08 0. 6.59E-08 1.09E-08 1.58E-07 CS13'- 2.34E-04 3.84E-04 8.10E-05 0. 1.1 9E-04 4.27E-05 2.07E-06 CS13' 8.30E-05 5.78E-05 5.93E-06 0. 2.04E-05 6.81 E-06 4.33E-07 CS13E; 2.35E-05 6.46E-05 4.18E-05 0. 3.44E-05 5.13E-06 2.27E-06 CS137,+D 3.27E-04 3.1 3E-04 4.62E-05 0. 1.02E-04 3.67E-05 1.96E-06 CS138 2.28E-07 3.1 7E-07 2.01 E-07 0. 2.23E-07 2.40E-08 1.46E-07 CS1 39+D 1.45E-07 1.61 E-07 7.74E-08 0. 1.21 E-07 1.22E-08 1.45E-1 1 BA1 39 4.14E-07 2.21 E-1 0 1.20E-08 0. 1.93E-10 1.30E-10 2.39E-05 BA14C0+D 8.31 E-05 7.28E-08 4.85E-06 0. 2.37E-08 4.34E-08 4.21 E-05 BA141 +D 2.00E-07 1.12E-10 6.51 E-09 0. 9.69E-1 1 6.58E-1 0 1.14E-07 BA14z+D 8.74E-08 6.29E-1 I 4.88E-09 0. 5.09E-1 1 3.70E-1 I 1.14E-09 LA140 1.01 E-08 3.53E-09 1.19E-09 0. 0. 0. 9.84E-05 LA141 1.35E-09 3.17E-10 6.88E-1 1 0. 0. 0. 7.05E-05 LA142 5.24E-10 1.67E-1 0 5.23E-1 1 0. 0. 0. 3.31 E-05 CE141 3.97E-08 1.98E-08 2.94E-09 0. 8.68E-09 0. 2.47E-05 CE143+D 6.99E-09 3.79E-06 5.49E-1 0 0. 1.59E-09 0. 5.55E-05 CE144 +D 2.08E-06 6.52E-07 1.11E-07 0. 3.61 E-07 0. 1.7DE-04 PR148 3.93E-08 1.18E-08 1.95E-09 0. 6.39E-09 0. 4.24E-05 PR144 1.29E-10 3.99E-1 1 6.49E-12 0. 2.11E-11 0. 8.53E-08 ND14,'+D 2.79E-08 2.26E-08 1.75E-09 0. 1.24E-08 0. 3.53E-05 PM147 3.1 8E-07 2.27E-08 1.22E-08 0. 4.01 E-08 0. 9.19E-06 PM148M+D 1.03E-07 2.05E-08 2.05E-08 0. 3.04E-08 0. 5.73E-05 PM148i 3.02E-08 3.63E-09 2.35E-09 0. 6.17E-09 0. 9.703E-05 PM14" 6.49E-09 6.90E-1 0 3.74E-1 0 0. 1.22E-09 0. 4.71 E-05 PM15' 2.92E-09 3.55E-1 0 2.31 E-1 0 0. 6.02E-1 0 0. 4.03E-05 SM151 2.56E-07 3.81 E-08 1.20E-08 0. 3.94E-08 0. 5.53E-06 SM1 5'i 3.65E-09 2.27E-09 2.19E-10 0. 6.91E-10 0. 3.02E-05 EU152 6.15E-07 1.12E-07 1.33E-07 0. 4.73E-07 0. 1.84E-05 EU154 2.30E-06 2.07E-07 1.89E-07 0. 9.09E-07 0. 4.81 E-05 EU155 4.82E-07 3.47E-08 2.72E-08 0. 1.30E-07 0. 8.69E-05 EU15C 5.62E-08 3.01 E-08 6.23E-09 0. 1.94E-08 0. 6.8.3E-05 TB160 1.66E-07 0. 2.06E-08 0. 4.94E-08 0. 3.63E-05 HO1 66M 1.08E-06 2.26E-07 1.91 E-07 0. 3.22E-07 0. 0.

W181 4.23E-06 1.04E-08 1.43E-09 0. 0. 0. 3.7!9E-07 W1 85 1.73E-06 4.32E-07 6.05E-08 0. 0. 0. 1.61 E-05 W187 4.29E-07 2.54E-07 1.14E-07 0. 0. 0. 3.57E-05 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 1.37E-08 0. 3.69E-1 0 0. 0. 0. 1.13E-04 Y91 M D 1.29E-1 0 0. 4.93E-1 2 0. 0. 0. 6.09E-09 Y91 2.01 E-07 0. 5.39E-09 0. 0. 0. 8.24E-05 Y92 1.21 E-09 0. 3.50E-1 1 0. 0. 0. 3.32E-05 Y93 3.83E-09 0. 1.05E-1 0 0. 0. 0. 1.1 YE-04 ZR93+D 5.53E-08 2.73E-08 1.49E-08 0. 9.65E-08 0. 2.58E-05 ZR95+D 4.12E-08 1.30E-08 8.94E-09 0. 1.91 E-08 0. 3.OOE-05 ZR97+D 2.37E-09 4.69E-10 2.16E-10 0. 7.11E-10 0. 1.2; E-04 NB93M 3.44E-08 1.13E-08 2.83E-09 0. 1.32E-08 0. 4.0; E-06 NB95 8.22E-09 4.56E-09 2.51 E-09 0. 4.42E-09 0. 1.9!;E-05 NB97 7.37E-1 1 1.83E-1 1 6.68E-12 0. 2.14E-11 0. 4.3 7E-07 M093 0. 1.06E-05 2.90E-07 0. 3.04E-06 0. 1.29E-06 M099+1D 0. 6.03E-06 1.15E-06 0. 1.38E-05 0. 1.08E-05 TC99M 3.32E-10 9.26E-10 1.20E-08 0. 1.38E-08 5.14E-10 6.08E-07 TC99 1.79E-07 2.63E-07 7.17E-08 0. 3.34E-06 2.72E-08 6.41E-06 TC1 01 3.60E-1 0 5.12E-10 5.03E-09 0. 9.26E-09 3.12E-10 8.7!iE-17 RU1 03+D 2.55E-07 0. 1.09E-07 0. 8.99E-07 0. 2.13E-05 RU1 05+D 2.1 8E-08 0. 8.46E-09 0. 2.75E-07 0. 1.76E-05 RU1 06+D 3.92E-06 0. 4.94E-07 0. 7.56E-06 0. 1.88E-04 RH105 1.73E-07 1.25E-07 8.20E-08 0. 5.31 E-07 0. 1.59E-05 PD107 0. 2.08E-07 1.34E-08 0. 1.88E-06 0. 9.66E-07 PD109 0. 2.51 E-07 5.70E-08 0. 1.45E-06 0. 2.53E-05 AG11OM+D 2.05E-07 1.94E-07 1.18E-07 0. 3.70E-07 0. 5.45E-05 AG111 8.29E-08 3.44E-08 1.73E-08 0. 1.12E-07 0. 4.80E-05 CD113M 0. 4.51 E-06 1.45E-07 0. 4.99E-06 0. 2.71 E-05 CD1 15M 0. 2.60E-06 8.39E-08 0. 2.08E-06 0. 8.23E-05 SN123 4.44E-05 7.29E-07 1.08E-06 5.84E-07 0. 0. 6.71 E-05 SN 125+D 1.19E-05 2.37E-07 5.37E-07 1.86E-07 0. 0. 1.1 2E-04 SN126+D 1.16E-04 2.1 6E-06 3.30E-06 5.69E-07 0. 0. 2.58E-05 SB124 3.87E-06 7.13E-08 1.51 E-06 8.78E-09 0. 3.38E-06 7.80E-05 SB1254FD 2.48E-06 2.71 E-08 5.80E-07 2.37E-09 0. 2.18E-06 1.93E-05 SB126 1.59E-06 3.25E-08 5.71 E-07 8.99E-09 0. 1.14E-06 9.4'1 E-05 SB127 3.63E-07 7.76E-09 1.37E-07 4.08E-09 0. 2.47E-07 6.16E-05 TE125M 3.83E-06 1.38E-06 5.12E-07 1.07E-06 0. 0. 1.13E-05 TE127M+D 9.67E-06 3.43E-06 1.15E-06 2.30E-06 3.92E-05 0. 2.41 E-05 TE127 1.58E-07 5.60E-08 3.40E-08 1.09E-07 6.40E-07 0. 1.22E-05 TE129M+D 1.63E-05 6.05E-06 2.58E-06 5.26E-06 6.82E-05 0. 6.12E-05 TE129 4.48E-08 1.67E-08 1.09E-08 3.20E-08 1.88E-07 0. 2.45E-07 TE1 31 M+D 2.44E-06 1.17E-06 9.76E-07 1.76E-06 1.22E-05 0. 9.39E-05 TE131+D 2.79E-08 1.15E-08 8.72E-09 2.15E-08 1.22E-07 0. 2.29E-09 TE1 32+D 3.49E-06 2.21 E-06 2.08E-06 2.33E-06 2.12E-05 0. 7.OOE-05 TE1 33M+D 6.44E-08 3.66E-08 3.56E-08 5.11E-08 3.62E-07 0. 1.48E-07 TE134+D 4.47E-08 2.87E-08 3.OOE-08 3.67E-08 2.74E-07 0. 1.66E-09 1129 4.66E-06 3.92E-06 6.54E-06 4.77E-03 7.01 E-06 0. 4.5; E-07 1130 1.03E-06 2.98E-06 1.19E-06 2.43E-04 4.59E-06 0. 2.29E-06 1131+ED 5.85E-06 8.1 9E-06 4.40E-06 2.39E-03 1.41 E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 2.79E-07 7.30E-07 2.62E-07 2.46E-05 1.15E-06 0. 3.113E-07 1133+CI 2.01 E-06 3.41 E-06 1.04E-06 4.76E-04 5.98E-06 0. 2.513E-06 1134 1.46E-07 3.87E-07 1.39E-07 6.45E-06 6.10E-07 0. 5.1 OE-09 1135+D 6.10E-07 1.57E-06 5.82E-07 1.01E-04 2.48E-06 0. 1.74E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

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

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

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

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

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

XE138+D 0. 0. 0. 0. 0. 0. 0.

CS134M+D 2.94E-08 6.09E-08 3.13E-08 0. 3.39E-08 5.95E-09 4.05E-08 CS134 8.37E-05 1.97E-04 9.14E-05 0. 6.26E-05 2.39E-05 2.45E-06 CS135 2.78E-05 2.55E-05 5.96E-06 0. 9.73E-06 3.52E-06 4.4(6E-07 CS136 8.59E-06 3.38E-05 2.27E-05 0. 1.84E-05 2.90E-06 2.7:2E-06 CS137+D 1.12E-04 1.49E-04 5.19E-05 0. 5.07E-05 1.97E-05 2.1 :2E-06 CS138 7.76E-08 1.49E-07 7.45E-08 0. 1.10E-07 1.28E-08 6.76E-1 1 CS139+D 4.87E-08 7.17E-08 2.63E-08 0. 5.79E-08 6.34E-09 3.3:3E-23 BA139 1.39E-07 9.78E-1 1 4.05E-09 0. 9.22E-1 1 6.74E-11 1.24E-06 BA140+D 2.84E-05 3.48E-08 1.83E-06 0. 1.18E-08 2.34E-08 4.33E-05 BA141 +D 6.71 E-08 5.01 E-11 2.24E-09 0. 4.65E-1 1 3.43E-1 1 1.4:3E-1 3 BA142+D 2.99E-08 2.99E-1 1 1.84E-09 0. 2.53E-1 1 1.99E-11 9.1,3E-20 LA140 3.48E-09 1.71 E-09 4.55E-10 0. 0. 0. 9.8:2E-05 LA141 4.55E-10 1.40E-10 2.31 E-11 0. 0. 0. 2.4.3E-05 LA142 1.79E-10 7.95E-1 1 1.98E-1 1 0. 0. 0. 2.4:2E-06 CE141 1.33E-08 8.88E-09 1.02E-09 0. 4.18E-09 0. 2.54E-05 CE143+D 2.35E-09 1.71 E-06 1.91 E-10 0. 7.67E-1 0 0. 5.14E-05 CE144+D 6.96E-07 2.88E-07 3.74E-08 0. 1.72E-07 0. 1.7!5E-04 PR143 1.31 E-08 5.23E-09 6.52E-10 0. 3.04E-09 0. 4.3 1E-05 PR144 4.30E-1 I 1.76E-11 2.18E-12 0. 1.01E-11 0. 4.74E-14 ND147+D 9.38E-09 1.02E-08 6.11E-10 0. 5.99E-09 0. 3.63E-05 PM147 1.05E-07 9.96E-09 4.06E-09 0. 1.90E-08 0. 9.47E-06 PM 14;M+D 4.14E-08 1.05E-08 8.21 E-09 0. 1.59E-08 0. 6.61 E-05 PM14£i 1.02E-08 1.66E-09 8.36E-10 0. 3.OOE-09 0. 9.90E-05 PM149 2.17E-09 3.05E-1 0 1.25E-10 0. 5.81 E-10 0. 4.43E-05 PM151 9.87E-10 1.63E-10 8.25E-1 1 0. 2.93E-1 0 0. 3.613E-05 SM151 8.73E-08 1.68E-08 3.94E-09 0. 1.84E-08 0. 5.70E-06 SM153 1.22E-09 1.01 E-09 7.43E-1 I 0. 3.30E-10 0. 2.8 5E-05 EU152 2.45E-07 5.90E-08 5.20E-08 0. 2.74E-07 0. 2.17E-05 EU154 7.91 E-07 1.02E-07 7.19E-08 0. 4.56E-07 0. 5.3'3E-05 EU155 1.74E-07 1.68E-08 1.04E-08 0. 6.57E-08 0. 9.63E-05 EU156 1.92E-08 1.44E-08 2.35E-09 0. 9.69E-09 0. 7.33 E-05 TB160 6.47E-08 0. 8.07E-09 0. 2.56E-08 0. 4.19E-05 HO166M 3.57E-07 1.10E-07 7.96E-08 0. 1.61 E-07 0. 0.

W181 1.42E-08 4.58E-09 4.79E-1 0 0. 0. 0. 3.91)E-07 W185 5.79E-07 1.91 E-07 2.02E-08 0. 0. 0. 1.6,5E-05 W187 1.46E-07 1.19E-07 4.17E-08 0. 0. 0. 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 INFllRST YR)

ISOTCPE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI PB210+D 1.81 E-02 5.44E-03 7.01 E-04 0. 1.72E-02 0. 5.74E-05 B1210+D 6.59E-07 4.51 E-06 5.66E-08 0. 5.48E-05 0. 5.1 !;E-05 P021C 6.09E-04 1.07E-03 1.23E-04 0. 3.60E-03 0. 6.75E-05 RN222+D 0. 0. 0. 0. 0. 0. 0.

RA223+D 7.11E-03 1.08E-05 1.42E-03 0. 3.10E-04 0. 3.43E-04 RA224+D 2.31 E-03 5.52E-06 4.61 E-04 0. 1.58E-04 0. 3.71 E-04 RA225+D 9.37E-03 1.10E-05 1.87E-03 0. 3.15E-04 0. 3.2'E-04 RA226+D 3.22E-01 8.13E-06 2.39E-01 0. 2.32E-04 0. 3.51 E-04 RA228+D 1.37E-01 4.41 E-06 1.51E-01 0. 1.26E-04 0. 5.9l3E-05 AC225 6.29E-06 8.59E-06 4.22E-07 0. 9.85E-07 0. 4.31,E-04 AC227+D 2.05E-03 3.03E-04 1.22E-04 0. 8.81 E-05 0. 8.613E-05 TH227+D 1.96E-05 3.52E-07 5.65E-07 0. 2.01 E-06 0. 5.75E-04 TH228+D 6.80E-04 1.14E-05 2.30E-05 0. 6.41 E-05 0. 5.97E-04 TH229 8.39E-03 1.26E-04 4.11E-04 0. 6.1OE-04 0. 5.43E-04 TH230 2.16E-03 1.23E-04 6.OOE-05 0. 5.99E-04 0. 6.313E-05 TH232+D 2.42E-03 1.05E-04 1.63E-04 0. 5.11E-04 0. 5.43E-05 TH234 1.14E-07 6.68E-09 3.31 E-09 0. 3.81 E-08 0. 1.21 E-04 PA231+0 4.31E-03 1.62E-04 1.68E-04 0. 9.1OE-04 0. 7.60E-05 PA233 7.33E-09 1.41E-09 1.26E-09 0. 5.32E-09 0. 1.61 E-05 U232+D 5.89E-03 0. 4.21 E-04 0. 6.38E-04 0. 7.19E-05 U233+D 1.24E-03 0. 7.543-05 0. 2.90E-04 0. 6.65E-05 U234 1.19E-03 0. 7.39E-05 0. 2.85E-04 0. 6.51 E-05 U235+D 1.14E-03 0. 6.94E-05 0. 2.67E-04 0. 8.28E-05 U236 1.14E-03 0. 7.09E-05 0. 2.73E-04 0. 6.1 lE-05 U237 7.89E-08 0. 2.10E-08 0. 3.24E-07 0. 2.09E-05 U238+D 1.09E-03 0. 6.49E-05 0. 2.50E-04 0. 5.83E-05 NP237+D 1.44E-03 1.25E-04 5.85E-05 0. 4.33E-04 0. 8.41 E-05 NP238 1.95E-08 5.22E-10 3.04E-10 0. 1.79E-09 0. 3.83E-05 NP239 1.76E-09 1.66E-10 9.22E-1 1 0. 5.21 E-10 0. 2.6'E-05 PU238 7.21 E-04 1.02E-04 1.82E-05 0. 7.80E-05 0. 7.7:3E-05 PU239 8.27E-04 1.12E-04 2.01 E-05 0. 8.57E-05 0. 7.0fE-05 PU240 8.26E-04 1.12E-04 2.01 E-05 0. 8.56E-05 0. 7.1!9E-05 PU241 +D 1.84E-05 9.42E-07 3.69E-07 0. 1.71 E-06 0. 1.48E-06 PU242 7.66E-04 1.08E-04 1.94E-05 0. 8.25E-05 0. 6.92E-05 PU244 8.95E-04 1.23E-04 2.22E-05 0. 9.45E-05 0. 1.0:3E-04 AM241 8.62E-04 3.29E-04 5.75E-05 0. 4.31 E-04 0. 7.87E-05 AM242M 8.70E-04 3.19E-04 5.80E-05 0. 4.30E-04 0. 9.90E-05 AM24. 8.60E-04 3.17E-04 5.62E-05 0. 4.22E-04 0. 9.2:3E-05 CM24,' 2.94E-05 2.97E-05 1.95E-06 0. 8.89E-06 0. 8.40E-05 CM243I 6.91 E-04 2.86E-04 4.09E-05 0. 1.91E-04 0. 8.2i3E-05 CM24'. 5.32E-04 2.49E-04 3.19E-05 0. 1.49E-04 0. 8.00E-05 CM24'5 1.07E-03 3.33E-04 6.1 OE-05 0. 2.85E-04 0. 7.4'3E-05 CM246 1.06E-03 3.32E-04 6.09E-05 0. 2.84E-04 0. 7.3:3E-05 CM247,+D 1.03E-03 3.27E-04 6.OOE-05 0. 2.80E-04 0. 9.6:3E-05 CM248i 8.60E-03 2.69E-03 4.95E-04 0. 2.31 E-03 0. 1.5:5E-03 CR252 3.51 E-04 0. 8.37E-06 0. 0. 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI Y90 9.62E-09 0. 2.58E-10 0. 0. 0. 1.02E-04 Y91 M-D 9.09E-1 1 0. 3.52E-12 0. 0. 0. 2.67E-10 Y91 1.41 E-07 0. 3.77E-09 0. 0. 0. 7.7'3E-05 Y92 8.45E-10 0. 2.47E-1 1 0. 0. 0. 1.43E-05 Y93 2.68E-09 0. 7.40E-1 1 0. 0. 0. 8.50E-05 ZR934D 4.18E-08 2.34E-09 1.09E-09 0. 8.87E-09 0. 2.43E-06 ZR95i D 3.04E-08 9.75E-09 6.60E-09 0. 1.53E-08 0. 3.03E-05 ZR974 D 1.68E-09 3.39E-10 1.55E-10 0. 5.12E-10 0. 1.05E-04 NB93M 2.55E-08 8.32E-09 2.05E-09 0. 9.57E-09 0. 3.84E-06 NB95 6.22E-09 3.46E-09 1.86E-09 0. 3.42E-09 0. 2.1 DE-05 NB97 5.22E-1 1 1.32E-1 1 4.82E-12 0. 1.54E-11 0. 4.87E-08 M093 0. 7.51 E-06 2.03E-07 0. 2.13E-06 0. 1.22E-06 MO99 FD 0. 4.31 E-06 8.20E-07 0. 9.76E-06 0. 9.99E-06 TC99M 2.47E-10 6.98E-10 8.89E-09 0. 1.06E-08 3.42E-10 4.1 3E-07 TC99 1.25E-07 1.86E-07 5.02E-08 0. 2.34E-06 1.58E-08 6.OBE-06 TC101 2.54E-10 3.66E-10 3.59E-09 0. 6.59E-09 1.87E-10 1.1OE-21 RU 103+D 1.85E-07 0. 7.97E-08 0. 7.06E-07 0. 2.1 BE-05 RU10';+D 1.54E-08 0. 6.08E-09 0. 1.99E-07 0. 9.42E-06 RU106+D 2.75E-06 0. 3.48E-07 0. 5.31 E-06 0. 1.7BE-04 RH 105 1.21 E-07 8.85E-08 5.83E-08 0. 3.76E-07 0. 1.41 E-05 PD107 0. 1.47E-07 9.40E-09 0. 1.32E-06 0. 9.11E-07 PD109 0. 1.77E-07 3.99E-08 0. 1.01 E-06 0. 1.96E-05 AG11()M+D 1.60E-07 1.48E-07 8.79E-08 0. 2.91 E-07 0. 6.04E-05 AG 11' 5.81 E-08 2.43E-08 1.21 E-08 0. 7.84E-08 0. 4.46E-05 CD113M 0. 3.18E-06 1.02E-07 0. 3.50E-06 0. 2.56E-05 CD1 'iM 0. 1.84E-06 5.87E-08 0. 1.46E-06 0. 7.74E-05 SN123 3.11E-05 5.15E-07 7.59E-07 4.38E-07 0. 0. 6.33E-05 SN125+D 8.33E-06 1.68E-07 3.78E-07 1.39E-07 0. 0. 1.04E-04 SN 126+D 8.45E-05 1.67E-06 2.40E-06 4.92E-07 0. 0. 2.43E-05 SB124. 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0. 2.18E-06 7.95E-05 SB12';+D 1.79E-06 2.OOE-08 4.26E-07 1.82E-09 0. 1.38E-06 1.97E-05 SB126 1.15E-06 2.34E-08 4.15E-07 7.04E-09 0. 7.05E-07 9.40E-05 SB127' 2.58E-07 5.65E-09 9.90E-08 3.10E-09 0. 1.53E-07 5.90E-05 TE12;M 2.68E-06 9.71 E-07 3.59E-07 8.06E-07 1.09E-05 0. 1.07E-05 TE12EM+D 6.77E-06 2.42E-06 8.25E-07 1.73E-06 2.75E-05 0. 2.27E-05 TE127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.48E-07 0. 8.68E-06 TE12GM+D 1.15E-05 4.29E-06 1.82E-06 3.95E-06 4.80E-05 0. 5.79E-05 TE12S 3.14E-08 1.18E-08 7.65E-09 2.41 E-08 1.32E-07 0. 2.37E-08 TE131M+D 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0. 8.40E-05 TE131+D 1.97E-08 8.23E-09 6.22E-09 1.62E-08 8.63E-08 0. 2.79E-09 TE132+D 2.52E-06 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0. 7.71 E-05 TE133M+D 4.62E-08 2.70E-08 2.60E-08 3.91 E-08 2.67E-07 0. 6.64E-08 TE134+D 3.24E-08 2.12E-08 1.30E-08 2.83E-08 2.05E-07 0. 3.59E-1 1 1129 3.27E-06 2.81 E-06 9.21 E-06 7.23E-03 6.04E-06 0. 4.44E-07 1130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0. 1.92E-06 1131+1) 4.16E-06 5.95E-06 3.41 E-06 1.95E-03 1.02E-05 0. 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 BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI 1132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0. 1.02E-07 1133+[) 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.31 E-06 0. 2.22E-06 1134 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0. 2.51 E-10 1135+[) 4.43E-07 1.16E-06 4.28E-07 7.65E-05 1.86E-06 0. 1.31 E-06 XE131M 0. 0. 0. 0. 0. 0. 0.

XE13'M 0. 0. 0. 0. 0. 0. 0.

XE13'i 0. 0. 0. 0. 0. 0. 0.

XE13E5M 0. 0. 0. 0. 0. 0. 0.

XE13'; 0. 0. 0. 0. 0. 0. 0.

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

XE138+D 0. 0. 0. 0. 0. 0. 0.

CS 13-'M+D 2.13E-08 4.48E-08 2.29E-08 0. 2.43E-08 3.83E-09 1.5BE-08 CS134 6.22E-05 1.48E-04 1.21 E-04 0. 4.79E-05 1.59E-05 2.59E-06 CS13'i 1.95E-05 1.80E-05 7.99E-06 0. 6.81 E-06 2.04E-06 4.21 E-07 CS136 6.51 E-06 2.57E-05 1.85E-05 0. 1.43E-05 1.96E-06 2.92E-06 CS137+D 7.97E-05 1.09E-04 7.14E-05 0. 3.70E-05 1.23E-05 2.11E-06 CS138 6.52E-08 1.09E-07 5.40E-08 0. 8.01 E-08 7.91 E-09 4.65E-13 CS139+D 3.41 E-08 5.08E-08 1.85E-08 0. 4.07E-08 3.70E-09 1.1OE-30 BA13S' 9.70E-08 6.91 E-11 2.84E-09 0. 6.46E-1 1 3.92E-11 1.72E-07 BA14C+D 2.03E-05 2.55E-08 1.33E-06 0. 8.67E-09 1.46E-08 4.1 BE-05 BA141+D 4.71 E-08 3.56E-1 1 1.59E-09 0. 3.31 E-11 2.02E-1 1 2.22E-17 BA142z+D 2.13E-08 2.19E-1 1 1.34E-09 0. 1.85E-1 I 1.24E-11 3.00E-26 LA140 2.50E-09 1.26E-09 3.33E-10 0. 0. 0. 9.25E-05 LA141 3.19E-10 9.90E-1 1 1.62E-11 0. 0. 0. 1.1 BE-05 LA142 1.28E-10 5.82E-1 1 1.45E-11 0. 0. 0. 4.25E-07 CE141 9.36E-09 6.33E-09 7.18E-10 0. 2.94E-09 0. 2.42E-05 CEl43+D 1.65E-09 1.22E-06 1.35E-1 0 0. 5.37E-1 0 0. 4.55E-05 CE144+D 4.88E-07 2.04E-07 2.62E-08 0. 1.21 E-07 0. 1.65E-04 PR143 9.20E-09 3.69E-09 4.56E-1 0 0. 2.13E-09 0. 4.03E-05 PR14z. 3.01 E-1I 1.25E-1 1 1.53E-12 0. 7.05E-12 0. 4.33E-18 ND147+D 6.29E-09 7.27E-09 4.35E-10 0. 4.25E-09 0. 3.49E-05 PM147 7.54E-08 7.09E-09 2.87E-09 0. 1.34E-08 0. 8.93E-06 PM1411M+D 3.07E-08 7.95E-09 6.08E-09 0. 1.20E-08 0. 6.7 4E-05 PM148 7.17E-09 1.19E-09 5.99E-1 0 0. 2.25E-09 0. 9.3 5E-05 PM149 1.52E-09 2.15E-10 8.78E-11 0. 4.06E-10 0. 4.03E-05 PM151' 6.97E-1 0 1.17E-10 5.91 E-11 0. 2.09E-1 0 0. 3.2.2E-05 SM151 6.90E-08 1.19E-08 2.85E-09 0. 1.33E-08 0. 5.2 5E-06 SM153 8.57E-1 0 7.15E-10 5.22E-1 1 0. 2.31 E-1 0 0. 2.55E-05 EU15z 1.95E-07 4.44E-08 3.90E-08 0. 2.75E-07 0. 2.53E-05 EU154 6.15E-07 7.56E-08 5.38E-08 0. 3.62E-07 0. 5.43E-05 EU15E 8.60E-08 1.22E-08 7.87E-09 0. 5.63E-08 0. 9.6')E-06 EU15E 1.37E-08 1.06E-08 1.71 E-09 0. 7.08E-09 0. 7.23E-05 TB160 4.70E-08 0. 5.86E-09 0. 1.94E-08 0. 4.3:3E-05 HO 166M 2.70E-07 8.43E-08 6.40E-08 0. 1.26E-07 0. 0.

W181 9.91 E-09 3.23E-09 3.46E-10 0. 0. 0. 3.6;3E-07 W185 4.05E-07 1.35E-07 1.42E-08 0. 0. 0. 1.563E-05 W187 1.03E-07 8.61 E-08 3.01 E-08 0. 0. 0. 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 Design Objectiva Dose Conversion Annual Quantity Nuclidce Half-Life Factors (mrem/Ci) Individual/Organ (Curies)

H-3 12.3 yr 1.75E-06 AdulVtTB 1.71 E+OE Na-24 15 h 5.44E-03 Teen/TB 551.5 Sc-46 83.9 d 2.02E-02 Teen/TB 148.5 Cr-51 27.8 d 1.56E-03 AdultVGI (LLI) 6,410.0 Mn-54 303 d 3.50E-02 Teen/TB 85.7 Fe-55 2.6 yr 4.48E-03 Child/Bone 2,232.0 Mn-56 2.576 h 1.86E-03 Teen/TB 1,612.0 Co-57 270 d 4.39E-03 Teen/TB 683.4 Co-58 71.3 d 1.03E-02 Teen/TB 291.3 Fe-59 45.6 d 4.08E-02 Adult/GI (LLI) 245.1 Co-60 5.26 yr 4.71 E-01 Teen/TB 6.37 Cu-64 12.8 h 1.32E-03 Teen/GI (LLI) 7,575.0 Ni-65 2.56 h 5.82E-04 Teen/TB 5,154.0 Zn-65 245 d 1.83E-01 Teen/TB 16.4 Br-84 31.8 mo 2.02E-03 Teen/TB 1,485.2 Rb-86 1.02 mo 3.06E-01 Child/TB 9.80 Rb-88 17.8 mo 6.92E-04 Teen/TB 4,335.3 Sr-89 52.7 d 1.56E-01 Child/Bone 64.1 Sr-90 27.7 yr 2.71 E-00 Adult/Bone 3.69 Sr-91 9.67 h 1.16E-03 Teen/TB 2,586.0 Sr-92 2.71 h 1.51 E-03 Teen/TB 1,986.8 Y-92 3.53 h 2.69E-04 Teen/TB 11,150.0 Nb-95 35 d 7.24E+00 Adult/GI (LLI) 1.38 Zr-95 65.5 d 6.17E-03 Teen/TB 486.2 Nb-97 72 mo 6.95E-04 TeenlTB 4,316.6 Zr-97 17 h 9.28E-04 Teen/TB 3,232.8 Mo-99 66.7 h 1.11E-03 Teen/Kidney 9,009.0 Tc-99m 6.05 h 1.42E-04 Teen/TB 21,126.8 Ru-1 03 39.5 d 2.74E-03 TeenlTB 1,094.9 Ag-11(1m 255 d 7.75E-02 Teen/TB 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months per quarter (average of approximately 1/2 hour per day each day of the quarter) for the second and third quarters of the year, 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months for the fourth quarter and 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months for the first quarter.

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 1.

Description:

Provide a brief description of the change.

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 LIlNo

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 reliabilityof 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

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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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Table of Contents 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 10CFR50.36a. 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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H. PROCESS CONTROL PROGRAM (PCP)

- shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10CFR Part 20, 10CFR 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 10CFR Part 50.

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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 3250 F 4 (RIA 2323 and 2324) Steam Line Modes 1, 2, 3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

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

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

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

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

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

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Table A-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements IntuetChannel Instrument 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 3250 F

a. Gross Gamma Activity Monitor 0 M R(3) 0(2) Modes 1, 2, 3 D ___________ Modes____2__3

6. ENGINEERED SAFEGUARDS PUMP ROOM VENTILATION HIGH RADIATION SYSTEM

a. Noble Gas Activity Monitor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 31 days 18 months (3) 31 days(1)(2) Above 2100F (Technical Specifications SR 3.3.10 and Modes 1, 2, 3, 4 SR 3.7.-3.iJ) I 11

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.

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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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

TABLE FREQUENCY NOTATION S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months M At least once per 31 days P Prior to 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 10CFR 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, 10CFR 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 1x 104 C. Stack Gas Effluent Wd,e ContinuousC Charcoal 1-131, 1-133 1x 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 1E-06 CuriiinuousC AIuliLoC

__ _r __ _r r-.--

%.:__ s D Ld Gt ar i -

dii I _ _ _ _ _ _ _ _ _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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after changing or after removal from sampler.

e With channels operable on iodine monitor RIA 2325 less than required per 11I.A.1, sampling shall also be performed at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, start-up or Thermal Power change exceeding 15 percent of Rated Thermal Power in one hour and analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing. When samples collected for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if, 1) analysis shows that the Dose Equivalent 1-131 concentration in the primary coolant has not increased more than a factor of 3, and 2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.

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E. GASEOUS WASTE TREATMENT SYSTEM

1. Requirement When gaseous waste exceeds a Xe-133 concentration of 1E-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 10CFR Part 20. The Operability and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10CFR Part 50.

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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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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

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

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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 . NEER'~.~¶II.~VYI~¶ STEAM ATOR BLOWII r~~I WSNSI .,JVMIA% COMPO ELUENTSAITLERZ o~~L~~I_____ () N ANA NA P.dIA I

16. STEAM GENERATOR BLOWDOWN EFFLUENT COMPOSITER lD(4) lNA l NA l 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous or batch releases are made.

(5) Turbine Sump Discharge Flow Meter FQI-5210 was calibrated at factory and doesn't require recalibration.

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

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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 105l One Batch/M (Gamma Emitters)

P M H-3 1 x 10o-Each Batch Composited Gross Alpha 1x 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 1x 1046 Blowdown, and Service Water)

M M Dissolved and Entrained Gases Grab Sample (Gamma Emitters) 1x l0o5 Continuousf M H-3 1 x 10o-

. Compositef Gross Alpha I x 10'T Continuousf Q Sr-89, Sr-90 5x 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 10CFR Part 20.2203, shall include an analysis that estimates the radiation exposure (dose) to a Member of the Public from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release(s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved and the cause of the exposure levels or concentrations. If the estimated dose(s) exceeds the above limits, and if the release condition resulting in violation of 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 1OCR 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 1OUR 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 implementsSection 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 10CFR 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 changed. 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 I 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

e Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

A composite sample is one in which the quantity (aliquot) of liquid samples is proportional to the quantity of liquid discharged and in which the method of sampling employed results in a specimen that is representative of the liquid released (continuous composites or daily grab composites which meet this criteria are acceptable).

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/m 3) (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. This is 40CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/l may be used.

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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 I Cs-137 18 0.06 150 18 80 180 Ba-La-140 1 15 1 l j l_

If no drinking water pathway exists, a value of 3,000 pCi/l may be used.

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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 10CFR 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 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Radiological Effluent Release Report.

3. Surveillance Requirement The concentration of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of the 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 10CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an Unrestricted Area.

(The dilution between Palisades and the South Haven drinking water supply has been established as 1000.)

Tanks included in this specification are those outdoor tanks that are 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowed outage time limits of the action requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Surveillance Requirements do not have to be performed on inoperable equipment.

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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.

PALISADES NUCLEAR PLANT ODCM OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 11 Page 57 of 59 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

Table F-1 Environmental Radiological Monitoring Program Summary Name of Facility Docket No Location of Facility Reporting Period_

(Conntv- State)

Medium or Pathway Type/Total Lower Limit All Indicator b Control Locations Number of l (Unit of Measure) l NDeutectifon l Mean Distance & Direction Range Rang-e OCCR EN SaitofMpedsre Anlss DtRin ea aeMa ~ Mangel REO RTABLENE Performed (LLD) Range ________ _______

Air Particulates Gross 13416 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.

PALISADES NUCLEAR PLANT ODCIA OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 11 Page 58 of 59 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

V. MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID AND GASEOUS WASTE TREATMENT SYSTEMS A. LICENSEE MODIFICATIONS Licensee initiated major modifications to the radioactive liquid and gaseous waste systems.

1. Shall be reported to the NRC pursuant to 10CFR 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.

PALISADES NUCLEAR PLANT ODCIA OFFSITE DOSE CALCULATION MANUAL Appendix A Revision 11 Page 59 of 59 TITLE: RELOCATED TECHNICAL SPECIFICATIONS PER NRC GENERIC LETTER 89-01 (TAC NO 75060)

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.

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