Text

JAFNPP - Site Audit Requests - Offsite Dose Calculation Model (DVP-01.02, Rev 9)
	ML063630360
Person / Time
Site:	FitzPatrick
Issue date:	09/09/2004
From:	; Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
References
	DVP-01.02, Rev 09
	Download: ML063630360 (344)
	v • d • e

ENTERGY NUCLEAR OPERATIONS, INC.

JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCUMENTS AND VENDOR PROCEDURES OFFSITE DOSE CALCULATION MANUAL DVP -01. 02 REVISION 9 APPROVED BY: 6~ DATEr RESfONSIBLE PROCEDURE OWNER

-l APPROVED BY: '4- s. -. - DATE _ _ _ _

GENERAL MANAGER PLANT OPERAT~nd-EFFECTIVE DATE:

FIRST ISSUE 13 FULL REVISION 0 LIMITED REVISION 0

INFORMATIONAL USE * *TSR*

~TECHNICAL*

PERIODICREVIEW DUE DATE

OFFSITE DOSE CALCULATION MANUAL DP-1.0 DVP-01. 02

Rev. CHANGE AND REASON FOR CHANGE 9 1. Part I (REC) Page 02, Section 1.2:

Under Document Revision Overview, changed paragraph to reflect that this revision is revision 09 as DVP-0l.02 and revision 18 since the inception of the ODCM as CDP-15.

Reason: To incorporate this revision into the document history. This change increases the accuracy of the ODCM.

2. Part I (REC) Page 20, Section 3.1.1.c.4:

Added the following before the existing paragraph:

"Alarm/trip setpoints are determined in accordance with Part 2, Section 4.3.2 to ensure the limits of Section 3.2.1 are not exceeded."

Reason: This information was inadvertently deleted

,during the ITS rewrite of DVP-0l.02 during the transition of RETS to the ODCM when references to the ODCM were deleted. This information is being restored to this section to ensure the(

correct reference is identified. This change-increases the accuracy of the ODCM.

3. Part I CREC) Page 21, Table 3.1-1:

Deleted footnotes (d) and (e) from the table.

Reason: This is an administrative change to eliminate a duplication of a portion of an existing definition that is stated in the Technical specifications. Note (d) duplicates a portion of the definition of the term 'operable'. Note Ce) also duplicates a portion of the definition of the term 'operable' . Change was made to eliminate the potential for confusion regarding what these notes might mean or require. This change does not decrease the accuracy of the ODCM.

Rev. No. 9ODCM, Summary of Changes Page 1 of 9

OFFSITE DOSE CALCULATION MANUAL DVP-01. 02 DP010

4. Part I (REC) Page 43, Section 5.1.2:

Changed "ODCM (Appendix A)" to "ODCM (Appendix H)"

Reason: Incorrect section referenced. Environmental monitoring sampling is located in Appendix H.

This change increases the accuracy of the ODCM.

5. Part II, Page 02, Section 1.3:

Under Document Revision overview, changed paragraph to reflect that this revision is revision 09 as DVP-0l.02 and revision 18 since the inception of the ODCM as CDP-Reason: To inco rporate this revision into the document history. This change increases the accuracy of the ODCM.

6. Part II, Page 12, Section 3.3.3.1.d.

corrected a typographical error in the example equation. The ECL value for Co-60 was incorrectly listed as 3E-2. The correct value is 3E-5 for Co-GO.

This change increases the accuracy of the ODCM.

Reason: Correction of a typographical error. This change increases the accuracy of the ODCM.

7. Part II, Page 27, Section 3.5.2.a.

Changed RES Department to Chemistry Department. The RES Department no longer exists and has been replaced by the Chemistry Department.

Reason: This change revises the ODCM to accurately

.reflect department organizational names.

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8. Part II, Page 36, Section 4.3.2.b.1.

Added the statement that K-effective values for the stack were derived from radioactive noble gas effluents for the years 1999 through 2003. (The data set for the vent K-effective did not change and remains 1985 through 1991).

Reason: New K-effective values for the stack were calculated using the most current data for the stack. The previous values were based on 1985 through 1991 releases. The new K-effective values were calculated based on noble gas effluents for the years 1999 through 2003. The K-effective values for the vents remained the same as the release from the vents have been minimal over the period of 1999 through 2003.

This change increases the accuracy of the ODCM by using the most current data for determining the K-effective values were applicable there by still providing conservative values that would be bounding for the case of a fuel failure.

Vent and Stack release data from the first two quarters of 2004 was evaluated for K-effective values and was bounded by the K-effective values provided in this revision of the ODCM.(

9. Part II, Page 37, Section 4.3.2.b.1.

Changed the K-effective values for the stack from 1.51E-4 to 2.32E-4 and the plus three-sigma value from 4.51E-5 to 1.38E-5 with a resulting K-effective value of 2.73E-4 (previous 2.86E-4)as derived from radioactive noble gas effluents for the years 1999 through 2003 for the stack.

Reason: New K-effective values for the stack were calculated using the most current data for the stack. The previous values were based on 1985 through 1991 releases. The new K-effective values were calculated based on noble gas effluents for the years 1999 through 2003. This change increases the accuracy of the ODCM by using the most current data for determining the K-effective values were applicable and still providing conservative values that would be bounding for the case of a fuel failure.

Rev. No. 9 ODCM, Summary of Changes Page 3 of 9

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10. Part lII, Page 38, Section 4.3.1.b.l.

Changed the allowable vent release rate limit to 7.515E+4 uCi/sec (previous 6.98e-4 uCi/sec)as calculated from equation 4-4a.

Reason: New K-effective values for the stack resulted in a lower mrem per uCi per sec value (mrem-m3 /uCi -sec) . B3y maintaining the stack release rate at 3.00E+5 uCi/sec the total allowable vent release rate in uCi/sec can be changed to 7.515e+4 uCi/sec. This change does not decrease the reliability of the ODCM.

11. Part II, Page 39, Section 4.3.l.b.l. and 4.3.1.b.2 Changed the allowable vent release rate limit to 7.515E+4 uCi/sec (previous 6.98E-4 uCi/sec) as calculated from equation 4-4a. see 9 above Reason: New K-effective values for the stack resulted in a lower mrem per uCi per sec value (mrem-m 3 /uCi-sec) . By maintaining the stack release rate at 3.OOE+5 uCi/sec the total vent release rate in uCi/sec can be increased to 7.515e+4 uCi/sec. This change does not decrease the.

reliability of the ODCM.

12. Part II, Page 44, Section 4.3.2.b.

Building vent allowable setpoints release rates and associated radiation monitor K-factors were revised.

Reason: Building vent flow rates used to determine previous setpoint point release rates and original radiation monitor K-factors were determined to be non-conservative relative to measured flow rates. New allowable setpoint release rates and K-factors were determined using the revised building ventilation flow rates. original flow calculations were based on design bases documentation and plant drawings. Revised allowable setpoint release rates and K-factors are based on engineering analysis of measured flow rates as documented in JAF-ICD-RBC-04561, included as reference 6.20 in ODCM, Part II. (CR-2003-00745)

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OFFSITE DOSE CALCULATION MANUAL DVP-01. 02 DP0.0

Added a footnote to the Reactor Building and Refuel Floor nominal setpoint value column that specifies that the maximum value allowed by Technical specification table 3.3.6.2-1 is <24,800 cpm.

Reason: These Technical specificat~ion allowable values were not previously listed in the ODCM. They were added to- ensure that the 30,000 cpm nominal setpoint value noted in the ODCM table was not misinterpreted as a maximum allowable setpoint value. These values differ because of conservatism that is added to the setpoint value based on the analysis of the total uncertainty in the ventilation radiation monitoring system components ("loop-back" calculation) . This change increases the reliability of the ODCM.

13. Part II, Page 45, Section 4.3.2.b.

" Changed the wording, which describes the use of monitor's sensitivity calculation performed by the manufacturer in calculating the monitor k-factors.

Reason: To more clearly describe that the efficiency factor used for calculating the radiation(

monitor K-factors were derived from the manufacturer's monitor sensitivity equation (CR-2003-00941 CA-l) . This change increases the accuracy of the ODCM.

" Revised building venti lation flow rates and associated radiation monitor K-factors. Included a reference to the document that documents the new building ventilation flow rates.

Reason: Previous building ventilation flow rates were based on Design Basis Documents and plant drawings and were determined to be non-conservative. Current building ventilation flow rates are based on engineering analysis of measured flow rates as documented in JAF-ICD-RBC-04561. JAF-ICD-RBC-04561 was footed in the building flow rate column and was added as reference 6.20 in the reference section of the ODCM. This change increases the accuracy of the ODCM.

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14. Changed Part II, Page 83, Section 6.0.

Added Interface Control Document JAF-ICD-RBL-04561 to the reference listing as reference 6.20.

Reason: This is a new reference which documents the flow rates that are to be used in determining the nominal setpoint values for gaseous effluent building ventilation and the associated monitor k-factors. Calculated values can be found in Part II, pages 44 and 45, section 4.3.2.b. (CR-03-00994, CA-Ol)

15. Part II, Appendix A, Page A-3, Table A-i Added three additional Environmental Concentration Limits (EcL) to Table A-i:

Nb-95m, ECL= 3.OOE-4 Zn-69m, ECL= 6.OOE-4 As-76, ECL= 1.OOE-4 Reason: These values are missing from the table, but are addressed in Dose Factor Appendices, and RETDAS/Seeker programs. values are 10 times the values of 10 CFR 20, Appendix B, Table 2, Column 2.

16. Part II, Appendix A, Page A-6, Table A-2, Aitf Values-Potable Water - Adult Changed the BONE Column dose Factors on Table A-2.

Reason: Editorial correction required due to probable transcription error in previous revision of DVP-01.02. The correct values were verified by WPO, Nuclear Engineering Analysis Group.

17. Part II, Page A-13, Table A-3, Ahitf Values - Freshwater.

Fish - Child Changed Tc-99m, Lung Dose Factor to 9.04E-4.

Reason: Per WPO, Nuclear Engineering Analysis Group, 9.04E-4 is recommended. The previous value of 9.07E-4 was not correct due to a typographical error in building the table. This change increases the accuracy of the ODCM.

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OFFSITE DOSE CALCULATION MANUAL DP0.0 DVP-01. 02

18. Part II, Page E-6 & E-7, Table E-1

Table E-1 was revised to list the calculated K-effective values for the stack that are based on noble gas effluents for the years 1999 through 2003.

Table was expanded to 2 pages. The K-effective values for the vents were not changed.

Reason: New K-effective values for the stack were calculated using the most current data for the. stack. The previous values were based on 1985 through 1991 releases. The new K-effective values were calculated based on noble gas effluents for the years 1999 through 2003. This change increases the accuracy of the ODCM by using the most current data for determining the K-effective values were applicable and still providing conservative values that would be bounding for the case of a fuel failure.

Added footnote to vent release page of the table explaining why the releases for the years 1985 through 1991 were used for calculation the vent K-effective value.

Reason: Footnote was added to explain why different data sets (year ranges) were used for the vents and stack for determining K-effective values. This change increases the accuracy of the ODCM.

19. Part II, Appendix F, Page F-10, Figure F-5 Revised Figure F-5, Liquid Effluent Release Pathways to include the East and West Storm Drains and the associated inputs.

Reason: This change increases the accuracy of the ODCM by identifying potential and existing liquid effluent pathways. Tritium has been identified as an effluent in the West Storm Drain (CR-2002-03695, CA-0013).

20. Part II, Appendix F, Page F-11, Figure F-6 Revised Figure F-6 Solid Radwaste Treatment System to include Fuel Pool Filters as part of the Radwaste System.

Reason: This change increases the accuracy of the ODCM by identifying a component in the Solid Radwaste System that was not previously identified.

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21. Part II, Appendix H, Table H-i, Pages H-5 through H-9.

Location, Distance and Direction columns were revised using Global Positioning System (GPS) inputs.

Reason: This change was implemented because GPS measurements provided more accurate distance and direction measurement than map readings.

This change improves the accuracy of the ODCM.

22. Part II, Appendix H, Table H-i, Page H-9.

Changes were made to the listed Food Product Garden Locations. Locations 55, 57, 144, 343, 422, 425, and 426 were added. Locations 59, 165, 175, 190 and C-i were deleted as possible food product locations.

Reason: This change was made to include possible new food product locations based on the land use census garden surveys. Five locations were deleted as noted inactive locations based on the previous five years of Land Use Census Garden Surveys. This change increases the accuracy of the ODCM

23. Part II, Appendix H, Page H-ll,Figure H-i Map of Sample Locations, was revised to reflect changes in food product sampling locations (see 15 above).

Reason: This change improves the accuracy of the ODCM by updating the sample location map with new sample locations identified in the Land Use Census and deleting inactive sample locations. This change increases the accuracy of the ODCM.

24. Part II Appendix I, Page 1-6, Table 1-2 Updated the row 1, "Corresponding Limits values" column with the vent release rate of 7.517E+4 uCi/sec which is used is Part II, section 4.3.2.b.for determining the release rate setpoints.

Reason: This change updates table 1-2 to be consistent with Vent release rate used in Part II, section 4.3.2.b. for determining the vent release rate setpoints and maintains the accuracy of the ODCM.

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OFFSITE DOSE CALCULATION MANUALDV-0.2 DVP-01. 02

25. Part II, Appendix H, Table 11-1, Page H-9.

Changes were made to the listed Food Product Garden Locations. Locations 55, 57, 144, 343, 422, 425, and 426 were added. Locations 59, 165, 175, 190 and C-1 were deleted as possible food produc~t locations.

Reas~on: This change was made to include possible new food product locations based on the land use census garden surveys. Five locations were deleted as inactive locations based on the previous five years of Land Use Census Garden Surveys. This change increases the accuracy of the ODCM.

26. Part II, Appendix H, Page H-11,Figure H-1 M.ap of Sample Locations, was revised to reflect changes in food product sampling locations (see 15 above).

Reason: This change increases the accuracy of the ODCM by updating the sample location map with new sample locations identified in the Land Use Census and deleting inactive sample locations.

Rev. No. 9 ~ODCM,of ChangesPae9o9 Rev. No. 9 Summary Page 9 of 9

DVP-O1.02 - OFFSITE DOSE CALCULATION MANUAL*

PART 1 - RADIOLOGICAL EFFLUENT CONTROLS (REC)

TABLE OF CONTENTS

1.0 INTRODUCTION

............................................................ 2 2.0 LIQUID EFFLUENTS......................................................... 6 3.0 GASEOUS EFFLUENTS .................................................... 19 4.0 TOTAL DOSE ............................................................ 38 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING ............................... 42 6.0 REPORTS .................. . ............................ 54 7.0 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS*.................................................... 57 8.0 PURGING OF THE PRIMARY CONTAINMENT.................................... 58 Rev. No. 9 Rev. No. 1f of Part 1 (REC)

~Page

DVP-01 .02 OFFSITE DOSE CALCULATION MANUAL*

PART 1 - RADIOLOGICAL EFFLUENT CONTROLS (REC)

1.0 INTRODUCTION

1.1 Purpose This Radioactive Effluent Controls Program (REC) was added to the Offsite Dose Calculation Manual (00CM) in response to NRC generic letter 89-01. The program intent is to conform with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public "as low as is reasonably achievable". Generic letter 89-01 described the NRC's determination that the Radiological Effluent Technical Specification (RETS) should be simplified to improve Technical Specifications (TS) by implementing programmatic controls into the TS and procedural details into the 00CM.

1.2 Document Revision Overview This is Revision 9 of the 00CM under the procedure designation of DVP-01 .02. There were 9 revisi~ons under the previous procedure designation of COP-I 5. This revision constitutes the 18th revision of the 00CM since its inception as Rev. 0 of CDP-15.

I 1.3 Definitions A. CQhannel _Calibration See Technical Specifications.

B. Channel Functional Test See Technical Specifications.

C. Channel Check .

See Technical Specifications.

D. Dose Equivalent 1-131 Dose Equivalent 1-131 shall be that concentration of 1-131 (microcurie/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134 and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in International Commission on Radiological Protection Publication 30 (ICRP-30), "Limits for Intake by Workers", or in NRC Regulatory Guide 1.109, Revision 1, October 1977.

Rev. No. 9 Rev. No. .29Page of Part 1 (REC)

E. Independent Spent Fuel Storage Installation (ISFSI) Controlled Area The JAFNPP ISFS1 is defined to be the same area as the JAFNPP Exclusion Area, which is the combined JAFNPP and Nine Mile Point Nuclear Station (NMPNS) reactor site area.

The boundary of the JAFNPP exclusion area traces the perimeter of the combined JAFNPP - NMPNS reactor sites. (See Figure 4.1 -1, Site Boundary Map).

F. Logic System Functional Test See Technical Specifications.

G. Member(s) of the Public Member(s) of the Public includes all persons who are not occupationally associated with the facilities on the Entergy/(NMPC) Niagara Mohawk Power Corporation site. This category does not include employees of the utilities, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plants.

H. Mode See Technical Specifications

1. Offgas Treatment System The Offgas Treatment System is the system designed and installed to: reduce radioactive gaseous effluents by collecting primary coolant system offgases from the main condenser; and, providing for delay of the offgas for the purpose of reducing the total radioactivity prior to release to the environment.

J. Offsite Dose Calculation Manual (ODCM)

The 00CM describes the methodology and parameters to be used in the calculation of the offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluents monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program.

The 00CM shall also contain the radioactive effluent controls and radiological environmental monitoring activities and descriptions of the information that should be included in the Annual Radiological Environment Operating and Radioactive Effluent Release reports required by Technical Specifications 5.6.2 and 5.6.3.

K. Operable See Technical Specifications.

Rev. No. -9 Rev. o. 9Page 3 of Part 1 (REC)

L. Process Control Program (PCP)

The PCP is a document which identifies the current formulas, sampling methods, analyses, tests, and determinations used to control the processing and packaging of solid radioactive wastes. The PCP controls these activities in such a way as to assure compliance with 10 CFR 20, 10 CFR 61, 10 CFR 71, and other applicable regulatory requirements governing the disposal of the radioactive waste.

M. Rated Thermal Power See Rated Thermal Power, Technical Specifications.

N. Site Boundar The Site Boundary is that line beyond which the land is not owned, leased, or otherwise controlled by Enitergy and NMPC. Refer to Figure 4.1 -1 for the map of the site boundary with regard to liquid and gaseous releases.

0. Solidification Solidification is the conversion of wet wastes into a form that meets shipping and burial ground requirements.

P. Source Check A Source Check is the qualitative assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.

Q. Surveillance Frequency Notation/Intervals The surveillance frequency notations/intervals used in these specifications are defined as follows:

Notifications Intervals Frequency (

D Daily At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months W Week ly At least once per 7 days M Monthly At least once per 31 days Q Quarterly At least once per 92 days

__________________(3 months)

SA Semiannually At least once per 184 days A Annually or Yearly At least once per 366 days 18M 18 Months At least once per 18 months (550 days)

R Operating Cycle At least once per 24 months

____ ______ ___ ___ ___(731 days)

K Rev. No. -9 Rev. o. 9Page 4A of Part 1 (REC)

R. Treatment Any process which effectively reduces the amount of radioactive material released to the environment. This includes such processes as filtration, evaporation/condensation, settling/decanting, and solidification.

S. Unrestricted Ares An unrestricted area shall be any area at or beyond the site boundary where access is neither limited or controlled by Entergy for purposes of protecting individuals against undue risk 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.

The definition of unrestricted area used in implementing the radiological effluent and radiological environmental monitoring controls has been expanded over that in 10 CFR 20.3(a)(1 7) (The new 10 CFR 20.1003). The unrestricted area boundary may coincide with the exclusion (fenced) area boundary, as defined in 10 CFR 100.3(a), but the unrestricted area does not include areas over water bodies. The concept of unrestricted areas, established at or beyond the site boundary, is utilized in the Limiting Conditions for Operation to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonable achievable, pursuant to 10 CFR 50.36a.

1.4 Rules for Limiting Condition for Operation and Surveillance Requirements The provisions of Technical Specifications LCO 3.0.5 are applicable to Part 1, Radioactive Effluent Controls Program, Limiting Conditions for Operation.

The provisions of Technical Specification SR 3.0.2 and SR 3.0.3 are applicable to the Part I, Radioactive Effluent Controls Program Surveillance Frequency.

Rev. No. -9 Rev. o. 9Page 5 of Part 1 (REC)

2.0 LIQUID EFFLUENTS 2.1 Liquid Effluent Monitors 2.1.1 Limiting Conditions For Operation

a. Applicability Applies to the instrumentation required for monitoring radioactive liquid effluent discharges to the environment as specified in Table 2.1-1.

b. Objective To ensure that radioactive liquid effluent discharges are properly monitored and recorded during release.

c. Specifications

1. The limiting conditions for operation of the instruments that monitor radioactive liquid effluents are given in Table 2.1-1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip set point less conservative than required by the ODOM (Part 2, Section 3.3), without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable, or change the set point so it is acceptably conservative.

2. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the action shown in Table 2.1-1. Take corrective actions to retumn 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.

2.1.2 Surveillance Requirements

a. Applicability Applies to the instrumentation for monitoring radioactive liquid effluent discharges.

b. Objective To ensure that instrumentation required for radioactive liquid effluent discharges are maintained and calibrated.

Rev. No. -9 Rev. o. 9Page 6 of Part I (REC)

c. Specifications

1. The alarm/trip set points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM (Part 2, Section 3.3).

2. The surveillance requirements for the radioactive liquid effluent monitoring instrumentation is shown on Table 2.1-2.

2.1.3 Bases The radioactive liquid effluent instrumentation is provided to monitor and control the releases of radioactive materials in liquid effluents during planned or unplanned releases. The alarm/trip set points for these instruments shall be calculated in accordance with methods in the 00CM (Part 2, Section 3.3) to ensure that the alarm/trip will occur prior to exceeding Part 1, Section 2.2.1 .c.1 limits. The operability and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60, 63, and 64.

Rev. No. -9 Rev. o. 9Page 7 of Part 1 (REC)

TABLE 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION I Minimum Channels Instrument j Operable Action Gross radioactivity monitors providing alarm and automatic termination of release Liquid radwaste effluent line 1(a)

Gross beta or gamma radioactivity monitors providing alarm but not providing automatic termination of release Service water system effluent line 1(b)

Flow rate measurement devices Liquid radwaste effluent line I(c)

NOTES FOR TABLE 2.1 -1 (a) With the number of operable channels less than the required minimum number, effluent releases may continue provided that prior to initiating a release:

1. Two independent samples are analyzed; (

2. Two technically qualified members of the facility staff verify the discharge. line valving; Otherwise, suspend release of radioactive effluents via this pathway.

(b) With the number of operable channels less than the required minimum number, effluent releases in this pathway may continue provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed for principal gamma emitters at a limit of detection of at least 5x1 0-7 microcuries/mI. The principal gamma emitters for which the LLD specification applies exclusively are described. in Note (c) to Table 2.2-1.

(c) With the number of operable channels less than the required minimum number, effluent releases via this pathway may continue provided the flow rate is estimated at least once per four hours during actual releases. Pump curves or tank level decreases generated in situ may be used to estimate flow.

Rev. No. -9 Rev. o. -a 9Page of Part 1 (REC)

TABLE 2.1-2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS(a)

Channel Channel Logic System iInstrument Channels Channel Functional Clbain() Functional Check(b) Test(g) Clbain() Test (ý Liquid Radwaste Discharge Daily When -- Quarterly Once per Monitor/ Isolation (c)(d)(e)(f) Discharging 24 months Liquid Radwaste Discharge Daily Quarterly Once per 18 --

Radioactivity Recorder(d) months Liquid Radwaste Discharge Daily Quarterly Once per 18 Flow Rate Measuring months Devices(d)

Normal Service Water Daily --- Qu arterly--

EffluentI NOTES FOR TABLE 2.1-2 (a) Functional tests, calibrations and channel checks need not be performed when these instruments are not required to be operable or are tripped.

(b) Channel checks shall be performed at least once per day during these periods when the instruments are required to be operable.

(c) A source check shall be performed prior to each release.

(d) Liquid radwaste effluent line instrumentation surveillance requirements need not be performed when the instruments are not required as the result of the discharge path not being utilized.

(e) An instrument channel calibration shall be performed with known radioactive sources standardized on plant equipment which has been calibrated with NIST traceable standards.

(f) Simulated automatic actuation shall be performed once per 24 months. Simulated automatic action means applying a simulated signal to the sensor to actuate the circuit.

(g) A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable Channel Functional Test of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specification tests at least once per refueling interval with the applicable extension.

Rev. No. -9 Rev. No. 9Page

9. of Part 1 (REC)

2.2 Concentration of Liquid Effluents 2.2.1 Limiting Conditions For Operation

a. Applicability Applies to the concentration of radioactive materials in liquid effluents.

b. Objective To ensure that the concentrations of radioactive materials in liquid effluents are kept to acceptable levels.

c. Specifications

1. The concentration of radioactive materials released from the plant to the unrestricted areas shall be limited to ten times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases the concentration shall be limited to 2xlO0"pCi/ml.

2. With the concentration of radioactive material released from the plant to unrestricted areas exceeding the above limits, restore the concentration to within the above limits or terminate the release.

2.2.2 Surveillance Requirements

a. Applicability Applies to the analysis of radioactive liquid wastes from the plant through a liquid pathway to an unrestricted area.

b. Objective To ensure that analyses are performed and concentration determined for radioactive liquid releases.

c. Specifications

1. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analyses program of Table 2.2-1.

2. The results of the radioactivity analyses shall be used in accordance with the methods in the ODCM (Part 2,Section 3.2) to ensure that the concentrations at the point of release are maintained within the limits of Section 2.2.1.

Rev. No. -9 Rev. o. 9Page 10 of Part I (REC)

2.2.3 Bases This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than ten times the concentration values specified in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402 for radionuclides other than dissolved or entrained noble gases. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposure above (1)the design objectives of 10 CFR 50, Appendix 1,Section ILA, to a member of the public and (2)the limits of 10 CER 20.1301 to the population. The concentration limit for dissolved or entrained noble gases is based on Xe-I 35 as the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using methodsddescribed in ICRP Publication 2.

Rev. No. -9 Rev. o. 9Page 11 of Part 1 (REC)

TABLE 2.2-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Liquid Release Sampling Mnmm J Type of Activity Lower Limit of Detection Frequency Frequency Analysis (LLD)(a)

Type

_______Freuenc ____________Ci/mI)

Batch Waste Release Tanks (b) Prior to each Each batch Principal gamma 5x I batch emitters(c) 1-131 1 X10-6 One batch per Monthly Dissolved and 1 X 10-5 month entrained gases (gamma emitters)

Prior to each Quarterly H-3 1 x fly, batch composite (d) ________________

Gross alpha I X 10-7' Prior to each Quarterly Sr-89, Sr-90 5 x IO batch composite (d) ________________

Fe-55 I X 10-Q5 Continuous Continuous~o Weekly Principle Gamma 5 x 107' Releases(e) composite~f) Emitters(c) 1-131 1X10-6 Monthly grab Monthly Dissolved and 1x 107' sample entrained gases (gamma emitters)

Continuous~o Monthly H-3 1 x 10O' composite~0 _________________

Gross alpha 1 x 10-'

ContinuousM~ Quarterly Sr-89, Sr-90 5 x 10' 0

CompositeM _______________

Fe-55 1 X10O' See notes next page Rev. No. Rev. o. 9Page 12 of Part 1 (REC)

NOTES FOR TABLE 2.2-1 (a) The LLD (Lower Limit of Detection) is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability and with only 5%

probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemnical separation):

LLD =4.66 Sb E -V -2.22 x 106 .Y -exp (-XAt)

Where:

LLD is the a priori lower limit of detection, as defined above (in microCuries 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 (in counts per minute);

E is the counting efficiency (in counts per disintegration);

V is the sample size (in units of mass or volume);

2.22 x 106 is the number of disintegrations per minute per microCurie; Y is the fractional radiochemnical yield (when applicable);

Ais the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and At should be used in the calculations.

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 ana p2osteriori (after the fact) limit for a particular measurement.

(b) A batch release is the discharge of liquid waste of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, -andthen mixed to assure representative sampling.

Rev. No. 9 Rev.No.9Page 13 of Part 1 (REC)

(c) The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-i 34, and Cs-I 37.

This list does not mean that only these nuclides are to be detected and reported. Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Radioactive Effluent Release Report. The LLD for Mo-99, Ce-141, and Ce- 144 is 5x 1(Y'.

(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 non-discrete volume, e.g., from a volume of a system that has an input flow during the continuous release.

(f) To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream. 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.

Rev. No. -9 Rev. o. 9Page 14 of Part 1 (REC)

2.3 Dose From Liquid Effluents 2.3.1 Limiting Conditions For Operation

a. Applicability Applies to radiation doses from liquid effluents containing radioactive materials.

b. Objective To ensure that the dose limitations of 10 CFR 50, Appendix I for liquids are met.

c. Specifications

1. The dose to a member of the public from radioactive materials released from the plant in liquid effluents to unrestricted areas shall be limited as follows:

a) During any calendar quarter, limited to less than or equal to 1.5 mrem to the whole body and to less than or equal to 5 mrem to any organ; and, b) During any calendar year, limited to less than or equal to 3 mrem to the whole body and to less than or equal to 10 mrem to any organ.

2. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, the following shall be done:

a) Identify the causes for su ch release rates; b) Define and initiate a program of corrective action; and c) Prepare and submit a report to the NRC within. 30 days.

2.3.2 Surveillance Requirements

a. Applicability Applies to the calculation of the radiation dose from liquid effluents containing radioactive materials.

Rev. No. 9 15 of Part 1 (REC)

Rev. o. 9Page

b. Objective To ensure that the radiation dose from radioactive liquid effluents is determined.

c. Specifications

1. Cumulative dose contributions from liquid effluents shall be determined in accordance with the ODOM (Part 2, Section 3.4) at least monthly for the current calendar quarter and current calendar year.

2.3.3 Bases This specification is provided to ensure that the requirements of 10 CFR 50, Appendix 1, Section lI.A, lIILA and IV.A are met. The Limiting Conditions for Operation ensures that the guides set forth in 10 CFR 50, Appendix 1,Section IL.A are met. The specifications provide the required operating flexibility and, at the same time, implement the guides set forth in 10 CFR 50, Appendix 1,Section IV.A, to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

Rev. No. -9 16 of Part 1 (REC)

Rev. o. 9Page

2.4 Liquid Radioactive Waste Treatment System Operations 2.4.1 Limiting Conditions For Operation

a. Applicability Applies to the operability of radioactive liquid processing equipment.

b. Objective To ensure liquid radwaste treatment system(s) are operated to prevent exceeding the dose limits of Part 1, Section 2.3.1 .c.1.

c. Specifications

1. The liquid radioactive waste treatment system shall be used when the projected dose from untreated liquid releases, over a 31 day period, to a member of the public would exceed:

a) 0.06 mrem to the whole body; or, b) 0.2 mrem to any organ.

2. With radioactive liquid waste being discharged in excess of the above limits, prepare and submit to the Commission within 30 days a report that includes the following information:

a) Explanation if liquid radwaste was being discharged without treatment; and if so:

b) Identification of any inoperable equipment or subsystems and the reason for the inoperability; c) Action(s) taken to restore the inoperable equipment to operable status; and d) Summary description of action(s) taken to prevent a recurrence.

.2.4.2 Surveillance Requirements

a. Applicability Dose projections apply to liquid effluents released to unrestricted areas.

Rev. No. 9 Rev. o. 9Page 17 of Part 1 (REC)

b. Objective To ensure that action levels to require operation of waste treatment systems are determined.

c. Specifications

1. Doses to individuals in unrestricted areas due to liquid releases shall be projected at least monthly in accordance with the ODCM (Part 2, Section 3.5).

2.4.3 Bases The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "las low as is reasonably achievable". This specification assures that the requirements of 10 CFR 50.36a, 10 CER 50, Appendix A,General Design Criterion 60, and design objective of 10 CER 50, Appendix 1,Section ILD are met. The specified limits governing the use of appropriate portions of the liquid radwaste treatment systemn were specified as a suitable fraction of the dose design objectives set forth in 10 CFR 50, Appendix 1,Section ILA, for liquid effluents.

Rev. No. 9 Rev.No~iPage 18 of Part 1 (REC)

3.0 GASEOUS EFFLUENTS 3.1 Gaseous Effluent Monitors 3.1.1 Limiting Conditions For Operation

a. Applicability Applies to the instrumentation required for monitoring the radioactive gaseous effluent pathways to the environment.

b. Objective To ensure that radioactive gaseous effluent discharges are properly monitored and recorded during release.

c. Specifications 1.ý Radioactive gaseous wastes released to the environment via the below listed pathways shall be monitored and recorded during release from the respective pathway.

a) Main stack exhaust b) Refuel floor exhaust c) Reactor building exhaust d) Turbine building exhaust e) Radwaste building exhaust

2. Each pathway listed above shall also be sampled for iodine and particulate radioactivity on a continuous basis during release from the respective pathway.

3. If Sections 3.1.1 .c.1 and 3.1.1 .c.2 above, cannot be met, effluent releases may continue via the respective pathway provided gaseous grab samples are collected in the case of a monitor out of service or auxiliary samplers are used in case a particulate and iodine sampler is out of service:

a) Return the instrument to operable status within 30 days; or b) Provide an explanation in the next Radioactive Release Report as to why the inoperability was not corrected within 30 days.

Rev. No. 9 Rev.No.9Page 19 of Part 1 (REC)

4. Alarm/Trip Setpoints are determined in accordance with Part 2, Section 4.3.2 to ensure the limits of Section 3.2.1 are not exceeded. With a radioactive gaseous effluent monitoring instrumentation channel alarm/trip setpoint less conservative than required by the above control:

a) Without delay, suspend the release of radioactive gaseous effluents monitored by the affected channel; or b) Declare the channel inoperable; or c) Change the setpoint so it is acceptably conservative.

3.1.2 Surveillance Requirements

a. Applicability

.Applies to instrumentation listed in Section 3.1.1 .c.1 and analyses of gaseous effluent releases.

b. Objective To ensure that instrumentation required for gaseous effluent releases is maintained and calibrated and the radioactivity of gaseous releases is determined.

c. Specifications

1. Operation of the gaseous effluent monitors and recorders shall be verified by performing instrument surveillance as specified on Table 3.1-2.

2. The iodine cartridge and the particulate filter for each pathway listed in Section 3.1.1 .c.1 shall be changed out at least weekly.

3. Grab samples, when required, shall be collected at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of collection. Auxiliary samplers shall run continuously and be changed out at least weekly.

3.1.3 Bases The radioactive gaseous effluent instrumentation is provided to monitor and control the releases of radioactive materials in gaseous effluents during planned or unplanned releases. The alarm/trip set points for these instruments shall be calculated in accordance with methods in the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of Part 1, Section 3.2.1 .c.1.

The operability and use of this instrumentation is consistent with the requirements of 10 CER 50, Appendix A, General Design Criteria 60, 63 and 64.

Refer to Technical Specification Bases 3.3.6.2 for references pertaining to surveillance and allowable outage times for selected monitors listed on Table 3.1-1 and Table 3.1-2.

Rev. No. 9 Rev. No. .20 of Part 1 (REC) 9Page

TABLE 3.1 -1 RADIATION MONITORING SYSTEMS Minimum No.

of Operable Instrument Channels per Trip ITotal I

f Alarm/Trip Level No. of Instrument Channels Provided by J

System Function Setting Design I Action 1 Main Stack Exhaust (b) 2 Mf Monitors 1(a)(h) Refuel Area (i) 2 Mf(g)

Exhaust Monitors(c) 1(a)(h) Reactor Building (i) 2 (f) (g)

Area Exhaust Monitors(c) 1(a)(h) Turbine Building (b) 2(f Exhaust Monitors OqJ6I 1(a)(h) Radwaste Building (b) 2 (f)

Exhaust Monitors NOTES FOR TABLE 3.1 -1 (a) A channel may be placed in an inoperable status for up to six hours during periods of required surveillance without placing the Trip System in the tripped condition provided the other OPERABLE channel is monitoring that Trip Function, that is, trip capability is maintained.

(b) Alarm/Trip level setting is in accordance with the methods and procedures of the ODCM (Part 2, Section 4.3.2). These alarm/trip level settings are set to ensure the limits in Specification 3.2.1.c.1 are not exceeded.

(c) Operability includes alarm.

(d) Deleted (e) Deleted (f) Refer to Specification 3.1.1.c.3 and 3.1.1.c.4.

(g) Refer to Technical Specification 3.3.6.2 for additional Required Actions.

(h) An inoperable channel need not be placed in the tripped condition where this would cause the Trip to occur. Inthese cases, the inoperable channel shall be restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or the indicated action shall be taken.

(i) The allowable values are specified in Technical Specification Table 3.3.6.2-1.

Rev. No. 9 Rev. o. 9Page 21 of Part 1 (REC)

TABLE 3.1-2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS(a)

Instrument Channel Channel Logic System Channels Check(b) Calibr'ation~d) Funtinal Test (c)

Main Stack Exhaust Monitors Daily Quarterly--

and Recorders Refuel Area Exhaust Monitors Daily Quarterly -

and Recorders Reactor Building Area Exhaust Daily Quarterly R Monitors, Recorders and Isolation Turbine Building Exhaust Daily Quarterly--

Monitors and Recorders Radwaste Buildng Exhaust Daily Quarterly -

Monitors and Recorders SBGT Actuation --- R' NOTES FOR TABLE 3.1-2 (a) Channel Calibrations and Channel Checks need not be performed when these instruments are not required to be operable or are tripped.

(b) Channel Checks shall be performed at least once per day during these periods when the instruments are required to be operable.

(c) Simulated automatic actuation shall be performed once per 24 months. Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit.

(d) A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable Channel Functional Test of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specification and non-Technical Specification tests at least once*per refueling interval with the applicable extension.

Rev. No. -9 Rev. o. 9Page 22 of Part I (REC)

3.2 GASEOUS DOSE RATES 3.2.1 Limiting Conditions of Operation

a. Applicability Applies to the radiation dose rate from radioactive material in gaseous effluents from the plant.

b. Objective To ensure that the dose rates at or beyond the site boundary from gaseous effluents do not exceed the annual dose limits of 10 CFR 20 for unrestricted areas.

c. Specifications

1. The dose rate at or beyond the site boundary due to radioactive materials released from the plant in gaseous effluents shall be limited as follows:

a) *-ý500 mrem/year to the whole body and :g3000 mrem/year to the skin from noble gases; and, b) *1500 mrem/year to any organ from Iodine-I 31, Iodine-I 33, Tritium and for radioactive materials in particulate form with half-lives greater than 8 days (inhalation pathway only).

2. With the dose rates exceeding the above limits, without delay restore the release rate to within the above limits.

3.2.2 Surveillance Requirements

a. Applicability Applies to the calculation of the dose rates from radioactive materials in gaseous effluents from the plant.

b. Objective To ensure that appropriate calculations are performed to determine the dose rates from gaseous effluents from the plant.

Rev. No. -9 Rev. o. 9Page 23 of Part I (REC)

c. Specifications

1. The dose rate due to nobie gases in gaseous effluents shall be determined to be continuously within the limits of Section 3.2. 1.c. 1, in accordance with the methods and procedures of the 00CM (Part 2, Section 4.3.1).

2. The dose rate due to lodine-131, lodine-133, Tritium and to radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents, shall be determined to be within the above limits in accordance with the methods and procedures of the 00CM (Part 2, Section 4.3.3). This will be done by obtaining representative samples and performing analyses in accordance with the sampling and analyses program specified in Table 3.2-1.

3.2.3. Bases This specification provides 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 at or beyond the Site Boundary in excess of the design objectives of Appendix I to 10 CFR Part 50. This specification is provided to ensure that gaseous effluents from the plant will be appropriately controlled. It provides operational flexibility for releasing gaseous effluents to satisfy the Section ILA and ILlC design objectives of Appendix I to 10 CER Part 50.

The specified limits restrict, at-all times, the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to <500 mrem/year to the whole body or to < 3000 mrem/year to the skin. These limits also restrict the corresponding thyroid dose rate above background to a child via the inhalation pathway to_<

500 mremlyear.

Rev. No. 9 Rev. o. 9Page 24 of Part 1 (REC)

TABLE 3.2-1 RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Type of Lower Limit of Gaseous Sampling Analysis Activity Detection Release Type Frequency Frequency Analysis (LLD)(') (pCi/ml)

Main Stack Monthly Grab Monthly Noble Principal Gamma I X 10-4 Sample(d) Gases(b) Emitters (b)

RfulorVn Quarterly Grab Quarterly H-3 1 X 10-6 FloorVentSample Reactor Building Continuous(c) Weekly Charcoal 1-131 1 X 10.12 Vent Sample(e)___________________

Turbine Building 1-133 None VetContinuous(c) Weekly Principal Gamma I x 10-11 Radwaste Particulate Emitters (b)

Building Vent Sample(e)__________________

(1-131,1-133, None others)

Continuous~c) 1 WkIMo Gross Alpha I x 10-11 Particulate Sample Continuous(c) 4 WkIQr Sr-89, Sr-90 i x 10-11 Composite Particulate Sample Continuous(') Noble Gas Noble Gases I x 1-Monitor Gross Beta or Gamma Incinerated Oil(') Prior to Each Each Batch-(9) Principal Gamma 5 x 10-7 Batch~~ - Emitters (b) 1-131 1 X1 -

See notes next page Rev. No. 9 Rev. o. 9Page 25 of Part 1 (REC)

NOTES FOR TABLE 3.2-1 (a) The LLD is defined, for purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability and 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 Sb E -V -2.22 x 106 . Yf* exp (-AAt)

Where:

LLD is the a priori lower limit of detection, as defined above (in microcuries per unit mass or volume);

5 b is the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute);

E is the counting efficiency (in counts per disintegration);

V is the sample size (in units of mass or volume);

2.22 x 1C6 is the number of disintegrations per minute per microcurie; Y is the fractional radiochemical yield (when applicable);

Ais the radioactive decay constant for the particular radionuclide; and At for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and A~ should be used in the calculations.

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.

Rev. No. -9 Rev. No. 26r.

9Pageof Part 1 (REC)

(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, Xe-1 35m, and Xe-1 38 for gaseous emissions; and, Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-I 34, and Cs-i 37 for particulate emissions. This list does not mean that only these nuclides are to be detected and reported.

Other peaks that are measurable and identifiable, together with the above nuclides, shall also be identified and reported in the Radioactive Effluent Release Report. The LLD for Mo-99, Ce-141, and Ce-144 is 5x1071 . For oil samples, Table 2.2-1, Note (c) applies.

(c) The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications.

This determination shall be made using design flow rates if flow meters are not provided or are inoperable.

(d) Main stack gaseous sampling and analysis shall also be performed following shutdown, startup, or a thermal power change exceeding 20% of rated- thermal power in one hour.

1. This requirement applies only if:

" Analysis shows that the dose equivalent 1-131 concentration in the primary coolant has increased more than a factor of 3; and

" The noble gas monitor shows that effluent activity has increased more than a factor of 3; and

" Corrections for increases due to changes in thermal power level have been made in both cases.

(e) Main stack iodine and particulate sampling shall also be performed daily following each shutdown, startup or thermal power change exceeding 20% of rated thermal power in one hour.

1. Daily sampling is not required for thermal power changes if the offgas charcoal filters are in service.

2. In addition, this requirement applies only if:

" Analysis shows that the dose equivalent 1-131 concentration in the primary coolant has increased more than a factor of 3; and

" The noble gas monitor shows that effluent activity has increased more than a factor of 3; and

" Corrections for increases due to changes in thermal power level have been made in both cases.

Rev. No. -9 27 of Part 1 (REC)

Rev. o. 9Page

3. Daily sampling shall be performed until two consecutive samples show no increase in concentration but not to exceed 7consecutive days.

4. LLDs may be increased by a factor of 10 for analysis of daily samples.

5. Analysis of daily and weekly samples shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of changing.

(f) Incinerated oil may be discharged via points other than the main stack and building vents (i.e.,

auxiliary boiler). Release shall be accounted for based on pre-release grab sample data.

(g) Samples of incinerated oil releases shall be collected from and representative of filtered oil in liquid form. Whenever oil samples cannot be filtered such as No. 6 bunker fuel oil, raw oil samples shall be collected and analyzed.

Rev. No. 9 28 of Part I (REC)

Rev. o. 9Page

3.3 Air Dose, Noble Gases 3.3A1 Limiting Conditions For Operation

a. Applicability Applies to the air dose due to noble gases released from the plant.

b. Objective To ensure that the noble gas dose limitations of 10 CFR 50, Appendix 1,are met.

c. Specifications

1. -The air dose to areas at or beyond the site boundary from noble gases released from the plant in gaseous effluents shall be limited:

a) During any calendar quarter, to less than or equal to 5 mrad from gamma radiation, and less than or equal to 10 mrad from. beta radiation; and, b) During any calendar year, to less than or equal to 10 mrad from gamma radiation and less than or equal to 20 mrad from beta radiation.

2. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission, within 30 days, a report that:

(a) Identifies the cause(s) for exceeding the limit(s); and b) Defines the corrective actions that have been taken to reduce the releases; and c) Identifies the proposed corrective actions to be taken to ensure that subsequent releases will be in compliance with the above limits.

3.3.2 Surveillance Requirements

a. Applicability Applies to the calculation of the air dose due to noble gas effluent.

Rev. No. 9 Rev. o. 9Page 29 of Part 1 (REC)

b. Objective To ensure that appropriate calculations are performed to determine the air dose from noble gas effluents.

c. Specifications

1. Cumulative air dose contributions for noble gases shall be calculated at least monthly in accordance with the ODCM (Part 2, Section 4.4.2) for the current calendar quarter and the current calendar year.

3.3.3 Bases This specification is provided to assure that the requirements of 10 CFR 50, Appendix 1, Section 11.8, lll.A and IV.A are met. The Limiting Conditions for Operation are the guides set forth in Appendix 1,Section 11.B. The specification provides the required operating flexibility and, at the same time, implements the guides set forth in Appendix 1,Section IV.A, to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable."

Rev. No. -9 Rev.

Page No.

9 30.1.of Part 1 (REC)

3.4 Dose Due to lodine-131, lodine-133, Tritium and Radionuclides in Particulate Form 3.4.1 Limiting Conditions For Operation

a. Applicability Applies to the cumulative dose from Iodine-1 31, Iodine-i 33, Tritium, and radionuclides in particulate form in gaseous effluents.

b. Objective To ensure that the dose limitations of 10 CFR 50, Appendix I, are met.

c. Specifications

1. The dose to a member of the public at or beyond the site boundary from Iodine-i 31, Iodine-i 33, Tritium, and radionuclides in particulate form with half-lives greater than 8 days released from the plant in gaseous effluents shall be limited:

a) During any calendar quarter to less than or equal to 7.5 mrem to any organ; and, b) During any calendar year to less than or equal to 15 mrem to any organ.

c) Less than 0.1 % of the limits of Specifications 3.4.1.c.1.a and 3.4.1.c.1.b as a result of burning contaminated oil.

2. With the calculated dose from the release of Iodine-i 31, Iodine-i 33, Tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and. submit to the Commission within 30 days a report that:

a) Identifies the cause(s) for exceeding the limit; and b) Defines the corrective actions that have been taken to reduce the releases; and c) Identifies the proposed corrective actions to be taken to ensure that subsequent releases will be in compliance with the above limits.

Rev. No. -9 Rev. o. 9Page 31 of Part 1 (REC)

3.4.2 Surveillance Requirements

a. Applicability Applies to the calculation of the dose due to Iodine-I 31, Iodine-i 33, Tritium, and radionuclides in particulate form in gaseous effluents.

b. Objective To ensure that appropriate calculations are performed to determine the dose from Iodine-131, Iodine-i 33, Tritium, and radionuclides in particulate form.

c. Specifications

1. Cumulative dose contributions shall be calculated at least monthly in accordance with the 00CM (Part 2, Section 4.4.2.c) for the current calendar quarter and the current calendar year.

3.4.3 Bases This specification is provided to assure that the requirements of 10 CFR 50, Appendix I, Section ll.C, lll.A and IV.A are met. The Limiting Conditions for Operation are the guides set forth in Appendix I, Section 11.0. The specifications provide the required operating flexibility and, at the same time, implement the guides set forth in Appendix 1,Section lV.A, to assure that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable."

Rev. No. -9 Rev. o. 9Page 32 of Part 1 (REC)

3.5 Offgas Treatment System 3.5.1 Limiting Conditions For Operation

a. Applicability Applies to the system installed for reduction of radioactive materials in gaseous waste prior to discharge.

b. Objective To minimize concentration of radioactive materials released from the site.

c. Specifications

1. The offgas treatment system shall be used to reduce the concentration of radioactive materials in gaseous effluents prior to release from the plant within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after the start-up of the second turbine driven, feedwater pump.

2. The offgas charcoal beds shall be used, when offgas treatment system operation is required and the projected doses over a 31 day period due to gaseous effluent releases to a member of the public would exceed:

a) 0.2 mrad for gamma radiation b) 0.4 mrad for beta radiation; or c) 0.3 mrem to any organ

3. With gaseous effluent from the main condenser being discharged without use of the charcoal beds for greater than seven days when treatment is required, and projected doses are in excess of the above limits, prepare and submit to the Commission, within 30 days, a Special Report that includes the following information:

a) Explanation of why gaseous effluent is being discharged without charcoal bed treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.

b) Action(s) taken to restore the inoperable equipment to operable status; and c) Summary description of action(s) taken to prevent a recurrence.

Rev. No. -9 Rev. o. 9Page 33 of Part 1 (REC)

3.5.2 Surveillance Requirements

a. Applicability Applies to the calculation of the radiation dose from gaseous effluents containing radioactive materials.

b. Objective To ensure that treatment of gaseous wastes by the offgas system is implemented when required.

c. Specifications

1. Ifthe charcoal beds are not in service when the offgas treatment system is required, doses due to gaseous releases from the site shall be projected at least monthly in accordance with the ODCM (Part 2, Section 4.5).

3.5.3 Bases This specification is provided to ensure that the system will be available for use when required to reduce projected doses due to gaseous releases. This specification assures that the requirements of 10 CFR 50.36a, 10 CFR 50, Appendix A, General Design Criterion 60, and design objective in 10 CFR 50, Appendix 1, Section ILD are met. The specified limits governing the use of appropriate portions of the systems are specified as a suitable fraction of the guide values set forth in 10 CFR 50, Appendix 1,Sections ILlB and ll.C, for gaseous effluents.

The requirement for offgas treatment system operability provides assurance that the release of radioactive materials in gaseous waste will be kept "as low as is reasonably achievable."

Operability of the system is based upon start-up of the second turbine driven feedwater pump.

This is due to the fact that excess air in-leakages in the main condenser as a result of operating only one turbine driven feedwater pump will exceed offgas treatment system limitations and consequently render the system inoperable. Start-up of the second turbine driven feedwater pump will decrease air in-leakages and assure offgas treatment system availability.

Rev. No. 9 Rev. o. 9Page 34 of Part 1 (REC)

3.6 Main Condenser Steam Jet Air Ejector Radiation Monitors 3.6.1 Limiting Conditions for Operation

a. Applicability Applies to the instrumentation required for monitoring the main Condenser offgas steam jet air ejector (SJAE) radiation when the reactor is in Mode 1, and Mode 2 or 3 with any main steam line not isolated and SJAE is not in operation.

b. Objectives To ensure that the SJAE release rates are maintained at a level compatible for further treatment and release.

c. Specifications Except as specified in 1. and 2. below, both SJAE system radiation monitors shall be operable with a trip level setting of < 500,000 pCi/sec. The trip time delay setting for closure of the SJAE isolation valve shall be < 15 minutes.

1. A channel may be placed in an inoperable status for up to six hours during periods of required surveillance without placing the Trip System in the tripped condition provided the other operable channel is monitoring that Trip Function. Otherwise, in the event that one of the two SJAE radiation monitors is made or found to be inoperable, continued operation is permissible provided that the inoperable monitor is tripped.

2. Upon the loss of both SJAE system radiation monitors, either temporarily monitor radiation levels at the SJAE or initiate an orderly shutdown and have the main steam lines or the SJAEs isolated within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Rev. No. -9 Rev. o. 9Page 35 of Part 1 (REC)

3.6.2 Surveillance Requirements

a. Applicability Applies to the instrumentation required for monitoring the main condenser offgas steam jet air ejector (SJAE) radiation when the reactor is in Mode 1, and Mode 2 or 3 with any main steam line not isolated and SJAE is in operation.

b. Objective To ensure that the SJAE release rates are properly monitored.

c. Specifications Operation of the SJAE radioactive offgas monitors shall be verified by performing instrument surveillance as specified on Table 3.6-1.

3.6.3 Bases This specification is provided to assure that remedial action is taken to limit the noble gas release rate at the SJAE. The requirement provides reasonable assurance that the amount of noble gas that must be treated and/or released is controlled to a level that prevents exceeding the limits specified in Part 1,1 Section 3.2. 1.

Two air ejector offgas monitors are provided and when their trip point is reached, cause an isolation of the air ejector offgas line. Isolation is initiated when both instruments reach their high trip point or one has an upscale trip and the other a downscale trip. There is a 15 minute delay before the air ejector offgas isolation valve is closed. This delay is accounted for by the 30 minute holdup time of the offgas before it is released to the stack. Both instruments are required for trip but the instruments are so designed that any instrument failure gives a downscale trip.

Rev. No. 9 Rev. o. 9Page 36 of Part 1 (REC)

Table 3.6-1 MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS (a) instrument Channels Channel Check (b)

Channel Calibration (e)(f)

JLogicSystem Functional Test (c)(d)

SJAE Radiation Monitors/ Daily Quarterly Once per 24 months

a. Channel calibrations and channel checks need not be performed when these instruments are not required to be operable or are tripped.

b. Channel checks shall be performed at least once per day during these periods when the instruments are required to be operable.

c. Simulated automatic actuation shall be performed once every 24 months. Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit.

d. The logic system functional test shall include a calibration of time delay relay necessary for proper functioning of the trip system.

e. The radiation sensors are excluded from the quarterly calibration. The radiation sensors shall be calibrated every 24 months.

f. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable channel functional test of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specification tests at least once per refueling interval with the applicable extension.

Rev. No. 9 Rev. o. 9Page 37 of Part I (REC)

4.0 TOTAL DOSE 4.1 Total Dose From Uranium Fuel Cycle(

4.1.1 Limiting Conditions For Operation

a. Applicability Applies to radiation dose from releases of radioactivity and radiation from uranium fuel cycle sources.

b. Objectives

1. To assure that the requirements of 40 CFR 190 are met.

2. To assure that the requirements of 10 CFR 72.104 are met in accordance with Section 3.2.3, Required Action A.2, Certificate of Compliance 1014, Appendix A, Technical Specification for the Hi-Storm Cask System.

c. Specifications

1. The dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited as follows:

a) Less than or equal to 25 mrem/year to the whole body; and, b) Less than or equal to 25 mrem/year to any organ except the thyroid which shall be limited to less than or equal to 75 mrem/year.

2. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 2.3.1.c.1, 3.3.1.c.1, 3.4.1 .c.1 .a or 3.4.1 .c.1 .b, calculations shall be made including an estimate of direct radiation contributions to determine whether the limits of Section 4. 1.1I.c.1 have been exceeded. If this is the case, a report defining corrective actions to be taken to reduce subsequent releases to levels within limits, along with a schedule for achieving conformance, shall be prepared and submitted to the Commission within 30 days. This report, as defined in 10 CFR 20.2203(c), shall include estimates of 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 concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose(s) exceed(s) the above limits, and if the release condition resulting in violation of 40 CFR 190 and 10 CFR 72.104(a) has not already been corrected, the report shall include a request for variance in accordance with the provisions of 40 CFR 190 and 10 CFR 72.

Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete.

Rev. No. 9 Rev. o. 9Page 38 of Part 1 (REC)

4.1.2 Surveillance Requirements

a. Applicability Applies to the calculation of total dose due to releases of radioactivity and radiation from uranium fuel cycle sources.

b. Objective To ensure that appropriiate calculations are performed to determine total dose to a member of the public.

c. Specifications

1. Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 2.3.2.c.1, 3.3.2.c.1, and 3.4.2.c.1 and in accordance with the ODCM (Part 2, Section 5.0).

2. 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 (Part 2, Section 5.4). This requirement is applicable only under conditions set forth in Section 4.1.1 .c.2.

4.1.3 Bases This specification is provided to meet the dose limitations of 40 CFR 190 and 10 CFR 72.104(a). This specification requires the preparation and submittal of a report whenever the calculated dose from plant radioactive effluents exceed twice the design objective doses of 10 CFR 50, Appendix 1. The 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 limits of 40 CFR 190 and 10 CFR 72.104(a). For the purpose of the report, it may be assumed the dose commitment to the member of the public from other uranium fuel cycle sources is negligible. However, 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 40 CFR 190 or 10 CFR 72.104(a), the report, with a request for variance (provided the release conditions resulting in a violation of 40 CFR 190 or 10 CFR 72.104(a) have not already been corrected), shall be submitted in accordance with provisions of 40 CFR 190.11 and 10 CFR 20.2203(c). This request is considered a timely request and fulfills the requirements of 40 CFR 190 and 10 CFR 72 until NRC staff action is completed. The variance only relates to the limits of 40 CFR 190 or 10 CFR 72.104(a) and does not apply in any way to the requirements for dose limitation addressed in Specifications 2.0 and 3.0. 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.

Rev. No. 9 Rev. o. 9Page 39 of Part 1 (REC)

FIGURE 4.1-1 SITE BOUNDARY MAP I

Lake Ontario

f e0 ENERGY EN1ERGY NUCLEAR

..FlT2PA7WCK.1+/-C NIACARA MOHAWK 64NER RD r7SITE& EXCLUSON AREA BOUNDARY b

Rev. No. 9 Rev. o. 9Page 40 of Part 1 (REC)

NOTES TO FIGURE 4.1-1 (a) NMP1 stack (height is 350 feet)

(b) NMP2 stack (height is 430 feet)

(c) JAFNPP stack (height is 385 feet)

(d) Building vents (e) NMP1 radioactive liquid discharge (Lake Ontario, bottom)

(f) NMP2 radioactive liquid discharge (Lake Ontario, bottom)

(g) JAFNPP radioactive liquid discharge (Lake Ontario, bottom)

(h) Site boundary (i) Lake Ontario shoreline Additional Information:

-- NMP2 reactor building vent is located 187 feet above ground level

-- JAFNPP reactor and turbine building vents are located 173 feet above ground level

-- JAFNPP radwaste building vent is 112 feet above ground level Rev. No. -9 41 of Part I (REC)

Rev. o. 9Page

5.0 'RADIOLOGICAL ENVIRONMENTAL MONITORING 5.1 Monitoring Program 5.1.1 Limiting Conditions For Operation

a. Applicability At all times.

b.Objective To evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material.

c. Specifications

1. W ith the radiological environmental monitoring program not being conducted as specified in Table 5.1-1, prepare and submit to the Commission, 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.

(Deviations are permitted from the required sampling schedule if samples are unobtainable due to hazardous conditions, seasonal unavailability, theft, uncooperative residents, or to malfunction of automatic sampling equipment. If the latter, efforts shall be made to complete corrective action prior to the end of the next sampling period.)

2. 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 5.1 -

2 when averaged over any calendar quarter, prepare and submit to the Commission a report within thirty (30) days from the end of the affected calendar quarter or within thirty (30) days from the time it is determined that a reporting level has been exceeded. This report shall identify the cause(s) for exceeding the limits(s) and define the corrective action(s) to be taken to reduce radioactive effluents so that the calculated annual dose to a member of the public is less than the calendar year limits of Specifications 2.3.1 .c.1 .b,3.3.1 .c.1 .b, and 3.4.1 .c.1 .b. When more than one of the radionuclides in Table 5.1-2 are detected in the sampling medium, this report shall be submitted if:

concentration (1) +concentration (2) +...~.

limit level (1) limit level (2)

When radionuclides other than those in Table 5.1-2 are detected and are the result of plant effluents, this report shall be submitted if the calculated annual dose to an individual is equal to or greater than the calendar year limits of Specifications 2.3.1 .c.1 .b, 3.3.1 .c.1 .b, and 3.4.1 .c.1 .b.

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.

Rev. No. 9 Rev. o. 9Page 42 of Part 1 (REC)

3. With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table 5.1-1, locations for obtaining replacement samples shall be identified and added 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. .The cause of the unavailability of samples and the new location(s) for obtaining replacement samples shall be identified in the next Radioactive Effluent Release Report. Also included in the report shall be a revised figure(s) and table for the 00CM reflecting the new location(s).

5.1.2 Surveillance Requirements The radiological environmental monitoring samples shall be collected, pursuant to Table 5.1 1,from the locations given in the table and figure(s) in the 00CM (Appendix H) and shall bet6 analyzed pursuant to the requirements of Table 5.1-1, and the detection capabilities required by Table 5.1-3.

5.1.3 Bases The radiological environmental monitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures to members of the public resulting from station operation. This monitoring program ensures that 10 CFR 50, Appendix 1,Section IV.B.2 is met. It 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, based on the effluent measurements and the modeling of the environmental exposure pathways. The initial 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 Limit of Detection (LLDs). The LLDs required by Table 5.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a piirio (before the fact) limit representing the capability of a measurement system. The LLD is not an a posteriori (after the fact) limit for a particular measurement.

Rev. No. -9 Rev. o. 9Page 43 of Part I (REC)

TABLE 5.1-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Type and Pathway Number of Samples(a) and Collection Frequency of and/or Sample Locations Freguency(a) Analysis AIRBORNE Radioiodine and Samples from 5 locations: Continuous Radioiodine Particulates sample Canisters:

a. 3 samples from offsite locations operation with Analyze weekly for in different sectors of the highest sample 1-131 calculated site average D/Q collection (based on all licensed site weekly or as Particulate reactors) required by Samples:

dust loading, Gross beta

b. 1 sample from the vicinity of a whichever is radioactivity community having the highest more frequent following filter calculated site average DIQ changeb)

(based on all licensed site composite (by reactors) location) for gamma isotopicdc) quarterly

c. 1 sample from a control location (as a minimum) 9 to 20 miles distant and in the least prevalent wind direction(d)

Direct Radiation(e) 32 stations with two or more Quarterly Gamma dose dosimeters placed as follows: monthly or quarterly

a. An inner ring of stations in the general area of the site boundary

b. An outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors. There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring

c. The balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations See notes following table Rev. No. -9 Rev. o. 9Page 44 of Part 1 (REC)

TABLE 5.1-1 (continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Number of Samples(a) and Sampling and Type and Pathway and/or Locations Collection Frequency of Sample Freguency(a) Analysis WATERBORNE Surface(O a. 1 sample upstream(d) Composite Gamma isotopic sample over analysis

b. 1 sample from the site's most one month monthly.

downstream cooling water intake period(g) Composite for Tritium analysis quarterly(c)

Sediment from 1 sample from a downstream Twice per year Gamma isotopic Shoreline area with existing or potential analysis semi-recreational value annually(c)

INGESTION Milk a. Samples from milch animals in 3 Twice per Gamma isotopic locations within 3.5 miles distant month, April and 1-131 having the highest calculated site through analysis twice average D/Q. If there are none, December per month when then 1 sample from milch animals (samples will be milch animals in each of 3 areas 3.5 to 5.0 miles collected in are on pasture distant having the highest January (April through calculated site average D/Q through March December);

(based on all licensed site if 1-131 is monthly reactors)(h) detected in (January November and through March),

b. 1 sample from milch animals at a December of if required(c) control location (9 to 20 miles the preceding distant and in a less prevalent year) wind _direction)(d)

See notes following table Rev. No. -9 Rev. o. 9Page 45 of Part 1 (REC)

TABLE 5.1-1 (continued)

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (

Fish a. 1 sample of each of 2 commercially Twice per year Gamma or recreationally important species isotopic(c) in the vicinity of a site discharge analysis of point edible portions

b. 1 sample of each of 2 species (same as in a. above or of a species with similar feeding habits) from an area at least 5 miles distant from the site(d)

Food Products a. In lieu of the garden census as Once during Gamma specified in Part 1, Section 5.2, harvest isotopic(c) samples of at least 3 different kinds season analysis of of broad leaf vegetation (such as edible vegetables) grown nearest each of portions.

two different offsite locations of (isotopic to highest predicted site average DIQ include (Based on all licensed site 1-131)

Reactors)

One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 miles distant in a least prevalent wind direction sector(d)

NOTES FOR TABLE 5.1-1 (a) It is recognized that, at times, it may not be possible or practical 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. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the ODOM) for all licensed site reactors.

(b) Particulate sample filters should be analyzed for gross beta 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 is greater than 10 times a historical yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

Rev. No. -9 Rev. o. 9Page 46 of Part 1 (REC)

(c) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant.

(d) The purpose of these samples 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 which provide valid background data may be substituted.

(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for measuring direct radiation.

(f) The,"upstream sample" shall be taken at a distance beyond significant influence of the discharge.

The "downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical.

(g) Composite samples should be collected with equipment (or equivalent) which is capable of collecting an aliquoit at time intervals which are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to ensure that a representative sample is obtained.

(h) A milk sampling location, as required in Table 5.1-1 is defined as a location having at least 10 milking cows present at a designated milk sample location. It has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes.

Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry. In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less-than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer.

Rev. No. -9 Rev. o. 9Page 47 of Part I (REC)

TABLE 5.1-2 REPORTING LEVELS (

FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Airborne Food Water Particulate or Fish Milk Products Analysis (pCi/I) Gases (pCi/rn 3) (pCi/kg. wet) (pCi/I) (pCi/kg. wet)

H-3 30,000 ________ _____________

Mn-54 1,000 ___ ____ 30,000 _ ____

Fe-59 400 _________ 10,000 Co-58 1,000 _________ 30,000 Co-60 300 _________ 10,000 ______

-Zn-65 300 _________ 20,000 Zr/Nb-95 400 ________ _______ _____

1-131 20 0.9 _ _____ 3 100 Cs-1 34 30 10 1,000- 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba/La-i 40 200 ______ 1________ 300 Rev. No. 9 Rev. o. 9Page 48 of Part 1 (REC)

TABLE 5.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS(a)

______ LOWER LIMIT OF DETECTI ON (LLD)(b) i_____

Airborne Fish Food Water Particulate or (pCi/kg, Milk Products Sediment Analysis (pCi/I) Gases wet) (pCi/I) (pCi/kg, wet) (pCi/kg, dry)

_________ (Pci/rn3) ______

Gross Beta 4 0.01 ____________

H-3 3,000 _____ _____

Mn-54 15 130 Fe-59 30 260 ____

Co-58,60 15 130 ____

Zn-65 30 260 Zr/N b-95 15 1-131 156 0.07 1 60

-Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 1______ 1____ 15 1_____ 1______

NOTES FOR TABLE 5.1-3 (a) The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation),

4.66 Sb LLD =

E -V -2.22 - Y - exp (-XAt)

Rev. No. 9 Rev. o. 9Page 49 of Part 1 (REC)

Where:

LLD isthe a priori lower limit of detection, as defined above (in pico .Curie 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 (in counts per minute);

E is the counting efficiency (in counts per transformation);

V is the sample size (in units of mass or volume);

2.22 is the number of transformations per minute per picoCurie; Y is the fractional radiochemnical yield (when applicable);

Ais the radioactive decay constant for the particular radionuclide; At 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 calculations.

(b) 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.

(c) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore, an LLD value of 15 pCi/liter is used.

Rev. No. -9 Rev. o. 9Page 50 of Part 1 (REC)

5.2 Land Use Census Program 5.2.1 Limiting Conditions For Operation

a. Applicability At all times.

b. Objective To identify locations of mulch animals and gardens of greater than 50 square meters within 5 miles of the site.

c. Specifications

1. A land use census shall be conducted and shall identify the locations of all milch animals, the nearest residence, and all gardens' of greater than 50 square meters producing fresh leafy vegetables, in each of the 16 meteorological sectors within a distance of 5 miles from the site.0)

2. With a land use census identifying a milch animal in a location(s) which represents a calculated DIQ value greater than the values currently being used in calculating Surveillance Requirement 3.4.2.c.1, identify the new location(s) in the next Radioactive Effluent Release Report.

3. With the land use census identifying a milch animal location(s) that represents a calculated D/Q (via the same exposure pathway) 50% greater than at a location from which samples are currently being obtained in accordance with Table 5.1-1, add the new location(s) to the radiological environmental monitoring program within 30 days.

The sampling location(s), excluding the control station location, having the lowest calculated DIQ (via the same exposure pathway) may be deleted from this monitoring program after October 31 of the year in which this land use census is conducted. Identify the new location(s) in the next Radioactive Effluent Release Report and include the additions in the ODOM.

'Broad leaf vegetation sampling may be performed in lieu of the garden census as specified in Table 5.1-1.

Rev. No. 9 Rev. o. 9Page 51 of Part I (REC)

5.2.2 Surveillance Requirements The land use census shall be conducted during the growing season at least once per 12 months using the information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities, etc. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

5.2.3 Bases This specification is provided to ensure that changes in the use of areas. at and beyond the site boundary are identified and that modifications to the monitoring program are made if required by the results of this census. The best survey information, such as that from door-to-door surveys, aerial surveys, consultations with local agricultural authorities, etc., shall be used.

This census satisfies the requirements of 10 CFR 50, Appendix 1,Section IV.B.3. Restricting the census to gardens of greater than 50m' 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 (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109, Revision 1, October 1977, 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 (i.e., similar to lettuce and cabbage), and, (2) a vegetable yield of 2 kg/in2 . In lieu of the garden census the significance of the garden exposure pathway can be evaluated by the sampling of green leafy vegetables as specified in Table 5.1-1.

Rev. No. -9 Rev. o. 9Page 52 of Part I (REC)

5.3 Interlaboratory Comparison Program 5.3.1 Limiting Conditions For Operation

a. Applicability At all times.

b. Objective To provide quality control of environmental sample analyses.

c. Specifications

1. Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program. Participation in this program shall include all media for which samples are routinely collected and for which intercomparison samples are available.

2. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence in the Annual Radiological Environmental Operating Report.

5.3.2 Surveillance Requirements 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.

5.3.3 Bases The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in the environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.

Rev. No. -9 Rev. o. 9Page 53 of Part 1 (REC)

6.0 REPORTS 6.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the plant during the previous calendar year shall be submitted by May 15 of each year.

The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM),

and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The report shall include a comparison with preoperational studies, operational controls (as appropriate), and environmental surveillance reports from the previous five years, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the Land Use Census required by Specification 5.2.

The report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period at the locations specified in Table 5.1-1, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.

This missing data shall be submitted in a supplementary report as soon as possible.

The report shall also include the following: A summary description of the Radiological Environmental Monitoring Program; at least two legible maps (one map shall cover stations near the site boundary; a second shall ihcidide the more distant sitations) covering all sampling locations and keyed to a table giving distances and directions from the centerline of one reactor; the*results of participation in the Interlaboratory Comparison Program required by Specification 5.3, and discussion of all analyses in which the LLDs required by Table 5.1-3 were not routinely achievable.

Rev. No. -9 Rev. o. 9Page 54 of Part 1 (REC)

6.2 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the plant during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a.

6.2.1 The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant. The material provided shall be consistent with the objectives outlined in the ODCM (Part 2) and Process Control Program and in conformance with 10 CFR 50.36A and 10 CFR 50, Appendix 1,Section IV.B. 1. The summary can be provided using as guidance Regulatory Guide 1.21, Revision 1, June 1974, "Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant", with data summarized on a quarterly basis following the format of Appendix B thereof.

6.2.2 The report may include an annual summary of meteorological data collected over the previous year. If the meteorological data is not included, ENO shall retain it on file and provide it to the US Nuclear Regulatory Commission upon request. This same report shall include an assessment of the radiation doses due to the radioactive liquid and gaseous effluents released from the plant during the previous calendar year to the public. All assumptions used in making these assessments (i.e., specific activity, exposure time and location) shall be included in these reports.

The assessment of radiation doses shall be performed in accordance with the 00CM.

6.2.3 The report shall include any change to the PCP or the 00CM made during the reporting period, as well as a listing of new locations for dose calculations and/or environmental monitoring identified by the land use census pursuant to Specification 5.2.

6.2.4 The report shall also include an assessment of radiation doses to the likely most exposed member of the public from reactor releases and other nearby uranium fuel cycle sources (including doses from primary effluent pathways and direct radiation) during the previous calendar year, to show conformance with 40 CFR 190, Environmental Radiation Protection Standards for Nuclear Power Operations. This assessment of radiation doses is performed in accordance with the ODOM.

6.2.5 The report shall include the following information for each class of solid waste (defined by 10 CFR

61) shipped offsite during the report period:

a. Container volume;

b. Total curie quantity (specify whether determined by measurement or estimate);

c. Principal radionuclides (specify whether determined by measurement or estimate);

d. Source of waste and processing employed (e.g., dewatered spent resin, compacted dry waste, evaporator bottoms);

e. Type of container (e.g., LSA, Type A, Large Quantity), and,

f. Solidication agent or absorbent (e.g., cement, Dow media, etc) 6.2.6 The report shall include a list and description of unplanned releases, to unrestricted areas of radioactive materials in gaseous and liquid effluents made during the reporting period.

Rev. No. 9 Rev. o. 9Page 55 of Part I (REC)

6.2.7 The report shall contain the cause for unavailability of any environmental sample required by Table 5.1-1 and shall identify the locations for obtaining replacement samples. This shall also include a revised figure(s) and table for the ODCM reflecting the new location(s). Refer to Section 5.1.1 .c.3.

6.2.8 The report shall contain new locations identified in the land use census in accordance with Sections 5.2.1 .c.2 or 5.2.1 .c.3.

6.2.9 The report shall contain the events leading to the conditions which resulted in exceeding the radioactivity limits for the specified outdoor liquid radwaste tanks specified in the Technical Requirements Manual, TRM 3.7.E.

6.2.10 The report shall contain details of any major modifications to Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems as discussed in Section 7.0.

Rev. No. -9 Rev. o. 9Page 56 of Part 1 (REC)

7.0 MAJOR MODIFICATIONS TO RADIOACTIVE LIQUID, GASEOUS, AND SOLID WASTE TREATMENT SYSTEMS*

Major modifications to radioactive waste systems (liquid, gaseous, and solid):

1. Shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the modification is completed and made operational. 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 10 CFR 50.59,

b. Sufficient information to support the reason for the modification without benefit of additional or supplemental information; and

c. A description of the equipment, components, and processes involved and the interfaces with other plant systems.

2. The following evaluations shall be reported to the Commission in the Radioactive Effluent Release Report, where such evaluations are required to be performed in order to assure compliance with the requirements of 10 CFR 50.59.

a. An evaluation of the modifications, which show the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto.

b. An evaluation of the modification, which shows expected maximum exposure to individuals in the Unrestricted Area and to the general population that differ from those previously estimated in the license application and amendments thereto; and

c. A comparison of the predicted release of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the modifications are to be made.

() Entergy Nuclear Operations, Inc., may elect to submit the information called for in this Specification as part of the annual 10 CFR 50.59 Safety Evaluation Report.

Rev. No. 9 Rev. o. 9Page 57 of Part 1 (REC)

8.0 PURGING OF THE PRIMARY CONTAINMENT 8.1 Limiting Condition for Operation

a. Applicability Applies to the purging operations of the primary containment purge system.

b. Objective To ensure that the primary containment is purged through the Standby Gas Treatment System.

c. Specifications

1. The containment shall be purged through the Standby Gas Treatment System whenever the primary containment is required to be Operable per the Technical Specifications. If this requirement cannot be met, then purging shall be discontinued without delay.

2. With the requirements of Part 1, Section 8.1.c.1 not met, the plant must be placed in Mode 3 in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Mode 4 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

8.2 Bases Limitations on purging the containment are established to maintain releases as low as reasonably achievable.

Rev. No. 9 Rev. o. 9Page 58 of Part 1 (REC)

DVP-01 .02 PART 2 - OFFSITE DOSE CALCULATION MANUAL*

TABLE OF CONTENTS

1.0 INTRODUCTION

...................................................... 2 2.0 DEFINITIONS ...................................................... 3 3.0 LIQUID EFFLUENT METHODOLOGY...................................... 7 4.0 GASEOUS EFFLUENT METHODOLOGY..........................- -..... 33 5.0 40 CFR 190 AND 10 CFR 72.1 04(a) DOSE EVALUATION ..................... 79

6.0 REFERENCES

....................................................... 82 Rev. No. 9 I. of Part 2 (QDCMý Rev. No. 9Page

1.0 INTRODUCTION

1.1 Purpose This manual provides the methodology to calculate radiation doses to individuals in the vicinity of the James A. FitzPatrick Nuciear Power Plant. It also provides methodology for calculating effluent monitor set points and allowable release rates to ensure compliance with Technical Specifications 5.5.1 and 5.5.4, James A. FitzPatrick Nuclear Power Plant, Docket Number 50-333, and 10 CFR 20 1001-20.2402 release criteria.

1.2 Methodologies and Parameters The ODCM follows the methodology and models suggested by the "Guidance Manual For Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants" (NUREG-0133 October 1978) and "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I" (Regulatory Guide 1.109, Revision 1 dated October 1977).

Simplifying assumptions have been made and justified where applicable to provide a more workable document for implementing programmatic controls in the Technical Specifications 5.5.1 and 5.5.4, as well as the procedural details of Part 1 of this document. Alternate calculating methods to those presented here may be used provided the general methodology is similar, well documented and the results are more precise.

Additionally, as available, the most up-to-date revision of the Regulatory Guide 1.109 dose conversion factors and site specific environmental transfer factors may be substituted for those currently included and used in this document.

1.3 Document Revision Overview This is Revision 9 of the 00CM under the procedure designation of DVP-01 .02. There were 9 revisions under the previous procedure designation of CDP-iS5. This revision 6 ~4 constitutes the 18th revision of the 00CM since its inception as Rev. 0 of CDP-15.

Rev. No. -9 Rev. No. ..2 9Page of Part 2 (ODCM)

2.0 DEFINITIONS Age Groups Infants, children, teens and adults are age groups evaluated by this ODCM.

Beta A beta particle (electron)

Beta Dose The dose component to skin dose due to beta emitting radionuclides in air.

cc Cubic Centimeter Ci Curie. A unit of radioactivity equal to 3.7E+10 disintegrations per second.

See also microCurie (pCi).

C1 Concentration of a nuclide in the release source. Units of pCi/cc or pCi/mi.

CFR Code of Federal Regulations Dose A measure of the radiation energy deposited per unit mass (in mrem or mrad), that the organ or the individual receives from exposure to radioactive effluents dispersed in the environment.

Dose Commitment The total dose delivered to the organ or whole body over a 50 year period resulting from uptake of radioactive material.

Dose Factor Normally, a factor that converts the effect of ingesting or inhaling radioactive material into the body, to dose to a specific organ. Body elimination, radioactive decay, and organ uptake are some of the factors that determine a dose factor for a given nuclide.

Dose Pathway A specific path that radioactive material physically travels through in the environment prior to exposing an individual to its emitted radiation. The grass/cow/milk food chain is a dose pathway.

Rev. No. 9 Rev.

Page No.

9 3..1 of Part 2 (ODOM)

Dose Rate The dose received per unit time.

DoseRate

2) for ground-level (d/q) The short-term atmospheric deposition factor (n1 releases and a specified release duration.

(D/Q) A long term relative deposition coefficient. A factor with units of 1/Mn2 which describes the deposition of particulate matter from a plume at a point downrange from the source. It can be thought of as the part of the cloud that will fall out and deposit over one square meter of ground.

ECL The Effluent Concentration Limit (ECL) is equal to 10 times the effluent concentration values listed in 10 CFR 20, Appendix B, Table 2, Column 2.

Gamma A gamma photon Gamma Dose The dose component to skin or whole body dose due to gamma-emitting radionuclides in air.

Ground Plane Radioactive material deposited uniformly over the ground emits radiation that produces an exposure pathway when an individual is present in the area. It is assumed that an adult receives the same exposure as an infant, regardless of the physical height differences. Only the whole body and skin is considered for the purpose of the ODCM.

H-3 Hydrogen-3, or tritium. An isotope of hydrogen that is a low-energy beta emitter.

I&8DP Radioiodines and particulates with half-lives greater than eight days (includes H-3 where applicable).I LLD Lower Limit of Detection. The smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95 percent probability and with only 5 percent probability of falsely concluding that a blank observation represents a "1real" signal.

LCO Limiting Conditions for Operation in Part 1 m3 Cubic meters m2 Square meters Rev. No. 9 4 of Part 2 (ODCM)

Rev. o. 9Page

Nuclide An atomic nucleus that contains a specified number of protons and neutrons. Nuclide (I)signifies a specific nuclide under consideration (e.g.,

1st, 2nd, 3rd, etc.). If nuclide (i) is 1-131, then the M',l (dose factor) under consideration should be M.3 ,for example.

Organ For the purpose of the ODCM, either the bone, liver, thyroid, kidney, lung, GI-LLI, skin or the W. Body (Whole body). W. Body is considered an organ for consistency with the ODCM nomenclature.

Qj Q0 (dotted) denotes a release rate in Ci/sec or liCi/sec for nuclide (i).

Qi Denotes Ci of nuclide (i) released over a specified time interval.

Receptor The individual receiving radiation exposure from effluent releases at JAFNPP at a given location, or who ingests food products contained with trace amounts of radioactive materials. A receptor can receive dose from one or more dose pathways.

Release Source A subsystem, tank, vent or stack where radioactive material can be released independently of other radioactive release points.

Restricted Area An area access to which is limited by Entergy for the purpose of protecting individuals against risks from exposure to radiation and radioactive materials.

pCi MicroCuries. 1 Ci = I E+6 p~uries. The pCi is the standard unit of radioactivity for all dose calculations in the JAFNPP ODCM.

(xlq) The short-term atmospheric deposition factor (sec/rd) for ground-level releases and a specified release duration.

(X/Q) A long term relative atmospheric dispersion coefficient. It describes the physical dispersion characteristics of a semi-infinite cloud of noble gases as the cloud travels downwind from the release point.

(X/Q)ý Long term finite cloud atmospheric dispersion parameter for computation of external gamma radiation exposures (sec/rri?). (By definition, the gamma (X/Q) is the equivalent relative concentration of radioactivity in a semi-infinite cloud that would yield the same radiation exposure as a finite cloud aloft; it accounts for the actual plume dimensions and elevation above the receptor, and gamma radiation spectra.)

Rev. No. 9 .5 of Part 2 (ODOMA Rev. o. 9Page

Unrestricted Area An unrestricted area shall be any area at or beyond the site boundary where access is neither limited nor controlled by Entergy for purposes of protecting individuals against undue risk 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.

Vent Building ventilation air exhausts via roof top ducts.

(X/W) The annual average relative concentration (sec/rr?) for a given liquid pathway (potable water or fish ingestion) for a specified release duration.

Rev. No. 9 Rev. No. 9Page 6.. of Part 2 (00CM)

3.0 LIQUID EFFLUENT METHODOLOGY 3.1 Applicable Site Characteristics The JAFNPP Final Safety Analysis Report (FSAR) contains the official description of the site characteristics. The description that follows is a brief summary for dose calculation purposes.

The James A. FitzPatrick Nuclear Power Plant is located on the eastern portion of the Nine Mile Point promontory on Lake Ontario in Oswego County, NY. The site is approximately seven miles northeast of the City of Oswego. Radioactive liquid releases normally enter Lake Ontario where the Circulating Water Discharge Tunnel terminates on the lake bottom approximately 1,400 feet from the shoreline.

3.2 10 CFR 20, ECL Lim its-Determi nation of the Fraction (FL) of Release Limits and Minimum Required Dilution 3.2.1 Requirements In accordance with Part 1, Section 2.2.1.c.1, the concentration of liquid radioactive material released to unrestricted areas (Appendix G) shall not exceed 10 times the concentrations specified in 10 CFR 20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases. Concentration of radionuclides in liquid waste is determined by sampling and analyses in accordance with Part 1, Radiological Effluent Controls, Section 2.2.

In accordance with Part 1, Radiological Effluent Controls, Section 2.2 for dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/mI.

3.2.2 Methodology This section presents the calculating method to be used for determining FL, the fraction of Part 1, Section 2.2.1 .c.1 limits, of release concentrations of liquid radioactive effluents.

This method addresses the calculation for a specific release source. Administrative controls are applied to assure that the summation of FL values for each release source does not exceed the Part 1, Section 2.2.1.c.1 limit. Normally, all potentially radioactive liquid effluents are released to the unrestricted area through a single monitored release path as indicated in Appendix F. However, the service water system presents a potential release point for radioactive liquid effluents. To assure the combined releases do not exceed Part 1, Section 2.2.1 .c.1 effluent concentration limits (ECLs), the alarm set point, as determined in Section 3.3 includes a conservatism factor of 0.5.

Rev. No. -9 Rev. o. 9Page 7 of Part 2 (ODOM)

The basic equation which determines the fraction (FL) of the ECL is:

Eq. 3-1 FL ~] x Where:

FL = The fraction of ECLs resulting from the release source being discharged (dimensionless) f, The undiluted release rate of the release source as measured at the liquid effluent monitor location, in gpm.

f2 The discharge structure exit flow in gpm. (Summation of circulating water pump and service water pump discharge flow; minus the flow redirected for tempering)

C = Each undiluted concentration of of nuclide (i) in pCi/mI (includes both gamma and beta emitters)

ECL = The ECL for nuclide (i) in pCi/mI. The ECLý is equal to 10 ECLI1 times the corresponding effluent concentration value listed in 10 CFR 20, Appendix B, Table 2, Column 2.

Using this approach, the fraction of the ECL is determined using a nuclide-by-nuclide evaluation.

Rev. No. -9 Rev. o. 9Page 8 of Part 2 (ODOM)

3.2.3 Calculating Process for Determining tfjf The following section provides a procedure for determining the minimum required dilution factor (f2/f1) to ensure that FL:5 1 during the actual release. With FL < 1,the minimum required dilution factor can be expressed as:

Eq. 3-2 n ci (mi)nm ~=: ~

ECUj

a. Obtain (G), the undiluted assay value of nuclide (i), in pCi/mi.

b. From Appendix A,Table A-I, obtain the corresponding ECLý for nuclide (i) in pCi/mi. The ECL1 is equal to 10 times the corresponding effluent concentration

,value listed in 10 CFR 20, Appendix B, Table 2, Column 2.

c. Divide C,by ECL 1.

d. Repeat steps b and c above for each nuclide and sum the totals.

e. Enter only the total Gamma activity and the minimum required dilution factor (f2/f,)min on the liquid release permit.

Rev. No. 9 Rev. o. 9.Page

9. of Part 2 (ODOM)

3.3 Determination of Setpoints for Radioactive Liquid Effluent Monitors 3.3.1 Requirements Part 1, Section 2.1.1.c.1 requires that the radioactive liquid effluent monitor be operable and set to initiate an alarm and/or trip in the event that the limits of Part 1, Section 2.2. 1.c. 1 are approached. The alarm and/or trip set points shall be determined and adjusted by the methodology which follows. The set point values should be applied above normal background levels.

The alarm set point for the liquid effluent radiation monitor is derived from the ECLs applied at the unrestricted area boundary where the discharge tunnel flows into Lake Ontario.

An Implementation Plan as defined in AP-02.04 shall be initiated and included in any 00CM revision whenever the methodology for calculating liquid setpoints is changed and the change in methodology results in a new calculated setpoint.

3.3.2 Methodology The alarm set points do not consider dilution, dispersion, or decay of radioactive material beyond the unrestricted area boundary (i.e., the alarm setpoints are based on a concentration limit at the end of the discharge tunnel).

3.3.3 Radwaste Liquid Effluent Monitor

a. A sample of each batch of liquid radwaste is analyzed for 1-131 and other principal gamma emitters prior to release. The fraction FL of 10 CFR 20, ECLs, and the minimum required dilution factor to achieve FL = 1 is determined in accordance with the preceding section for the activity to be released. For cases other than minimum dilution calculation, FL < 0.5.

b. A conservative alarm and/or trip setpoint (pCi/mI) is determined in accordance with the following equation.

Eq. 3-3 S = 0. 5 x C9 FL Where:

S =The alarm and/or trip set point above background corresponding to the limiting concentration of undiluted liquid effluent (pCi/mI).

0.5 =Conservatism factor to account for releases from multiple points, and to allow for nuclides not detected by the monitor.

Rev. No. 9 10. of Part 2 (00CM)

Rev. o. 9Page

Cg = Total undiluted concentration of gamma emitters in pCi/mI as determined in the laboratory.

FL The fraction of the Part 1, Section 2.2.1 .c.1, ECLs for unrestricted areas resulting from the release source being discharged.

3.3.3.1 Calculating Process The following section provides a procedure for determining the radwaste liquid effluent monitor set point. Typical parameter values are used for illustration.

a. Determine the undiluted gamma concentrations from laboratory analysis of the liquid effluent sample. For the purpose of this example, assume only Co-60 is present at a concentration of 3.OE-05 pCi/mI.

b. Determine the beta activity from the most recent composite results (Cb).

For the purposes of this example, assume only H-3 is present at a concentration of 2.2E-02 pCi/mi.

c. Determine f2 from pump curves and current plant operating configuration.

A typical value is 3.78E+5 gpm.

d. Determine the minimum required dilution factor in accordance with equation 3-2.

[ými 11 n ____

min(ECL)J Rev. No. 9 Rev. o. 9Page 11 of Part 2 (ODO-M)

For this example, ECL values for Cobalt-60 and Tritium are obtained from Appendix A, Table A-I (ECLs):

'2 3E-05 +2.2E-02

[ 1imin 3E-05 1IE-2

= 3.2 L 1min

e. Determine or calculate the required f1 at the liquid effluent monitor location. A typical value is 100 gpm.

f. A typical value of the dilution factor from current plant operating conditions is:

(3.78E+5 gpm)II00 gpm = 3,780, which is >3.2. Therefore the release can be made at the current release rates and concentrations maintained within the 10 CFR 20 Part 1, Section 2.2.1.c.1 ECLs. I

g. Determine FL, the fraction of 10 CFR 20 ECLs resulting from the release source being discharged at a dilution factor of 3,780, in accordance with equation 3-1.

FL[j n ci 1=1 (ECL) i (00/3.78E+5) 0 x 3.2 (from 3.3.3.1.d)

=(2.65E-4) x 3.2

=8.47E-4 Rev. No. -9 Rev. o. 9Page 12 of Part 2 (ODOM)

h. The liquid effluent monitor set point, S in pCi/mi, from equation 3-3 is:

Eq. 3-3a S = 0.5 x C FL

= 0.5 x [(3E-5)/(8.47E-4)]

= 1.77E-2 L Appropriate calibration factors are applied to this limiting concentration determined in step 3.3.3.g to determine an effluent monitor alarm potentiometer set point.

Rev. No. 9 Rev. o. 9Page 13 of Part 2 (ODCM)

3.3.4 Service Water Liquid Effluent Monitor

a. A conservative alarm setpoint (cps) for the service water liquid effluent monitor is determined in accordance with the following methodology:

Eq. 3-3b 2

DF-=

Where:

OF =the dilution factor which results from the flow rate in the discharge structure divided by the undiluted release rate of the effluent release source.

f = the undiluted release rate of the effluent source measured at the service water liquid effluent monitor (gpm).

f2f -the discharge structure flow rate in gpm (summation of circulating water pumps and service water pumps discharge flows; minus the flow redirected for tempering).

Eq. 3-3c SP=0.5 x ECLW x DF+

Eff k K Where:

SP = set point Of liquid effluent monitor in cps.

0.5 =conservatism factor to account for releases from multiple points or a reduction in the OF value due to changes in discharge canal flow, and to allow for nuclides not detected by the monitor.

Cg9 Total undiluted concentration of gamma emitters in pCi/mI ECLW, weighted ECL for historical nuclide mix (See Section 3.3.4.b)

C9 n C.-

ECL1 Rev. No. -9 Rev. o. 9Page 14 of Part 2 (00CMA

Eff = efficiency of the liquid effluent monitor in pCi/mI/cps.

Bkg = normal monitor background (cps).

b. Those nuclides present in previous batch releases from the liquid radwaste effluent system, nuclides present in historical Radioactive Effluent Release Reports or those nuclides present in the service water system may be used to calculate the ELCW value. Other values for ECIW may be used based on plant conditions (i.e. in the event of known leakage into the RBCLC system).

Rev. No. -9 15 of Part 2 (ODOM)

Rev. o. 9Page

3.4 Dose Determination for Radioactive Liquid Effluents 3.4.1 Annual Dose Assess ment-Rad ioactive Effluent Release Report Submittal

a. Requirements Technical Specification 5.6.3 requires a Radioactive Effluent Release Report to be submitted that includes an assessment of the radiation doses to the public due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year. The dose assessment required by this report is due prior to May 1 of each year in accordance with 10 CFR 50.36a.

b. Methodology This section provides the methodology to calculate the doses to all age groups and organs from all radionuclides identified in the liquid, effluents. The method is based on the methodology suggested by NUREG-01 33, October 1978, Sections 4.3 and 4.3.1 and Regulatory Guide 1.109. The determination of viable liquid dose pathways is described in Appendix A, Table A-4.3. The site-related dose factors for all viable pathways are listed in Appendix A, Tables A-2 and A-3. Table A-3 dose factors are compiled by age groups, for all organs and radionuclides common to a Boiling Water Reactor (BWR).

The following equation provides for a dose calculation to the whole body or any organ for a given age group based on actual release conditions during a calendar year for radioactive liquid releases. The equation for D, is to be summed over all i nuclides:

Eq. 3-4a D. = AiT At1 Q,1 IT (DF),

Eq. 3-4b n

DT= EDiT Where:

DT = Total dose commitment for organ TOf an age group.

Di Dose commitment in mrem received by organ Tof age group (to be specified) resulting from releases during time interval At1 for nuclide (1).

Rev. No. -9 Rev. o. 9Page 16 of Part 2 (ODOM)

AlT The site-related dose commitment factor to the whole body or any oran for each identified radionuclide (i).. The 4,values listed in Appendix A, Tables A-2 and A-3 are site specific, in mrem/hr per pCi/mI. Dose commitment factors are compiled by age groups, for organs and radionuclides common to a BWR environment. The derivation of k values is described in Appendix A, Table A-4. 1.

At, The number of hours in the calendar year.

Q= The total quantity of nuclide (i) released during the time period

,At,, in pCi.

(DF), The total volume of dilution released duringhLt 1 (i.e.,

summation of circulating water pump and service water pump discharge flow; minus the flow redirected for tempering).

By entering the appropriate annual parameter values onto a form similar to that shown in Table 3.4.2, whole body or organ doses may be calculated as outlined in step 3.4.2.c.

In addition, more realistic assumptions may be made concerning the dilution and ingestion of fish and potable water by individuals who live and fish in the area.

3.4.2 Monthly Dose Assessment - Verification of Compliance with 10 CIFR 50, Appendix I Limits

a. Requirements Part 1, Section 2.3.2 requires an assessment to be performed at least once every month in any quarter in which radioactive effluent is discharged, to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 1.5 mrem to the wholel body and 5 mrem to any organ in a calendar quarter, and to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 3.0 mrem to the whole body and 10 mrem to any organ during a calendar year.

b. Methodology This section presents the calculating method to be used for the 10 CFR 50 Appendix I compliance verification. The method is based on the models suggested by NUREG-0133 October 1978 Sections 4.3 and 4.3.1 and Regulatory Guide 1.109.

Rev. No. -9 17 of Part 2 00DCM)

Rev. o. 9Page

1. General Approach(

The general approach used is similar to that described for use in calculations for the Annual Dose Assessment Report. The liquid effluent dose pathways considered are fresh water fish, potable water and lake shoreline deposits (Appendix D). These pathways need to be considered for verifying compliance with the requirements specified above.

Site-specific dose factors for the fresh water fish, potable water and shoreline pathways are provided in Appendix A, Tables A-2 and A-3.

For JAFNPP, both the adult and teenager are normally the most limiting age groups (Appendix D), but the dose for child and infant may also be calculated by this method using the appropriate dose factors from Appendix A, Table A-3.

The following equation is used to determine a dose to the whole body or any organ for a given age group based on actual release conditions during a specified time interval for radioactive liquid releases. The equation for D,, is to be summed over all i nuclides:

Eq. 3-5a D.=AT At1 Q11 DiT (DF),

Eq. 3-5b n

DT E ZD, T Where:

DT = Dose commitment for organ Tof an age group.

DiT = Dose commitment in mrem received by organ Tof age group (to be specified) from release time interval Al for nuclide (i).

AiT = The dose factor for the fresh water fish, potable water lake shoreline deposits pathways for nuclide (i) for organ Tof age group (to be specified). (Appendix A, Tables A-2 and A-3 for Af, A., and A1 sh),

At 1 = The number of hours in the reporting period.

Rev. No. -9 Rev. o. 9Page 18 of Part 2 (00CM)

Q= The total quantity of nuclide (i) released during the time period At, in pCi.

(OF), = The total volume of dilution released duringhLt, (i.e.,

the summation of circulating water pumps and service water pumps discharge volumes; minus the volume redirected for tempering).

2. Limited Analysis Approach Based on the radionuclide distribution typical in radioactive effluents at JAFNPP, the calculated dose to individuals are dominated by the radionuclides, Cs-I 34, Cs-I 37, Zn-65, Mn-54 and Co-60. From 1980 through 1987, these nuclides, in the fresh water fish and potable water pathways, contributed at least 92 percent of the adult's whole body dose and at least 81 percent of the teenager's liver dose, which is the critical organ. Therefore, the dose commitment due to radioactivity in liquid effluents may be reasonably evaluated by limiting the dose calculating process to these radionuclides for the adult's whole body and the teenager's liver dose.

To allow for any unexpected variability in the radionuclide distribution, a conservatism factor of 0.8 is introduced into the equation. After calculating the dose based on these five nuclides, the cumulative dose should therefore be divided by 0.8. (Refer to Appendix D for a detailed evaluation and explanation of this limited analysis approach).

If the limited analysis approach is used, the calculation should be limited to the adult's whole body dose and teenager's liver dose from the fish and potable water pathways. Only the five previously specified nuclides need be evaluated.

3. Approach Selection Criteria The limited analysis approach fully satisfies the requirements and can thus be used for routine releases. The more general approach may be used for more refined calculations for routine releases.

For non-routine releases, i.e., other than through the discharge canal, Section 3.4.3 is to be used.

C. Calculating Method The methodology that follows is a step-by-step breakdown to calculate doses based on equation 3-5. If the limited analysis approach is used, the calculation should be limited to the adult whole body dose and teenager's liver dose from the fish and potable water pathways. Only the five previously specified radionuclides need to be evaluated for the limited approach.

NOTE: Table 3.4.2 provides a convenient form for compiling the dose accounting information.

Rev. No. -9 19 of Part 2 (ODOM)

Rev. o. 9Page

1. Determine (At,) the number of hours of the reporting period.

2. Obtain (DF), for the time period At1 for the release source(s) of interest.

DF, is the total volume of dilution, (i.e. the circulating water flow multiplied by the time) in milliliters.

3. Obtain Q,, (pCi) for nuclide (i) for the time period Ai.

4. Obtain AlT from the appropriate Liquid Dose Factor Table: Appendix A, Table A-2 for the fish and potable water pathways; Appendix A, Table A-3 for all other pathways.

5. Solve for Dose (i)

Eq. 3-6a A.Tx At, xQ1 1 DiT (DF),

6. Repeat steps 3 through 5 above for each nuclide reported and each organ required. If the limited analysis method is used, limit the radionuclides to Co-60, Mn-54, Zn-65, Cs-I 34 and Cs-i 37 and determine the adult's whole body dose and the teenager's liver dose.

7. Sum the DiT values to obtain the total dose. If the limited analysis method is being used, divide the cumulative dose by a conservatism factor of 0.8 to account for any unexpected variability in radionuclide distribution and any contribution from the lake shoreline deposits pathway.

Eq. 3-6b n

DT j=1 (0. 8*

When limited approach is used Rev. No. 9 Rev. o. 9Page 20 of Part 2 (ODCM)

TABLE 3.4.2 FISH PATHWAY Time/Date Start: ___________Time/Date Stop: _________it, hours Total Dilution Volume (DF),: _ ______________MIS Age Group: ______Organ: __________Dose Factor Table No. ____

Nuclide (i) 41AI Dose (i) mrem Mn-54 Co-60 Zn-65 Cs- 134 Cs-137 Others.

Total Dose T = mrem Eq. 3-6a If based on limited analysis -0.8 mremn Rev. No. -9 Rev. o. SPage 21 of Part 2 (ODOMa

3.4.3 Dose Assessment - Methodology For Liquid Releases Through the Storm Drain (

This section provides the methodology to calculate the doses to all age groups and organs from liquid releases other than routine releases through the discharge canal, such as releases via the storm drain.

a. Requirements Non-routine liquid releases, when they occur, are to be added into the Radioactive Effluent Release Report(s) and the annual dose assessment report (Section 3.4. 1) and the verification of compliance with 10 CFR 50 Appendix I regulatory guidelines (Section 3.4.2). The following are the Technical Specification requirements for non-routine liquid releases, other than through the discharge canal.

Technical Specification 5.6.3 requires a Radioactive Effluent Release Report to be submitted prior to May I of each year in accordance with 10 CFR 50.36a that

-includes an assessment of the radiation doses to the public due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year.

Part 1, Section 2.3.2.c requires an assessment to be performed at least once every month in any quarter in which radioactive effluent is discharged, to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 1.5 mrem to the whole body and 5 mrem to any organ in a calendar quarter, and to verify that radioactive liquid effluents from the plant do not result in a cumulative dose in excess of 3.0 mrem to the whole body and 10 mrem to any organ during a calendar year.

b. Methodology Exposure pathways of interest are the ingestion of contaminated fish and drinking of contaminated water. Exposure from shoreline deposits following non-routine releases was determined to be insignificant and has been excluded from this section.

The model used accommodates (in a single unified approach) releases ranging from instantaneous (slug) to continuous (steady-state).

The method of analysis selected for dilution of the released radioactivity in the lake makes use of the continuous-release model in Regulatory Guide 1.113, adapted to provide annual average concentrations for releases of shorter duration (including instantaneous). The model assumes an exposure interval of one year, regardless of the duration of the release.

Rev. No. 9 Rev. o. 9Page 22 of Part 2 (ODCM)

For the fish-ingestion pathway, the fish is assumed to be adjacent to the release point for the duration of the release, and then to follow the radioactive plume for an overall exposure interval of one year. For the potable water pathway, the water supply is at 8.5 miles west of the plant (Oswego water intake), and is assumed to be continuously contaminated as a result of frequent current reversals.

The following equations present the annual dose due to the potable water and freshwater fish pathways for any given release, regardless of the release duration. These doses are to be assigned to an appropriate reporting interval (e.g., quarter) during which the release occurred.

Potable Water PathwAay Eq. 3-7a DiT =K a x Ux DFiTX CiX 4X(XIW) X At Eq. 3-7b n

DT= ~D i Where:

DT = Dose commitment for organ Tof an age group (mrem).

DiT = Dose commitment received by organ Tof an age group (to be specified) for nuclide I (mrem).

Ka Is the unit conversion factor, I .OE+.09 (mI-pCi per liter-pCi).

Uf = Is the water consumption rate for the age group of interest.

Adult: 730 liters/yr Teen: 510 liters/yr Child: 510 liters/yr Infant: 330 liters/yr OFIT = Dose conversion factor (mrem per pCi ingested) for radionuclide I, for organ Tand age group of interest, from Tables E-1 1 through E-1 4 of Regulatory Guide 1.109.

C! The average activity concentration of nuclide i in the effluent at the release point into the lake (pCi/mI).

Rev. No. -9 23 of Part 2 (ODCM)

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q = The volumetric discharge rate of the effluent (rri/sec).

q is equal to the total volume of contaminated liquid release (in3) divided by the duration of the release.

(X/W) = The annual average relative concentration (seclrri3 ) for the potable water pathway, as shown in Table 3.4.3 for a list of release durations. Release durations were selected to accommodate a change of no more than 20% between consecutive )(/Ws.

At = The exposure period which is one year (yr).

Freshwater Fish Pathway Eq. 3-8a DiT = K.axUf x BF x DFiT xCi X x XV/ W) XAt Eq. 3-8b n

Where:

DT = Dose commitment of organ Tof an age group (mrem).

DiT = Dose commitment received by organ Tof an age group (to be specified) for nuclide i (mrem).

K. Is the unit conversion factor, 1.OE+09 (mi-pCi per liter-pCi).

Uf Is the freshwater fish consumption rate for the age group of interest, as follows:

Adult: 21 (kg/yr)

Teen: 16 (kg/yr)

Child: 6.9 (kg/yr)

BF1 The bioaccumulation factor for radionuclide j, in freshwater fish (pCi/kg per pCi/liter), from Table A-I of Regulatory Guide 1.109.

Rev. No. -9 24. of Part 2 (ODOM)

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DFIT Dose conversion factor (mrem per pCi ingested) for radionuclide i, for organ and age group of interest, from Tables E-I1* through E-14 of Regulatory Guide 1.109.

q = The average activity concentration of nuclide i in the effluent (pCi/mI) at the release point into the lake.

q = The volumetric discharge rate of the effluent (if/sec).

q is equal to the total volume of contaminated liquid released (in3) divided by the duration of the release.

(X/W) = The annual average relative concentration (sec/ni 3 ) for the fish ingestion pathway, as shown in Table 3.4.3 for a list of release durations. Release durations were selected to accommodate a change of no more than 20% between consecutive X/Ws.

At = The exposure period which is one year (yr).

Rev. No. 9 25.. of Part 2 (00CMa Rev. No...~Page

TABLE 3.4.3 RELEASE INTERVAL VERSUS ANNUAL AVERAGE CONCENTRATION (X/W)

Release Duration (days)

I(X/W) Fish Ingestion (sec/rr?)

I Potable Water 0.0 3.49E-04* 1.84E-04*

0.0- 0.5 3.89E-04 1.88E-04

0.5- 1.0 4.28E-04 1.92E-04

1.0- 1.5 4.68E-04 1.96E-04

1.5- 2.5 5.47E-04 2.04E-04

2.5- 3.5 6.26E-04 2.1 2E-04

3.5- 5.0 7.44E-04 2.25E-04

5.0- 6.5 8.62E-04 2.37E-04

6.5- 8.5 1.02E-03 2.54E-04

8.5- 11.0 1.22E-03 2.75E-04

11.0 13.5 1.41 E-03 2.95E-04

13.5 17.0 1.69E-03 3.24 E-04

17.0 21.0 2.01 E-03 3.57E-04

21.0 25.5 2.36E-03 3.95E-04

25.5 31.0 2.80E-03 4.40E-04

31.0 38.0 3.35E-03 4. 98E-04

38.0 46.0 3.98E-03 5.64E-04

46.0 56.0 4.77E-03 6.47E-04

56.0 68.0 5.71 E-03 7.46E-04

68.0 82.0 6.82E-03 8.61 E-04

82.0 99.0 8.1 6E-03 1.OOE-03

99.0 119.5 9.77E-03 1.17E-03

119.5 144.0 1.17E-02 1.37E-03

144.0 173.5 1.40E-02 1.62E-03

173.5 209.0 1.68E-02 1.91 E-03

209.0 251.5 2.02E-02 2.25E-03

251.5 302.5 2.42E-02 2.67E-03

302.5 365.0 2.90E-02** 3.1 3E-03**

Instantaneous release (for reference)

- Continuous release Rev. No. -9 Rev. o. 9Page 26 of Part 2 (ODOM)

3.5 Dose Projections - Determination of Need to Operate Liquid Radwaste Treatment System 3.5.1 Requirements Part 1, Section 2.4.1 .c requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce radioactive material in untreated liquid effluents when the projected monthly dose due to liquid releases to unrestricted areas, averaged over 31 days, would exceed 0.06 mrem to the whole body or 0.2 mrem to any organ.

Doses are to be projected at least once per month.

3.5.2 Calculating Methodology The method is based on whole body dose and limiting organ dose (liver) as calculated for the Monthly Dose Assessment. The adult is normally the limiting age group to be used for the dose projection to the whole body. The teen is normally the limiting age group to be used for the dose projection to the liver. Other age groups and/or limiting organs may be used if previous dose calculations indicate that the adult and teen are not the limiting age groups and the liver is not the limiting organ.

The following calculating methodology is provided for performing this dose projection.

a. Monthly Dose Projection Each month the expected dose to man shall be projected. Projections shall be based on historical or prior month dose/Curie and historical or prior month concentration conversion factors. The historical factors are calculated from historical release data for both a refuel outage year and a nonrefuel outage year. The current historical factors are on file within the Chemistry Department.

1. Each month make an estimate of the volume of liquid radwaste to be discharged during that month. The following variables should be considered in estimating radwaste volumes to be released:

(a) Projected plant operational status (run, shutdown, refuel, etc.).

(b) Status of radwaste treatment equipment. Equipment which is inoperable, such as the waste concentrator, should be factored into the source term or volume of liquid waste to be discharged from the plant.

Rev. No. -9 27 of Part 2 (ODOM)

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(c) Additional factors indicating that actual liquid releases could differ(

significantly in the next month.

(d) Historical liquid waste discharge volumes.

2. Determine which dose/Ci and Ci/gal conversion factors should be used.

Historical conversion factors can be used. Prior month conversion factors may be used if they are more representative of current release conditions. In the event that there was no release of liquid radwaste during the prior month, then the historical conversion factors can be used if liquid releases are expected during the projection month.

(a) The prior month dose/Ci conversion factors are calculated by obtaining the results of the prior month adult whole body and teen liver dose calculation.

(b) Divide the doses by the total number of Curies released from the plant during this same time period. This calculation yields a dose per Curie conversion factor for the adult whole body and teen liver for the most recent prior calendar month.

(c) The prior month Ci/gal concentration factor is calculated by obtaining the total number of Curies released from the plant during the prior month. Divide the Curie total by the total number of gallons of waste discharged during this same time period. This calculation yields the Ci/gal concentration conversion factor for the most recent month.

3. Multiply the estimated volume of liquid radwaste to be discharged, by the historical or prior month dose/Ci and Ci/gal conversion factors. This calculation yields a dose estimate to the adult whole body and teen liver for the projected month.

(a) Adult Whole Body Dose TDtb =TVxCg9x Dctb (b) Teen Liver Dose TDi=TvxCg9x D.,

Rev. No. -9 Rev. o. 9Page 28 of Part 2 (ODCM)

Where:

T, Total volume of radwaste to be discharged during the month in gallons (estimated)

C9 Curies per gallon conversion factor (historical or prior month)

Dctb = Dose per Curies adult whole body (historical or prior month) in mrem TDtb = Total dose for adult whole body in mrem Dc Dose per Curies teen liver (historical or prior month) in mrem TD, = Total dose for teen liver in mrem If the calculated doses are greater than 0.06 mrem to the whole body or 0.2 mrem to the liver, the appropriate subsystems of the liquid radwaste system shall be used to.reduce the radioactivity levels prior to release.

b. Batch Dose Projections The projected dose due to release of each batch can be made prior to the release of the batch. The projection of the dose related to each batch allows for an accurate method of estimating the dose from each batch prior to release and confirms the need to operate the subsystems of the radwaste system. The projection of dose based on each batch release helps to eliminate any inaccuracies as a result of using historical or estimated values in the monthly projection. The use of this dose projection on a batch release basis is not required by the technical specification and is used at the discretion of the Chem istry/E nvironmental Management.

The method is based on whole body dose and limiting organ dose (liver) as calculated in step 3.4.2. The adult is the limiting age group for projecting dose to the whole body and the teen is the limiting age group for projecting dose to the liver.

The following calculating methodology is provided for performing this dose projection:

1. Obtain the latest result of the monthly calculation of the adult whole body and teen liver dose (step 3.4.2).

2. Divide the doses by the total number of Curies released from the plant during the month. This yields a dose per Curie conversion factor for the adult whole body and teen liver for the most recent calendar month.

3. Maintain a running total of the Curies released during the past 30 days. Add to this the Curie content of the current batch to be released (31 day total).

Rev. No. -9 Rev. o. 9Page 29 of Part 2 (ODOM)

(7

4. Multiply the 31 day total from step (3), above by the dose per Curie conversion factors calculated in step (2), above. This yields the 31 day, whole body and liver doses projected for the release of the current batch.

5. If the calculated doses are greater than 0.06 mremn to the whole body or 0.2 mrem to the liver, the appropriate subsystems of the liquid radwaste system shall be used to reduce the radioactivity levels prior to release.

c. Continuous Liquid Release Dose Projections Each month that a continuous liquid release is in progress, or is anticipated, the expected dose to man can be projected. The projection shall be based on historical, prior month or current dose/Curie and nuclide concentration (Curie/gallon) conversion factors. The historical conversion factors are calculated from prior releases. The prior month conversion factors are calculated from the prior month continuous liquid releases if such releases occurred. Current conversion factors are calculated from samples obtained at or near the beginning of the dose projection month.

1. Determine which dose/Ci and Ci/gal conversion factors should be used.

Historical conversion factors can be used. Prior month or current conversion factors should be used if they are more representative of current release conditions.

(a) The current month Ci/gal concentration is calculated by using current sample results for radionuclide concentration and converting the results to Ci/g a .

(b) The current month estimated Curies released is calculated by multiplying the concentration by the known or expected flow rates for the effluent pathway times the period of release.

(c) Using the dose assessment methodology specified in section 3.4, calculate the adult whole body and teen liver doses using known or estimated flow rates and dilution factors.

(d) Divide the doses calculated in section (c) above by the estimated number of Curies to be released. This calculation yields a dose per Curie conversion factor for the current release parameters.

(e) The prior month dose/Ci conversion factors are calculated by obtaining the results of the prior month adult whole body and teen liver dose calculations.

Mf Divide the doses by the total number of Curies released from the plant via continuous releases during this same time period. This calculation yields a dose per Curie conversion factor for the adult whole body and teen liver for the most recent prior calendar month.

Rev. No. -9 30 of Part 2 (ODOMI Rev. o. 9Page

(g) The prior month Ci/gal concentration factor is calculated by obtaining the total number of Curies released from the plant via continuous releases during the prior month. Divide the Curie total by the total number of gallons of waste discharged during this same time period. This calculation yields the Ci/gal concentration conversion factor for the most recent month.

2. Multiply the estimated volume of continuous liquid effluent to be discharged by the historical, prior month or current dose/Cl and Ci/gal conversion factors. This calculation yields dose estimates to the adult whole body and teen liver for the projected month.

(a) Adult Whole Body Dose TDtb =TV XC9gxDctb (b) Teen Liver Dose TDi=Tv xC9gx Dcl Where:

T, Total volume of radwaste to be discharged during the month in gallons (estimated)

C9 Curies per gallon conversion factor (historical, prior month, or current)

Dctb = Dose per Curies adult whole body (historical, prior month, or current) in mrem TDtb Total dose for adult whole body in mremn Dc, = Dose per Curie teen liver (historical, prior month, or current) in mrem TDI Total dose for teen liver in mrem If the calculated doses are greater than 0.06 mrem to the whole body or 0.2 mremn to the liver or other critical organ, efforts should be made to reduce the effluent release rate or concentration.

Rev. No. -9 Rev. o. 9Page 31 of Part 2 (ODO-M)

d. Total Liquid Release Dose Projections Doses from continuous releases, when they occur, should be added to doses from batch releases to ensure that the limits, 0.06 mrem to the whole body or 0.2 mrem to any organ, are not exceeded.

Rev. No. 9 Rev. o. 9Page 32 of Part 2 (ODCM)

4.0 GASEOUS EFFLUENT METHODOLOGY 4.1 Gaseous Waste Streams James A. FitzPatrick Nuclear Power Plant (JAFNPP) discharges gaseous effluents through a stack, and discharges ventilation air from the reactor building, turbine building, radwaste building, and refuel floor through separately monitored vent release points.

There are three vent release locations. The refuel floor and reactor building vent is a combined release point. Normal gaseous effluent streams, and effluent discharge points are tabulated in Appendix F, Table F-1.

For the purpose of estimating offsite radionuclide concentrations and radiation doses, radionuclide concentrations are first measured in gaseous effluents and ventilation air exhausted from the plant. Part 1, Radiological Effluent Controls, Table 3.2-1 identifies the specific radionuclides in gaseous discharges for which sampling and analysis is done.

4.2 Data Requirements for Gaseous Effluent Calculations Dose calculations to demonstrate compliance with Part 1, Sections 3.2, 3.3 and 3.4 are normally performed using historical meteorological data and receptor location(s).

Historical meteorological data for use in performing dose calculations are provided in Appendix C. Dose calculations to show conformance with Part 1 dose limits may be performed using real meteorological data, real receptor locations, and sector wind frequency distribution if desired.

Historical meteorological data factors are calculated and used in dose calculations for the Radioactive Effluent Release Report. The report shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. Historical information and conservative receptor assumptions, are also used for ease of Part 1, Limiting Conditions for Operation (LCO) dose limit calculations. JAFNPP uses an elevated release model for stack discharges and mixed mode model for reactor, turbine, radwaste and refuel floor vents.

Those radionuclides that appear in the gaseous effluent dose factor tables are representative of BWR isotopes that may be considered in dose calculations.

The historical meteorological data and associated dispersion factors (X/Q, D/Q) are found in Appendix C. The dispersion factors used for receptor dose calculations are calculated based on site meteorological data and plant specific release point parameters.

Rev. No. -9 33 of Part 2 (ODCM)

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4.3 Instantaneous Release Rate and Set Point Determination 4.3.1 Determining Instantaneous Noble Gas Release Rates

a. Requirements Part 1, Radiological Effluent Controls, Section 3.2.1.c limit the instantaneous dose rate from noble gases in airborne releases from the plant tof50O mremlyr -.whole body, and *3,000 mrem/yr - skin.

The results of the sampling and analysis program of Part 1, Radiological Effluent Controls, Table 3.2-1 are used to demonstrate compliance with these limits.

b. Methodology The instantaneous dose rates to the whole body and skin from noble gases are evaluated to determine gaseous effluent release rates and alarm and/or trip set points.

The following calculating method is provided for determining the instantaneous dose rates to the whole body and skin from noble gases in all monitored airborne release paths from JAFNPP. Conservatism factors in the instantaneous release rate equations are adequate to account for simultaneous releases from the NMP stack and vent. JAFNPP discharges gaseous effluents through a stack, and ventilation air from the reactor building, turbine building, radwaste building, and refuel floor through monitored vent release points.

The calculating methods are in accordance with NUREG-Ol 33, October 1978, Section 5.1 and 5.2.

The equations for computing instantaneous dose rates are:

Whole Body Dose Rate Vent Eq. 4-1la n __

DRTB= K, x(X/Q) xQ Rev. No. -9 34 of Part 2 (ODCM)

Rev. o. 9Page

Elevated Stack E.4l Eq. 4-1 b n __

DRTB E K, x(XI Q) x Q, i=1 The equations for DRTB are to be summed over all vent and elevated stack release sources.

Skin Dose Rate Vent Eq. 4-2a DRSKIN [Li + 1.1 Mi] (XQx 6i Elevated Stack Eq. 4-2b n

DRSKN [Li (x1Q) +i. i mi (x-lQ),] x 6, Where:

DRTB -Whole body dose rate from noble gases in airborne releases, in mrem/sec.

DRSKIN -Skin dose rate from noble gases in airborne releases in mrem/sec.

-The whole body dose factor due to gamma emissions for each noble gas nuclide (i) reported in the release source, in mrem-m 3/pC!-sec.

-The skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source in mrem-m 3/pCi-sec.

-The air dose factor due to gamma emissions for each noble gas nuclide (i) reported in the assay of the release source.

The constant 1.1 converts 'mrad' to 'mrem' since the units of Mi are in: (mrad-m 3/pCi-sec)

Rev. No. -9 35 of Part 2 (QDCM)

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(X/Q) =For vent or elevated stack releases, the highest annual average, concentration X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/rn 3 (Appendix C,Table C-1).

(X/QX For elevated stack releases, the highest annual average, finite cloud X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in seC/rn 3 (Appendix C,Table C-2).

Q= The release rate of noble gas nuclide (i) from the release source of interest, in pCi/sec.

The equations for DRSKIN are to be summed over all vent and elevated stack release sources.

1. Limited Analysis Approach - Instantaneous Noble Gas Release Rate The above methodology can be simplified to provide for a rapid determination of cumulative noble gas release limits based on the requirements specified above.

For ease of calculation and without unduly reducing the conservatism of the calculations, all releases may be treated as if discharged from two release points, an elevated stack and the reactor vent. The reactor vent is used to represent the combined discharge of the reactor building, turbine building, radwaste building, and refuel floor vents. Beginning with equations 4-la and 4-1b, the simplification proceeds as follows.

From an evaluation of past releases, an effective whole body dose factor()

can be derived. This dose factor is, in effect, a weighted average whole body dose factor (i.e., weighted by the radionuclide distribution typical of past operation). See Appendix E for a detailed explanation and evaluation of Kff.

The value of Kff has been derived from the radioactive noble gas effluents for the years 1985 through 1991 for the plant vents and the years 1999 through 9 2003 for the elevated stack release sources..

To compensate for any unusual variability in the radionuclide distribution, 3 sigma was added to the average K,,f values and are as follows:

Keff = 9.27 E-5+ 3a

= 9.27E-5 + (3 X 4.78E-5)

= 2.36E-4 (mrem-rtf)/(pCi-sec)

(Vent Releases based on 1985 through 1991 Vent Release Data)

Rev. No. 9 Rev. o. 9Page 36 of Part 2 (ODOM)

K~f= 2.32E-4 + 3a

= 2.32E-4 + (3 x 1.38E-5)

= 2.73E-4 (mrem-rr9/pCi-sec)

(Stack Releases)

Either of these values, as appropriate, may be used in conjunction with the total noble gas release rate (EQ,) to verify that the instantaneous dose rate is within the allowable limits. The simplified dose equations are as follows:

Vent Eq. 4-3a n

DRT,9 = Keff X (XIQ) X F-Q Elevated Stack Eq. 4-3b n

DRTB =Keff x (X/Q)y x E Y Where:

DRTB =Whole body dose rate from noble gases in airborne releases, in mrem/sec.

(X/Q) =For vent releases, the highest annual average reactor vent concentration X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/rn 3 . (Appendix C, Table C-I)

(X/ = For elevated stack releases, the highest annual average finite cloud XIQ, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/in 3 . (Appendix C, Table C-2) n.

7-Q The total release rate of all noble gas nuclides from the i=1 release source of interest, in pCi/sec.

Rev. No. 9 37 of Part 2 (ODOM)

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A single cumulative (or gross) noble gas release rate limit for elevated stack releases (6 stack) and vent releases (Avent) may be derived by combining equations 4-3a and 4-3b.

Eq. 4-4a DRT1-8 [Keff (vent) x (XIQ) x Q (vent)] +

[Keff (stack) x (X/Q)y x Q (stack)]

These limits may be determined by taking the highest calculated annual average p(I-Q)Y, for elevated stack releases and the highest calculated annual average reactor vent (3U7-) for vent releases, at any of the land based sectors, at or beyond the site boundary. From Appendix C, Tables C-i and C-2, these values are:

(X/QX = 1.16E-7 se (Stack Releases)

(X/Q) =3.58-7 -s-e-3 (Reactor Vent Releases) m Also, the Part 1 dose limit of Section 3.2.1 .c.l.a is DR%. = 500 mrem/yr=

1.585E-5 mrem/sec. Q)(stack) was selected by requiring the stack not to yield a dose in excess of 300 mrem/yr or 9.51 E-6 mrem/sec.

Eq. 4-4b Q(stack) = DRTB3 (stack)

IIKeff (stack) x (XIO)YI Substituting the preceding values into equation 4-4b, Q(stack) = 3.003E+5 pCi/sec which was rounded to 3.OE+5 pCi/sec. Q(stack) was then substituted into equation 4-4a and solved for Q(vent). Therefore, the following are the cumulative (or gross) noble gas release rate limits:

Elevated Stack Release Rate Limit = 3.OOE+5 pCi/secjoI' Vent Release Rate Limit = 7.515E+4 pCi/sec Rev. No. 9 Rev. o. 9Page 38 of Part 2 (ODOM)

As long as the noble gas release rates do not exceed these values Ioqfrt (3.OOE+5 pCi/sec for elevated stack releases and 7.51 5E+4 pCi/sec for vent releases), no additional dose rate calculations are needed to verify compliance with the instantaneous release rate limits of Part 1, Radiogical Effluent Controls, Section 3.2.1.c.

2. General Approach - Whole Body and Skin Nuclide Specific Instantaneous Release Rate Calculations The methods described herein may be used for more refined calculations or used if the actual releases exceed the values of:

Elevated Stack Release = 3.OOE+5 PCi/sec Vent Release = 7.515E+4 pCi/sec I 60f Whole Body Dose Rate Eq. 4-5a Vent n __

DRT= K, Kx(XIQ) x Q The equation for DRTB is to be summed over all vent release sources.

Eq. 4-5b Elevated Stack n

DRTB= K, x (XIQ)y x Q Where:

DRTB - Dose rate to the whole body due to gamma emissions from all noble gas nuclides, mrem/sec.

KIs -The whole body dose factor due to gamma emissions from noble gas radionuclide (i), in mrem-r 3 /pCi-sec (see Appendix B, Table B-1).

Rev. No. -9 39 of Part 2 (00CM)

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(X/Q) = For vent releases, the highest annual average concentration X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/rn 3 (Appendix C, Table C-I).

(X/Q)ý For elevated stack releases, the highest annual average finite cloud X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/rn3 (Appendix C, Table C-2).

Stack Q(/Q~y = 1.16E-7 sec/rn 3 3

Vent (X/Q) = 3.58E-7 seC/rn Qj Release rate of the th~nuclide from the release source of interest, in pCi/sec.

Skin Dose Rate Vent Eq. 4-6a n

DRSKIN [L i + 1.1 M, ] (30IQ)x Q, The equation for DRSKIN is to be summed over all vent release sources.

Elevated Stack Eq. 4-6b DRSKIN =£ [Li (X/Q) + 1.1 M, (XIQ-),] x 6 Where:

DRSKIN = Dose rate to skin due to beta and gamma radiation from all noble gas nuclides (mrem/ sec).

Li The skin dose factor due to beta emissions from noble gas nuclide (i), in mrem-rn 3/pCi-sec (Appendix B, Table B-i).

M! The air dose factor due to gamma emissions from noble gas nuclide (i), in mrad-m 3/pCi-sec (Appendix B, Table B-2).

1.1 = Conversion factor for M from rnrad to mrem.

Rev. No. 9 40 of Part 2 (ODOM)

Rev. o. 9Page

X/Q =For vent or elevated stack releases, the highest annual average concentration X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/rn 3 (Appendix C,Table C-(X/Q For elevated stack releases, the highest annual average finite cloud X/Q, calculated using long term meteorological data, for any land sector, at or beyond the site boundary, in sec/rn 3 (Appendix C, Table C-2).

Q= Release rate of the Ptnu~clide from the release source of interest in pCilsec.

c. Calculating Process The following outline provides a step-by-step explanation of how the whole body and skin dose rates are calculated on a nuclide-by-nuclide basis to evaluate compliance with Part 1, Radiological Effluent Controls, Section 3.2. This method is used for more refined calculations or if the actual releases exceed the value specified in the Limited Analysis Approach - Instantaneous Noble Gas Release Rate.

3

1. For a vent, the X/Q value = _____sec/rn and _______is the most limiting land sector at or beyond the site boundary.

For an elevated stack release, the Q(/Q) value 3

-___sec/rn and ___is the most limiting land sector at or beyond the site boundary and the (XIQý, value = sec/rn 3 and

'__ ____is the most limiting land sector at or beyond the site boundary.

2. Enter the release rate in ft/min of the release source and convert it to cc/sec; L2ix 2.8317E+4 cc x min

)f min ff 60 sec

- ______cc/sec volume release rate Rev. No. -9 Rev. o. 9Page 41 of Part 2 (ODOM)

(

3. Determine q. for nuclide (i) by obtaining the pCi/cc assay value of the release source and multiplying it by the release rate computed in the previous steps.

Q,=( ')Ci xL)c cc sec Qj= _____ pCi/sec for nuclide (i)

4. To evaluate the whole body dose rate, obtain the Kvalue for nuclide (i) from Appendix B, Table B-2.

5. Solve for DRT~j:

Vent mrem-m 3 sec DRTrBi = K1 x (XIQ) x XPCi pCl-sec .sec Elevated Stack mrem-m 3 Xsec DRTBi = K1 x (XI1Q)y x 6i (

pCl-sec sec 0 DRTBi = Whole body dose rate from nuclide (i) for the specified release source in mrem/sec

6. To evaluate the skin dose rate obtain the Lý and Mi values from Appendix B Table B-2 for nuclide (i).

7. Solve for DRsKIN i Vent DRSKIN i = [Li + 1.1 M1] (XI-Q) x ,

Rev. No. -9 42 of Part 2 (00CM)

Rev. o. 9Page

Elevated Stack DRSKN,I= tL, (X/Q) + 1.1 M, (XIQ), I x di DRSKINI i Skin dose rate from nuclide (i) for the specified release source, in mremfsec

8. Repeat steps 1 through 7 above for each noble gas nuclide (i) reported in the assay of the release source.

9. The dose rate to the whole body from radioactive noble gas gamma radiation from the specified release source is:

n DR7B= DRT~

10. The dose rate to the skin due to noble gas radiation from the specified release source is:

n DRSKIN E ~KI The dose rate contribution of this release source shall be added to all other gaseous release sources that are in progress at the time of interest.

Part 1, Radiological Effluent Controls, Section 3.2.1.c.1.a requires the following:

DRTB *5500 mrem/yr (1.585E-5 mrem/sec)

DRSKIN *ý3,000 mrem/yr (9.51 3E-5 mrem/sec)

Where:

DRTB =The sum of the whole body dose rate contributions

(mr~em/sec) from all noble gas nuclides from all concurrent releases.

DRSKIN =The sum of skin dose rate contributions (mrem/sec) from all noble gas nuclides from all concurrent releases.

Rev. No. -9 Rev. o. 9Page 43 of Part 2 (ODCM)

4.3.2 Setpoint Determination

a. Requirements To comply with Part 1, Specification 3.2.1 .c.1 .a, the alarm/trip setpoints are established to ensure that the Noble gas releases do not exceed the appropriate cumulative (or gross) Noble gas release rate limit specified in Limited Analysis Approach - Instantaneous Noble Gas Release Rate.

An Implementation Plan as defined in AP-02.04 shall be initiated and included in any ODOM revision whenever the methodology for calculating gaseous setpoints or gaseous monitor k-factors are changed and the change to the methodology or k-factors results in a new calculated setpoint.

If the stack setpoint limit is changed in the ODCM, an Exempt Setpoint installation Notification (Attachment 6 of MCM-8A) shall be forwarded'to the Setpoint Coordinator.

b. Methodology This section describes the methodology for determining alarm/trip setpoints for the stack and vent gaseous release pathways. To allow for multiple sources of releases from different or common release points, the allowable operating setpoints will be administratively controlled to allocate a percentage of the total allowable release to each of the release sources. The cumulative Noble gas release rate limit for the stack (elevated) release is 3.0E+5 pCi/sec. The individual release rate limits for the other gaseous release points (assumed to be vent releases), are based upon an allocated percentage of the cumulative vent release rate limit (7.515E+4 pCi/sec).

The sum of the four vent release points cannot exceed 7.51 5E+4 pCi/sec. The I 1110 setpoint release rates for the vents follow.

Setpoint Release K-factor Nominal Setpoint Release Point Rate (pCi/sec) (pCi)/(sec-cpm) Value (cpm)

Turbine Building 46,500 0.62 75,000 6 Reactor Building 10,800 0.36 30,000*

Refuel Floor 12,000 0.40 30,000*

Radwaste Building 5,700 0.19 30,000

Maximum allowable value by Technical Specification table 3.3.6.2-1 is *524,800 cpm.

Nominal setpoint value is the bases for the maximum allowable value.

Rev. No. 9 44 of Part 2 (00CM)

Rev. o. 9Page

The K-factors for the vents were calculated by multiplying the calculated efficiency for Kr-85, 1.11 E-8 pCiI(cc-cpm) derived from the manufacturer's sensitivity equation, by the flow rate for the release point.

Flow rate* K factor Release Point (cfm) (pCi)/(sec-cpm)

Turbine Building 118,000 0.62 Reactor Building 68,000 0.36 Refuel Floor 77,000 0.40 Radwaste Building 36,000 0.19

Reference 6.20 Stack monitor K-factors are reviewed on a periodic basis. A conservative factor of 1.2 pCi/(sec-cps) was selected taking into account potential worst case conditions of standby gas treatment in service. The alarm/setpoint value for the stack was calculated by dividing the setpoint release rate by the K-factor. The setpoint limit for the stack follows.

Setpoint Release K-factor Nominal Setpoint Rate (pCi/sec) (pCi)/(sec-CoPS) Value (cps)

Stack 300,000 1.2 250,000 The whole body dose is more limiting than the calculated skin dose. Therefore, the skin dose rate calculations are not required if the simplified dose rate calculation is used (i.e., using Kff to determine release rate limits).

The calculating processes of step 4.3. 1.c are to be used if the actual releases of noble gases exceed the predetermined limits of 3.OE+5 pCi/sec for elevated stack releases or 7.51 5E+4 pCi/sec for vent releases.

Under these conditions, a nuclide-by-nuclide evaluation is required to evaluate compliance with the dose rate limits of Part 1, Section 3.2.1.c.1.a.

Rev. No. 9 45 of Part 2 (ODOM)

Rev. o. 9Page

4.3.3 Determining the Radiolodine, Tritium, and Eight Day Particulate Instantaneous Release Rates

a. Requirements Part 1, Radiological Effluent Controls, Section 3.2.1.c.1.b limits the instantaneous dose rate from 1-131, 1-133, tritium, and particulate with half-lives greater than eight days released from the plant to_<1,500 mrem/yr to any organ, from the inhalation pathway only.

b. Methodology The following calculating method is provided for determining the dose rate from radioiodines, tritium, and particulate. It is based on NUREG-Qi 33, October 1978, Sections 5.2.1 and 5.2.1.1.

Actual concentrations of lodine-131, Iodine-i 33, and radionuclides in particulate form with half-life greater than 8 days released from the plant in gaseous effluents shall be determined using gamma isotopic analysis. Tritium and strontium are determined by offsite analysis. Sampling and analysis shall be performed in accordance with frequency specified in Table 3.2-1 of Part 1, Radiological Effluents Controls.

The limiting age groups are the child and teen, and the limiting organ is the thyroid, per Table B-6.5, Appendix B. Based on an analysis of doses to various organs and age groups for the inhalation pathway, the child and teen were verified as being the controlling age groups and the thyroid as being the limiting organ. This pathway is the only one that need be considered for instantaneous releases. The long term sector average concentration (X/Q) values are based on historical meteorological data.

Dose factors for nuclides listed in Appendix B, Table B-3 will be used.

Inhalation Pathway The equation for DRI&8DpT is to be summed over all release sources (s). Eq4-m n__

s=1 i=1 Rev. No. 9 Rev. o. 9Page 46 of Part 2 (ODO-M)

Where:

T =The organ of interest (thyroid) for the age group of interest.

Qi= Total release rate of nuclide (i), (pCi! sec) for each release source (s).

DRI&8 DP = Total dose rate to the thyroid of the limiting age group from T jodines, tritium, and eight day particulate via the inhalation pathway (mrem/yr) for all release points p.

(X/Q). The long term sector average concentration X/Q value based on historical meteorological data in (sec/rn 3) for release source s (Appendix C).

P!= The dose factor for the inhalation pathway in (mrem/yr per pCi/rn3 ) for nuclide (i) (Appendix B, Table B-3). The derivation of Pi values is given in Appendix B, Table B-6. 1.

m =The number of release sources of interest.

The maximum allowable release rate of all radioiodines, tritium, and particulate, summed together, is determined by the following relationship:

Eq. 4-10 M(ERA C)s DRThyroid 0.

Where:

DRThyrold = Dose rate to the thyroid from the inhalation pathway set equal to Part 1, Radiological Effluent Controls, Section 3.2.1 .c.1 .b limit of <1 ,500 mrem/year.

Piffhyroid) =The dose factor of 1-131 for the inhalation pathway, 1.62E+7 mrem/yr per pCi/rn 3 (Appendix B, Table B-3).

(X/Q). The long term sector average concentration X/Q value for any land sector value based on historical meteorological data in (sec/rn 3) for release sources (Appendix C),

Rev. No. -9 47 of Part 2 (ODCM)

Rev. o. 9Page

f Q= Maximum allowable release rate of all radioiodines, tritium, and particulate summed together in pCi/sec.

(FRAC), Fraction of 1500 mrem/yr limit allocated to release source s, such that Y_(Frac), = 1.0.

0.8 =A conservatism factor.

Rev. No. 9 48 of Part 2 (ODOM)

Rev. o. 9Page

4.4 Dose Determination for Radioactive Gaseous Effluents This section addresses the methodologies for calculating the offsite radiation exposures (to all age groups and organs) from radionuclides in the gaseous effluents for the following:

(a) Long-term (routine) releases - Annual dose assessment for inclusion in the Radioactive Effluent Release Report (Sec. 4.4.1),

(b) Long-term (routine) releases - Verification of compliance with 10 CFR 50 Appendix I (Sec. 4.4.2), and (C) Short term releases (Sec. 4.4.3).

As described in NUREG-0133 (Ref. 6.2, Sec. 3.3), gaseous releases are characterized as "long" or "short" term depending on the frequency and duration of the releases. This characterization forms the basis for more accurate offsite dose assessments by matching the releases with more appropriate atmospheric dispersion and decay conditions.'

Long-term gaseous releases refer to releases that are generally continuous and stable, with small fractional variations. Short-term releases, on the other hand, are intermittent or infrequent, with a defined total cumulative duration of 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months or less during a calendar year, and no more than 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months per quarter; they also include anticipated non-routine operational occurrences.

Offsite radiation doses from short-term releases [item (c) above], when they occur, are to be incorporated into both the annual dose assessment [item (a)] and the verification of compliance with regulatory guidelines [item (b)]. However, routine releases from JAF are essentially all long term and are continuously monitored by stack and vent effluent radiation monitors. Therefore, short-term releases at JAF are considered to be only unmonitored non-routine releases and are not applicable for definition of the alarm/trip setpoints for the stack and vent effluent monitors. In addition, in line with NUREG-Ol 33, short-term releases are not used in assessing compliance with the Part 1, Section 3.2.1.c release limits as discussed in Secion 4.3 of the ODCM.

Rev. No. -9 Rev. o. 9Page 49 of Part 2 (ODOM)

4.4.1 Annual Dose Assessment - Radioactive Effluent Release Report Submittal

a. Requirements Technical Specification 5.6.3 requires a Radioactive Effluent Release Report be submitted prior to May 1 of each year covering the operation of the plant during

.the previous year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the plant.

The material provided shall be consistent with the objectives outlined in Part 1, Section 6.2.

b. Methodology This section provides the methodology to calculate the doses to all age groups and organs from radionuclides identified in the gaseous effluents.

The method is based on the methodology suggested by NUREG-0133, October 1978, Sections 5.3 and 5.3.1. The determination of viable gaseous dose pathways is described in Appendix B, Table B-6.4. The site related dose factors for viable pathways are listed in Appendix B. Dose factors are compiled by age groups, for organs and radionuclides common to a BWR environment. Normally calculated annual long term historical atmospheric dispersion factors are used to perform the annual dose assessment. Actual meteorological data and sector wind frequency distributions for the year of interest may be used in lieu of the annual long term historical factors.

The following equations provide for a dose calculation to the whole body or any organ for a given age group based on actual releases during a specific time interval for radioactive gaseous release sources:

1. Annual Air Dose Due to Noble Gases Vent Eq. 4-11a n __

DGamma-Air =Y M, x (XIQ x Q Rev. No.. 9 Rev. o. 9Page 50 of Part 2 (ODOM)

Elevated StackEq4-b Eq. 4-11 b n __

Gamma -Airi XQ j Where:

DG~mamAir = The gamma air dose from radioactive noble gases, in mrad.

=j The gamma air dose factor for radioactive noble gas nuclide 'i, in mrad-m 3/pCi-sec (Appendix B, Table B-2).

(X/Q) = The long term historical atmospheric dispersion factors for vent releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/rn 3.

(X/Q)ý The long term historical atmospheric dispersion factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest insec/rn 3 .

Qj The number of pCi of nuclide Tireleased during the year of interest from the release source of interest.

The equations for DGamma-Air are to be summed over all vent and elevated stack release sources.

Eq.4-1 2 n __

DBeta-Air= E N1 x (X/Q) x Q Rev. No. -9 Rev. No. .51.

9Page of Part 2 (ODCMA

Where:

DBetaAj, Beta air dose from radioactive noble gases in mrad.

N1 The beta air dose factor for radioactive noble gas nuclide (i) in mrad-m 3/pCi-sec (see Appendix B, Table B-2).

(X/Q) = The long term historical atmosphe ric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/rn 3 .

=j The number of pCi of nuclide Tireleased during the year of interest from the release source of interest.

The equations for DBeta-Air are to be summed over all vent and elevated stack release sources.

2. Annual Whole body Dose Due to Noble Gases Vent Eq. 4-12a n __

DB ~ (XIQ) xQ, Elevated Stack Eq. 4-12b n

DTB K, x (XIQ)y x Q Where:

DTB - Whole body dose from noble gases in airborne releases, in mrem.

K. = The whole body dose factor due to gamma emissions for each noble gas nuclide (i) reported in the release source, in mrem-m 3/pCi-sec (Appendix B, Table B-1).

K.

Rev. No. -9 Rev. o. 9Page 52 of Part 2-(ODOM,)

(X/Q) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/rr?.

=XQ The long term historical atmospheric dispersion factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/in3 .

Q. = The number of microCuries for each noble gas nuclide (i) released during the year of interest from the release source of interest.

The equations for D-rB are to be summed over all vent and elevated stack release sources.

3. Annual Total Skin Dose Due to Noble Gases Vent Eq. 4-12c n

DSKIN [Li + 1. 1 M11 (XIQ) X Q Elevated Stack Eq. 4-12d n

DSKIN [Li (XIQ) + 1.1 M. (XQ-Where:

DSKIN - Skin dose from noble gases in airborne releases in inrem.

L. -The skin dose factor due to beta emissions for each noble gas nuclide (i) reported in the assay of the release source in mrem-M 3/pCi-sec (Appendix B, Table B-I).

-The air dose factor due to gamma emissions for each noble gas nuclide (i) reported in the assay of the release source.

The constant 1.1 converts 'mrad' to 'inrem' since the units of M,are in mrad-M 3/pCi-sec (Appendix B, Table B-I).

Rev. No. -9 Rev. o. 9Page 53 of Part 2 (00CM)

(X/Q) = The long term historical atmospheric dispersion factors for vent or elevated stack releases (annual average) for the location of interest. Actual meteorological data and sector wind frequency distributions may be used to determine annual X/Q for the year of interest in sec/rrd.

(X/QX The long term historical atmospheric dispersion factor for elevated stack releases (annual average) for the location of interest based on the finite cloud methodology. Actual meteorological data and sector wind frequency distributions may be used to determine annual XIQ for the year of interest in sec/in3 .

Q= The number of microCuries for each noble gas nuclide (i) released during the year of interest from the release source of interest.

The equations for DSKIN are to be summed over all vent and elevated stack release sources.

4. Annual Dose Due to Radioliodines, Tritium, and Eight Day Particulate Inhalation Pathways Eq. 4-13 n _

(DI&SDP) 7 = (3.17E-8) EY i x (XIQ) x Q Ground Plane Deposition Pathway Eq. 4-14 n __

(DIUsDP)ý (3.17E-8) EL R, x (DIQ) x Q j=1 T Rev. No. -9 Rev. o. 9Page 54 of Part 2 (00C-M)

Cow's Milk Pathway E.41 Eq. 4-15 n __

(D,&SDP) = (3.17E-8) Y E x (DIQ) x Q Goat's Milk Pathway Eq. 4-16 n __

(D,&SDP) = (3.17E-8) Ei R, x (D/Q) x Q i=1 Meats Eq. 4-17 n __

(D,&8 DP). (3.17E-8) Ei R, x (DIQ) x Q Vegetation Eq. 4-18 n __

(DI&SDPýr (3.17E-8) Y E x (DIQ) x Q i=1 For tritium, the dose is calculated by substituting X!Q for (D/Q) and FýH3 for R. in equations 4-15 to 4-18.

Total Annual Dose From Release Source of Interest Eq. 4-19a p

z= I Rev. No. -9 Rev No 9Page 55 -of Part 2 (ODO-M)

Total Annual Dose Eq. 4-1 9b DT~ E (D~s) s=1 Where:

T - The organ of interest for the age group of interest.

s - The release source of interest.

z - Pathway of interest.

p = The number of pathways of interest.

m = Number of release sources of interest.

(DI&8DP)T Annual dose to the organ Tfor the age group of interest from iodines, tritium, and eight day particulate via the pathway of interest in (mrem).

3.1 7E-8 = The inverse of the number of seconds per year in (years/sec).(

DTS - Total annual dose to organ Tfrom all applicable pathways for the age group of interest and for the release source of in (mrem).

DOT - Total annual dose to organ T from all applicable pathways fo r the age group of interest and for all release sources of interest in (mrem).

-j The number of pCi of nuclide Tireleased during the year of interest from the release source of interest.

RiT = The dose factor for nuclide (i) for organ Tfor the pathway specified, units vary with pathway. The derivation of Rý values is given in Appendix B, Table B-6.2.

Rev. No. -9 56 of Part 2 (ODOMj Rev. o. 9Page

(D/Q) = The long term historical annual average relative deposition values for elevated stack or vent releases for the ground plane deposition pathway. For the meat, cow, goat, and vegetable pathways, the long term historical grazing average deposition values for elevated stack and vent releases are used (Appendix C). A factor with units Of rn- 2 which describ-es the deposition of particulate matter from a plume at a point downrange from the source. Actual meteorological data and sector wind frequency distribution may be used to determine annual average DIQ for the year of interest. D/Q is not used to calculate doses associated with H-3 releases.

(X/Q) = The long term historical annual average atmospheric dispersion factors for vent or elevated stack releases for the location of interest (Appendix C). Actual meteorological data and sector wind frequency distributions may be used to determine annual XIQ for the year of interest in sec/rn 3 . The X/Q is used to determine doses for H-3 releases.

4.4.2 Monthly Dose Assessment - Verification of Compliance with 110 CFR 50, Appendix I

a. Determining the Gamma Air Dose for Radioactive Noble Gas Release Source(s)

1. Requirement Part 1, Radiological Effluent Controls, Section 3.3.2.c.1 limits the air dose from gamma radiation due to noble gases released from the plant in the gaseous effluent *1 0 mrad during any calendar year, and ý5 mrad in any calendar quarter.

Part 1, Section 3.3.2.c.1, requires that cumulative air dose contributions from noble gases be calculated at least monthly for the current calendar quarter and current calendar year.

Rev. No. 9 Rev.No. j...Page 57 of Part 2 (ODOM)

2. Methodology The following calculational method is provided for determining the noble gas gamma air dose and is based on NUREG-0133 October 1978 Section 5.3.1. The dose calculation is independent of age group. The equation may be used for Part 1, Section 3.3.2.c.1 dose calculations, the dose calculation for the annual report, or for projecting dose, provided that the appropriate value of (X/Q) is used. The equation for gamma air dose is:

Vent Eq. 4-20a n

DGamma -Air Mix (XIQ) x Q Elevated Stack Eq. 4-20b n

DGamma -Air = Mix (XIQ)y x Q

(

Where:

DGamma-Alr - The gamma air dose from radioactive noble gases in mrad.

Mi - The gamma air dose factor for radioactive noble gas nuclide 'i', in mrad-M 3/pC!-sec (Appendix B, Table B-2).

(X!Q) - The highest long term annual average atmospheric dispersion factors for vent releases for any land sector, in sec/rn 3 (Appendix C,Table C-i).

(X/Q)ý - The highest long term annual average atmospheric dispersion factor for elevated stack releases for any land sector based on the finite cloud methodology, in sec/in 3 (Appendix C, Table C-2).

K Rev. No. -9 Rev No 9Page 5-.8 of Part 2 (ODOM)

Q. The number of pCi of nuclide Tireleased (or projected to be released) during the dose calculation exposure period (e.g., month, quarter, or year) from the release source of interest.

The equations for DGamma..Air are to be summed over all vent and elevated stack release sources.

(a) Limited Analysis Approach The following limited analysis approach may be used to establish monthly release objectives (pCi/month) that will ensure compliance with 10 CFR 50, Appendix I gamma dose limits.

From an evaluation of past releases, a single effective gamma air dose factor (MKff) has been derived, which is representative of the radionuclide abundances and corresponding dose contributions typical of past operation. (Appendix E has a detailed explanation and evaluation of Meff). The value of Mff has been derived from the radioactive noble gas effluents for the years 1985 through 1991.

To compensate for any unusual variability in the radionuclide distribution, 3 sigma was added to the average qvff value, and are as follows.

Meff =9.75E-5 + 3a

- 9.75E-5 + (3 X 4.95E-5)

- 2.46E-4 (mrad-rd3)I(pCi-sec)

(vent release)

Meff = 1.57E-4 + 3a

- 1I.57E-4 + (3 X 4.70E-5)

- 2.98E-4 (mrad-rri 3)/(pCi-sec)

(stack release)

The effective gamma air dose factor may be used in conjunction with the total noble gas release to simplify the dose evaluation and to verify that the cumulative gamma air dose is within the equivalence of the limits of Part 1, Radiological Effluent Controls, Section 3.3.1.c.1.

Rev. No. 9 Rev.No.SPage 59 of Part 2 (ODCM)

Equations 4-20a and 4-20b can be used to establish monthly release objectives. Combining equations 4-20a and 4-20b yields the following:

Eq. 4-21 DGamma-air, = [Meff(vent) x (XIQ) x Q(vent)] +

[Meff(stack) x (XIQ)y x Q(stack)]

Part 1, Radiological Effluent Controls, Section 3.3.2.c states that the doses must be evaluated once per month. The yearly dose limit is 10 mrads, which corresponds to a monthly allotment of 0.83 nirads. 0.83 nirads can be substituted into equation 4-21 for IDGamrna-air~The highest calculated annual average

~(/Q)V 1.16E-7 sec/ni 3 , for elevated stack releases and the highest calculated annual average reactor vent (X/Q),

3.58E-7 sec/ni 3 , for vent releases, can be substituted into equation 4-21. Q(stack) and Q(vent) were selected so that the technical specifications limit of 10 mrad/yr or 0.83 mrad/month would not be exceeded. In addition, Q(stack) was selected by requiring the stack not to exceed 60% of 0.83 mrad/month.

Eq. 4-22 Q(stack) = DGamma-air (stack)

[Meff(stack) x (X/Q )Y]

Substituting the preceding values into equation 4-22, yields Q(stack) = 1.44E10 pCi/month. Q(stack) was then substituted into equation 4-21 and solved for Q(vent). Therefore, the following are the cumulative noble gas monthly release objectives.

Q(vent release) = 3.77E+9 pCi/month Q(elevated stack release) = 1.44E+10 pCi/month As long as these values are not exceeded during any month, compliance with the quarterly and annual noble gas release limits of Part 1, Radiological Effluent Controls, Section 3.3.1 .c.1 is demonstrated. When the limited approach method is used, the calculations of 4.4.2.a(2) must be performed monthly at a minimum.

The gamma air dose limit does not cause, the beta air dose limit to be exceeded when the limited analysis approach of this section is used.

IRev. No. -9 Rev. o. 9Page 60 of Part 2 (ODOM)

b. Determining the Beta Air Dose for Radioactive Noble Gas Release Sources The beta air dose calculations of this step are required to be performed when the radionuclide specific dose analysis of Gamma Air Dose is performed. The radionuclide specific dose analysis is performed at least monthly in accordance with Part 1, Section 3.3.2.c.1.

1. Requirement Part 1, Radiological Effluent Controls, Section 3.3. 1.c.1 limits the air dose from beta radiation, due to noble gases released from the plant in the gaseous effluents, to less than or equal to 20 mrad during any calendar year and less than or equal to 10 mrad in any calendar quarter.

Part 1, Section Section 3.3.2.c.1 requires that cumulative air dose contributions from noble gases released from the plant be calculated at least monthly for the current calendar quarter and current calendar year.

When the nuclide specific dose calculation is used to evaluate compliance with the gamma air dose limits, the beta air dose shall be evaluated on a nuclide specific basis using the methodology presented below.

2. Methodology The following calculating method is provided for determining the beta air dose and is based on NUREG-0133, October 1978, Section 5.3.1. The dose calculation is independent of any age group. The equation may be used for dose calculations for Part 1, Section 3.3.2. c.1, Radiological Effluent Release Reports, or for projecting dose, provided that the appropriate value of (X/Q) is used.

Rev. No. 9 61 of Part 2 (ODOMI Rev. o. 9Page

The equation for beta air dose is:

Eq. 4-23 n

DBeta-Air " ,x(I)xQ Where:

D~e~r =Beta air dose from radioactive noble gases in (mrad).

N1 The beta air dose factor for radioactive noble gas nuclide 'i' in mrad-m 3/pCi-sec (Appendix B, Table B-2).

(X/Q) = For vent or elevated stack releases, the highest annual average, X/Q, calculated using long term historic meteorological data, for any land sector, at or beyond the site boundary, in sec/in 3 (Appendix C).

=i The number of pCi of nuclide 'i released (or projected to be released) during the dose calculation exposure period from the release source of interest.

The equation for DBeta-Air is to be summed over all release sources.

C. Determining the Radioiodine, Tritium, and Eight Day Particulate Dose to any Organ from Cumulative Releases

1. Requirement Part 1, Radiological Effluent Controls, Section 3.4.1.c limits the dose to the whole body or any organ resulting from the release of radioiodines, tritium, and particulate with half-lives greater than eight days released from the plant to less than 7.5 mrem/quarter and less than 15 inrem/yr to any organ.

Part 1, Section 3.4.2.c requires that cumulative dose contributions be calculated at least monthly for the current calendar quarter and current calendar year.

Rev. No. 9 Rev. No. -&2~

9Page of Part 2 (ODOM)

2. Methodology The following calculating method is provided for determining the organ dose due to releases of radiojodines (1-131, 1-133), tritium, and particulate with half-lives greater than 8 days. It is based on NUREG-0133, October 1978, Section 5.3.1. The equations can be used for any age group provided that the appropriate dose factors are used and the total dose reflects only those pathways that are applicable to the age group and the receptor location. The deposition factor, (D/Q), represents the rate of fallout from the cloud that affects a square meter of ground at various distances from the site. The total dose to an organ can then be determined by summing the pathways that apply to the receptor in the sector. The equations are:

Inhalation Pathway Eq. 4-24 n __

(DI&8 DPýr = (3.17E-8) EI R, x (XIQ) x Q j=1 T Ground Plane Pathway Eq. 4-25 (DI&8 Dpý = (3.17E-8) XR, x (DIQ) x Q T=

Cow's Milk Pathway Eq. 4-26a (DW&DP) = (3.17E-8) Rx (DIQ) x Q Ri Goat's Milk Pathway Eq. 4-26b.

(D, 8 DP)T= (3.17E-8) R Rx (D/Q) xQ, Rev. No. 9 Rev. o. 9Page 63 of Part 2 (ODO-M)

Meats 4-26c MeatsEq.

n (D,&8DP) = (3.17E-8) E R1. Tx (DIQ) x Q Vegetation Eq. 4-26d n

(D,&SDP)1 = (3.17E-8) E R x (DIQ) x Q 1=1 For tritium, the dose is calculated by substituting X/Q for (DIQ) and RH-3Tin Rr equations 4-26a to 4-26d.

Total Dose From a Release Source for Applicable Pathways Eq .4-27a DTS E (DI&SDP)T z= 1 Total Annual Dose From All Release Sources of Interest Eq.4-27b m

DT= E (DTs) s=1 Where:

T = The organ of interest in a specified age group.

s = The release source of interest.

z = The pathway of interest.

p = The number of pathways of interest.

Rev. No. -9 Rev. o. 9Page 64 of Part 2 (ODOM)

m = The number of release sources of interest.

(DIUDO) = Dose in mrem to the organ Tof a specified age group from T radioiodines, tritium, and 8 day particulate due to a particular pathway.

DS = Total dose to organ Tfrom all applicable pathways for a specified age group for the release source of interest in (mrem).

DT = Total dose to organ Tfrom all applicable pathways for a specified age group and for all release sources of interest in (mrem).

3.17E-8 =The inverse of the number of seconds per year in (years/sec).

RiT= The dose factor for nuclide (i) organ T Of the specified age group. The units are either mrem-m 3/yr-pCi for pathways using (XQ), or mrem- M2_sec/yr-pCi for pathways using (DIQ) (Appendix B, Tables B-4 and B-5).

(X/Q) =The concentration (X/Q) value for a specific location where the receptor is located. The units are (sec/rn 3) (Appendix C).

The X/Q is used to determine doses for H-3 releases.

(D/Q) =The deposition value for a specific location where the receptor is located. The units are (rn- 2) (Appendix C). DIQ is not used to calculate doses associated with H-3 releases.

Q= The number of pCi of nuclide (i) released (or projected to be released) during the dose calculation exposure period from the release source of interest.

Rev. No. 9 Rev. o. 9Page 65 of Part 2 (ODCM).

(a) Limited Analysis Approach Based on an analysis of doses to all organs and age groups from all monitored atmospheric release pathways, the milk and vegetation pathways have been identified as being the most significant pathways. The infant's thyroid (milk pathway) and child's thyroid (vegetation pathway) have been idenified as being the limiting age groups and organ. These pathways contribute the majority of the total dose received by the infant and child thyroid.

The radioiodines and tritium contribute essentially all of the dose via the milk and vegetation pathways. Therefore, it is possible to demonstrate compliance with the dose limit Part 1, Radiological Effluent Controls, Section 3.4.1.c.1 for radioiodines, tritium, and particulate with half-lives greater than 8 days by evaluating only the infant and child thyroid dose due to radioiodines and tritium in the milk and vegetation pathways.

The calculating method to be used includes a conservatism factor of 0.5 which assures that the calculated dose is always greater than or equal to the actual dose despite possible atypical distributions of radionuclides in the gaseous effluent. The following equations are used to calculate the doses from the milk and vegetation pathways.

Eq.4-28a Dmnlk-inf TS 3.17E-8 [ (DIQ)s lodiEs Rmlk-chd ir X Q8

+/-( (X/Q)s X Rmlkct,h H-3T X QH-3s]

Eq.4-28b

=3.17E-8Fx D veg-inf TS 0.- (D/Q)s odes Rveg.-chdf TX is}

÷((XIQ)s x Rveg-chd H-3T X QH-3s]

Rev. No. -9 Rev. o. 9Page 66 of Part 2 (ODOM)

Eq .4-28c m

DT= EDTs s=1 Select the equation (i.e., either 4-28a or 4-28b) that yields the highest dose. Substitute that equation into 4-28c for q, and solve for DT.

Where:

R~wk-jflIT = The dose factor for iodine nuclide (i), organ T (thyroid),

of the specified age group (infant) for the milk pathway.

The units are either mrem-mP/yr-pCi for pathways using (X/Q), or mrem-rrf-sec/yr-pCi for pathways using (D/Q). (See Appendix B).

Rmlk~nfH- = The dose factor for iodine nuclide (tritium), organ T (thyroid), of the specified age group (infant) for the milk pathway. The units are either mrem-n-?/yr-pCi for pathways using (X/Q), or mrem-nif-seclyr-pCi for pathways using (D/Q). (See Appendix B).

Rvleg-chd t - The dose factor for iodine nuclide (i), organ T(thyroid),

of the specified age group (child) for the vegetation pathway. The units are either mrem-rr?/yr-pCi for pathways using (XIQ), or mrem-rT?-sec/yr-pCi for pathways using (D/Q). (See Appendix B).

R,9§H-3T = The dose factor for iodine nuclide (tritium), organ T (thyroid), of the specified age group (infant) for the milk pathway. The units are either mrem-rr?/yr-pCi for pathways using (X/Q), or mrem-rri-sec/yr-pCi for pathways using (D/Q). (See Appendix B).

Dr~k-WT S = Dose in mrem to the infant's thyroid due to radioiodines and H-3 in the milk pathway for the release source of interest.

Dveg-chd TS- Dose i n mremn to the child's thyroid due to radioiodines and H-3 in the vegetation pathway for the release source of interest.

DS Dose in mrem to the most limiting age group's. thyroid, from all pathways.

DT = Total dose in mrem to the most limiting age group's thyroid, from all pathways for all release sources of interest.

s The release source of interest.

Rev. No. -9 Rev. o. 9Page 67 of Part 2 (ODCM)

m = The number of release sources of interest.

Qi = For elevated stack releases, q, is the total number of microCuries of nuclide i released from the stack during the dose calculation exposure period. For vent releases, q., is the total number of microCuries of nuclide i released from the four vents during the dose calculation period.

QH-3 = For elevated stack releases, (43S is the total number of microCuries of nuclide tritium released from the stack during the dose calculation exposure period. For vent releases, OH3 is the total number of microCuries of nuclide triotiumn released from the four vents during the dose calculation period.

D/Q3 The deposition value for a specific location where the receptor is located in (mr2 ). For elevated stack releases the grazing season DIQ for the stack will be used. For vent releases, the grazing season DIQ for the reactor vent will be used.

X/Q, The concentration (X/Q) value for a specific location where the receptor is located. The units are sec/rr?.

The grazing season X/Q is used to determine doses for H-3 releases. For elevated stack releases the grazing season X/Q for the stack will be used. For vent releases, the grazing season X/Q for the reactor vent will be used.

(b) Approach Selection Criteria The limited analysis approach may be used for long-term (routine) releases to demonstrate compliance with the dose limit of Part 1, Radiological Effluent Controls, Sections 3.4. 1.c. 1.a and 3.4. 1.c.1.b (7.5 mrem/qtr and 15 mrem/yr) for radioiodines, tritium, and particulate.

However, for the dose assessment included in the Radioactive Effluent Release Report, doses will be evaluated for designated age groups and organs via designated pathways from radio-iodines, tritium, and particulates measured in the gaseous ef-fluents according to sampling and analyses required by Part 1, Section 3.4.2.c.1.

Rev. No. 9 Rev. o. 9Page 68 of Part 2 (ODCM)

4.4.3 Short Term Releases As described in the introductory part to Sec. 4.4 (and in NUREG-0133),

short-term releases are intermittent or infrequent, with a defined total cumulative duration of 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months or less during a calendar year, and no more that 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months per quarter. Radiological impact assessment models for short-term releases may make use of the long-term atmospheric dispersion factors (as described in Sections 4.4.1 and 4.4.2) if it can be demonstrated that past short-term releases were sufficiently random in both time of day and duration to be represented by the annual average dispersion conditions. Otherwise, use should be made of the short-term dose equations, as described below.

a. Requirements Short-term releases, when they occur, are to be incorporated into the Radioactive Effluent Release Report(s) and the annual dose assessment report (Section 4.4.1) and the verification of compliance with 10 CFR 50 Appendix 1, regulatory guidelines (Section 4.4.2). The following are the Technical Specification requirements for short-term releases.

Technical Specification 5.6.3 requires a Radioactive Effluent Release Report covering the operation of the unit during the previous year, be submitted prior to May 1of each year in accordance with 10 CFR 50.36a. Part 1, Section 6.2 also requires that this report includes an assessment of the radiation doses to the public due to the radioactive liquid and gaseous effluents released from the unit during the previous calendar year.

Part 1, Section 3.3. 1.c.1I limits the air dose from gamma radiation due to noble gases released from the plant in the gaseous effluent to *1l0 mrad during any calendar year, and *5 mrad in any calendar quarter.

Part 2, Section 3.3.2.c, requires that cumulative air dose contributions from noble gases be calculated at least monthly for the current calendar quarter and current calendar year.

b. Methodology Routine releases via the main stack and Vents are continuous. The methodology described below for short-term releases is thus for non-routine unmonitored ground-level releases.

Rev. No. 9 Page 69 of Part 2 (ODOM)

The equations for offsite radiation exposures resulting from short-term releases are similar to thoe provided for vent releases in Sections 4.4.1 and 4.4.2 above.

They are as follows:

1. Air Dose Due to Noble Gases Eq. 4-29 n

DShohl Gamma -Air Mix (x/q) x qi M=

Eq. 4-30 n

DShort Beta -Air = N, x (xlq) x q Where:

q. The overall total activity (pCi) of radionuclide "i" released (or projected to be released) during the dose calculation exposure period (month, quarter, or year, as applicable) from a selected vent or unmonitored path, as a result of short-term releases.

(x/q) =The short term atmospheric dispersion factor (sec/rr) for ground-level releases and the receptor of interest, defined as (from NUREG-0324):

(x/q) = (xqLuyP (t _<2 hr)

(xlq) = (xqOd PC Xr (2 <t < 500 hr)

(x/q) = (XIQ)Ann.ual SA (t > 500 hr)

Where:

log [(X/Q )AnnuaISA' (xlq )Hour1YpcI log (8760) t = release duration (hrs) (or the total sum of frequent short-term release durations) during the dose calculation exposure period (Note: The limits 2 < t *500 are for annual analysis; for quarterly analysis, they are 2 < t *1 50)

Rev. No. -9 Page 70 of Part 2 (ODaM)

0(/Q)AnuaI SA =long-term sector average (SA) atmospheric dispersion factor (sec/rn 3 ) for ground level releases and the selected receptor, for distances out to 45 miles [from Table 0-1 5 for the site boundary, Table 0-1 8 for annual (all-season) meteorology, and Table 0-22 for grazing-season meteorology]

(x/q )Houly pc= short-term 85th percentile hourly plume centerline (PC) atmospheric dispersion factor (sec/n-?) for ground-level releases and the selected receptor [from Table C-i15 for the site boundary, Table C-i 7 for annual meteorology, and Table C-21 for grazing-season meteorology]

All other parameters have been defined in Section 4.4.1.b.(1).

Short-term gamma air doses are to be added to the long term gamma air doses. Combining equations 4-11a, 4-11b, (or 4-20a, 4-20b for quarterly) and 4-29 results in the following:

Eq. 4-31 DTataI Gamma-Air = DGamma-Air(STACK) + D~amma -Air (Vents)

+ DShort Gamma-Air(Unmonitored Non-routine Releases)

Short-term beta air doses are to be added to the long term beta air doses. Combining equations 4-12 (or 4-23 for quarterly) and 4-30 results in the following:

Eq. 4-32 DTotaI Beta-Air DBeta-Air

+ DShort Beta-Air(Unmonitored Non -routine Releases)

2. Annual Whole Body Dose and Skin Dose Due to Noble Gases The equations for whole body dose and skin dose which follow are for use in the preparation of the Radioactive Effluent Release Report (described above in Section 4.4.1). They are not applicable for the verification of compliance with 10 CER 50, Appendix I (Section 4.4.2).

Rev. No. -9 Rev. No. 9Page

71. of Part 2 (ODCM)

Eq. 4-32a DshýOt TB =Ki x(xlq) xqi Eq. 4-32b Dshort skin = [Li + 1. 1 M1] x (xlq) x qi All parameters in Equations 4-32a and 4-32b are as previously defined in Sections 4.1.4.b(2) and 4.4.3.b(1).

Short-term whole body and skin doses are to be added to the corresponding doses from long-term releases. Combining Equations 4-12a, 4-12b. and 4-32a yields the following equation for the total TB dose:

Eq. 4-32c DTotaI TB = DTB(STACK) + DTB( Vents)

+ DShort TB(Unmonitored Non-routine Releases)

Similarly, combining Equations 4-12c, 4-12d and 4-32b for the skin, yields:

Eq. 4-32d B Total Skin = Dskin(STACK) + Dskil( Vents)

+ DShort Skinl(Unmonitored Non -routine Releases)

3. Dose Due to Radiolodines, Tritium, and Eight Day Particulates Inhalation Pathway Eq. 4-33 n

(DShort &BDPT) = (3.17E-8) E~ Rj x (xlq) x q All parameters have been defined previously. Short-term doses from the inhalation pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-13 (or 4-24 for quarterly) and 4-33 results in the following:

Eq. 4-34 Rev. No. Rev. o. 9Page 72 of -Part 2 (ODOM)

[DTotaI I&BP1]T = [DI&8DPTIT

+ [DSho,.t IMBPAT(Unmonitored Non-routine Releases)

,Ground Plane Deposition Pathway Eq. 4-35

- n (DShod I&8DPTýr = (3.17E-8) Ei R, x (d/q) x q Where:

(dlq) = The short term deposition factor (1/rrif) for ground-level releases and the receptor of interest, defined as:

(dlq) = (d/q)m0 uOY PC (t < 2 hr)

(dlq) = (d/q)Houdy PC X r (2 < t <500 hr)

(dlq) = (DIQ)mnual SA (t > 500 hr)

Where:

log [(DIQ))..uaIsA'(dlq )HouIyPC]

log (8760) t = release duration (hrs) (or the total sum of frequent short-term release durations) during the dose calculation exposure period (Note: the limits 2 < t*

500 are for annual analysis; for quarterly analysis, they are 2 < t *ý 150)

(D/Q)Afln..j SA long-term sector average (SA) deposition (Il/rrf) for ground level releases and the selected receptor, for distances out to 45 miles [from Table C-i 6 for the site boundary, Table C-20 for annual (all-season) meteorology, and Table C-24 for grazing-season meteorology]

Rev. No. 9 Rev. o. 9Page 73 of Part 2 (ODOM)

(d/q)H~ly PC short-term 85th percentile hourly plume centerline (PC) deposition factor (1/rn2) for ground-level releases and the selected receptor [from Table 0-16 for the site boundary, Table C-19 for annual meteorology, and Table C-23 for grazing-season meteorology]

All other parameters have been defined in Section 4.4.1.b.(4).

Short-term doses from the ground plane pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-14 (or 4-25 for quarterly) with 4-35 results in the following:

Eq. 4-36

[DTotaJ I&BDPTI = [DI&8DPTI

+ [DShort ,&8 DPTI (Unmonitored Non -routine Releases)

Cow's Milk Pathway Eq. 4-37 n

(DShor.tI&DPT) = (3.17E-8) EZ Ril x (dlq) x q (

1=1 (

All parameters have been defined previously. Short-term doses from the cow's. milk pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-15 (or 4-26a for quarterly) with 4-37 results in the following:

Eq. 4-38

[DTotaI I&8DPTlI = [DI&BDPTIr

+ {DShort I&8DpT1 (Unmonitored Non -routine Releases)

Rev. No. -9 Rev. o. 9Page 74 of Part 2 (ODOMI

Goat's Milk Pathway E.43 Eq. 4-39 n

(DShortI&8DPTý = (3.17E-8) EX , x (dlq) x q All parameters have been defined previously. Short-term doses from the goat's milk pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-16 (or 4-26b for quarterly) with 4-39 results in the following:

Eq. 4-40

[DTotaI )&8DPTlI = [DI&8DPT1

+ DShodf I&BDPT}I (Unmonitored Non -routine Releases)

Meats Eq. 4-41 n

(DShort I&DPTýr = (3-17E-8) E I x (dlq) x q, i=1 All parameteirs have been defined previously. Short-term doses from the meat pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-17 (or 4-26c for quarterly) with 4-41 results in the following: Eq. 4-42 fD~otal I&8DPTIr [DI&8DPT1

+[DShort I&8DPT1(Unmonitored Non -routine Re'leases)

Vegetation Eq. 4-43 n

(DShort&8DpT) = (3.17E-8) XE i x (d/q) x q i=I All parameters have been defined previously. Short-term doses from the vegetation pathway are to be added to the corresponding long term doses from the same pathway. Combining equations 4-18 (or 4-26d for quarterly) with 4-43 results in the following:

Rev. No. -9 Rev. o. 9Page 75 of Part 2 (00CM)

Eq. 4-44

[D Total I&8DPTJ, = [D,&8PT1I

+[Dshort I&8DpT]j(Unmonitored Non-routine Releases)

For tritium, the dose is calculated by substituting x/q for d/q, and R-3 for RT in Equations 4-37, 4-39, 4-41, and 4-43.

Total Annual Dose From Release Point of Interest Eq. 4-45 p

D =cr E (D5 hort 4&81DPLr z=1 Short-term doses from unmonitored non-routine releases are to be added to the corresponding long term doses from the stack and vents. Combining Equations 4-19b (or 4-27b for quarterly) and 4-45, results in the following:

Total Annual Dose Eq. 4-46 DTotaj, DT IDShor4 K

Rev. No. Rev. o. 9Page 76 of Part 2 (ODOM)

4.5 Dose Projections - Determination of Need to Operate Offgas Radwaste Treatment System 4.5.1 Requirement Part 1, Section 3.5.2.c requires that doses to gaseous releases from the site be projected at least monthly if the charcoal beds are not in service when offgas treat-ment system operation is required.

4.5.2 Methodology The following calculational method is provided for determining the projected doses.

Eq. 4-47 31

_D "xD x 1.2 Eq. 4-48 PD 31 "xD x 1.2 PDx Eq. 4-49 PDI&P ý31 x DPx 1.2 x

Where:

PDY = Projected air dose due to noble gas gamma radiation during the current month (mrad) from all routine effluent pathways POP =Projected air dose due to noble gas beta radiation during the current month (mrad) from all routine effluent pathways PDI = Projected dose to any organ due to Tritium, lodine-1 31, Iodine-I 33 and particulates with half-lives greater than 8 days (mrem) 31 = Time period for projection (days)

X= Number of days to date during sample period used to project the doses Rev. No. Rev. o. 9Page 77 of Part 2 (00CM)ý

D= Air dose due to noble gas gamma radiation corresponding to the time period X (mrad)

Do Air dose due to noble gas beta radiation corresponding to the time period X (mrad)

Dl~ = Organ dose due to lodines, Tritium and Particulates corresponding to the time period X (mrem) 1.2 =Conservatism factor to provide a margin for changes in mixture and operational line up, etc.

A formal dose projection would be based on the most appropriate results of the monthly calculations of the gamma air dose, the beta air dose, and the organ dose due to Tritium, lodines and particulates with half-lives greater than 8 days. The doses calculated will be divided by the number of days in the sample period determined to be most appropriate for projecting doses. An appropriate period to base projection on should reflect similar radioactive release rates effective at the time of the projection.

The per-day doses will be multiplied by 31 days, i.e., the time period for projection.

The product is the projected dose for the coming 31 day period. Its value may be adjusted to account for any changes in operating conditions that could significantly alter the actual releases, such as failed fuel.

The calculated projected doses, PD, PD., and PD1,p will be compared to the following Part 1, Radiological Effluent Controls, Section 3.5.1 .c.2 limits:

0.2 mrad for gamma radiation, 0.4 mrad for beta radiation, or 0.3 mrem to any organ.

If any doses exceed the above limits, the offgas charcoal beds will be used whenever the operation of the offgas treatment system is required during the projected time period.

a. Limited Analysis Approach and Selection Criteria A simpler approach, a linear extrapolation of the most recent three-month dose for the coming month, could be used as long as the limits of Part 1, Radiological Effluent Controls, Section 3.5.1.c.2 are not reached, and that releases of radioactive material have not changed significantly during the time period used for projection.

Rev. No. -9 78 of Part 2 (00CM)

Rev. o. 9Page

5.0 40 CFR 190 AND 10 CFR 72.104(a) DOSE EVALUATION Part 1, Radiological Effluent Controls,. Section 4.1. .1.c requires that the annual (calendar year) dose or dose commitment to any member of the public from uranium fuel cycle sources be limited to *.25 mrem to the whole body or any organ (except the thyroid which is limited to *,75 mrem). Compliance with the dose limits of 40 CFR 190 will be deemed to demonstrate compliance with the 100 mrem/yr limits of 10 CFR 20.1301 (a) (1).

5.1 Evaluation Bases Dose evaluation to demonstrate compliance with the 40 CFR 190 and 10 CFR 72.104(a) dose limits need only be performed if the quarterly or annual doses calculated in steps 3.4.1, 3.4.2, 4.4.1, 4.4.2, and 4.4.3 exceed twice the dose limits of Part 1, Radiological Effluent Controls, Sections 2.3, 3.3 or 3.4 respectively. Quarterly doses exceeding 3 mrem to the whole body (liquid releases), 10 mrem to any organ (liquid releases), 10 mrads equivalent gamma air dose, 20 mrads equivalent beta air dose, or 15 mrem to the thyroid or any organ from radioiodines and particulates (atmospheric releases) and annual doses exceeding 6 mrem to the whole body (liquid releases), 20 mrem to any organ (liquid releases), 20 mrads equivalent gamma air dose, 40 mrads equivalent beta air dose, or 30 mrem to the thyroid or any organ from radioiodines and particulate (a-tmospheric releases) would require 40 CFR 190 and 10 CFR 72.104(a) evaluation. The dose evaluation includes dose contributions to a maximally exposed real individual from the calendar quarter in which the quarterly or annual limits were exceeded in addition to plant offsite dose contributions during the balance of the current calendar year.

40 CFR 190 and 10 CER 72.104(a) dose assessments, when required, will be made using actual meteorological data and frequency distribution data for the year covered by the evaluation.

For purposes of the evaluation, if required, it may be assumed that the dose commitment to the maximally exposed real individual from other uranium fuel cycle sources is neglig-ible. However, doses from JAFNPP will be added to the doses to the maximum exposed individual at Nine Mile Point Unit 1 and Unit 2, or to the nuclear fuel cycle facilities within a radius 8 km of the site.

As part of the Radiological Environmental Monitoring Program (REMP), JAF and Niagara Mohawk jointly support a TILD program that monitors the doses on and off-site. The environmental TLDs measure the direct gamma radiation from the sites; contributions from JAF, Nine Mile Units 1 and 2. The TILD results are presented annually in the JAF Radiological Environmental Operating Report (AREOR).

JAF and Niagara Mohawk issue Radioactive Effluent Release Reports. The dose contributions from effluents from the plant can be found in these reports.

Rev. No. 9 Rev. o. 9Page 79 of Part 2 (ODOM)

JAF also reports annually to the commission, in accordance with 10 CFR 72.4 and 72.44(d)(3), the quantity of each of the principal radionuclides released to the environment in liquid and gaseous effluents during the previous 12 months of operation, and such other information as may be required by the commission to estimate maximum potential radiation dose commitment to the public resulting from effluent releases (Per JAF AP-03.04).

5.2 Doses From Liquid Releases For the evaluation of doses to real individuals from liquid releases, the same calculating method as employed for Liquid Effluents Annual Dose Assessment will be used.

However, more realistic assumptions and any current field data or updated estimates may be used, if available, concerning the dilution and ingestion of fish and potable water by individuals who live and fish in the area. Also, the results of the Radiological Environmental Monitoring Program will be included in determining more refined estimates of doses to real individuals by providing data on actual measured levels of plant-related radionuclides in the environment.

5.3 Doses From Atmospheric Releases For the evaluation of doses to real individuals from the atmospheric releases, the same calculating methods as employed for Gaseous Effluent Annual Dose Assessment will be used except that the gamma and beta air doses are not calculated. Otherwise the same calculating sequence applies. However, any current field data or updated estimates may be used, if available, concerning the actual location of real individuals, the meteorological(

conditions, and the consumption of food (e.g., milk, meat and vegetation). Data obtained from the latest land use census Part 1, Section 5.2 should be used to determine locations for evaluating doses. Also, the results of the Radiological Environmental Monitoring Program will be included in determining more refined dose estimates to real individuals by providing data on actual measured levels of radioactivity and radiation at locations of interest.

5.4 Doses From Direct Radiation Because 40 CFR 190 and 10 CFR 72.104(a) requirements include consideration of the offsite dose contribution from direct radiation, an estimate must be provided in the evaluation.

The direct radiation dose contribution from turbine shine (N-16) under hydrogen water chemistry conditions was evaluated to determine the need for additional shielding. Site boundary doses at the land based sectors of the site are less than 1 mrem/yr from this source.

Rev. No. -9 Rev. o. 9Page 80 of Part 2 (00CM)

The Interim Radioactive Waste Storage Facility (IRWSF) was evaluated for doses to the site boundary from a fully loaded facility in JAF-CALC-RAD-00030, Rev. 1. The calculation shows the site boundary gamma dose for the land based sectors of the site from the contained sources within the Interim Waste Storage Facility to be less than I mrem/yr.

The Independent Spent Fuel Storage Installation (ISESI) was evaluated for doses to the site boundary from a Phase I configuration and cask storage source term. The Phase I ISFISI is loaded with 18 storage casks in a 9 x 2 array. Each cask is loaded with 68 spent fuel bundles. Calculations in JAF-CALC-SFS-03344, Rev. 0 and JAF-CALC-SFS-.

04025, Rev. 1 demonstrate that the site boundary gamma dose for the closest land based sector of the site is less than 1 mremlhr from a fully loaded Phase I configuration.

Turbine shine, a fully loaded IRWSF, and the Phase I loaded ISFSI are the major contributors to direct radiation exposure at the site boundary. New sources will be analyzed on a case by case basis.

5.5 Doses to Members of the Public due to On-Site Activities Members of the public are occasionally granted access to areas within the site boundary.

Exposure to these members of the public due to liquid releases while on-site is highly unlikely and is not considered. Therefore, only exposure due to gaseous releases and direct radiation are considered. TLD and periodic area survey information is used to ensure that the dose and dose rates to such members of the public are within the limits of 10 CFR 1301 (a)(1).

Rev. No. -9 Rev. o. 81 of Part2.. QQM 9Page

6.0 REFERENCES

6.1 Regulatory Guide 1.109, Rev. 1, October 1977 6.2 NUREG-0133, October 1978 6.3 AP-02.08, Quality Assurance Record Identification and Control*, Revision 2, April 18, 1995 6.4 Technical Specifications 6.5 James A. FitzPatrick Nuclear Power Plant, Docke t 50-333, Compliance with 10 CFR 50, Appendix 1.

6.6 Final Environmental Impact Statement Related to Operation of James A. FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50-333, March 1973 6.7 Environmental Report, Operating License Stage, James A. FitzPatrick Plant, New York Power Authority, May 1971 6.7.1 Supplement Environmental Report, Operating License Stage, November 1971 6.7.2 Supplement #2 Environmental Report, Benefit/Cost Analysis, May 1972 6.7.3 Supplement #3 Environmental Report, Answers to Atomic Energy Commission Questions, August 1982 6.8 Final Safety Analysis Report, James A. FitzPatrick Plant, New York Power Authority, Docket No. 50-333, Operating License No. DPR-59 6.9 New York Power Authority, Internal Memorandum from 0. Dunning to G. Re, September 20,1988 6.10 New York Power Authority, Corporate Radiological Engineering Calculation No. JAF-CALC-RAD-00025, Revision 1, Atmospheric Dispersion and Deposition Parameters for Routine Releases (1995) 6.11 CHAS. T. Main, Inc. X/Q and D/Q Tables for Nine Mile Point Unit 1, Nine Mile Point Unit 2 and James A. FitzPatrick Nuclear Power Plant, November 1985 (Contain 5 years of meteorological data, 1978 through 1982) 6.12 Idaho National Engineering Laboratory Technical Evalutation Report (TER) of the JAF ODOM for the NRC (EGG-PHY-8153, July 1988)

Rev. No. -9 Rev. o. 9Page 82 of Part 2 (ODOM)

6.13 New York Power Authority Corporate Radiological Engineering Calculation Number JAF-CALC-RAD-0001O, Revision 0, Verification Document for Radiological Effluent Controls and Offsite Dose Calculation Manual (Date Pending) 6.14 New York Power Authority Corporate Radiological Engineering Calculation Number JAF-CALC-RAD-00029, Aquatic Dispersion and Dose Assessment Methodology for Non-Routine Releases (1995) 6.15 Entergy Nuclear FitzPatrick, LLC and Entergy Nuclear Operations, Inc., James A.

FitzPatrick Independent Spent Fuel Storage Installation JAF-CALC-SFS-03346, Rev. 0, Dose Rates in the Vicinity of 125 Ton Hi-Track Transfer Cask 6.16 Entergy Nuclear FitzPatrick, LLC and Entergy Nuclear Operations, Inc., James A.

FitzPatrick Independent Spent Fuel Storage Installation JAF-CALC-SFS-04025, Rev. 1, Confinement Analysis and Compliance with Regulations for the Phase I ISFISI 6.17 Entergy Nuclear FitzPatrick, LLC and Entergy Nuclear Operations, Inc., James A.

FitzPatrick Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report 6.18 AP-03.04, Information Reporting Requirements, Revision 8 6.19 Certificate of Compliance No. 1014, Appendix A. Technical Specifications for the Hi-Storm 100 Cask System, Amendment 0 (as issued to JAF) 6.20 JAF-ICD-RBC-04561, Interface Control Document, Offsite Dose Manual Effluent Airflows, 04/23/03, Rev.0 Rev. No. -9 Rev. o. 9Page 83 of Part 2 (ODCM)

APPENDIX A LIQUID DOSE CALCULATION DATA Rev. No. -9 Rev. o. 9Page A-I of ODOM

APPENDIX A LIQUID DOSE CALCULATION DATA TABLE TITLE PAGE A-I Effluent Concentration Limits for Water in Unrestricted Areas A-3 A-2 Dose Factors, Limited Analysis Approach A-4 A-3 Dose Factors, All Remaining Pathways A-9 A-4 Dose Factor Derivation A-1 8 Rev. No. -9 Rev. o..A-2 9Pageof ODOM

TABLE A-1 EFFLUENT CONCENTRATION LIMITS FOR WATER IN UNRESTRICTED AREAS NUCLIDE' ECL (pCi/mi) J NUCLIDE1 JýECL(pCi/mI)

H-3 I .OOOE-02 Ru-I 03 3.OOOE-04 Be-7 6.OOOE-03 Ru-I 05 7.OOOE-04 Na-24 5.OQOE-04 Ru-i 06 3.OOOE-05 P-32 9.OQOE-05 Cd-i 09 6.OQOE-05 K-40 4.OOOE-05 Ag-11rn 6.OOOE-05 Cr-5i 5.OOOE-03 Sn- 113 3.OOOE-04 Mn-54 3.OOOE-04 In-i 13m 7.OOOE-03 Mn-56 7.OOOE-04 Sb-122 1.OOOE-04 Fe-55 1.OOOE-03 Sb-i 24 7.OOOE-05 Fe-59 I .OOOE-04 Sb-I 25 3.OOOE-04 Co-57 6.OOOE-04 Te-l 23M 9.OOQE-05 Co-58 2.OOOE-04 Te-125m 2.OOOE-04 Co-60 3.OOOE-05 Te-i 27 1.OOOE-03 Ni-63 1.OOOE-03 Te-1 27m 9.OOOE-05 NI-65 I .OOOE-03 Te-1 29m 7.OOOE-05 Cu-64 2.OOOE-03 Te-1 29 4.OOOE-03 Zn-65 5.O0OE-05 Te-I 31 m 8.OOOE-05 Zn-69 8.OOOE-03 Te-1 31 8.000E-04 Zn-69m 6.000E-04 Te-1 32 9.O0OE-05 As-76 I .OOOE-04 Te-1 34 3.OOOE-03 Br-82 4.OOOE-04 1-130 2.OOOE-04 Br-83 9.OOOE-03 1-131 1.000E-05 Br-84 4.OOOE-03 1-132 I .OOOE-03 Br-85 1,0OOOE-05 1-133 7.OOOE-05 Rb-86 7.OOOE-05 1-134 4.OOOE-03 Rb-88 4.OOOE-03 1-135 3.OOOE-04 Rb-89 9.OOOE-03 Cs-1 34 9.OOOE-06 Sr-85 4.OOOE-04 Cs-i 36 6.OOOE-05

(.

Sr-89 8.OOOE-05 Cs-i 37 I .O6OE-05 Sr-9O 5.OOOE-06 Cs-1 38 4.OOOE-03 Sr-91 2.OOOE-04 Ba-i 33 2.OOOE-04 Sr-92 4.000E-04 Ba-I 39 2.OOOE-03 Y-88 I .OOOE-04 Ba-i 40 8.OOOE-05 Y-90 7.OOOE-05 Ba-1 41 3.OOOE-03 Y-91 m 2.OOOE-02 Ba-I 42 7.OOOE-03 Y-9 I 8.OOOE-05 La-i40 9.OOOE-05 Y-92 4.OOOE-04 La-142 I .OOOE-03 Y-93 2.OOOE-04 Ce-I 39 7.OOOE-04 Zr-95 2.OOOE-04 Ce-141 3.OOOE-04 Zr-97 9.OOOE-05 Ce-143 2.OOOE-04 Nb-94 1.OOOE-04 Ce-144 3.OQOE-05 Nb-95 3.OOOE-04 Pr-I 43' 2.OOOE-04 Nb-95m 3.OOOE-04 Pr-144 6.OQQE-03 Nb-97 3.OOOE-03 Nd-i 47 2.OOQE-04 Mo-99 2.OOOE-04 W-i187 3.OOOE-04 Tc-99m I .OOOE-02 Np-239 2.OQOE-04 Tc-101 2.OOOE-02 (I) All ECL values are taken from 10 times IOCFR20 EC values.

K Rev. No. 9 Rev. No. .A-3 9Pageof 00CM

TABLE A-2 DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES Limited Analysis Approach PAGE Freshwater Fish (Adt) - Adult A-5 Potable Water (At) - Adult A-6 Freshwater Fish (km) - Teenager A-7 Potable Water (At.) - Teenager A-8 Rev. No. -9 Rev. o. 9Page A-4 of ODOM

TABLE A-2 A-t VALUES - FRESHWATER FISH - ADULT (mremlhr per ujCilml)

NUCLIDE BONE LIVER ITHYROID KIDNEY__ LUNG JGI-LLI SKIN [_T. BODY_

H-3 0 1.89E-02 1.89E-02 1.89E-02 1.89E-02 1.89E-02 0 1.89E-02 Na-24 3.39E 01 3.39E 01 3.39E 01 3.39E 01 3.39E 01 3.39E 01 0 3.39E 01 Cr-51 0 0 6.34E-02 2.34E-02 1.41 E-01 2.67E 01 0 1.06E-01 Mn-54 0 3.65E 02 0 1.09E 02 0 1.12E 03 0 6.96E 01 Fe-55 5.49E 01 3.79E 01 0 0 2.11 E01 2.17E 01 0 8.84E 00 Fe-59 8.66E 01 2.03E 02 0 0 5.69E 01 6.78E 02 0 7.80E 01 Co-57 0 1.74E 00 0 0 0 4.43E 01 0 2.90E 00 Co-58 0 7.43E 00 0 0 0 1.51 E 02 0 1.67E 01 Co-60 0 2.13E 01 0 0 0 4.01 E 02 0 4.71E 01 Cu-64 0 8.31 E-0 1 0 2.09E 00 0 7.08E 01 0 3.90E-01 Zn-65 1.93E 03 6.14E 03 0 4.11 E03 0 3.87E 03 0 2.78E 03 Sr-89 1.84E 03 0 0 0 0 2.96E 02 0 5.29E 01 Sr-90 4.54E 04 0 0 0 0 1.31 E03 0 1.11 E04 NbJ-95 3.72E 01 2.07E 01 0 2.05E 01 0 1.26E 05 0 1.11E 01 Zr-95 2.OOE-02 6.42E-03 0 1.01 E-02 0 2.03E 01 0 4.35E-03 As-76 0 .9.46E-01 0 1.78E 00 0 2.29E 03 0 9.04E-01 Nb-95m 3.27E 01 2.07E 01 0 2.05E 01 0 1.26E 05 0 1.11EO01 Zr-97 1.11 E-03 2.23E-04 0 3.37E-04 0 6.91 E 01 0 1.02E-04 Mo-99 0 8.60E 00 0 1.95E 01 0 1.99E 01 0 1.64E 00 Tc-99m 7.39E-04 2.09E-03 0 3.1 7E-02 1.02E-03 1.24E 00 0 2.66E-02 Ag-I 1Om 7.34E-02 6.79E-02 0 1.34E-01 0 2.77E 01 0 4.03E-02 Sb-124 5.59E-01 1.05E-02 1.35E-03 0 4.35E-01 1.59E 01 0 2.21 E-01 1-131 1.24E 01 1.78E 01 5.84E 03 3.05E+01 0 4.70E 00 0 1.02E 01 1-133 4.25E 00 7.39E 00 1.09E 03 1.29E 01 0 6.64E 00 0 2.25E 00 1-135 1.33E 00 3.47E 00 2.29E 02 5.57E 00 0 3.92E 00 0 1.28E 00 Cs-i 34 2.48E 04 5.91 E 04 0 1.91 E 04 6.34E 03 1.03E 03 0 4.83E 04 Cs-i 37 3.18E 04 4.35E 04 0 1.48E 04 4.91 E 03 8.42E 02 0 2.85E 04 Ba-1 40 1.62E 01 2.03E-02 0 6.92E-03 1.17E-02 3.34E 01 0 1.06E 00 La-140 1.25E-02 6.28E-03 0 0 0 4.61 E 02 0 1.66E-03 Ce-141 1.87E-03 1.26E-03 0 5.87E-04 0 4.83E 00 0 1.43E-04 Ce-144 9.74E-02 4.07E-02 0 2.41 E-02 0 3.29E 01 0 5.23E-03 W-1 87 2.47E 01 2.06E 01 0 0 0 6.75E 03 0 7.21 E 00 Np-239 2.37E-03 2.33E-04 0 7.28E-04 0 4.79E 01 0 1.29E-04

_______________ _______________ ________________ A________________ A .L ________________ L ________________ A .1. _______________

P(-. No. 9 P-'~'.No. A-5 9Pageof ODC-M\

~. -. A-2 A,, VALUES - POTABLE WATER - ADULT (mrem/hr per liCi/mi)

NUCLIDE] BONE LIVER [_THYROID KIDNEY__ LUNG 7 GI-L.LI J SKIN -- T. BODY H-3 0 5.29E-02 5.29E-02 5.29E-02 5.29E-02 5.29E-02 5.29E-02 Cr-S I 0 0 8.02E-04 2.96E-04 1.78E-03 3.37E-01 1.34E-03 Mn-54 0 2.302 00 0 6.86E-01 0 7.06E 00 4.39E-01 Fe-55 1.39E 00 9.'58E-01 0 0 5.35E-01 5,50E-0 1 2.23E-01 Fe-59 2.19E200 5.14E200 0 0 1.442 00 1.71E2+01 1.97E200 Co-57 0 8.83E-02 0 0 0 2.24E 00 1.472-01 Co-58 0 3.76E-01 0 0 0 7.622 00 8.422-01 Co-60 0 1.08E200 0 0 0 2.032 01 2.382 00 Zn-65 2.44E 00 7.772 00 0 5.192 00 0 4.892 00 3.512E00 Sr-89 1.55E 02 0 0 0 0 2.492 01 4.452 00 Sr-90 3.82E 03 0 0 0 0 1.102 02 9.382 02 Zr-95 1.53E-02 4.922-03 0 7.722-03 0 1.562 01 3.33E-03 Zr-97 8.472-04 1.71 2-04 0 2.582-04 0 5.292 01 7.822-05 Nb-95 3.1 4E-03 1.752-03 0 1.722-03 0 1.06201f 9.38E-04 Mo-99 0 2.172 00 0 4.922 00 0 5.042 00 4.13E-01 Ag-i lOin 8.07E-02 7.462-02 0 1.472-01 0 3.052 01 4.43E-02 Sb- 124 1.41 E 00 2.67E-02 3.42E-03 0 1.102 00 4.012 01 5.59E-01 1-13 1 2.10E 00 3.002 00 9.832 02 5.142 00 0 7.922-01 1.722 00 1-133 7.162-01 1.252 00 1.832 02 2.17E200 0 1.122 00 3.79E-01 1-135 2.232-01 5.852-01 3.862 01 9.38E-01 0 6.612E-0 1 2.162-01 Cs-134 3.142 01 7.462 01 0 2.422 01 8.022 00 1.312E 00 6.102 01 Cs-i 37 4.02E 01 5.492 01 0 1.872 01 6.202 00 1.062 00 3.612 01 Ba-140 1.022 01 1.292-02 0 4.372-03 7.36E-03 2.112E01 6.71 2-01I La-140 1.26E-03 6.352-04 0 0 0 4.662 01 1.682-04 Ce-141 4.72E-03 3.192-03 0 1.482-03 0 1.22E 01 3.62E-04 Ce-144 2.46E-01 1.032-01 0 6.102E-02 0 8.322 01 1.322-02 Na-24 8.57E-01 8.57E-01 8.5 72-01 8.57E-01 8.57E-01 8.57E-01 8.57E-01 Cu-64 0 4.202-02 0 1.06E-01 0 3.582 00 1.972-02 W-1 87 5.192-02 4.342-02 0 0 0 1.42E201 1.51 2-02 Np-239 6.002-04 5.902-05 0 1.842-04 0 1.212E 01 3.25E-05 Tc-99m 1.25E-04 3.52E2-04 0 5.35E-03 1.722-04 2.08E-01 4.48E-03 As-76 0 2.392-02 0 4.50E-02 0 5.802 01 2.282-02 Nb-95m 3.14E-03 1.75E-03 0 1.72E-03 0 1.06E201 9.38E-04 Rev. No. 9 Page A-6 offOO PaeA6 ODCM

TABLE A-2 At, VALUES - FRESHWATER FISH - TEENAGER (mrem/hr per uCilmI)

NUCLIDE IBONE I LIVER ITHYROID IKIDNEY__I LUNG IGI-LLI I SKI N I__T. BODY H-3 0 1.45E-02 1.45E-02 I1.45E-02 I1.45E-02 1.45E-02 0 I1.45E-02 Na-24 3.50E 01 3.50E 01 3.50E 01, 3.50E 01 .3.50E 01 3.50E 01 0 3.50E 01 Cr-5i 0 0 6.08E-02 2.40E-02 1.56E-01 1.84E 01 0 1.09E-01 Mn-54 0 3.59E 02 0 1.07E 02 0 7.35E 02 0 7.11 E 01 Fe-55 5.75E 01 4.07E 01 0 0 2.58E 01 1.76E 01 0 9.50E 00 Fe-59 8.92E 01 2.08E 02 0 0 6.57E 01 4.92E 02 0 8.04E 01 Co-57 0 1.81 E 00 0 0 0 3.37E 01 0 3.03E 00 Co-58 0 7.39E 00 0 0 0 1.02E 02 0 1.70E 01 Co-60 0 2.14E 01 0 0 0 2.78E 02 0 4.81E 01 Cu-64 0 8.74E-01 0 2.21 E 00 0 6.78E 01 0 4.11IE-01 Zn-65 1.75E 03 6.08E 03 0 3.89E 03 0 2.57E 03 0 2.84E 03 Sr-89 2.01E 03 0 0 0 0 2.39E 02 0 5.75E 01 Sr-90 3.78E 04 0 0 0 0 1.06E 03 0 9.35E 03 Nb-95 3.75E 01 2.08E 01 0 2.02E 01 0 8.89E 04 0 1.14E 01 Zr-95 2.07E-02 6.52E-03 0 9.58E-03 0 1.50E 01 0 4.48E-03 As-76 0 1.02E 00 0 1.93E 00 0 1.96E 03 0 9.83E-01 Nb-95m 3.75E 01 2.08E 01 0 2.02E 01 0 8.89E 04 0 1.14E 01 Zr-97 1.19E-03 2.35E-04 0 3.57E-04 0 6.37E 01 0 1.08E-04 Mo-99 0 9.17E 00 0 2.10E 01 0 1.64E 01 0 1.75E 00 Tc-99m 7.57E-04 2.11 E-03 0 3.15E-02 1.17E-03 1.39E 00 0 2.74E-02 Ag-Ib1 m 7.1 7E-02 6.78E-02 0 1.29E-01 0 1.91E 01 0 4.1 3E-02 Sb-124 5.88E-01 I1.08E-02 1.33E-03 0 5.14E-01 1.19E 01 0 2.29E-01 1-131 1.33E 01 1.87E 01 5.45E 03 3.21 E 01 0 3.69E 00 0 1.OOE 01 1-133 4.58E 00 7.77E 00 1.09E 03 1.36E 01 0 5.88E 00 0 2.37E 00 1-135 1.39E 00 3.58E 00 2.30E 02 5.56E 00 0 3.97E 00 0 1.33E 00 Cs-134 2.54E 04 5.99E 04 0 1.90E 04 7.27E 03 7.45E 02 0 2.78E 04 Cs-i 37 3.40E 04 4.53E 04 0 1.54E 04 5.99E 03 6.44E 02 0 1.58E 04 Ba-140 1.73E 01 2.12E-02 0 7.1 7E-03 1.42E-02 2.66E 01 0 1.11 E 00 La-140 I1.32E-02 6.50E-03 0 0 0 3.73E 02 0 1.73E-03 Ce-141 2.02E-03 I1.35E-03 0 6.35E-04 0 3.86E 00 0 I1.55E-04 Ce-i 44 1.06E-01 4. 38E-02 0 2.61 E-02 0 2.66E 01 0 5.68E-03 W-187 2.66E 01 2.17E 01 0 0 0 5.87E 03 0 7.61 E 00 Np-239 2.68E-03 2.52E-04 0 7.92 E-04 0 4.06E 01 0 1.40E-04 P---,,. No. 9 F-". o. 9Page A-7 of ODr(kl

TABLE A-2 At . VALUES - POTABLE WATER - TEENAGER (mremlhr per pCiImI)

NUCLIDE BONE [ LIVER THYROID___KIDNEY LUGGI-LLI [ SKIN T. BODY H-3 0 3.73E-02 3.73E-02 3.73E-02 3.73E-02 3.73E-02 0 3.73E-02 Cr-5I 0 0 7.05E-04 2.78E-04 1.81 E-03 2.13E-01 0 1.27E-03 Mn-54 0 2.08E 00 0 6.20E-01 0 4.26E 00 0 4.12E-01 Fe-55 1.33E 00 9.44E-01 0 0 5.99E-01 4.09E-01 0 2.20E-01 Fe-59 2.07E 00 4.83E 00 0 0 1.52E 00 1.14E 01 0 1.86E 00 Co-57 0 8.39E-02 0 0 0 1.56E 00 0 1.41 E-0 1 Co-58 0 3.42E-01 0 0 0 4.72E 00 0 7.89E-01 Co-60 0 9.90E-01 0 0 0 1.29E 01 0 2.23E 00 Zn-65 2.03E 00 7.05E 00 0 4.51 E 00 0 2.98E 00 0 3.29E 00 Sr-89 1.55E 02 0 0 0 0 1.85E 01 .0 4.44E 00 Sr-90 2.92E 03 0 0 0 0 8.21 E 01 0 7.22E 02 Zr-95 1.45E-02 4.58E-03 0 6.73E-03 0 1.06E 01 0 3..15E-03 Zr-97 8.35E-04 1.65E-04 0 2.51 E-04 0 4.47E 01 0 7.61 E-05 NbJ-95 2.90E-03 1.61 E-03 0 1.56E-03 0 6.87E 00 0 8.84E-04 Mo-99 0 2.12E 00 0 4.86E 00 0 3.81 E00 0 4.05E-01 Ag-ib0m 7.22E-02 6.84E-02 0 1.30E-01 0 1.92E 01 0 4.16E-02 Sb-124 1.36E 00 2.51 E-02 3.09E-03 0 1.19E 00 2.75E 01 0 5.32E-01 1-131 2.06E 00 2.89E 00 8.42E 02 4.97E 00 0 5.71 E-0 1 0 1.55E 00 1-133 7.08E-01 1.20E 00 1.67E 02 2.11IE 00 0 9.09E-01 0 3.66E-01 1-135 2.15E-01 5.53E-01 3.56E 01 8.74E-01 0 6.13E-01 0 2.05E-01 Cs-134 2.95E 01 6.94E 01 0 2.21 E 01 8.42E 00 8.63E701 0 3.22E 01 Cs-137 3.95E 01 5.25E 01 0 1.79E 01 6.94E 00 7.47E-01 0 1.83E 01 Ba-140 1.OOE 01 1.23E-02 0 4.16E-03 8.25E-03 1.54E 01 0 6.54E-01 La-1 40 1.23E-03 6.03E-04 0 0 0 3.46E 01 0 1.60E-04 Ce-141 4.69E-03 3.13E-03 0 1.47E-03 0 8.95E 00 0 3.59E-04 Ce-144 2.45E-01 1.01E-01 0 6.06E-02 0 6.171E01 0 1.31 E-02 Na-24 8.60E-01 8.60E-01 8.60E-01 8.60E-01 8.60E-01 8.60E-01 0 8.60E-01 Cu-64 0 4.05E-02 0 1.03E-01 0 3.14E 00 0 1.91 E-02 W-187 5.14E-02 4.19E-02 0 0 0 1.13E 01 0 1.47E-02 Np-239 6.20E-04 5.85E-05 0 1.84E-04 0 9.41 E 00 0 3.25E-05 Tc-99m 1.17E-04 3.26E-04 0- 4.86E-03 1.81E-04 2.14E-01 0 4.23E-03 As-76 0 2.36E-02 0 4.48E-02 0 4.55E 01 0 2.28E-02 Nb-95m 2.90E-03 1.61 E-03 0 1.56E-03 0 6.87E 00 0 8.84E-04 Rev. No. 9 A-8 of ODOM Rev. o. 9Page

TABLE A-3 DOSE CONVERSION FACTORS FOR LIQUID DISCHARGES All Remaining Pathways Page Lake Shoreline Deposits (Aftsh) -Adult A-1l0 Lake Shoreline Deposits (Ash) -Teenager A-li1 Potable Water (A,,,) -Child A-12 Freshwater Fish (k~) -Child A-13 Lake Shoreline Deposits (Akth) -Child A-14 Potable Water (A..) -Infant A-15 Freshwater Fish (A.) -Infant A-1 6 Lake Shoreline Deposits (kh) -Infant A-1 7 Rev. No. -9 Rev. No. .A-9.

9Pageof ODOM

iJA-3 VALUES - LAKE SHORELINE DEPOSITS - ADULT (mremlhr per pCi/mI)

NUCLIDE [ BONE I LIVER I THYROID I KIDNEY IF LUNG IGI-LLI I SKIN TT. BODY=

H-3 0 0 0 0 0 0 0 0 Na-24 3.56E-02 3.56E-02 3.56E-02 3.56E-02 3.56E-02 3.56E-02 4.13E-02 3.56E-02 Cr-51 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.38E-02 1.64E-02 I1.38E-02 Mn-54 4.13E 00 4.13E 00 4.13E200 4.13E200 4.13E 00 4.13E 00 4.852 00 4.13E 00 Fe-55 0 0 0 0 0 0 0 0 Fe-59 8.13E-01 8.13E-01 8.13E-01 8.13E-01 8.13E-01 8.13E-01 9.55E-01 8.13E-01 Co-57 5.62E-02 5.62E-02 5.62E-02 5.62E-02 5.62E-02 5.62E-02 6.18E-01 5.62E-02 Co-58 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.13E 00 1.32E 00 1.13E 00 Co-60 6.42E 01 6.42E 01 6.42E 01 6.42E 01 6.42E 01 6.42E 01 7.55E 01 6.42E 01 Cu-64 1.81E-03 1.81E-03 1.81 E-03 1.812E-03 1.81 E-03 1.812E-03 2.05E-03 1.81 E-03 Zn-65 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.23E 00 2.56E 00 2.23E 00 Sr-89 6.46E-05 6.46E-05 6.46E-05 6.46E-05 6.46E-05 6.46E-05 7.5 E-05 6.46E-05 Sr-90 0 0 0 0 0 0 0 0 Nb-95 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.08E-01 4.80E-01 4.08E-01 Zr-95 7.30E-01 7.30E-01 7.30E-01 7.30E-01 7.30E 01 7.30E-01 8.46E-01 7.30E-01 As-76 1.14E-02 1.14E-02 1.14E-02 1.14E-02 1.14E-02 1.14E-02 3.96E-01 1.14E-02 Nb-95m 5.85E-03 5.85E-03 5.85E-03 5.85E-03 5.85E-03 5.85E-03 3.67E-02 5.85E-03 Zr-97 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 8.78E-03 1.02E-02 8.78E-03 Mo-99 1.1 9E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.38E-02 1.19E-02 Tc-99m 5.7-4 5.47E-04 5.47E-04 5.47E-04 5.47E-04 5.47E-04 6.27E-04 5.47E-04 Ag-ib0m 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.03E 01 1.20E 01 1.03E 01 Sb-i 24 1.78E 00 1.78E 00 1.782 00 1.78E 00 1.78E 00 1.78E 00 2.06E 00 1.78E 00 1-131 5.13E-02 5.13E-02 5.13E-02 5.13E-02 5.13E-02 5.13E-02 6.23E-02 5.13E-02 1-133 7.34E-03 7.34E-03 7.34E-03 7.34E-03 7.34E-03 7.34E-03 8.93E-03 7.34E-03 1-135 7.66E-03 7.66E-03 7.66E-03 7.66E-03 7.662 03 7.66E-03 8.94E-03 7.66E-03 Cs-i 34 2.052 01 2.052 01 2.05E 01 2.05E 01 2.05E 01 2.052 01 2.39E 01 2.05E 01 Cs-I 37 3.072 01 3.072 01 3.072 01 3.072 01 3.07E 01 3.072 01 3.58E 01 3.07E 01 Ba-140 6.13E-02 6.13E-02 6.13E-02 6.13E-02 6.13E-02 6.13E-02 7.002-02 6.13E-02 La-140 5.812E-02 5.812E-02 5.812E-02 5.812E-02 5.812E-02 5. 812E-02 6.58E-02 5.812E-02 Ce-141 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.08E-02 4.59E-02 4.08E-02 Ce-i 44 2.072-01 2.07E-01 2.07E-01 2.07E-01 2.072-01 2.07E-01 2.392-01 2.07E-01 W-1 87 7.07E-03 7.07E-03 7.072-03 7.07E-03 7.07E-03 7.07E-03 8.212E-03 7.07E-03 Np-239 5.20E-03 5.20E-03 5.20E-03 5.202 03 5.20E-03 5.20E-03 6.02E-03 5.20E-03 Rev. No. 9 A-I 0 of ODOM Rev. o. 9Page

TABLE A-3 (Continued)

A-tsh VALUES - LAKE SHORELINE DEPOSITS - TEENAGER (mremlhr per piCilmI)

NUCLIDE] BONE JLIVER JTHYROID___KIDNEY__ LUNG GI-LLI J SKIN ]_T. BODY H-3 0 0 0 .0 0 0 0 0 Na-24 1.98E-01 1.98E-01 1.98E-01 .1.98E-01 1.98E-01 1.98E-01 2.31 E-0 I 1.98E-01 Cr-5I 7.76E-02 7.76E-02 7.76E-02 7.76E-02 7.76E-02 7.76E-02 9.17E-02 7.76E-02 Mn-54 2.31 E 01 2.31 E 01 2.31 E 01 2.312E 01 2.31 E 01 2.312 01 2.712E01 2.312 01 Fe-55 0 0 0 0 0 0 0 0 Fe-59 4.54E 00 4.542 00 4.54E 00 4.542 00 4.54E 00 4.54E 00 5.34E 00 4.54E 00 Co-57 3.14E 00 3.14E 00 3.142 00 3.142 00 3.14E 00 3.142 00 3.45E 00 3.14E 00 Co-58 6.31 E 00 6.31 E 00 6.31 E 00 6.312E 00 6.312E00 6.312E00 7.39E 00 6.312E 00 Co-60 3.58E 02 3.58E 02 3.58E 02 3.58E 02 3.58E 02 3.58E 02 4.21 E 02 3.582 02 Cu-64 1.01E-02 1.012E-02 1.012E-02 1.01E-02 1.012E-02 1.01E-02 1.14E-02 1.012E-02 Zn-65 1.24E 01 1.242 01 1.24E 01 1.24E201 1.24E201 1.242 01 1.43E 01 1.24E 01 Sr-89 3.612E-04 3.612E-04 3.61 E-04 3.61 E-04 3.612E-04 3.612E-04 4.18E-04 3.612E-04

-Sr-90 0 0 0 0 0 0 0 0 Nb-95 2.282 00 2.282 00 2.282 00 2.282 00 2.282 00 2.282 00 2.682 00 2.282 00 Zr-95 4.072 00 4.072 00 4.072 00 4.07E 00 4.072 00 4.072 00 4.722 00 4.072 00 As-76 6.382-02 6.382-02 6.382-02 6.38E-02 6.38E-02 6.-382-02 2.212E 00 6.382-02 Nb-95m 3.27E-02 3.272-02 3.272-02 3.272-02 3.27E-02 3.27E-02 2.052 01 3.27E-02 Zr-97 4.902-02 4.902-02 4.902-02 4.902-02 4.90E-02 4.902-02 5.70E-02 4.902-02 Mo-99 6.652-02 6.652-02 6.652-02 6.65E-02 6.652-02 6.65E-02 7.70E-02 6.652-02 Tc-99m 3.05E-03 3.05E-03 3.05E-03 3.05E-03 3.052-03 3.05E-03 3.502-03 3.05E-03 Ag-Ib0m 5.732 01 5.732 01 5.732 01 5.732 01 5.732 01 5.732 01 6.682 01 5.732 01 Sb-124 9.962 00 9.96E 00 9.96E 00 9.962 00 9.962 00 9.96E 00 1.152 01 9.962 00 1-131 2.872-01 2.872-01 2.87E-01 2.87E-01 2.87E-01 2.87E-01 3.48E-01 2.87E-01 1-133 4.09E-02 4.09E-02 4.09E-02 4.092-02 4.092-02 4.09E-02 4.98E-02 4.09E-02 1-135 4.282-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.28E-02 4.99E-02 4.28E-02 Cs-134 1.142 02 1.142 02 1.142 02 1.14E202 1.14E202 1.142 02 1.33E202 1.14E202 Cs-1 37 1.712E02 1.712E02 1.712E02 1.712E02 1.712E02 1.712E02 2.002 02 1.712E02 Ba-140 3.422-01 3.422-01 3.422-01 3.42E-01 3.422 01 3.42E-01 3.91 E-0 1 3.42E-01 La-140 3.242-01 3-.'24E-01 3.242-01 3.24E-01 3.24E-01 3.24E-01 3.67E-01 3.24E-01 Ce-141 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.28E-01 2.56E-01 2.28E-01 Ce-144 1.16E200 1.162 00 1.16E200 1.16E200 1.16E200 1.16E200 1.34E200 1.16E200 W-187 3.95E-02 3.95E-02 3.95E-02 3.95E-02 3.95E-02 3.95E-02 4.58E-0'2 3.952-02 Np-239 2.90E-02 2.902-02 2.90E-02 2.90E-02 2.90E-02 2.90E-02 3.36E-02 2.90E-02

,p-l..No. 9 Page A-1 1 of OD('ýkM

TABLE - ..;ontinued)

A~t, VALUES - POTABLE WATER - CHILD (mrem/hr oer uCi/mI)

NUCLIDEI BONE J LIVER THYROID___KIDNEY LUNG GI-LLI ( SKIN T. BODY-H-3 0 7.15E-02 7.15E-02 7.15E-02 7.15E-02 7.15E-02 0 7.15E-02 Cr-51 0 0 1.74E-03 4.76E-04 3.18E-03 1.66E-01 0 3.14E-03 Mn-54 0 3.77E 00 01.06E 00 0 3.16E 00 0 1.00E 00 Fe-55 4.05E 00 2.15E 00 0 0 1.22E 00 3.98E-01 0 6.66E-01 Fe-59 5.81 E 00 9.41 E 00 0 0 2.73E 00 9.79E 00 0 4.69E 00 Co-57 0 1.74E-01 0 0 0 1.42E 00 0 3.52E-01 Co-58 0 6.34E-01 0 0 0 3.70E 00 0 1.94E 00 Co-60 0 1.86E 00 0 0 0 1.03E 01 0 5.49E 00 Zn-OS 4.83E 00 1.29E 01 0 8.1IOE 00 0 2.26E 00 0 7.99E 00 Sr-89 4.65E 02 0 0 0 0 1.80E 01 0 1.33E 01 Sr-90 5.99E 03 0 0 0 0 8.07E 01 0 1.52E 03 Zr-95 4.09E-02 8.99E-03 0 1.29E-02 0 9.37E 00 0 7.99E-03 Zr-97 2.46E-03 3.56E-04 0 5.11IE-04 0 5.39E 01 0 2.1IOE-04 Nb-95 7.93E-03 3.09E-03 0 2.90E-03 0 5.71 E 00 0 2.21 E-03 Mo-99 0 4.,69E 00 0 1.OOEO01 0 3.88E 00 0 1.16E 00 Ag-ib1 m 1.90E-01 1.28E-01 0 2.39E-01 0 1.52E 01 0 1.02E-01 Sb-I 24 3.91 E 00 5.07E-02 8.63E-03 0 2.17E 00 2.45E 01 0 1.37E 00 1-131 6.06E 00 6.1 OEO00 2.01 E03 1.OOEO01 0 5.43E-01 0 3.46E 00 1-133 2.09E 00 2.58E 00 4.79E 02 4.30E 00 0 1.04E 00 0 9.76E-01 1-135 6.17E-01 1.11IE 00 9.83E 01 1.70E 00 0 8.46E-01 0 5.25E-01 Cs-134 8.25E 01 1.35E 02 0 4.19E 01 1.50E 01 7.29E-01 0 2.85E 01 Cs-137 1.15E 02 1.10E 02 0 3.59E 01 1.29E 01 6.91 E-0 1 0 1.63E 01 Ba-140 2.93E 01 2.57E-02 0 8.35E-03 1.53E-02 1.48E 01 0 1.71 E 00 La-140 3.56E-03 1.24E-03 0 0 0 3.47E 01 0 4.19E-04 Ce-141 1.40E-02 6.98E-03 0 3.06E-03 0 8.70E 00 0 1.03E-03 Ce-144 7.33E-01 2.30E-01 0 1.27E-01 0 5.99E 01 0 3.91 E-02 Na-24 2.04E 00 2.04E 00 2.04E 00 2.04E 00 2.04E 00 2.04E 00 0 2.04E 00 Cu-64 0 8.63E-02 0 2.09E-01 0 4.05E 00 0 5.21 E-02 W-1 87 1.51E-0O1 8.95E-02 0 0 0 1.26E 01 0 4.02E-02 Np-239 I1.85E-03 1.33E-04 0 3.84E-04 0 9.83E 00 0 9.34E-05 Tc-99m 3.25E-04 6.38E-04 0 9.27E-03 3.24E-04 3.63E-01 0 1.06E-02 As-76 0 5.36E-02 0 9.44E-02 0 5.43E 01 0 6.80E-02 Nb-95m 7.93E-03 3.09E-03 0 2.90E-03 0 5.71 E 00 0 2.21 E-03 Rev. No. 9 A-I 2 of ODCM Rev. o. 9Page

TABLE A-3 (Continued)

A,,, VALUES - FRESHWATER FISH - CHILD (mrem/hr r~er uCi/mI)

NUCLIDE] BONE LIVER THYROID KIDNEY__ LUNG [GI-LLI SKI N T. BODY H-3 0 1.19E-02 1.19E-02 1.19E-02 1.19E-02 1.19E-02 0 1.19E-02 Na-24 3.80E 01 3.80E 01 3.80E 01 3.80E 01 3.80E 01 3.80E 01 0 3.80E 01 Cr-51 0 0 6.48E-02 1.77E-02 1.18E-01 6.19E 00 0 1.17E-01 Mn-54 0 2.81 E 02 0 7.87E 01 0 2.35E 02 0 7.47E 01 Fe-55 7.54E 01 4.OOEO01 0 0 2.26E 01 7.41 E00 0 1.24E 01 Fe-59 1.08E 02 1.75E 02 0 0 5.07E 01 1.82E 02 0 8.72E 01 Co-57 0 1.62E 00 0 0 0 1.32E 01 0 3.27E 00 Co-58 0 5.90E 00 0 0 0 3.44E 01 0 1.81E 01 Co-60 0 1.73E 01 0 0 0 9.60E 01 0 5.IEO01 Cu-64 0 8.03E-01 0 1.94E 00 0 3.77E 01 0 4.85E-01 Zn-65 1.80E 03 4.79E 03 0 3.02E 03 0 8.40E 02 0 2.98E 03 Sr-89 2.60E 03 0 0 0 0 1.OOE 02 0 7.41E 01 Sr-90 3.34E 04 0 0 0 0 4.50E 02 0 8.48E 03 Nb-95 4.42E,01 1.72E 01 0 1.62E 01 0 3.19E 04 0 1.23E 01 Zr-95 2.51 E-02 5.52E-03 0 7.90E-03 0 5.75E 00 0 4.91 E-03 As-76 0 9.96E-01 0 1.76E 00 0 1.01 E03 0 1.27E 00 Nb-95m 4.42E 01 1.72E 01 0 1.62E 01 0 3.19E 04 0 1.23E 01 Zr-97 1.51 E-03 2.18E-04 0 3.14E-04 0 3.31 E 01 0 1.29E-04 Mo-99 0 8.72E 00 0 1.86E 01 0 1.86E 01 0 2.16E 00 Tc-99m 9.08E-04 1.78E-03 0 2.59E-02 9.04E-04 1.01 E 00 0 2.95E-02 Ag-1I Om 8.13E-02 5.49E-02 0 1.02E-01 0 6.53E 00 0 4.39E-02 Sb-1 24 7.28E-01 9.44E-03 1.61 E-04 0 4.04E-01 4.55E 00 0 2.55E-01 1-131 1.69E 01 1.70E 01 5.62E 03 2.79E 01 0 1.51 E00 0 9.67E 00 1-133 5.82E 00 7.20E 00 1.34E 03 1.20E 01 0 2.90E 00 0 2.72E 00 1-135 1.72E 00 3.1 OE 00 2.74E 02 4.75E 00 0 2.63E 00 0 1.47E 00 Cs-I 34 3.07E 04 5.03E 04 0 1.56E 04 5.60E 03 2.71 E 02 0 1.06E 04 Cs-137 4.29E 04 4.1 OE 04 0 1.34E 04 4.81 E 03 2.57E 02 0 6.06E 03 Ba-1 40 2.1 BE 01 1.19E-02 0 6.21 E-03 1.14E-02 1.10E 01 0 1.27E 00 La-140 1.66E-02 5.78E-03 0 0 0 1.61 E 02 0 1.95E-03 Ce-141 2.60E-03 1.30E-03 0 5.69E-04 0 1.62E 00 0 1.93E-04 Ce-144 1.36E-01 4.27E-02 0 2.37E-02 0 1.11 E 01 0 7.28E-03 W-1 87 3.37E 01 2.OOE 01 0 0 0 2.81 E 03 0 8.97E 00 Np-239 3.44E-03 2.47E-04 0 7.14E-04 0 1.83E 01 0 1.74E-04 R'-". No. 9 Page A-1 3 of ODC114 ,

TABLE. - .3 .,ontinued)

Aftsh VALUES - LAKE SHORELINE DEPOSITS - CHILD (mrem/hr per pCi/mI)

Rev. No.' 9 Rev. o[ A-14 9Pageof ODCM

TABLE A-3 (Continued)

A-t VALUES - POTABLE WATER - INFANT (mremlhr [)er uCi/Im)

NUCLIDE {BONE JLIVER THRI IDJNEY LUNG GILISKI N [_T.BODY H-3 0 7.02E-02 7.02E-02 7.02E-02 7.02E-02 7.02E-02 0 7.02E-02 Cr-51 0 0 2.10OE-03 4.58E-04 4.08E-'03 9.37E-02 0 3.21 E-03 Mn-54 0 4.54E 00 ý0 1.01 E00 0 1.67E 00 0 1.03E200 Fe-55 3.17E 00 2.05E 00 0 0 1.002 00 2.60E-01 0 5.47E-01 Fe-59 7.02E 00 1.23E 01 0 0 3.63E 00 5.86E 00 0 4.83E 00 Co-57 0 2.62E-01 0 0 0 8.94E-01 0 4.26E-01 Co-58 0 8.21 E-0l1 0 0 0 2.04E 00 0 2.05E 00 Co-60 0 2.46E 00 0 0 0 5.86E 00 0 5.81 E 00 Zn-65 4.20E 00 1.43E 01 0 6.98E 00 0 1.22E 01 0 6.63E 00 Sr-89 5.72E 02 0 0 0 0 1.18E 01 0 1.64E 01 Sr-90 4.22E 03 0 0 0 0 5.27E 01 0 1.07E 03 Zr-95 4.70E-02 1.14E-02 0 1.23E-02 0 5.76E 00 0 8.12E-03 Zr-97 3.37E-03 5.79E-04 0 5.84E-04 0 3.69E 01 0 2.64E-04 Nb-95 9.58E-03 3.94E-03 0 2.83E-03 - 0 3.33E 00 0 2.28E-03 Mo-99 0 7.75E 00 0 1.16E 01 0 2.55E 00 0 1.51 E00 Ag-110m 2.27E-01 1.66E-01 0 2.37E-01 0 8.59E 00 0 1.09E-01 Sb-I 24 4.88E 00 7.18E-02 1.29E-02 0 3.05E 00 1.50E 01 0 1.51 E 00 1-131 8.19E 00 9.64E 00 3.17E 03 1.13E 01 0 3.44E-01 0 4.24E 00 1-133 2.85E 00 4.15E 00 7.54E 02 4.88E 00 0 7.02E-01 0 1.21 E 00 1-135 8.30E-01 1.65E 00 1.47E 02 1.84E 00 0 5.97E-01 0 6.02E-01 Cs-I 34 8.60E 01 1.60E 02 0 4.13E 01 1.69E 01 4.35E-01 0 1.62E 01 Cs-.137 1.19E 02 1.39E 02 0 3.74E 01 1.51 E 01 4.35E-01 0 9.87E 00 Ba-140 3.89E 01 3.90E-02 0 9.26E-03 2.39E-02 9.58E 00 0 2.012E 00 La-140 4.81 E-03 1.90E-03 0 0 0 2.23E 01 0 4.87E-04 Ce-141 1.79E-02 ý1.09E-02 0 3.37E-03 .0 5.65E 00 0 1.28E-03 Ce-144 6.79E-01 2.78E-01 0 1.12E-01 0 3.892 01 0 3.81 E-02 Na-24 2.30E 00 2.30E 00 2.30E 00 2.30E 00 2.30E 00 2.30E 00 0 2.30E 00 Cu-64 0 1.39E-01 0 2.35E-01 0 2.85E100 0 6.43E-02 W-1 87 2.06E-01 1.43E-01 0 0 0 8.41 E00 0 4.95E-02 Np-239 2.53E-03 2.26E-04 0 4.51 E-04 0 6.54E 00 0 1.28E-04 Tc-99m 4.38E-04 9.03E-04 0 9.712E-03 4.72E-04 2.62E-01 0 1.16E-02 As-76 0 9.14E-02 0 1.11IE-01 0 3.65E 01 0 9.33E-02 Nb-95m 9.58E-03 3.94E-03 0 2.83E-03 0 3.33E 00 0 2.28E-03 Rp-- No. 9 -A-I5 of ODC" 4 -

R~'-~No. 9Page

TABLE- - 43, .ontinued)

AVALUES - FRESHWATER FISH . INFANT (mremlhr Der uCl/mi)

NUCLIDE] BONE LIVER THYROID__ KIDNEY LUNG GI-LLI -F SKIN FT. BODY_

H-3 0 0 0 0 0 0 0 0 Na-24 0 0 0 0 0 0 0 0 Cr-51 0 0 0 0 0 0 0 0 Mn-54 0 0 0 0 0 0 0 0 Fe-55 0 0 0 0 0 0 0 0 Fe-59 0 0 0 0 0 0 0 0 Co-57 0 0 0 0 0 0 0 0 Co-58 0 0 0 0 0 0 0 0 Co-60 0 0 0 0 0 0 0 0 Cu-64 0 0 0 0 0 0 0 0 Zn-65 0 0 0 0 0 0 00 Sr-89 0 0 0 0 0 0 0 0 Sr-90 0 0 0 0 0 0 0 0 Nb-95 0 0 0 0 0 0 0 0 Zr-95 0 0 0 0 0 0 0 0 As-76 0 0 0 0 0 0 0 0 Nb-95m 0 0 0 0 0 0 0 0 Zr-97 0 0 0 0 0 0 0 0 Mo-99 0 0 0 0 0 0 0 0 Tc-99m 0 0 0 0 0 0 0 0 Ag-11rn 0 0 0 0 0 0 0 0 Sb-124 0 0 0 0 0 0 0 0 1-131 0 0 0 0 0 0 0 0 1-133 0 0 0 0 0 0 0 0 1-135 0 0 0 0 0 0 0 0 Cs-134 0 0 0 0 0 0 0 0 Cs-1 37 0 0 0 0 0 0 0 0.

Ba-1 40 0 0 0 0 0 0 0 0 La-140 0 0 0 0 0 0 0 0 Ce-141 0 0 0 0 0 0 0 0 Ce-144 0 0 0 0 0 0 0 0 W-187 0 0 0 0 0 0 0 -~0 Np-239 0 0 0 0 0 0 0 -0 Rev. No. 9 Rev. o. A-I 9Page 6 of ODOM

TABLE A-3 (Continued)

A~tsh VALUES - LAKE SHORELINE DEPOSITS - INFANT (mremlhr per ijCI/mI)

NUCLIDET BONE LIVER [_THYROID___KIDNEY ILUNG GI-LLI SKIN [_T. BODY H-3 0 0 0 0 Na-24 0 0 0 0 Cr-5i 0 0 0 0 Mn-54 0 0 0 0 Fe-55 0 0 0 0 Fe-59 0 0 0 0 Co-57 0 0 0 0 Co-58 0 0 0 0 Co-60 0 0 0 0 Cu-64 0 0 0 0 Zn-65 0 0 0 0 Sr-89 0 0 0 0 Sr-90 0 0 0 0 Nb-95 0 0 0 0 Zr-95 0 0 0 0 As-76 0 0 0 0 Nb-95m .0 0 0 0 Zr-97 0 0 0 0 Mo-99 0 0 0 0 Tc-99m 0 0 0 0 Ag-1 1Om 0 0 0 0 Sb-i 24 0 0 0 0 1-131 0 0 0 0 1-133 0 0 0 0 1-135 0 0 0 0 Cs- 134 0 0 0 0 Cs-i37 0 0 0 0 Ba-i 40 0 0 0 0 La-i40 .0 0 0 0 Ce-i4i 0 0 0 0 Ce-i44 0 0 0 0 W-1i87 0 0 0 0 Np-239 0 0 0 0

-t .4 .4 1 4 .L ______________ ______________ A No. 9 R~-~ o. 9Page A-i 7 of ODC0`'ý

TABLE A-4 DERIVATION OF LIQUID DOSE FACTORS Table Page A-4.1 Dose Factor (j%) Derivation A-1 9 A-4.2 Parameters for the Liquid Effluent Pathway A-23 A-4.3 Justification for Liquid Pathways Used to A-25 Assess Dose to Man Rev. No. 9 A-1 8 of ODOM Rev. o. 9Page

TABLE A-4.1 LIQUID DOSE FACTOR (A.j DERIVATION For purposes of calculating the dose contribution to organs of various receptor age groups, a composite dose factor, N1 , may be used for each radionuclide i. The composite dose factor, A, is the sum of the freshwater fish, A6, potable water, A,,, and shoreline deposits pathway, AkhI dose factors. Aq embodies pathway transfer parameters (e.g., bioaccumulation factors),

pathway usage factors, organ dose conversion factors, and dilution factors between the release point and assumed point of exposure pathway. The composite dose factor may be expressed as:

(A-4. 1)

Ait = (K0 (UwID.) + K0 Uf BFIDf) DF, + (K0 Z W T, U~hIDsh ) (l&I -e-Th) DE1 Where:

Ad = is the composite dose parameter for the total body or organ of an age group for radionuclide, i, for all appropriate pathways, mrem/hr per pCi/mI.

K. = is a unit conversion factor, 1.14E5 yr-pCi-mI per pCi-hr-1 (NUREG-Ol 33).

U, = water consumption rate for age group of interest (Table A-4.2).

Ut = freshwater fish consumption rate for age group of interest (Table A-4.2).

Ush =duration of time an individual is located on the beach (Table A-4.2).

D = dilution factor which reflects the dilution from the point of release to the nearest potable water intake (Table A-4.2).

Df =dilution factor which reflects the dilution from the point of release to the nearest point assumed for the freshwater fish catch (Table A-4.2).

D~h = dilution factor which reflects the dilution from the point of release to the nearest point assumed for shoreline deposit (Table A-4.2).

BFj = bioaccumulation factor for radionuclide i, in freshwater fish, pCi/kg per pCi/I, from Table A-i of Regulatory Guide 1.109.

T1 = is the radiological half-life of radionuclide, i, in days.

Aj = is the radiological decay constant for radionuclide, i, in sec1 .

W = is the shoreline width factor (Table A-4.2).

Tb = the period of time for which sediment or soil is exposed to the contaminated water (Table A-4.2).

Rev. No. 9 Rev. o. 9Page A-I 9 of ODOM

K = assumed transfer constant from water to sediment, in liters/kg per hr as defined in Z.

IVI mass of sediment, in kg/rd of surface as defined in Z.

Z =K, x M,, x (24/.693), in I per rdf-day (Table A-4.2).

DF1 dose conversion factor for radionuclide, i, for organ and age group of interest. Used to calculate the radiation dose from an intake of a radionuclide, mremfpCi (Regulatory Guide 1.109, Tables E-1 1 to E-1 4).

DE, dose conversion factor for radionuclide, i, for organ and age group of interest. Used to calculate the radiation dose from an external exposure of a radionuclide, mrem/hr per pCi/rn2 (Regulatory Guide 1.109, Table E-6).

Example Calculation:

1. Potable Water The potable water pathway dose factor, k~, is calculated from Equation A-4.1 by setting the usage factors for freshwater fish and shoreline deposits equal to zero.

Equation A-4.1 reduces to the following:

Ai,= KO (UI/D,) DF1 For Co-60, the total body dose factor for an adult due to the ingestion of potable water is:

DE, 4.72E-06 mrem/pCi U=. 730 liters/yr D, 165 K, 1.14E5 yr-pCi-mI per pCi-hr-I These values yield an A~t factor of 2.38 mrem/hr per pCi/mI as listed in Table A-2 of this appendix.

Rev. No. 9 A-20 of ODCM Rev. o. 9Page

11. Freshwater Fish The freshwater fish pathway dose factor, i%, is calculated from Equation A-4.1 by t setting the usage factors for potable water and shoreline deposits equal to zero.

Equation A-4.1 reduces to the following:

A =t K (Uf BFID!) DF, For Co-60, the total body dose factor for an adult due to the ingestion of freshwater fish is:

DF, = 4.72E-06 mremfpCi Ur= 21 kg/yr Dr = 12 BF, = 50 pCi/kg per pCi/I K,= 1.14E5 yr-pCi-mi per pCi-hr-I These values yield an &f factor of 47.1 mrem/hr per pCi/mI as listed in Table A-2 of this appendix.

Ill. Lake Shoreline Deposits The shoreline deposits pathway dose factor, kh, is calculated from Equation A-4.1 by (

setting the usage factors for potable water and freshwater fish equal to zero. Equation A-4.1 reduces to the following:

Ai tsh = (K0, Z W T, U,,h/D.h) (l-eA"iTb) DE, For Co-60, the total body dose factor for an adult from shoreline deposits is:

USh =12 hrs/yr DO1 =18 W =0.30 T, 1.92E3 days Tb =15 years or 4.73E8 sec

(

Rev. No. -9 Rev. o. A-21 9Pageof ODOM

K. = 1.14E5 yr-pCi-ml per pCi-hr-I Z = 100 1per m2-day Ai = 4.2E-9 sec-'

DE1 = 1.70E-8 mrem/hr per pCilrr? (Regulatory Guide 1.109, Table E-6)

These values will yield and At~h factor of 64.2 mrem/hr per pCi/mI as listed in Table A-3 of this appendix.

Rev. No. 9 Rev. o. 9Page A-22 of ODCM

TABLE A-4.2 PARAMETER FOR THE LIQUID EFFLUENT PATHWAY PARAMETER VALUE REFERENCE TABLE U, (liters/yr)-Potable Water/

- infant 330 R.G. 1.109 E-5

- child 510 R.G. 1.109 E-5

- teen 510 R.G. 1.109 E-5

- adult 730 R.G. 1.109 E-5 Uf (kg/yr)-Freshwater Fish/

- infant 0 R.G. 1.109 E-5

- child 6.9 R.G. 1.109 E-5

- teen 16 R.G. 1.109 E-5

- adult 21 R.G. 1.109 E-5 Uh (hr/yr)-Lake Shoreline Deposits/

- infant 0 R.G. 1.109 E-5

- child 14 R.G. 1.109 E-5

- teen 67 R.G. 1.109 E-5

- adult 12 R.G. 1.109 E-5 BFI (pCi/kg per pCi/l)- Each R.G. 1.109 A-1 Freshwater Fish Rad ion uclide D,, (dimensionless)-'Potable 165 Site Specific Water (JAF FSAR Fig. 16.1-1 9)

Df (dimensionless)-Freshwater 12 Site Specific Fish (JAF FSAR Fig. 16.1-19)

Ds h (dimension less)-Lake 18 Site Specific Shoreline Deposits (JAF FSAR Fig. 16.1-19)

Rev. No. 9 Rev.No.9Page A-23 of 00CM

TABLE A-4.2 (Continued)

PARAMETER FOR THE LIQUID EFFLUENT PATHWAY PARAMETER VALUE REFERENCE TABLE DF, Potable Water/Freshwater Each R.G. 1.109 E-1 1 to Fish (mrem/pCi) Radionuclide E-14 DE, Lake Shoreline Deposits Each R.G. 1.109 E-6 (mrem/hr per pCi/rri) Radionuclide Z (I per m2?-day)-Lake 100 R.G. 1.109 pg-14 Shoreline Deposits W (dimensionless)-Lake 0.3 R.G. 1.109 A-2 Shoreline Deposits Tb (sec)-Lake Shoreline 4.73E8 R.G. 1.109 E-1 5 Deposits

Transit Time (hours)- 31 Site Specific Potable Water (Based on a current speed of 0.4 ft./sec JAF FSAR Fig. 16.1-1 9)

Transit Time (hours)- 0 Site Specific Freshwater Fish (JAF FSAR Fig. 16.1-119)

Consumption

Transit Time (hours)- 2.9 Site Specific Lake Shoreline Deposits (JAF FSAR Fig. 16.1-1 9)

Location of maximally exposed individual for potable water is Oswego, 8.5 miles west of JAF discharge. Location of maximally exposed individual for freshwater fish consumption is the JAF discharge vicinity. Location of maximally exposed individual for lake shoreline deposits is Sunset Bay, 0.8 miles east of JAF discharge.

Rev. No. -9 Rev. o. 9Page A-24 of ODCM

TABLE A-4.3 JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MANr PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION

1. POTABLE WATER This pathway is considered for all required analysis.

2. FRESHWATER FISH This pathway is considered for all required analysis.

3. FRESHWATER SHELL This pathway was not considered for the annual dose calculations and the 40CFR190 dose analysis.

Reference 6.9 states that direct ingestion of aquatic invertebrates from Lake Ontario is not a common practice.

4. FRESHWATER PLANTS No known pathway exists for the J.A. FitzPatrick plant and none is included in the dose analysis of References 6.5 through 6.8. Regulatory Guide 1.109, Appendix E, Section 2, page 1.109-36, states "Ingestion of aquatic plant material is not normally assumed."

5. SALTWATER FISH Not applicable to a freshwater site.

6. SALTWATER SHELL Not applicable to a freshwater site.

FISH

7. SALTWATER PLANTS Not applicable to a freshwater site. (

8. DISCHARGE CANAL This pathway is not applicable since the J.A. FitzPatrick Plant discharges through a tunnel SHORELINE to a diffuser offshore.

9. RIVER SHORELINE Not applicable to a Great Lake site.

DEPOSITS

10. LAKE SHORELINE This pathway is not necessary to demonstrate DEPOSITS compliance with 10CFR20 and 10CFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is considered for the annual dose calculations, the 400FR190 dose analysis, and Section 3.4.2.b (1).

11. OCEAN SHORELINE Not applicable to a Great Lake Site.

DEPOSITS Rev. No. -9 Rev. o. 9Page A-25 of ODOM

TABLE A-4.3 (Continued)

JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION

12. TIDAL BASIN Not applicable to a Great Lake site.

DEPOSITS

13. SWIMMING This pathway is not necessary to demonstrate compliance with I1OCFR20 and 1IOCFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is not used in the ODCM since its dose contribution is very small (Appendix D, Table D-8).

14. BOATING This pathway is not necessary to demonstrate compliance with 10CFR20 and 1IOCFR50 as specified in Sections 4.2, and 4.3.1 of NUREG-0133. This pathway is not used in the ODCM since its dose contribution is very small (See Appendix D, Table D-8).

15. STORED FRUITS There are two possible methods of establishing this AND VEGETABLES pathway; by using water from the lake for irrigation or using well water for irrigation, which may have become contaminated through discharges to the lake. References 6.6 and 6.7 document that a limited irrigation pathway exists; however, Reference 6.5 states that recent surveys indicate that the irrigation pathways discussed in the other documents no longer use lake water for irrigation. Since Reference 6.5 is the most recent document it is concluded that the irrigation pathway does not exist and need not be considered in any dose analysis.

References 6.5 through 6.8 state that the possibility of groundwater contamination is extremely remote and no impact on groundwater is expected.

16. FRESH FRUITS This pathway need not be considered.

AND VEGETABLES See justification for pathway 15.

17. MEAT (CONTAMI- This pathway need not be considered.

NATED FORAGE) See justification for pathway 15, Rev. No. -9 Rev. o. 9Page A-26 of ODCM

TABLE A-4.3 (Continued)

JUSTIFICATION FOR LIQUID PATHWAYS USED TO ASSESS DOSE TO MAN7 PATHWAY JUSTIFICATION FOR OMISSION OR INCLUSION

18. MEAT (CONTAMI- This pathway need not be considered.

NATED FEED) See Justification for pathway 15.

19. MEAT (CONTAMI- This pathway is not necessary to demonstrate NATED WATER) compliance with I OCFR20 and 10CFR50 as specified in Section 4.2 and 4.3.1 of N UREG-0 133. The dose calculations shown in References 6.5 through 6.8 do not consider this pathway as a part of the analysis; hence, it is concluded that this pathway is insignificant and need not be considered for annual and 40CFR190 dose calculations.

20. COWS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 15.

FORAGE)

21. COWS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 15.

FEED)

22. COWS MILK This pathway need not be considered.

(CONTAMINATED See justification for pathway 19. (.

WATER)

23. GOATS MILK This pathway need not be considered.

(CONTAM INATED See justification for pathway 15.

FORAGE)

24. GOATS MILK This pathway need not be considered.

(CONTAM INATED See justification for pathway 15.

FEED)

25. GOATS MILK This pathway need not be considered.

(CONTAM INATED See justification for pathway 19.

WATER)

Rev. No. -9 Rev. o. 9Page A-27 of ODCM

APPENDIX B GASEOUS DOSE CALCULATION DATA Rev. No. 9 B-I of ODOM Rev. o. 9Page

APPENDIX B GASEOUS DOSE CALCULATION DATA TABLE TITLE PAGE B-I Noble Gas Data Transfer Factors (lL)B-3 B-2 Air Dose Transfer Factors (Mi, N~) B-4 B-3 Inhalation Environmental Pathway Dose B-5 Conversion Factors (P1) - Limiting Age Groups -

Instantaneous B-4 Limited Analysis Approach - Limiting Age B-7 Groups and Pathways - Gaseous Discharge Environmental Pathway Dose Conversion Factors (Ri.)

B-5 Environmental Pathway Dose Conversion B-i 0 Factors (R-) for All Remaining Pathways B-6 Derivation of Gaseous Dose Factors B-30 Rev. No. 9 Rev.No.~Page B-2 of 00CM

TABLE B-I TRANSFER FACTORS FOR MAXIMUM DOSE TO A PERSON OFFSITE DUE TO RADIOACTIVE NOBLE GASES Dose Transfer Factors I GAMMA BETA GAMMA + BETA

.. AINCLD jL 1 (L + 1.1 M) i mrem mrern mrem

__________ iisec/mW e~k 3 pQC scm Kr-83m 2.4E-9 -- 6.7E-7 Kr-85m 3.7E-5 4.6E-5 8.9E-5 Kr-85 5.1IE-7 4.2E-5 4.3E-5 Kr-87 1.9E-4 3.1 E-4 5.3E-4 Kr-88 4.7E-4 7.5E-5 6.OE-4 Kr-89 5.3E-4 3.2E-4 9.3E-4 Kr-90 4.9E-4 2.3E-4 8.OE-4 Xe-1 31 m 2.9E-6 1.5E-5 2.OE-5 Xe-133m 8.OE-6 3.1lE-5 4.2E-5 Xe-133 9.3E-6 9.7E-6 2.2E-5 Xe-1 35m 9.9E-5 2.3E-5 I.4E-4 Xe-1 35 5.7E-5 5.9E-5 1.3E-4 Xe-I 37 4.5E-5 3.9E-4 4.4E-4 Xe-1 38 2.8E-4 1.3E-4 4.5E-4 Ar-41 2.8E-4 8.5E-5 4.OE-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-i.

Rev. No. 9 Rev. o. B-3 of ODOM

~Page

TABLE B-2 TRANSFER FACTORS FOR MAXIMUM OFFSITE AIR DOSE Air Dose Transfer Factors GQAMMA-BT RADIONUCIEm N1 3

mrad mrad 3 C c/ pCi sec/rn Kr-83m 6.1IE-7 9.1IE-6 Kr-85m 3.9E-5 6.2E-5 Kr-85 5.4E-7 6.2E-5 Kr-87 2.QE-4 3.3E-4 Kr-88 4.8E-4 9.3E-5 Kr-89 5.5E-4 3.4E-4 Kr-90 5.2E-4 2.5E-4 Xe-I 31m 4.9E-6 3.5E-5 Xe-133m 1.OE-5 4.7E-5 Xe-1 33 1.I1E-5 3.3E-5 Xe-1 35m 1.I1E-4 2-3E-5 (

Xe-1 35 6.1IE-5 7.8E-5 Xe-i 37 4.8E-5 4.OE-4 7 Xe-1 38 2-9E-4 1.5E-4 Ar-41 2.9E-4 I .OE-4 Ref: Regulatory Guide 1.109, Revision 1, Table B-I.

Rev. No. -9 Rev. o. 9Page B-4 of 00CM

T' ~N~33 Pi VALUES - INHALATION - CHILD mremlyr pCi/m3 NUCLIDE J BONE LIVER jTHYROID KIDNEY LUNG GI-LLI SKIN {T. BODY H-3 0 1.12E 03 1.12E203 1.12E 03 1.12E203 1.12E 03 0 1.12E203 Cr-51 0 0 8.55E 01 2.43E201 1.70E 04 1.08E 03 0 1.54E 02 Mri-54 0 4.29E 04 0 1.OOE 04 1.58E 06 2.29E 04 0 9.512E 03 Fe-55 4.74E 04 2.5E 04 0 0 1.1 1E 05 2.87E 03 0 7.77E 03 Fe-59 2.07E 04 3.34E 04 0 0 1.27E 06 7.072 04 0 1.67E 04 Co-57 0 9.03E 02 0 0 5.07E 05 1.32E 04 0 1.07E 03 Co-58 0 1.77E203 0 0 1.11 E06 3.44E 04 0 3.16E 03 Co-60 0 1.31 E 04 0 0 7.07E 06 9.622 04 0 2.26E 04 Zn-65 4.26E 04 1.132 05 0, 7.14E 04 9.95E 05 1.63E 04 0 7.03E 04.

Sr-89 5.99E205 0 0 0 2.16E 06 1.67E 05 0 1.72E 04 Sr-90 1.01 E08 0 0 0 1.48E 07 3.43E 05 0 6.44E206 Zr-95 1.90E 05 4.18E 04 0 5.96E 04 2.23E 06 6.11IE 04 0 3.70E 04 Nb-95 2.35E 04 9.18E 03 0 8.62E 03 6.14E 05 3.70E 04 0 6.55E 03 Mo-99 0 1.72E 02 0 3.92E 02 1.35E 05 1.272 05 0 4.125E 01 Ag-11rn 1.69E204 1.14E 04 0 2.12E 04 5.48E206 1.00E 05 0 9.14E 03 Sb-I 24 5.74E 04 7.40E 02 1.26E 02 0 3.24E 06 1.64E 05 0 2.OOE 04 1-131 4.812E 04 4.81IE 04 1.622 07 7.88E 04 0 2.84E 03 0 2.73E 04 1-133 1.66E 04 2.03E 04 3.85E 06 3.38E 04 0 5.48E 03 0 7.70E 03 1-135 4.92E 03 8.73E 03 7.92E 05 1.34E 04 0 4.44E 03 0 4.14E 03 Cs-1 34 6.51 E05 1.012E06 0 3.30E,05 1.21E05 3.85E203 0 2.25E 05 Cs-136 6.512E04 1.71 E05 0 9.55E 04 1.45E204 4.18E 03 0 1.16E 05 Cs-i 37 9.07E 05 8.25E 05 0 2.82E 05 1.04E 05 3.62E 03 0 1.28E 05 Ba-140 7.40E 04 6.48E 01 0 2.11IE 01 1.74E 06 1.02E 05 0 4.33E 03 La-140 6.44E 02 2.25E 02 0 0 1.83E 05 2.26E 05 0 7.55E 01 Ce-1 41 3.92E 04 1.95E 04 0 8.55E 03 5.44E 05 5.66E 04 0 2.90E 03 Ce-144 6.77E206 2.12E 06 0 1.17E 06 1.20E 07 3.89E 05 0 3.61 E05 Rev. No. 9 Rev. o. 9Page B-5 of ODCM

TABLE B-3 (Continued)

P, VALUES - INHALATION - TEEN mremlyr 3

pCi/M

.NUCLIDE BONE I LIVER THYROIDjKNE LUNG ... SI ...

H-3 0 1.27E 03 1.27E 03 1.27E 03 1.27E 03 1.27E 03 0 1.27E 03 Cr-5I 0 0 7.50E 01 3.07E 01 2.10E 04 3.00E 03 0 1.35E 02 Mn-54 0 5.11IE 04 0 1.27E 04 1.98E 06 6.68E 04 0 8.40E 03 Fe-55 3.34E 04 2.38E 04 0 0 1.24E 05 6.39E 03 0 5.54E 03 Fe-59 1.59E 04 3.70E 04 0 0 1.53E 06 1.78E 05 0 1.43E 04 Co-57 0 9.44E 02 0 0 5.86E 05 3.14E 04 0 9.20E 02 Co-58 0 2.07E 03 0 0 1.34E 06 9.52E 04 0 2.78E 03 Co-60 0 1.51 E04 0 '08.72E 06 2.59E 05 0 1.98E 04 Zn-65 3.86E 04 1.34E 05 0 8.64E 04 1.24E 06 4.66E 04 0 6.24E 04 Sr-89 4.34E 05 0 0 0 2.42E 06 3.71 E 05 0 1.25E 04 Sr-90 I1.08E 08 0 0 0 1.65E 07 7.65E 05 0 6.68E 06 Zr-95 1.46E 05 4.58E 04 0 6.74E 04 2.69E 06 1.49E 05 0 3.15E 04 Nb-95 1.86E 04 1.03E 04 0 1.OOE 04 7.51 E 05 9.68E 04 0 5.66E 03 Mo-99 0 1.69E 02 0 4.I11E 02 1.54E 05 2.69E 05 0 3.22E 01 Ag-1I Om 1.38E 04 1.31 E04 0 2.50E 04 6.75E 06 2.73E 05 0 7.99E 03 Sb-124 4.30E 04 7.94E 02 9.76E 01 0 3.85E 06 3.98E 05 0 1.68E 04 1-131 3.54E 04 4.91 E 04 1.46E 07 8.40E 04 0 6.49E 03 0 2.64E 04 1-133 1.22E 04 2.05E'04 2.92E 06 3.59E 04 0 1.03E 04 0 6.22E 03 1-135 3.70E 03 9.44E 03 6.21 E 05 1.49E 04 0 6.95E 03 0 3.49E 03 Cs-134 5.02E 05 1.13E 06 0 3.75E 05 1.46E 05 9.76E 03 0 5.49E 05 Cs-136 5.15E 04 1.94E 05 0 1.10E 05 1.78E 04 1.09E 04 0 1.37E 05 Cs-I 37 6.70E 05 8.48E 05 0 3.04E 05 1.21 E 05 8.48E 03 0 3.11IE 05 Ba-140 5.47E 04 6.70E 01 0 2.28E 01 2.03E 06 2.29E 05 0 3.52E 03 La-140 4.79E 02 2.36E 02 0 0 2.14E 05 4.87E 05 0 6.26E 01 Ce-141 2.84E 04 1.90E 04 0 8.88E 03 6.14E 05 1.26E 05 0 2.17E 03 Ce-144 I4.89E 06 2.02E 06 0 1.21 E 06 1.34E 07 8.64E 05 0 2.62E 05 No. 9 No 9Page B-6of ODr

T 'r-3.4 Ill VALUES - COW MILK - INFANT rn-rn rem/yr jjCilsec NUCLIDE] BONE ] LIVER. THYROID ]KIDNEY. . LUNG. 4. GI-LLI*. SKIN .j T.:1ODY H-3* 0 2.38E 03 2.38E 03 2.38E 03 2.38E 03 2.38E 03 0 2.38E 03 Cr-5I 0 0 5.45E 04 1.19E 04 1.06E 05 2.43E 06 0 8.35E 04 Mn-54 0 2.51 E 07 0 5.56E 06 0 9.22E 06 0 5.69E 06 Fe-55 8.98E 07 5.80E 07 0- 0 2.83E 07 .7.36E 06 0 1.55E 07 Fe-59 1.22E 08 2.13E 08 0 0 6.29E 07 1.02E 08 0 8.39E 07 Co-57 0 5.72E 06 0 0 0 1.95E 07 0 9.30E 06 Co-58 0 1.39E 07 0 0 0 3.46E 07 0 3.47E 07 Co-60 0 5.90E 07 0 0 0 1.40E 08 0 1.39E 08 Zn-65 3.53E 09 1.21E 10 0 5.87E 09 0 1.02E 10 0 5.58E 09 Sr-89 6.93E 09 0 0 0 0 1.42E 08 0 1.99E 08 Sr-90 8.19E 10 0 0 0 0 1.02E 09 0 2.09E 10 Zr-95 3.85E 03 9.39E 02 0 1.01 E 03 0 4.68E 05 0 6.66E 02 Nb-95 3.14E 05 1.29E 05 0 9.27E 04 0 1.09E 08 0 7.48E 04 Mo-99 0 1.04E 08 0 1.55E 08 0 3.42E 07 0 2.02E 07 Ag-Ib0m 2.46E 08 1.79E 08 0 2.56E 08 0 9.3012 09 0 1.19E 08 Sb-124 1.18E 08 1.73E 06 3.13E 05 0 7.37E 07 3.63E 08 0 3.65E 07 1-131 1.36E 09 1.60E 09 5.27E 11 1.87E 09 0 5.72E 07 0 7.05E 08 1-133 1.84E 07 2.67E 07 4.86E 09 3.14E 07. 0 4.52E 06 0 7.83E 06 1-135 5.65E 04 1.12E 05 1.01 E07 1.25E 05 0 4.07E 04 0 4.1OE 04 Cs-1 34 2.41E 10 4.50E 10 0 1.16E 10 4.75E 09 1.22E 08 0 4.54E 09 Cs- 136 9.91 E08 2.91 E09 0 1.16E 09 2.37E 08 4.42E 07 0 1.09E 09 Cs-137 3.47E 10 4.06E 10 0 1.09E 10 4.41 E09 1.27E 08 0 2.88E 09 Ba-1 40 1.21 E 08 1.21 E 05 0 2.87E 04 7.42E 04 2.97E 07 0 6.23E 06 La-140 2,03E 01 8.01EO00 0 0 0 9.41 E04 0 2.06E 00 Ce-141 2.28E 04 1.39E, 04 0 4.29E 03 0 7.18E 06 0 1.64E 03 Ce-1 44 1.49E 06 6.10E 05 0 2.46E, 05 0 8.55E 07 0 8.35E 04

mremfyr pCi/rn 3 Rev. No. 9 Rev. o. 9Page B-7 of ODCM

TABLE B-4 (Continued)

R,VALUES - GOAT MILK - INFANT pCi/sec NU CLJDE I BONE I LIVER THYROID [_KIDNEY LUNG J GI-ILI SKIN T. BOD :Y H-3* 0 4.86E 03 4.86E 03 4.86E 03 4.86E 03 4.86E 03 0 4.86E 03 Cr-51 0 0 6.54E 03 1.43E 03 1.27E 04 2.92E 05 0 1.OOE 04 Mn-54 0 3.01 E06 0 6.67E 05 0 1.11E 06 0 6.82E 05 Fe-55 1.17E 06 7.54E 05 0 0 3.69E 05 9.57E 04 0 2.01IE 05 Fe-59 1.58E 06 2.77E 06 0 0 8.18E 05 1.32E 06 0 1.091106 Co-57 0 6.86E 05 0 0 0 2.34E 06 0 1.121106 Co-58 0 1.67E 06 0 0 0 4.15E 06 0 4.16E,06 Co-60 0 7.08E 06 0 0 0 1.69E 07 0 1.67E 07 Zn-65 4.23E 08 1.45E 09 0 7.04E 08 0 1.23E, 09 0 6.70E 08 Sr-89 1.46E 10 0 0 0 0 2.99E 08 0 4.17E 08 Sr-90 1.72E 11 0 0 0 0 2.15E 09 0 4.38E 10 Zr-95 4.63E 02 1.13E 02 0 1.21 E02 0 5.61 E04 0 7.99E 01 Nb-95 3.77E 04 1.55E 04 0 1.11 E04 0 1.31 E07 0 8.97E 03 Mo-99 0 1.25E 07 0 1.86E 07 0 4.10E 06 0 2.43E 06 Ag- IOrn 2.95E 07 2.15E 07 0 3.08E 07 0 1.12E 09 0 1.42E 07 Sb-124 1.41 E 07 2.08E 05 3.75E 04 0 8.85E 06 4.36E, 07 0 4.38E 06 1-131 1.63E 09 1.92E 09 6.32E 11 2.25E 09 0 6.86E 07 0 8.45E 08 1-133 2.20E 07 3.21 E 07 5.84E 09 3.77E 07 0 5.43E 06 0 9.40E 06 1-135 6.78E 04 1.35E 05 1.21 E 07 1.50E 05 0 4.88E 04 0 4.92E 04 Cs-I 34 7.24E 10 1.35E I11 0 3.47E 10 1.42E 10 3.67E 08 0 1.36E 10 Cs-I 36 2.97E 09 8.74E 09 0 3.48E 09 7.12E 08 1.33E 08 0 3.26E 09 Cs-137 1.04E 11 1.22E 11 0 3.27E 10 1.32E 10 3.81 E 08 0 8.63E 09 Ba-140 1.45E 07 1.45E 04 0 3.44E 03 8.91 E 03 3.56E 06 0 7.47E 05 La-1 40 2,44E 00 9.61 E-01 0 0 0 1,13E 04 0 2,47E-01 Ce-141 2.73E 03 1.67E 03 0 5.14E 02 0 8.62E 05 0 1.96E 02 Ce-144 1.79E 05 7.32E 04 0 2.96E 04 0 1.03E 07 0 I.OOE 04

mrem/yr 3

pCi/rn F' ' No. 9 FNo.9 B-8 (7>Page of OlD(

TABLE )"ntinued)

R, VALUES - VEGETATION - CHILD m2_mremlyr pCilsec NUCLIDE j BONE j LIVER _THYROID KINYLUNG GI-LLI SKIN JT. BODY H-3* 0 4.01 E03 4.01 E03 4.01 E03 4.01E 03 4.01 E03 0 4.01 E03 Cr-51 0 0 6.49E 04 1.77E 04 1.18E 05 6.20E 06 0 1.17E 05 Mn-54 0 6.65E 08 0 1.86E 08 0 5.58E 08 0 1.77E 08 Fe-55 8.01 E 08 4.25E 08 0 0 2.40E 08 7.87E 07 0 1.32E 08 Fe-59 3.97E 08 6.42E 08 0 0 1.86E 08 6.69E 08 0 3.20E 08 Co-57 0 2.98E 07 0 0 0 2.44E 08 0 6.04E 07 Co-58 0 6.45E 07 0 0 0 3.76E 08 0 1.97E 08 Co-60 0 3.78E 08 0 0 0 2.10E 09 0 1.12E 09 Zn-65 8.12E 08 2.16E 09 0 1.36E 09 0 3.80E 08 0 1.35E 09 Sr-89 3.59E 10 0 0 0 0 1.39E 09 0 1.03E 09 Sr-90 1.24E 12 0 0 0 0 1.67E 10 0 3.15E 11 Zr-95 3.86E 06 8.50E 05 0 1.22E106 0 8.86E 08 0 7.56E 05 Nb-95 4.1OE 05 1.60E 05 0 1.50E 05 0 2.95E 08 0 1.14E 05 Mo-99 0 7.70E 06 0 .1.64E 07 0 6.37E 06 0 1.91 E 06 Ag-Ib0m 3.21 E 07 2.17E 07 0 4.04E 07 0 2.58E 09 0 1.74E 07 Sb-1 24 3.52E 08 4.57E 06 7.78E 05 0 1.95E 08 2.20E 09 0 1.231108 1-131 1.43E 08 1.44E 08 4.75E 10 2.36E 08 0 1.28E 07 0 8.17E 07 1-133 3.56E 06 4.41 E06 8.19E 08 7.34E 06 0 1.78E 06 0 1.67E 06 1-135 6.28E 04 1.13E 05 1.00E 07 1.73E 05 0 8.61 E04 0 5.34E 04 Cs-I 34 1.60E 10 2.63E 10 0 8.16E 09 2.93E 09 1.42E 08 0 5.55E 09 Cs-136 8.23E 07 2.26E 08 0 1.21 E 08 1.80E 07 7.95E 06 0 1.46E, 08 Cs-1 37 2.39E 10 2.29E 10 0 7.46E 09 2.68E 09 1.43E 08 0 3.38E 09 Ba-140 2.77E 08 2.43E 05 0 7.90E 04 1.45E 05 1.40E 08 0 1.62E 07 La-140 3.25E 03, 1.14E 03 0 0 0 3.17E 07 0 3.83E 02 Ce-141 6.56E 05 3.27E 05 0 1.43E 05 0 4.08E 08 0 4.85E 04 Ce-1 44 1.27E 08 3.98E 07 1 0 2.21 E 07 0 1.04E, 10 0 6.78E 06

mrem/yr pCi/rn3 Rev. No. 9 Rev. o. 9Page B-9 of ODCM

TABLF R, VALUES - GROUND PLANE - ADULT m2_mremlyr pjCilsec NUCLIDE J BONE J LIVER THYROID- KIDNEY__ LUNG GI-LLI SKNT. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E, 08 7.46E, 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51 E04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E, 08 2.45E 08 2.451108 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61 E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-ib0m 3.45E, 09 3.45E 09 3.45E 09 3.45E, 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-124 5.99E, 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 .6.92E 08 5.99E 08 1-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1,72E.07 2.09E 07 1.72E 07 1-133 2.46E 06 2.46E, 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.OOE 06 2.46E 06 1-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-I 34 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 Cs-1 36 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.71 E08 1.51 E08 Cs-1 37 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10 Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 La-1 40 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 1.92E 07 2.18E,07 1.92E 07 Ce- 141 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.54E 07 1.37E 07 Ce-144 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 8.05E 07 6.96E 07 Rev. No. 9 9Page B-1 Rev.

o. of ODOM

TABLE TABLE bntinued)

J Ri VAL UES - INHALATION - ADULT mrem/yr 3

pCinM NUCLIDE BONE LIVER JTHYROID[ KIDNEY__._LUNG GILL ( SKIN T. BODY H-3 0 1,26E 03 1.26E 03 1.26E 03 1.26E 03 1.26E 03 0 1.26E 03 Cr-Si 0 0 5.95E 01 2.28E 01 1.44E 04 3.32E 03 0 1.00E 02 Mn-54 0 3.96E 04 0 9.84E 03 1.40E 06 7.74E 04 0 6.30E 03 Fe-55 2.46E 04 1.70E 04 0 0 7.21 E 04 6.03E 03 0 3.94E 03 Fe-59 1.18E 04 2.78E 04 0 0 1.02E206 1.88E 05 0 1.06E204 Co-57 0 6.92E 02 0 0 3.69E 05 3.14E 04 0 6.71 E 02 Co-58 0 1.582 03 0 0 9.28E 05 1.06E 05 0 2 .07E 03 Co-60 0 1.15E204 0 0 5.97E 06 2.85E 05 0 1.48E204 Zn-65 3.242 04 1.03E 05 0 6.90E 04 8.642 05 5.34E 04 0 4.66E 04 Sr-89 3.04E 05 0 0 0 1.40E 06 3.50E 05 0 8.72E 03 Sr-90 9.92E 01' 0 0 0 9.60E 06 7.22E 05 0 6.10OE 06 Zr-95 1.07E 05 3.44E 04 0 5.42E 04 1.77E 06 1.50E 05 0 2.33E 04 Nb-95 1.412E 04 7.82E- 03 0 7.74E 03 5.05E 05 1.04E 05 0 4'21E 03 Mo-99 0 1.21iE 02 0 2.91 E 02 9.12E 04 2.48E 05 0 2.30E 01 Ag-l Om 1.08E 04 1.OOE 04 0 1.97E 04 4.63E 06 3.02E 05 0 5.94E 03 Sb-I 24 3.12E 04 5.89E 02 7.55E 01 0 2.48E 06 4.06E 05 0 1.24E 04 1-131 2.52E 04 3.58E 04 1.19E 07 6.132 04 0 6.28E 03 0 2.05E 04 1-133 8.64E 03 1.48E 04 2.15E 06 2.58E 04 0 8.88E 03 0 4.522 03 1-135 2.68E203 6.98E203 4.48E205 1.11 E04 0 5.25E 03 0 2.57E203 Cs-i 34 3.732 05 8.48E 05 0 2.87E205 9.76E 04 1.04E 04 0 7.28E205 Cs-1 36 3.90E 04 1.46E205 0 8.56E204 1.20E 04 1.17E204 0 1.10E205 Cs-i 37 4.78E205 6.212E 05 0 2.222 05 7.522 04 8.402 03 0 4.28E205 Ba-i40 3.90E 04 4.902 01 0 1.672 01 1.27E206 2.182 05 0 2.57E 03 La-140 3.442 02 1."742 02 0 0 1.*362 05 4.582 05 0 4.582 01 Ce-141 1.99E 04 1.352 04 0 6.262 03 3.62E 05 1.202 05 0 1.532 03 Ce-144 3.432 06 1.432 06 0 8.482 05 7.782 06 8.162 05 0 1.842 05 Rev. No. 9 Rev. o. 9Page B-I 1 of ODOM

TABLE B-5 (Continued)

R,VALUES - VEGETATION - ADULT m -_mremlyr pCilsec NUCLIDE BON E j LIVER* THYROID KIDNEY LUNG...........[ KIN.....T BODYý H-3* 0 2.25E 03 2.25E 03 2.25E 03 2.25E 03 2.25E 03 0 2.25E 03 Cr-51 0 0 2.77E 04 1.02E 04 6.15E 04 1.17E 07 0 4.64E 04 Mn-54 0 3.13E 08 0 9.31 E 07 0 9.58E 08 0 5.97E 07 Fe-55 2.10OE 08 1.45E 08 0 0 '8.08E 07 8.31 E 07 0 3.38E 07 Fe-59 1.26E 08 2.96E 08 0 0 8.27E 07 9.87E 08 0 1.13E 08 Co-57 0 1.17E 07 0 0 0 2.97E 08 0 1.94E 07 Co-58 0 3.08E 07 0 0 0 6.24E 08 0 6.90E 07 Co-60 0 1.67E 08 0 0 0 3.14E 09 0 3.69E 08 Zn-65 3.17E 08 1.01 E 09 0 6.75E 08 0 6.36E 08 0 4.56E 08 Sr-89 9.95E 09 0 0 0 0 1.60E 09 0 2.86E 08 Sr-90 6.05E 11 0 0 0 0 1.75E 10 0 1.48E 11 Zr-95 1.18E 06 3.77E 05 0 5.92E 05 0 1.20E 09 0 2.55E 05 Nb-95 1.42E 05 7.91 E 04 0 7.82E 04 0 4.80E 08 0 4.25E 04 Mo-99 0 6.14E 06 0 1.39E 07 0 1.42E 07 0 1.17E 06 Ag-Ib0m 1.05E 07 9.75E 06 0 1.92E 07 0 3.98E 09 0 5.79E 06 Sb-I 24 1.04E 08 1.96E 06 2.52E 05 0 8.08E 07 2.94E 09 0 4.12E 07 1-131 8.07E 07 1.15E 08 3.78E 10 1.98E 08 0 3.05E 07 0 6.62E 07 1-133 2.1IOE 06 3.66E 06 5.38E 08 6.39E 06 0 3.29E 06 0 1.12E 06 1-135 3.91 E04 1.02E 05 6.75E 06 1.64E 05 0 1.16E 05 0 3.78E 04 Cs-134 4.67E 09 I.I1E 10 0 3.60E 09 1.19E 09 1.94E 08 0 9.08E 09 Cs-136 4.26E 07 1.68E 08 0 9-37E 07 1.28E 07 1.91 E07 0 1.21 E08 Cs-I 37 6.36E 09 8.70E 09 0 2.95E 09 9.81 E 08 1.68E 08 0 5.70E 09 Ba-1 40 1.29E 08 1.61 E 05 0 5.49E 04 9.25E 04 2.65E 08 0 8.42E 06 La-140 1,.98E 03 9,99E 02 0 0 0 7,33E 07 0 2,64E 02 Ce-141 1.97E 05 1.33E 05 0 6.19E 04 0 5.09E 08 0 1.51 E04 Ce-144. 3.29E 07 1.38E 07 0 8.16E 06 0 1.11E 10 0 1.77E 06

mrem/vr 3

pCi/rn No. 9 II Page B-1 2 of MrC

TABLE bntinued)

R,VALUES - COW MEAT -ADULT m 2-mremlyr pCi/sec NUCLIDE BONE LIVER THYROID KIDNEY LUNG GI-ILI SKIN _T.. BODY.

H-3* 0 3.24E 02 3.24E 02 3.24E 02 3.24E 02 3.24E 02 0 3.24E 02 Cr-5I 0 0 2.181103 8.04E 02 4.84E 03 9.18E 05 0 3.65E 03 Mn-54 0 5.90E 06 0 1.76E 06 0 1.81 E07 0 1.13E 06 Fe-55 1.95E 08 1.35E 08 0 0 7.51 E 07 7.72E 07 0 3.14E 07 Fe-59 1.44E 08 3.39E 08 0 0 9.46E 07 1.13E 09 0 1.30E 08 Co-57 0 3.60E 06 0 0 0 9.14E 07 0 5.99E 06 Co-58 0 1.04E207 0 0 0 2.12E 08 0 2.34E 07 Co-60 0 5.03E 07 0 0 0 9.46E 08 0 1.11 E08 Zn-65 2.26E 08 7.19E 08 0 4.8 1E 08 0 4.53E 08 0 3.25E 08 Sr-89 1.66E 08 0 0 0 0 2.66E 07 0 4.76E 06 Sr-90 8.38E 09 0 0 0 0 2.42E 08 0 2.06E 09 Zr-95 1.06E 06 3.40E 05 0 5.34E 05 0 1.08E 09 0 2.30E 05 Nb-95 1.22E 06 6.76E 05 0 6.68E 05 0 4.102E 09 0 3.64E 05 Mo-99 0 4.96E 04 0 1.12E 05 0 1.15E 05 0 9.44E 03 Ag-lI Om 4.25E 06 3.94E 06 0 7.74E 06 0 1.61 E09 0 2.34E 06 Sb-124 1.11 E07 2.1OE 05 2.70E 04 0 8.67E 06 3.16E208 0 4.41 E06 1-131 5.37E 06 7.68E 06 2.52E 09 1.32E 07 0 2.03E 06 0 4.40E 06 1-133 1.99E-01 3.46E-01 5.09E 01 6.04E-01 0 3.11 E-01 0 1.05E-01 1-135 2.33E-17 6.1IOE-1 7 4.02E-1 5 9.77E-17 0 6.88E-1 7 0 2.25E-17 Cs-134 4.35E 08 1.03E 09 0 3.35E208 1.11 E08 1.81 E07 0 8.46E 08 Cs-i 36 6.04E 06 2.38E 07 0 1.33E 07 1.82E 06 2.71 E 06 0 1.72E 07 Cs-i 37 5.88E 08 8.04E 08 0 2.73E208 9.07E 07 1.56E 07 0 5.27E 08 Ba-140 1.44E 07 1.812E 04 0 6.16E 03 1.04E 04 2.97E 07 0 9.44E 05 La-140 1.*88E-02 9,48E-03 0 0 0 6.96E 02 0 2.50E-03 Ce-141 7.38E 03 4.992 03 0 2.322 03 0 1.91 E 07 0 5.66E 02 Ce-1 44 9.34E 05 3.902 05 0 2.32E 05 0 3.16E 08 0 5.01 E 04

mrem/yr 3

pCi/rn Rev. No.. 9 Rev. No. 9Page B-I13 of ODCM

TABLE B-5 (Continued)

R1 VALUES -COW MILK -ADULT m2 -mremlyr pCilsec NUCLIDE] BONE LIVER THYROID KNE J LUGILI._ .SK. T BODY H-3* 0 7.63E 02 7 *63E 02 7-63E 02 7.63E 02 7.63E 02 0 7.63E 02 Cr-5I 0 0 8.85E 03 3.26E 03 1.96E 04 3.72E 06 0 1.481104 Mn-54 0 5.41 E06 0 1.61 E06 0 1.66E 07 0 1.03E 06 Fe-55 1.67E 07 1.15E 07 0 0 6.43E 06 6.61 E 06 0 2.69E 06 Fe-59 1.61E 07 3.79E 07 0 0 1.06E 07 1.26E 08 0 1.45E 07 Co-57 0 8.18E 05 0 0 0 2.07E 07 0 1.36E 06 Co-58 0 2.70E 06 0 0 0 5.47E 07 0 6.05E 06 Co-60 0 1.10E 07 0 0 0 2.06E 08 0 2.42E 07 Zn-65 8.72E 08 2.77E 09 0 1.86E 09 0 1.75E 09 0 1.25E 09 Sr-89 7.99E 08 0 0 0 0 1.28E 08 0 2.29E 07 Sr-90 3.15E 10 0 0 0 0 9.11 E08 0 7.74E 09 Zr-95 5.34E 02 1.71 E 02 0 2.69E 02 0 5.43E 05 0 1.16E 02 Nb-95 4.37E 04 2.43E 04 0 2.40E 04 0 1.48E 08 0 1.31 E 04 Mo-99 0 1.24E 07 0 2.80E 07 0 2.87E 07 0 2.35E 06 Ag- I Om 3.71 E 07 3.43E 07 0 6.74E 07 0 1.40E 10 0 2.04E 07 Sb-124 1.45E 07 2.73E 05 3.51 E04 0 1.13E 07 4.11 E08 0 5.74E 06 1-131 1.48E 08 2.12E 08 6.94E 10 3-63E 08 0 5.59E 07 0 1.21 E08 1-133 1.96E 06 3.41 E 06 5.01IE 08 5.95E 06 0 3.06E 06 0 1.041106 1-135 6.46E 03 1.69E 04 1.12E 06 2.71 E04 0 1.91 E04 0 6.24E 03 Cs-I 34 3.74E 09 8.89E 09 0 2.88E 09 9.55E 08 1.56E 08 0 7.27E 09 Cs-i 36 1.32E 08 5.21 E 08 0 2.90E 08 3.97E 07 5.92E 07 0 3.75E 08 Cs-I 37 4.98E 09 6.80E 09 0 2.31 E 09 7.68E 08 1.32E 08 0 4.46E 09 Ba-140 1.35E 07 1.69E 04 0 5.76E 03 9.69E 03 2.78E 07 0 8.83E 05 La-140 2.26E 00 1.14E 00 0 0 0 8.37E 04 0 3.01 E-01.

Ce-141 2.55E 03 1.72E 03 0 8.OOE 02 0 6.58E 06 0 1.95E 02 Ce-144 2.29E 05 9.58E 04 0 5.68E 04 0 7.75E 07 0 1.23E 04

mrem/yr pCi/rn 3

( ', No. 9 No.

Page 9 B-14 of ODr

TABLE " ontinued)

R, VALUES - GOAT MILK - ADULT 2

m -mremlyr pCi/sec NUCLDEBNE LIVR fTHYROID JKIDNEY__ LUNG G GILLI SKIN,.BD H-3* 0 1.56E 03 1.56E 03 1.56E 03 1.56E 03 1.56E 03 0 1.56E 03 Cr-5i 0 0 1.06E 03 3.91 E 02 2.36E 03 4.47E 05 0 1.78E 03 Mn-54 0 6.49E205 0 1.93E205 0 1.99E 06 0 1.24E 05 Fe-55 2.17E 05 1.50E 05 0 0 8.36E 04 8.60E 04 0 3.49E 04 Fe-59 2.10E 05 4.93E205 0 0 1.38E 05 1.64E 06 0 1.89E 05 Co-57 0 9.812E04 0 0 0 2.49E 06 0 1.63E205 Co-58 0 3.24E 05 0 0 0 6.57E 06 0 7.27E 05 Co-60 0 1.32E 06 0 0 0 2.48E 07 0 2.91 E 06 Zn-65 1.05E 08 3.33E 08 0 2.23E208 0 2.10E 08 0 1.50E 08 Sr-89 1.68E 09 0 0 0 0 2.69E 08 0 4.812E 07 Sr-90 6.62E 10 0 0 0 0 1.91 E09 0 1.63E210' Zr-95 6.41 E01 2.06E 01 0 3.23E201 0 6.52E204 0 1.39E 01 Nb-95 5.24E 03 2.922 03 0 2.882 03 0 1.77E 07 0 1.572 03 Mo-99 0 1.482 06 0 3.362 06 0 3.44E 06 0 2.822 05 Ag-1I Om 4.45E206 4.112E06 0 8.09E206 0 1.68E209 0 2.44206 Sb-124 .1.74E 06 3.28E 04 4.21 E 03 0 1.352 06 4.93E 07 0 6.892 05 1-131 1.78E 08 2.54E 08 8.33E 10 4.362 08 0 6.70E 07 0 1.462 08 1-133 2.352 06 4.092 06 6.012E08 7.142 06 0 3.682 06 0 1.25E 06 1-135 7.75E 03 2.032 04 1.342 06 3.252 04 0 2.292 04 0 7.49E 03 Cs-134 1.122 10 2.67E 10 0 8.642 09 2.87E 09 4.67E 08 0 2.182 10 Cs-1 36 3.962 08 1.56E209 0 8.70E208 1.19E 08 1.78E 08 0 1.13E209 Cs-i 37 1.49E 10 2.042 10 0 6.932 09 2.302 09 3.95E 08 0 1.34E 10 Ba-140 1.622 06 2.03E 03 0 6.912E02 1.16E 03 3.33E 06 0 1.062 05 La-140 2.71 E-01 I1.37E-01 0 0 0 1.002 04 0 3,612E-02 Ce-141 3.06E 02 2.07E 02 0 9.60E 01 0 7.90E 05 0 2.342 01 Ce-144 2.75E 04 1.152 04 0 6.82E203 0 9.302 06 0 1.48E 03

mrem/vr 3

pCi/rn Rev. No.. 9 B-1 5 of ODOM Rev.No.9Page

TABLE B-5 (Continued)

R, VALUES - GROUND PLANE - TEEN m2_mrem/yr pCi/sec NUCLIDE BOE LIVER THYROID JKIDNEY LUNG GI-LLI F SKIN T. BODY H-3 0 0 0 0 0 0 0 0 Cr-51 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 I1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E.09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 1.88E 08 I1.88E 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2 .16E 04 2.16E 04 2.16E 04 2.16E 04 2.51 E04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.37E 08 1.61 E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-I 1Om 3.45E 09 3,45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-I 24 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 1-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 1-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.OOE 06 2.46E 06 1-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-I 34 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 Cs-1 36 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.71 E08 1.51 E08 Cs-1 37 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10 Ba-140 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 La-140 I,92E 07 I,92E 07 1,92E 07 1,92E 07 1,92E 07 1.912E 07 2,18E 07 1I.92E 07 Ce-1 41 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.37E 07 1.54E 07 1.37E 07 Ce-144 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 6.96E 07 8.05E 07 6.96E 07 I No.. 9 B-1 6 of ODO>'

No. 9Page

TABI-r 'ontinued)

RVALUES - INHALATION - TEEN mrem/yr pCi/rn3 NUCLIDE j BONE J LIVER. FTHYROID KIDNEY__ LUNG J GI-LLI SKIN _T. BODY H-3 0 1.27E 03 1.272 03 1.27E 03 1.27E 03 1.27E 03 0 1.27E 03 Cr-51 0 0 7.50E201 3.07E 01 2.10E204 3.00E 03 0 1.35E202 Mn-54 0 5.112E 04 0 1.27E 04 1.98E 06 6.682 04 0 8.402 03 Fe-55 3.342 04 2.382 04 0 0 1.24E 05 6.392 03 0 5.54E 03 Fe-59 1.592 04 3.702 04 0 0 1.53E 06 1.782 05 0 1.432 04 Co-57 0 9.442 02 0 0 5.862 05 3.142 04 0 9.20E 02 Co-58 0 2.072 03 0 0 1.342 06 9.522 04 0 2.78E 03 Co-60 0 1.512E04 0 0 8.72E 06 2.59E 05 0 1.98E 04 Zn-65 3.862 04 1.342 05 0 8.642 04 1.24E 06 4.66E 04 0 6.24E 04 Sr-89 4.34E 05 0 0 0 2.422 06 3.71 E 05 0 1.25E 04 Sr-90 1.082 08 0 0 0 1.652 07 7.65E 05 0 6.682 06 Zr-95 1.462 05 4.582 04 0 6.74E 04 2.692 06 1.49E 05 0 3.15E 04 Nb-95 1.862 04 1.032 04 0 1.OOE 04 7.51 E 05 9.682 04 0 5.66E 03 Mo-99 0 1.69E 02 0 4.11 E02 1.54E 05 2.69E205 0 3.22E 01 Ag-11rn 1.38E204 1.31 E 04 0 2.502 04 6.75E 06 2.732 05 0 7.99E 03 Sb-I 24 4.30E 04 7.942 02 9.76E 01 0 3.85E 06 3.98E 05 0 1.68E 04 1-131 3.542 04 4.912E04 1.462 07 8.402 04 0 6.49E 03 0 2.64E 04 1-133 1.222 04 2.052 04 2.92E 06 3.592 04 0 1.03E 04 0 6.222 03 1-135 3.702 03 9.44E 03 6.212E05 1.492 04 0 6.95E 03 0 3.49E 03 Cs-i 34 5.022 05 1.13E 06 0 3.752 05 1.462 05 9.76E 03 0 5.49E 05 Cs-1 36 5.15E204 1.94E 05 0 1.10E205 1.78E204 1.09E204 0 1.37E 05 Cs-1 37 6.702 05 8.482 05 0 3.042 05 1.212E05 8.48E 03 0 3.11IE 05 Ba-i 40 5.472 04 6.702 01 0 2.282 01 2.03E 06 2.292 05 0 3.52E 03 La-140 4.792 02 2.362 02 0 0 2,142 05 4.872 05 0 6.262 01 Ce-1 41 2.84E204 1.90E 04 0 8.88E 03 6.14E 05 1.26E 05 0 2.17E203 Ce-i 44 4.892 06 2.022 06 0 1.21 E 06 1.342 07 8.642 05 0 2.62E 05 Rev. No. 9 Rev. o. 9Page B-I 7 of ODCM

TABLE B-5 (Continued)

R, VALUES - VEGETATION - TEEN m2_mremlyr p Culsec NUCLIDE] BONE LIVER jTHYROID ' KIDNEY LUNG GI-LLI SKIN T. BODY H-3* 0 2.59E 03 2.59E 03 2.59E 03 2.59E 03 2.59E 03 0 2.59E 03 Cr-5I 0 0 3.42E 04 1.35E 04 8.79E 04 1.03E 07 0 6.16E 04 Mn-54 0 4.54E 08 0 1.36E 08 0 9.32E 08 0 9.01 E 07 Fe-55 3.26E 08 2.31 E 08 0 0 1.47E 08 1.OOE 08 0 5.39E 07 Fe-59 1.79E 08 4.18E 08 0 0 1.32E208 9.89E208 0 1.61 E08 Co-57 0 1.79E 07 0 0 0 3.34E 08 0 3.002 07 Co-58 0 4.37E 07 0 0 0 6.02E 08 0 1.012E 08 Co-60 0 2.492 08 0 0 0 3.24E 09 0 5.60E 08 Zn-65 4.24E 08 1.47E 09 0 9.41 E 08 0 6.23E 08 0 6.86E 08 Sr-89 1.51E 10 0 0 0 0 1.80E 09 0 4.33E208 Sr-90 7.51IE11 0 0 0 0 2.11EI10 0 1.85E211 Zr-95 1.72E206 5.44E 05 0 7.99E 05 0 1.26E 09 0 3.74E 05 Nb 1.92E 05 1.072 05 0 1.03E 05 0 4.56E 08 0 5.86E 04 Mo-99 0 5.64E206 0 1.29E207 0 1.01 E07 0 1.08E 06 Ag-il1 Om 1.522 07 1.44E 07 0 2.74E 07 0 4.03E 09 0 8.73E 06 Sb-1 24 1.552 08 2.85E 06 3.51 E 05 0 1.35E 08 3.12E 09 0 6.032 07 1-131 7.68E 07 1.08E 08 3.14E 10 1.85E 08 0 2.13E 07 0 5.78E 07 1-133 1.95E 06 3.32E 06 4.632 08 5.812E06 0 2.512E06 0 1.01 E 06 1-135 3.53E204 9.10E204 5.85E206 1.442 05 0 1.01IE 05 0 3.37E 04 Cs-i 34 7.102 09 1.67E 10 0 5.312E09 2.03E 09 2.08E 08 0 7.76E 09 Cs-136 4.372 07 1.72E 08 0 9.362 07 1.482 07 1.38E207 0 1.15E 08 Cs-137 1.01E 10 1.35E 10 0 4.59E 09 1.78E 09 1.92E 08 0 4.69E 09 Ba-140 1.38E 08 1.69E205 0 5.74E204 1.14E 05 2.13E 08 0 8.91 E06 La-140 1.812E03 8.89E202 0 0 0 5.11 E07 0 2.37E 02 Ce-i 41 2.832 05 1.89E 05 0 8.89E 04 0 5.40E 08 0 2.17E 04 Ce-l 44 5.27E207 2.18E 07 0 1.30E 07 0 1.33E 10 0 2.83E 06

mremfyr pCi/rn3 r- No. 9 No. 9Page B-1 8 of 01)(

TABLE 'ontinued)

R,VALUES -COW MEAT -TEEN m _mremlyr pCilsec NUCLIDE f BONE j LIVER jTHYROID JKIDNEY LUNG GI-LUI SKIN T T. BODY H-3* 0 1.93E 02 1.93E 02 1.93E 02 1.93E 02 1.93E 02 0 1.93E 02 Cr-51 0 0 1.62E 03 6.39E 02 4.17E 03 4.90E 05 0 2.92E 03 Mn-54 0 4.50E 06 0 1.34E 06 0 9.42E 06 0 8.93E 05 Fe-55 1.58E 08 1.12E 08 0 0 7.12E 07 4.86E 07 0 2.62E 07 Fe-59 1.15E 08 2.69E 08 0 0 8.48E 07 6.36E 08 0 1.04E 08 Co-57 0 2.89E 06 0 0 0 5.40E 07 0 4.85E 06 Co-58 0 8.06E 06 0 0 0 1.11 E08 0 1.86E 07 Co-6O 0 3.91 E 07 0 0 0 5.09E 08 0 8.80E 07 Zn-65 1.59E 08 5.52E 08 0 3.53E 08 0 2.34E 08 0 2.58E 08 Sr-89 1.40E 08 0 0 0 0 1.67E 07 0 4.01 E06 Sr-90 5.42E 09 0 0 0 0 1.52E 08 0 1.34E 09 Zr-95 8.50E 05 2.68E 05 0 3.94E 05 0 6.19E 08 0 1.84E 05 Nb-95 9.49E 05 5.27E 05 0 5.11 E 05 0 2.25E 09 0 2.90E 05 Mo-99 0 4.10E 04 0 9.39E 04 0 7.35E 04 0 7.83E 03 Ag- 1Orn 3.22E 06 3.05E 06 0 5.81 E06 0 8.56E 08 0 1.85E 06 Sb-1 24 9.09E 06 1.68E 05 2.06E 04 0 7.94E 06 1.83E 08 0 3.55E 06 1-131 4.46E 06 6.24E 06 1.82E 09 1.08E 07 0 1.24E 06 0 3.35E 06 1-133 1.66E-01 2.82E-01 3.94E 01 4.95E-01 0 2.14E-01 0 8.61 E-02 1-135 1.89E-17 4.88E-1 7 3.14E-1 5 7.70E-1 7 0 5.40E-1 7 0 1.81 E-1 7 Cs-i 34 3.46E 08 8.14E 08 0 2.59E 08 9.87E 07 1.01IE 07 0 3.78E 08 Cs-1 36 4.71 E06 1.85E 07 0 1.01 E07 1.59E 06 1.49E 06 0 1.24E 07 Cs-i 37 4.88E 08 6.49E 08 0 2.21 E 08 8.59E 07 9.24E 06 0 2.26E 08 Ba-1 40 1.19E 07 1.46E 04 0 4.95E 03 9.82E 03 1.84E 07 0 7.68E 05 La-140 1,55E-02 7.60E-03 0 0 0 4.36E 02 0 2,02E-03 Ce-141 6.20E 03 4.14E 03 0 1.95E 03 0 1.18E 07 0 4.75E 02 Ce-144. 7.87E 05 3.26E 05 0 1.94E 05 0 1.98E 08 0 4.23E 04

mrem/yr 3

pC/rn Rev. No. 9 B-1 9 of ODOM Rev. o. 9Page

TABLE B-5 (Continued)

R,VALUES - COW MILK - TEEN m 2 -mremlyr pCilsec NUCLIDE j BONE J LIVER _THYROID T KIDNEY LUNG G.1 GI-I SKIN T. BODY.

H-3* 0 9.94E 02 9.94E 02 9.94E 02 9.94E 02 9.94E 02 0 9.94E 02 Cr-5I 0 0 1.44E 04 5.67E 03 3.69E 04 4.34E 06 0 2.59E 04 Mn-54 0 9.02E 06 0 2.69E 06 0 1.85E 07 0 1.79E 06 Fe-55 2.96E 07 2.10OE 07 0 0 1.33E 07 9.08E 06 0 4.89E 06 Fe-59 2.81 E 07 6.57E 07 0 0 2.07E 07 1.55E 08 0 2.54E 07 Co-57 0 1.43E 06 0 0 0 2.68E 07 0 2.41 E 06 Co-58 0 4.55E 06 0 0 0 6.27E 07 0 1.05E 07 0o-60 0 1.86E 07 0 0 0 2.42E 08 0 4.19E 07 Zn-65 1.34E 09 4.65E 09 0 2.97E 09 0 1.97E 09 0 2.17E 09 Sr-89 I1.47E 09 0 0 0 0 1.75E 08 0 4.22E 07 Sr-90 4.46E 10 0 0 0 0 1.25E 09 0 1.IOE 10 Zr-95 9.34E 02 2.95E 02 0 4.33E 02 0 6.80E 05 0 2.03E 02 Nb-95 7.45E 04 4.13E 04 0 4.01 E 04 0 1.77E 08 0 2.28E 04 Mo-99 0 2.23E 07 0 5.11IE 07 0 4.OOE 07 0 4.26E 06 Ag-11rn 6.13E 07 5.80E 07 0 1.11 E08 0 1.63E 10 0 3.53E 07 Sb-124 2.58E 07 4.76E 05 5.86E 04 0 2.25E 07 5.20E 08 0 1.01IE 07 1-131 2.69E 08 3.76E 08 1.IOE 11 6.47E 08 0 7.44E 07 0 2.02E 08 1-133 3.58E 06 6.07E 06 8.48E 08 1.06E 07 0 4.59E 06 0 1.85E 06 1-135 1.15E 04 2.95E 04 1.90E 06 4.66E 04 0 3.27E 04 0 1.09E 04 Cs-134 6.49E 09 1.53E 10 0 4.85E 09 1.85E 09 1.90E 08 0 7.09E 09 Cs-I 36 2.25E 08 8.84E 08 0 4.81 E 08 7.59E 07 7.12E 07 0 5.94E 08 Cs-137 9.02E 09 1.20E 10 0 4.08E 09 1.59E 09 1.71 E 08 0 4.18E 09 Ba-140 2.43E 07 2.98E 04 0 1.01IE 04 2.OOE 04 3.75E 07 0 1.57E 06 L3-1401 4,.06E 00 2,OOE 00 0 0 0 I.15E 05 0 5.31 E-01 Ce-141 4.67E 03 3.12E 03 0 1.47E 03 0 8.91 E06 0 3.58E 02 Ce-144 4.22E 05 1.74E 05 0 1.04E 015 0 1.06E 08 0 2.27E 04

mrem/yr pCi/rn3

,r No. 9 Page B-20 of OW"

TA13LF--".l, Nontinued)

R, VALUES - GOTMILK - TEEN m 2-mremlyr pCi/sec

NUCLIDE] BONE j LIVER THYROID JKIDNEY J LUNG GI-LLI j SKIN [T. BODY H-3* 0 2.03E 03 2.03E 03 2.03E 03 2.03E 03 2.03E 03 0 2.03E 03 Cr-51 0 0 1.72E 03 6.80E 02 4.43E203 5.21 E05 0 3.10E 03 Mn-54 .0 1.08E 06 0 3.23E 05 0 2.22E 06 0 2.15E 05 Fe-55 3.85E 05 2.73E 05 0 0 1.73E 05 1.18E 05 0 6.36E 04 Fe-59 3.66E 05 8.54E 05 0 0 2.69E 05 2.02E 06 0 3.30E 05 Co-57 0 1.72E 05 0 0 0 3.21 E 06 0 2.89E 05 Co-58 0 5.46E 05 0 0 0 7.52E 06 0 1.26E, 06 Co-60 0 2.23E 06 0 0 0 2.91 E 07 0 5.03E 06 Zn-65 1.61 E 08 5.58E 08 0 3.57E 08 0 2.36E 08 0 2.60E 08 Sr-89 3.09E 09 0 0 0 0 3.68E 08 0 8.85E 07 Sr-90 9.36E 10 0 0 0 0 2.63E 09 0 2.31E 10 Zr-95 1.12E 02 3.54E201 0 5.20E 01 0 8.16E 04 0 2.43E201 Nb-95 8.94E 03 4.96E 03 0 4.81 E 03 0 2.12E 07 0 2.73E 03 Mo-99 0 2.68E206 0 6.13E 06 0 4.80E 06 0 5.11 E05 Ag-11rn 7.35E 06 6.96E 06 0 1.33E 07 0 1.95E 09 0 4.23E 06 Sb-124 3.10E 06 5.71 E04 7.03E 03 0 2.71 E06 6.24E 07 0 1.212E06 1-131 3.22E 08 4.51 E 08 1.32E 11 7.77E 08 0 8.93E 07 0 2.42E 08 1-133 4.30E 06 7.29E 06 1.02E 09 1.28E 07 0 5.512E 06 0 2.22E 06 1-135 1.38E 04 3.54E 04 2.28E 06 5.60E 04 0 3.93E 04 0 1.31 E 04 Cs-I 34 1.95E 10 4.58E 10 0 1.46E 10 5.56E 09 5.70E 08 0 2.13E 10 Cs-136 6.74E 08 2.65E 09 0 1.442 09 2.28E 08 2.13E 08 0 1.78E 09 Cs-137 2.71E 10 3.60E 10 0 1.23E 10 4.76E 09 5.12E 08 0 1.25E 10 Ba-140 2.92E 06 3.58E 03 0 1.21 E 03 2.41 E 03 4.50E 06 0 1.88E205 La-I 40 4.87E-01 2.40E-01 0 0 0 1.38E 04 0 6.37E-02 Ce-141 5.60E202 3.74E 02 0 1.76E 02 0 1.07E 06 0 4.30E 01 Ce-144 5.06E 04 2.09E 04 0 1.25E 04 0 -1.27E 07 0 2.72E 03

mrem/vr p-Ci/rn 3 Rev. No.. 9 B-21 of ODCM Rev. o. 9Page

TABLE B-5 (Continued)

R, VALUES - GROUND PLANE - CHILD 2

m -mrem/yr pCilsec NUCLIDE '

BONE *1 LIVER [THYROID_ _KID'NEY LUNG GI-IL!i j~ SKIN [T. BODY H-3 0 0 0 0 0 0 0 0 Cr-5I 4.65E 06 4.651106 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E'09 1.38E 09 Fe-55 0 0 0 0 0 0 0 .- 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 1.88E 08 1.88E 08 1.88E 08 I1.88E 08 I1.88E 08 I1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 4.45E 08 3.80E 08 Co-60 2.15E 10 2.15EI10 2.15EI10 2.15E 10 2.15E 10 2.15E 10 2.53E 10 2.15E 10 Zn-65 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 7.46E 08 8.57E 08 7.46E 08 Sr-89 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.16E 04 2.51 E04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.45E 08 2.85E 08 2.45E 08 Nb-95 1.37E 08 1.37E 08 1.37E 08 1.37E 08 .1.37E 08 1.37E 08 1.61 E 08 1.37E 08 Mo-99 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 3.99E 06 4.62E 06 3.99E 06 Ag-I I Om 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 3.45E 09 4.02E 09 3.45E 09 Sb-I 24 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 5.99E 08 6.92E 08 5.99E 08 1-131 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 1.72E 07 2.09E 07 1.72E 07 1-133 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 2.46E 06 3.OOE 06 2.46E 06 1-135 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.53E 06 2.95E 06 2.53E 06 Cs-I 34 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 6.90E 09 8.05E 09 6.90E 09 Cs-136 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.51 E08 1.71 E08 1.51 E08 Cs-1 37 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.03E 10 1.20E 10 1.03E 10 Ba-I 40 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.05E 07 2.35E 07 2.05E 07 La-140 I.*92E 07 1.92E207 1l.92E 07 1.*92E 07 1,92E 07 1,92E 07 2,18E 07 1,92E 07 Ce-141 1.37E207 1.37E207 1.37E 07 1.37E 07 1.37E207 1.37E 07 1.54E 07 1.37E 07 Ce-144 6.96E 07 6.96E 07 6.96E 07 6.*96E 07 6.96E 07 6.96E 07 8.05E 07 -16.96E 07 F' No. 9 F No. 9Page B-22 of OD('

TABLK>. ~onti nued)

R, VALUES - INHALATION - CHILD mremlyr pci/rn3 NUCLI DE J BONE j LIVER THYROID KDEY j UGG-L KN jT.BODY H-3 0 1.12E 03 1.12E 03 1.12E 03 1.12E 03 1.12E 03 0 1.12E 03 Cr-5I 0 0 8.55E 01 2.43E 01 1.70E 04 1.08E 03 0 1.54E 02 Mn-54 0 4.29E 04 0 1.00E 04 1.58E 06 2.29E 04 0 9.51 E 03 Fe-55 4.74E 04 2.52E 04 0 0 1.11IE 05 2.87E 03 0 7.77E 03 Fe-59 2.07E 04 3.34E 04 0 0 1.27E 06 7.07E 04 0 1.67E 04 Co-57 0 9.03E 02 0 0 5.07E 05 1.32E 04 0 1.07E 03 Co-58 0 1.77E 03 0 0 1.11 E06 3.44E 04 0 3.16E 03 Co-60 0 1.31 E 04 0 0 7.07E 06 9.62E 04 0 2.26E 04 Zn-65 4.26E 04 1.13E 05 0 7.14E 04 9.95E 05 1.63E 04 0 7.03E 04 Sr-89 5.99E 05 0 0 0 2.16E 06 1.67E 05 0 1.72E 04 Sr-90 1.01E 08 0 0 0 1.48E 07 3.43E 05 0 6.44E 06 Zr-95 1.90E 05 4.18E 04 0 5.96E 04 2.23E 06 6.11 E 04 0 3.70E 04 Nb-95 2.35E 04 9.18E 03 0 8.62E 03 6.14E 05 3.70E 04 0 6.55E 03 Mo-99 0 1.72E 02 0 3.92E 02 1.35E 05 1.27E 05 0 4.25E 01 Ag-Ib0m 1.69E 04 1.14E 04 0 2.12E 04 5.48E 06 1.00E 05 0 9.14E 03 Sb-124 5.74E 04 7.40E 02 1.26E 02 0 3.24E 06 1.64E 05 0 2.OOE 04 1-131 4.81 E 04 4.81 E 04 1.62E 07 7.88E 04 0 2.84E 03 0 2.73E 04 1-133 1.66E 04 2.03E 04 3.85E 06 3.38E 04 0 5.48E 03 0 7.70E 03 1-135 4.92E 03 8.73E 03 7.92E 05 1.34E 04 0 4.44E 03 0 4.14E 03 Cs-1 34 6.51 E05 1.01 E06 0 3.30E 05 1.21 E05 3.85E 03 0 2.25E 05 Cs-1 36 6.51 E04 1.71 E05 0 9.55E 04 1.45E 04 4.18E 03 0 1.16E 05 Cs-I 37 9.07E 05 8.25E 05 0 2.82E 05 1.04E 05 3.62E 03 0 1.28E 05 Ba-1 40 7.40E 04 6.48E 01 0 2.11IE01 1.74E 06 1.02E 05 0 4.33E 03 La-140 6.44E 02 2,25E 02 0 0 1,83E 05 2.26E 05 0 7.55E 01 Ce-141 3.92E 04 1.95E 04 0 8.55E 03 5.44E 05 5.66E 04 0 2.90E 03 Ce-144 6.77E 06 2.12E 06 0 1.17E 06 1.20E 07 3.89E 05 0 3.61 E05 Rev. No.. 9 Rev. o. 9Page B-23 of ODCM

TABLE B-5 (Continued)

R, VALUES - COW MEAT - CHILD m2_mremlyr NUCLIDE j ~~BONE LIVER 1THYROID JKID:NEY J

_ _ _ _ _ _ Cl/sec LN GI-LLI SI .BD H-3* 0 2.331102 2.33E 02 2.33E 02 2.33E 02 2.33E 02 0 2.33E 02 Cr-51 0 0 2.53E 03 6.901102 4.61 E 03 2.41 E 05 0 4.55E 03 Mn-54 0 5.15E 06 0 1.44E 06 0 4.32E 06 0 1.37E 06 Fe-55 3.04E 08 1.61 E 08 0 0 9.11IE 07 2.98E 07 0 4.99E 07 Fe-59 2.04E 08 3.30E 08 0 0 9.58E 07 3.44E 08 0 1.65E 08 Co-57 0 3.78E 06 0 0 0 3.1IOE 07 0 7.66E 06 Co-58 0 9.41 E 06 0 0 0 5.49E 07 0 2.88E 07 Co-60 0 4.641E 07 0 0 0 2.57E 08 0 1.37E 08 Zn-65 2.39E 08 6.35E 08 0 4.OOE 08 0 1.12E 08 0 3.95E 08 Sr-89 2.65E 08 0 0 0 0 1.03E 07 0 7.57E 06 Sr-90 7.01 E 09 0 0 0 0 9.44E 07 0 1.78E 09 Zr-95 1.51 E 06 3.32E 05 0 4.75E 05. 0 3.46E 08 0 2.95E 05 Nb-95 1.64E 06 6.38E 05 0 6.OOE 05 0 1.18E 09 0 4.56E 05 Mo-99 0 5.71 E04 0 1.22E 05 0 4.72E 04 0 1.41 E04 Ag- IOrn 5.34E 06 3.61 E 06 0 6.72E 06 0 4.29E 08 0 2.88E 06 Sb-124 1.65E 07 2.13E 05 3.63E 04 0 9.13E 06 1.03E,08 0 5.77E 06 1-131 8.27E106 8.32E 06 2.75E 09 1.37E 07 0 7.41 E 05 0 4.73E 06 1-133 3.09E-01 3.82E-01 7.10E 01 6.37E-01 0 1.54E-01 0 1.45E-01 1-135 3.43E-1 7 6.17E-17 5.4611-15 9.46E-1 7 0 4.70E-1 7 0 2.92E-1 7 Cs-1 34 6.1OE 08 1.00E 09 0 3.1OE 08 1.11 E08 5.39E 06 0 2.11 E08 Cs-136 8.12E 06 2.23E 07 0 1.19E 07 1.77E 06 7.85E 05 0 1.45E 07 Cs-137 8.99E 08 8.60E 08 0 2.80E 08 1.01IE 08 5.39E 06 0 1.27E 08 Ba-140 2.20E 07 1.93E 04 0 6.27E 03 1.15E 04 1.11E 07 0 1.28E 06 La-14 2.83E-02 9.90E-03 0 0 0 2.76E 02 0 3.34E-03 Ce-141 1.17E 04 5.82E 03 0 2.55E 03 0 7.26E 06 0 8.64E 02 Ce-144 1.48E 06 4.65E 05 0 2.57E 05 0 1.21 E 08 0 7.92E 04

mremlyr pCi/rn 3 No. 9 r B-24 of OD(

N.9Page 7ý

TABLEý ýýr-rontlnued)

R,VALUES - COW MILK - CHILD m 2_mremlyr pC l/sec-F NUCID j BONE [ LVR THYROID: KIDNEY LUGG-LLI j SKIN JT.BD .B D H-3* 0 1.57E 03 1.57E 03 1.57E 03 1.57E 03 1.57E 03 0 1.57E 03 Cr-51 0 0 2.93E 04 8.00E 03 5.34E 04 2.80E206 0 5.27E 04 Mn-54 0 1.35E 07 0 3.78E 06 0 1.13E 07 0 3.59E 06 Fe-55 7.43E 07 3.94E 07 0 0 2.23E 07 7.30E 06 0 1.22E 07 Fe-59 6.53E 07 1.06E 08 0 0 3.06E 07 1.10E 08 0 5.26E 07 Co-57 0 2.45E 06 0 0 0 2.012E 07 0 4.96E 06 Co-58 0 6.95E 06 0 0 0 4.052 07 0 2.132 07 Co-60 0 2.892 07 0 0 0 1.60E 08 0 8.522 07 Zn-65 2.63E 09 7.002 09 0 4.412E 09 0 1.232 09 0 4.35E209 Sr-89 3.64E209 0 0 0 0 1.412E08 0 1.04E208 Sr-90 7.53E210 0 0 0 0 1.012E09 0 1.91E210 Zr-95 2.17E 03 4.77E 02 0 6.832 02 0 4.982 05 0 4.252 02 Nb-95 1.68E205 6.55E204 0 6.152 04 0 1.212E08 0 4.682 04 Mo-99 0 4.06E 07 0 8.67E 07 0 3.36E 07 0 1.002 07 Ag-Ib0m 1.33E208 8.98E207 0 1.67E208 0 1.07E210 0 7.18E 07 Sb-1 24 6.112E07 7.92E205 1.35E205 0 3.39E207 3.82E208 0 2.14E207 1-131 6.522 08 6.552 08 2.17E 11 1.082 09 0 5.832 07 0 3.72E208 1-133 8.702 06 1.08E207 2.002 09 1.792 07 0 4.332 06 0 4.072 06 1-135 2.722 04 4.892 04 4.332 06 7.492 04 0 3.722 04 0 2.312E 04 Cs-I 34 1.502 10 2.462 10 0 7.612E09 2.732 09 1.322 08 0 5.182 09 Cs-I 36 5.072 08 1.392 09 0 7.422 08 1.112E08 4.902 07 0 9.022 08 Cs-I 37 2.172 10 2.082 10 0 6.782 09 2.442 09 1.302 08 0 3.072 09 Ba-1 40 5.872 07 5.152 04 0 1.682 04 3.07E204 2.982 07 0 3.432 06 La-140 9.732 00 3.402 00 0 0 0 9.482 04 0 1.152 00 Ce-1 41 1.152 04 5.73E203 0 2.512E03 0 7.152 06 0 8.512E02

.Ce-144 1.042 06 3.262 05 0 1.80E 05 0 8.502 07 0 5.55E 04

mremfvr 3

p.Ci/M Rev. No.. 9 Rev. o. 9Page B-25 of ODCM

TABLE B-5 (Continued)

R, VALUES - GOAT MILK - CHILD 2

m -mrgnLr NUCLID7E BONET LIVER* THYROID: KINE LUNG $.IL KIN T. BODY H-3* 0 3.20E 03 3.20E 03 3.20E 03 3.20E 03 3.20E 03 0 3.20E 03 Cr-5I 0 0 3.512E03 9.60E 02 6.41 E 03 3.36E 05 0 6.33E 03 Mn-54 0 1.62E206 0 4.54E205 0 1.36E 06 0 4.312E05 Fe-55 9.65E205 5.12E 05 0 0 2.90E 05 9.492 04 0 1.59E 05 Fe-59 8.48E 05 1.37E 06 0 0 3.982 05 1.432 06 0 6.84E 05 Co-57 0 2.94E 05 0 0 0 2.41 E 06 0 5.96E 05 Co-58 0 8.342 05 0 0 0 4.86E 06 0 2.552 06 Co-60 0 3.472 06 0 0 0 1.92E 07 0 1.022 07 Zn-65 3.152 08 8.402 08 0 5.29E 08 0 1.472 08 0 5.222 08 Sr-89 7.65E 09 0 0 0 0 2.96E 08 0 2.19E 08 Sr-90 1.582 11 0 0 0 0 2.13E 09 0 4.01E 10 Zr-95 2.60E 02 5.73E 01 0 8.202 01 0 5.97E 04 0 5.10E 01 Nb-95 2.02E 04 7.86E 03 0 7.39E 03 0 1.45E 07 0 5.62E 03 Mo-99 0 4.87E 06 0 1.04E 07 0 4.032 06 0 1.21 E 06 Ag-Ib1 m 1.59E207 1.08E 07 0 2.01 E07 0 1.28E 09 0 8.61 E06 Sb-I 24 7.332 06 9.15E 04 1.62E 04 0 4.072 06 4.58E207 0 2.57E 06 1-131 7.822 08 7.862 08 2.602 11 1.292 09 0 7.002 07 0 4.472 08 1-133 1.042 07 1.292 07 2.402 09 2.15E 07 0 5.20E 06 0 4.88E-06 1-135 3.262 04 5.87E 04 5.1 92 06 8.992 04 0 4.47E 04 0 2.77E-04 Cs-1 34 4.49E 10 7.372 10 0 2.282 10 8.192 09 3.97E 08 0 1.55E 10 Cs-I 36 1.522 09 4.18E 09 0 2.23E 09 3.322 08 1.47E 08 0 2.712E09 Cs-I 37 6.52E 10 6.24E 10 0 2.03E 10 7.32E 09 3.91 E 08 0 9.212E09 Ba-140 7.05E206 6.17E 03 0 2.01 E03 3.68E203 3.57E 06 0 4.11 E05 La-140 1,17E 00 4,08E-01 0 0 0 1,14E 04 0 1,38E-01 Ce-141 1.38E 03 6.882 02 0 3.02E 02 0 8.58E, 05 0 1.02E 02 Ce-144 1.25E205 3.91 E04 0 2.14E 04 0 1.02E 07 0 6.66E203

mremlyr pCi/rn3 No. 9 B-26 of OD(--\

No. 9Page

TABLr' .r,-r->ontinued)

R,VALUES - GROUND PLANE - INFANT m -_mrem/yr pCilsec NUCLID E BONE J LIVER JTHYROID jKIDNEY LUNG GI-LLI SKIN. T. BODY H-3 0 0 0 0 0 0 0 0 Cr-SI 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 4.65E 06 5.50E 06 4.65E 06 Mn-54 I1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.38E 09 1.62E 09 1.38E 09 Fe-55 0 0 0 0 0 0 0 0 Fe-59 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 2.73E 08 3.20E 08 2.73E 08 Co-57 I1.88E 08 1.88E 08 1.88E 08 1.88E 08 1.882 08 1.88E 08 2.07E 08 1.88E 08 Co-58 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.80E 08 3.802 08 4.45E 08 3.80E 08 Co-60 2.15E210 2.15E210 2.15E 10 2.15E210 2.15EI10 2.15E210 2.53E 10 2.15E210 Zn-65 7.46E 08 7.462 08 7.462 08 7.462 08 7.462 08 7.46E 08 8.572 08 7.46E 08 Sr-89 2.16E204 2.162 04 2.16E204 2.16E204 2.16E204 2.16E204 2.512E04 2.16E 04 Sr-90 0 0 0 0 0 0 0 0 Zr-95 2.452 08 2.45E 08 2.452 08 2.452 08 2.452 08 2.452 08 2.85E 08 2.452 08 Nb-95 1.372 08 1.372 08 1.372 08 1.372 08 1.37E 08 1.372 08 1.612E08 1.372 08 Mo-99 3.992 06 3.992 06 3.99E 06 3.992 06 3.99E 06 3.992 06 4.62E 06 3.992 06 Ag- I Om 3.452 09 3.452 09 3.452, 09 3.452 09 3.45E 09 3.452 09 4.022 09 3.45E 09 Sb-I 24 5.992 08 5.992 08 5.992 08 5.992 08 5.99E 08 5.992 08 6.922 08 5.99E 08 1-131 1.722 07 1.722 07 1.722 07 1.722 07 1.722 07 1.72E 07 2.092 07 1.72E 07 1-133 2.462 06 2.462 06 2.462 06 2.462 06 2.462 06 2.462 06 3.002 06 2.46E 06 1-135 2.53E 06 2.53E 06 2.532 06 2.532 06 2.53E 06 2.53E 06 2.952 06 2.53E 06 Cs-I 34 6.90E 09 6.902 09 6.902 09 6.902 09 6.902 09 6.902 09 8.05E 09 6.90E 09 Cs-136 1.512E08 1.512E08 1.512E08 1.512E08 1.512E08 1.512E08 1.712E08 1.51 E08 Cs-1 37 .1.032 10 1.032 10 1.032 10 1.032 10 1.032 10 1.032 10 1.202 10 1.032 10 Ba-140 2.05E 07 2.05E 07 2.052 07 2.052 07 2.052 07 2.05E 07 2.35E 07 2.05E 07 La-1 40 1.922 07 1.922 07 1.922 07 1.922 07 1.92E 07 1.922 07 2.182 07 1.92E 07 Ce-141 I1.37E 07 1.372 07 1.372 07 1.372 07 1.372 07 1.37E 07 1.542 07 1.37E 07 Ce-144 6.962 07 6.962 07 6.96E 07 6.962 07 6.962 07 6.96E 07 8.05E 07 6.96E 07 Rev. No. 9 Rev. o. B-27 9Pageof ODOM

TABLE B-5 (Continued)

R,VALUES - INHALATION - INFANT pCi/rn3 NUCLIDE BONE j LIVER THYROID KIDNEY LUNG:. G16LLI SKIN jT. B3ODY H-3 0 6.47E, 02 6,47E 02 6.47E 02 6A7E 02 6.47E 02 0 6.47E 02 Cr-5I 0 0, 5.75E 01 1.32E 01 11.28E 04 3.57E 02 0 8.95E 01 Mn-54 0 2.53E 04 0 4.98E 03 1.00E 06 7.06E 03 0 4.98E 03 Fe-55 1.97E 04 1.17E 04 0 0 8.69E 04 1.09E 03 0 3.33E 03 Fe-59 I1.36E 04 2.35E 04 0 0 1.02E 06 2.48E 04 0 9.48E 03 Co-57 0 6.51 E 02 0 0 3.79E 05 4.86E 03 0 6.41 E 02 Co-58 0 1.22E 03 0 0 7.77E 05 1.11 E04 0 1.82E 03 Co-60 0 8.02E 03 0 0 4.51 E06 3.19E 04 0 1.18E 04 Zn-65 1.93E 04 6.26E 04 0 3.25E 04 6.47E 05 5.14E 04 0 3.11IE 04 Sr-89 3.98E 05 0 0 0 2.03E 06 6.40E 04 0 1.14E 04 Sr-90 4.09E 07 0 0 0 1.12E 07 1.31 E05 0 2.59E 06 Zr-95 1.15E 05 2.79E 04 0 3.11 E04 1.75E 06 2.17E 04 0 2.03E 04 Nb-95 I1.57E 04 6.43E 03 0 4.72E 03 4.79E 05 1.27E 04 0 3.78E 03 Mo-99 0 1.65E 02 0 2.65E 02 1.35E 05 4.87E 04 0 3.23E 01 Ag-ib0m 9.98E 03 7.22E 03 0 1.09E 04 3.67E 06 3.30E 04 0 5.OOE 03 Sb-124 3.79E 04 5.56E 02 1.OOE 02 0 2.65E 06 5.91 E 04 0 1.20E 04 1-131 3.79E 04 4.44E 04 1.48E 07 5.18E 04 0 1.06E 03 0 1.96E 04 1-133 1.32E 04 1.92E 04 3.56E 06 2.24E 04 0 2.16E 03 0 5.60E 03 1-135 3.86E 03 7.60E 03 6.96E 05 8.47E 03 0 1.83E 03 0 2.77E 03 Cs-I 34 3.96E 05 7.03E 05 0 1.90E 05 7.97E 04 1.33E 03 0 7.45E 04 Cs-1 36 4.83E 04 1.35E 05 0 5.64E 04 1.18E 04 1.43E 03 0 5.29E 04 Cs-137 5.49E 05 6.12E 05 0 1.72E 05 7.13E 04 1.33E 03 0 4.55E 04 Ba-140 5.60E 04 5.60E 01 0 1.34E 01 1.60E 06 3.84E 04 0 2.90E 03 La-1 40 5.05E 02 2.OOE 02 0 0 1.68E 05 8.48E 04 0 5.15E 01 Ce-141 2.77E 04 1.67E 04 0 5.25E 03 5.17E 05 2.16E 04 0 1.99E 03 Ce-144 3.19E 06 1.21 E06 0 5.38E 05 9.84E 06 1.48E 05 0 1.76E 05 F No. 9 F No. 9Page 8-28 of OD(

TABLr >Fontinued)

R,VALUES - VEGETATION - INFANT AND R,VALUES - COW MEAT - INFANT m-mrem/yr NUCLIDE BONE LIVER THYROIDj__KIDNEY__ LUNG -GI-LLI KI T.BODY H-3* 0 0 0 0 0 0 0 0 Cr-5i 0 0 0 0 0 0 0 0 Mn-54 0 0 0 0 0 0 0 0 Fe-55 0 0 0 0 0 0 0 0 Fe-59 0 0 0 0 0 0 0 0 Co-57 0 0 0 0 0 0 0 0 Co-58 0 0 0 0 0 0 0 0 Co-60 0 0 0 0 0 0 0 0 Zn-65 0 0 0 0 0 0 0 0 Sr-89 0 0 0 0 0 0 0 0 Sr-90 0 0 0 0 0 0 0 0 Zr-95 0 0 0 0 0 0 0 0 Nb-95 0 0 0 0 0 0 0 0 Mo-99 0 0 0 0 0 0 0 0 Ag-ib1 m 0 0 0 0 0 0 0 0 Sb-124 0 0 0 0 0 0 0 0 1-131 0 0 0 0 0 0 0 0 1-133 0 0 0 0 0 0 0 0 1-135 0 0 0 0 0 0 0 0 Cs-134 0 0 0 0 0 0 0 0 Cs-136 0 0 0 0 0 0 0 0 Cs-1 37 0 0 0 0 0 0 0 0 Ba-140 0 0 0 0 0 0 0 0 La-14 0 0 0 0 0 0 0 0 Ce-141 0 0 0 0 0 0 0 0 Ce-144 0 0 0 0 0 0 0 0

mremlyr pCi/rn3 Rev. No. 9 Rev. o. 9Page B-29 of 00CM

TABLE B-6 DERIVATION OF GASEOUS DOSE FACTORS TABLE PAGE B-6.1 Derivation of (P,) Values B-31 B-6.2 Derivation of Gaseous Dose Factors -32 BF)

B-6.3 Parameters for the Gaseous Effluent Pathway B-41 B-6.4 Justification for Gaseous Pathways Used to B-44 Assess Dose B-6.5 Organ Doses for Gaseous Releases - Inhalation B-46 Pathway Rev. No. 9 Rev.No.9Page 8-30 of ODOM

TABLE B-6.1 DERIVATION OF (P,) VALUES The pathway dose factor, P1, for radioiodines, tritium, and 8-day particulates includes transport parameters of the ith nuclide, the receptor usage rate of the pathway media, and the appropriate dose conversion factor. For the inhalation pathway, the value of P,is calculated as follows:

Pi = K' (BR) DFA, (mrem/yr per Xiltim 3 )

Where:

K' =a constant of unit conversion, 10' pCi/pCi.

(B3R) =the breathing rate of the age group, in rr9/yr (Table E-5 of Regulatory Guide 1.109).

DFA, the maximum organ inhalation dose factor for the appropriate age group for the ith radionuclide, in mrem/pCi (Tables E-7 to E-1 0 of Regulatory Guide 1.109).

Example Calculation:

For the 1-131 child thyroid dose factor for exposure from inhalation:

DFAý = 4.39E-03 mrem/pCi BR = 3700 m3/yr These values will yield a Pi factor of 1.62E7 mrem/yr per pCi/rn3 as listed in Table B-3 of this appendix.

Rev. No. 9 B-31 of 00CM Rev. o. 9Page

TABLE B-6.2 DERIVATION OF GASEOUS DOSE FACTORS (11ý The pathway dose factor lý for radioiodines, tritium, and 8 day particulates include transport parameters of the ith nuclide, the receptor usage rate of the pathway media, and the appropriate dose conversion factor. In developing the R~ values, separate expressions are written for each of the potential pathways.

1. INHALATION For the inhalation pathway, the value of F~is calculated as follows:

R. K' (BR) a (DFAi)a, (mrem/yr per AiCi/m')

Where:

K' = a constant of unit conversion, 1iif pCi/pCi.

(BR)a = the breathing rate of the receptor of age group (a) in rr?/yr (Table B-6.3).

(DFAý) a = the organ inhalation dose factor for the receptor of age group (a)for the ith radionuclide, in mrem/pCi (Tables E-7 to E-1 0 of Regulatory Guide 1.109).

Example Calculation:

For the 0o-60 child whole body dose factor from exposure due to inhalation.

(DFA 1ý)a = 6.12E-6 mrem/pCi (B3R)a = 3700 m3/yr These values yield a R~ factor of 2.26E4 mrem/yr per pCi/rr? as listed in Table B-5 of this appendix.

11. GROUND PLANF For the ground plane pathway, the value of R3 is calculated as follows:

R=K'K" (SF) DFGj [(I1 -e -"1 (M22 -rrem/yr per iICi/sec)

Rev. No. 9 Rev. o. 9Page B-32 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (F§ Where:

K' = a constant of unit conversion, 10P pCi/pCi.

K" = a constant of unit conversion, 8760 hr/yr.

= the decay constant for the ith radionuclide, sec'.

t = the exposure time, 4.73E8 sec (Table B-6.3).

DFG1 = the ground plane dose conversion factor for the ith radionuclide, mrem/hr per pCi/rn 2. (See Table E-6 of Regulatory Guide 1.109).

SF = the shielding factor, 0.7, dimensionless (Table 8-6.3).

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to the ground plane:

Xj = 4.20E-9 sec' DFGj = 1 .70E-8 mrem/hr per pCi/in2 2

These values yield a Rý factor of 2.15E1 0 m?-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

Ill. VEGETATION A. Radioiodines And Eight Day Particulates For the vegetation pathway, 1`3, is calculated as follows:

R. =K' (r) ( X 0-i( + X" (DFLa [uaf e~'LU+ Ug (M 2 -mremlyr per p.Ci/sec)

Where:

K' =a Constant of unit conversion, 10~ pCi/pCi.

L Ua =the consumption rate of fresh leafy vegetation by the receptor in age group (a), in kg/yr (Table B-6.3).

Rev. No. 9 Rev. o. 9Page B-33 of ODOM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (F1ý Ua = the consumption rate of stored vegetation by the receptor in age group (a), in kg/yr (Table 8-6.3).

fL =the fraction of the annual intake of fresh leafy vegetation grown locally (Table B-6.3).

fg the fraction of the annual intake of stored vegetation grown locally (Table B-6.3).

tL = the average time between harvest of leafy vegetation and its consumption, in seconds (Table B-6.3).

th = the average time between harvest of stored vegetation and its consumption, in seconds (Table B-6.3).

Y" = the vegetation areal density, in kg/rd (Table B-6.3).

r = fraction of deposited activity retained on vegetation (Table B-6.3).

A,= the decay constant for the ith radionuclide, in sec'.

Aw = the decay constant for removal of activity on leaf and plant surfaces by weathering, 5.73E-7 sec' (corresponding to a 14 day half-life).

('DFLI), the maximum organ ingestion dose factor for the ith radionuclide for the receptor in age group (a), in mrem/pCi (Tables E-1 1 to E-14 of Regulatory Guide 1.109).

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of vegetation:

L Ua =26 kg/yr Ua = 520 kg/yr fg 0.76 Rev. No. -9 Rev. o. 9Page B-34 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (F1ý tL = 8.6E4 sec th = 5.18E6 sec 2

Y4 = 2 kg/rn r = 0.2 A1 = 4.2E-9 sec7

,kW = 5.73 E-7 sec-1 (DFLi)a, = 1 .56E-5 mrem/pCi 2

These values yield an R~ factor of 1.12E9 m?-mrem/yr per pCi/sec as listed in Table B-4 of this appendix.

B. Tritium The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. F~is calculated as follows:

Ri=KK (U~, fL + U.i fg) (DFLi)a, [0-75 (0.5/H)]

(rnremlyr per aCi/m3 )

Where:

K' = unit conversion constant, 1(: pCi/pCi.

K... = unit conversion constant, io0 gm/kg.

0.75 = the fraction of vegetation which is water (NUREG-Ol 33).

0.50 = the ratio of the specific activity of the vegetation that is water to the atmospheric water (NUREG-0133).

H = absolute atmospheric humidity, in gm/rif (Table B-6.3).

All other parameters are as previously defined above.

Rev. No. 9 Rev.No.1Page B-35 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(F Example Calculation For the H-3 child whole body dose factor from exposure due to ingestion of vegetation:

L Ua = 26 kglyr S

Ua = 520 kg/yr fL = I f9 = 0.76 (DFLi)a = 2.03E-7 mrem/pCi H = 8 gm/rn 3 (NUREG-0133)

These values yield a R~ factor of 4.01 E3 mrem/yr per pCi/nfý as listed inTable B-4 of this appendix.

IV. MEAT A. Radioiodines And Eight Day Particulates Rl K1 QF (UaP) Ff (r) [DL),

flf + -f )e -it (M 2 -mrem/yr per ItCi/sec)

Where:

Up = the receptor's meat consumption rate for age (a), in kg/yr (Table B-6.3).

Ff = the stable element transfer coefficients, in days/kg (Table E-1 of Regulatory Guide 1.109).

= the transport time from pasture to receptor, in sec (Table B-6.3).

th = the transport time from crop field to receptor, in sec (Table B-6.3).

Rev. No. -9 Rev. o. 9Page B-36 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(I Yp= the agricultural productivity by unit area of pasture feed grass, in kg/ni (Table B-6.3).

Y,= the agricultural productivity by unit area of stored feed, in kg/ni (Table B-6.3).

fp = fraction of the year that the cow is on pasture (Table B3-6.3).

f, = fraction of the cow feed that is pasture grass while the cow is on pasture (Table 13-6.3).

Qf= the cow's consumption rate, in kg/day (wet weight). See Table 8-6.3.

All other parameters were defined previously.

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of meat:

Uap 41 kg/yr Ff = 1.3E-2 days/kg th =7.78E6 sec

=1.73E6 sec fp ~ 6/12 =0.5 (DFLi)a = 1.56E-5 mrem/pCi yr, = 0.7 kg/rn 2 Y. = 2.0 kg/rn 2 QF = 50 kg/day These values yield a Ri factor of 1.37E8 rrf-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

Rev. No. 9 Rev. o. 9Page B-37 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(I B. Tritium The concentration of tritium in meat is based on the airborne concentration rather than the deposition. R.is calculated as follows:

R. = K1 K111 F QF Up (DL )a [0.75 (0.5/H)]

(mrem/yr per I.iCilm 3 )

Example Calculation All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of meat. Substituting values into the preceding equation, results in a R. factor of 2.33E2 mrem/yr per pCi/rr? as listed in Table B-5 of this appendix.

V. COW'S MILK A. Radioiodines and Eight Day Particulates For the cow's milk pathway, R is calculated as follows:

I? K' aFLp)Fý (r) (DFLJ)0, + , the-Xt (.

(m 2 -mrem/yr per jtCi/sec)

Where:

Uap = the receptor's milk consumption rate for age (a), in liters/yr (Table B-6.3).

4 = the transport time from pasture to cow, to milk, to receptor in sec (Table B-6.3).

Fm = the stable element transfer coefficients, in days/liter (from Regulatory Guide 1.109, Table E-1).

All other parameters were defined previously.

Rev. No. 9 B-3 of ODOM Rev.No.9Page

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (Iý Examl~le Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of cow's milk:

tf= 1.73E5 sec Ulap = 330 I/yr Fm = 1.OE-3 days/I 2

These values yield a R~ factor of 8.52E7 m?-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

B. Tritium The concentration of tritium in cow's milk is based on the airborne concentration rather than the deposition. R~ is calculated as follows:

Rz. = K' K"'. F, QFUap (DEL.) a [0.75(0.5/H)]

(mrem/year per LCi/m 3 )

Example Calculation All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of cow's milk. Substituting values into the preceding equation, results in a Rý factor of 1.57E3 mrem/yr per pCi/ftr as listed in Table B-5 of this appendix.

VI. GOATS5 MILK A. Radioiodines and Eight Day Particulates For the goat's milk pathway, R,is calculated as follows:

R.= K1Q(X Rp Fm (r) (DEL) [JPL + (1fp 4) e -Xith I e Xilf (M 2 -mrem/yr per gi~lsec)

Rev. No. 9 Rev. o. 9Page B-39 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(F Where:

= the transport time from pasture to goat, to milk, to receptor in sec (Table B-6.3).

Fm = the stable element transfer coefficients. For the radionuclide in question, use Table E-2 of Regulatory Guide 1.109. If the radionuclide is not listed in Table E-2, use Table E-1 (i.e., the same value used for the cow's milk pathway).

All other parameters were defined previously.

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of goat's milk:

OF= 6 kg/day (wet weight)

Fm = I .OE-3 days/I tf = 1.73E5 sec 2

These values yield a R~ factor of 1.02E7 m?-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

B. Tritium The concentration of tritium in goat's milk is based on the airborne concentration rather than the deposition. Fý is calculated as follows:

Ri= K' K"' Fý QF Uap (DFL,), [0.75(0.5/H)]

(mrem/yr per g+/-Cim3 )

Example Calculation:

All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of goat's milk. Substituting values into the preceding equation, result in a R factor of 3.20E3 mrem/yr per pCi/rr? as listed in Table B-5 of this appendix.

Rev. No. -9 Rev. o. 9Page B-40 of ODCM

TABLE B-6.3 PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE Uap (liters/yr)-cow's milk/

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 U21, (liters/yr)-goat's milk!

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 L

Ua (kg/yr)-vegetationl

- infant 0 R.G. 1.109 E-5

- child 26 R.G. 1.109 E-5

- teen 42 R.G. 1.109 E-5

- adult 64 R.G. 1.109 E-5 S

U. (kglyr)-vegetationl

- infant 0 R.G. 1.109 E-5

- child 520 R.G. 1.109 E-5

- teen 630 R.G. 1.109 E-5

- adult 520 R.G. 1.109 E-5 Uap (kgfyr)-meatl

- infant 0 R.G. 1.109 E-5

- child 41 R.G. 1.109 E-5

- teen 65 R.G. 1.109 E-5

- adult 110 R.G. 1.109 E-5 (BR)2 (m/lyr)-inhalation/

- infant 1400 R.G. 1.109 E-5

- child 3700 R.G. 1.109 E-5

- teen 8000 R.G. 1.109 E-5

- adult 8000 R.G. 1.109 E-5 Rev. No. 9 Rev. o. 9Page B-41 of 00CM

TABLE B-6.3 (Continued)

PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE r (dimensionless) 1.0 for R.G. 1.109 E-1 5 Radioiodine 0.2 for R.G. 1.109 E-1 5 Particulates f, (dimensionless) 1.0 R.G. 1.109 E-1 5

f. (dimensionless) 0.76 R.G. 1.109 E-1 5 tL (sec)-vegetation 8.6E4 R.G. 1.109 E-15 tý (sec)-vegetation 5.1 8E6 R.G. 1.109 E-1 5 (DFAi)a, (mrem/pCi)- Each R.G. 1.109 E-7 to inhalation Radionuclide E-1 0 2

DFG, (mrem/hr per pCi/m?)-Each R.G. 1.109 E-6 ground plane Radionuclide SF (dimensionless) 0.7 R.G. 1.109 E-1 5 t (sec)-ground plane 4.73E8 R.G. 1.109 E-1 5 R.G. 1.109 E-3 (.

QF (kg/day)-cow milk 50 QF (kg/day)-goat milk 6 R.G. 1.109 E-3 YP, (kg/rn 2) 0.7 R.G. 1.109 E-1 5 Yý (kg/rn 2) 2.0 R.G. 1.109 E-1 5 (DFLi)a, (mremlpCi)- Each R.G. 1.109 E-1 1 to meat/milk/vegetation Radionuclide E-14 X~(sec") 5.73E-7 R.G. 1.109 E-1 5 tf(sec)-cow milk/ 1.73E5 R.G. 1.109 E-1 5 goat milk th (sec)-cow milk! 7.78E6 R.G. 1.109 E-1 5 goat milk Y,, (kg/rn 2) 2.0 R.G. 1.109 E-15

(

Rev. No. 9 Page B-42 of ODOM

TABLE B-6.3 (Continued)

PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE fp (dimensionless) 0.5 site specific f, (dimensionless) 1.0 NUREG-01 33 page 33 Fm, (days/liter) Each R. G. 1.109 E-1 Radionuclide Ff (days/kg) Each R.G. 1.109 E-l Stable Element tf(sec)-meat 1.73E6 R.G. 1.109 E-1 5 th (sec)-m eat 7.78E6 R.G. 1.109 E-1 5 H (gm/rn3 ) 8.0 NUREG-01 33 page 34 Rev. No. 9 Rev. o. 9.Page B-43 of ODOM

TABLE B-6.4 JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT PATHWAY JUSTIFICATION FOR USAGE

1. NOBLE GAS EXPOSURE (GAMMA)

a. Whole body This pathway is used in the ODOM to calculate dose rates only. This pathway is required by Part I (REC) and NUREG-0133.

b. Gamma Air This pathway is used in the ODOM. This pathway is required by Part 1 (REC) and NUREG-01 33.

2. NOBLE GAS EXPOSURE (BETA)

a. Skin This pathway is used in the ODCM to calculate dose rates only. This pathway is required by Part 1 (REC) and NUREG-0133.

b. Beta Air This pathway is used in the ODOM. This pathway is required by Part 1 (REC) and NUREG-01 33.

3. GROUND PLANE This pathway is used in the ODCM to calculate dose DEPOSITION only. It is not used to calculate dose rates. This pathway is required for use in dose calculation by Part y 1 (REC). Part I (REC) does not require it to be used for dose rate calculations.

4. INHALATION This pathway is used in the ODOM to calculate dose and dose rates. This pathway is required for use in dose and dose rate calculations by the Part I (REC) and NUREG-0133.

5. VEGETATION This pathway is used in the ODOM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. Part 1 (REC) and NUREG-0133 do not require it to be used for dose rate calculations. The calculation of dose factors for stored fruit and vegetables and fresh is combined in one equation in both the ODOM and NUREG-01 33.

K Rev. No. 9 Rev. o. 9Page B-44 of ODOM

TABLE B-6.4 (Continued)

JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT PATHWAY JUSTIFICATION FOR USAGE

6. MEAT This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-01 33. Part 1 (REC) does not require it to be used for dose rate calculations. The calculation of dose factors for Meat Contaminated Feed and Meat Contaminated Forage is combined in one equation in both the 00CM and NUREG-Ol 33.

7. COW'S MILK This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-01 33. Part 1 (REC) does not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the 00CM and NUREG-Ol 33.

8. GOAT'S MILK This pathway is used in the 00C 'Mto calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. Part 1 (REC) and NUREG-0133 do not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the 00CM and NUREG-Ol 33.

Rev. No. 9 Rev. o. 9Page B-45 of 00CM

TABLE B-6.5 ORGAN DOSES FOR GASEOUS RELEASES (INHALATION PATHWAYS)-

___ ______ _ _ ___ ___ ___ADULT _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1 BONE J LIVER THYROID TKIDNEY T LUNG _GI-LLI T. BODY YEAR j (mrem) (mrem) _______ (mrem) (mrem)J (mrem)(m 7 mr 1997 1996 1.89E-07 5.06E-07 J7.25E-04 1.88E-04 7.34E-04 2.84E-04 I7,25E-04 I7.27E-04 I7.25E-04 I7.25E-04 I1.89E-04 I1.91E-04 I1.88E-04 I1.88E-04 1995 7.91 E-07 5 . 34E-05 1.51 E-04 5.37E-05 I5.65E-05 5.34E-05 5.28E-05 1994 7.63E-07 I6. 17E-05 I2.53E-04 I6.23E-05 I7.46E-05 I6.19E-05 I6. 1OE-05 1993 1.05E-06 J6.07E-05 j1.32E-04 6.07E-05 8.13E-05 j6.11 E-05 6__.OOE-05

________ _______ T.EEN . _ _ _ _ _ _ _ _ _ _ _ _

I BONE fLIVER THYROID JKIDNEY LUNG J GI-LLl T. BODY YEAR (mrem) (mrem) (mrem) (mrem) _________ (mrem) I(mrem)_

1997 1996 2.68E-07 7.11IE-07 I7.31 E-04 I7.42E-04 I7.31 E-04 I7.34E-04 I7.31 E-04 1.91 E-04 3.15E-04 I1.91 E-04 I1.95E-04 I1.90E-04 7.31 E-04 1.90E-04 1995 7.04E-07 I5.40E-05 j1 .84E-04 I5.46E-05 I5.91 E-05 5.40E-05 5.33E-05 1994 1.07E-06 I6.26E-05 I3.09E-04 I6.35E-05 I8.17E-05 I6.24E-05 6.16E-05 1993 6.56E-07 6.16E-05 1.55E-04 6.16E-05 j9.21E-05 6.15E-05 6.06E-05

____ ____ _________CHILD._ _ _ _ _ _ _ __ _ _ _ _ _

I BONE ILIVER JTHYROID rKIDNEY J LUNG GI-LLI T. BODY YEAR j (mrem) 1(m r e M) __________ (mrem) _________ (mrem) I(mrem) 1997 1996 3.67E-07 9.69E-07 I6.44E-04 I6.59E-04 I6.44E-04 I6.47E-04 I6.44E-04 I1 .68E-04 I3.20E-04 I1 .68E-04 I1.71 E-04 I1 .67E-04 6.44E-04 1.67E-04 1995 1.53E-06 I4.78E-05 I2.08E-04 I4.82E-05 I5.19E-05 I4.72E-05 4.71 E-05 1994 1.44E-06 I5.53E-05 I3.52E-04 I5.61 E-05 I7.07E-05 I5.44E-05 5.45E-05 1993 1.96E-06 j5.44E-05 1.72E-04 J5.43E-05 J7.92E-05 j5.36E-05 5.36E-05 YEAR BONE (mrem) j

_________INFANT LIVER (mrem)

THYROID (mrem)

_T KIDNEY (mrem I

LUNG (mrem)

I J

GI-LLI (mrem)

IT.

BODY (mrem) 1997 1996 2.50E-07 7.13E-07 3.72E-04 9.71 E-05 I3.85E-04 I3.72E-04 I3.74E-04 I3.72E-04 I2.37E-04 I9.72E-05 I9.96E-05 I9.66E-05 3.72E-04 9.68E-05 1995 9.91 E-07 2.79E-05 I1.74E-04 I2.79E-05 I3.09E-05 I2.72E-05 2.72E-05 1994 1.09E-06 3.25E-05 3.04E-04 I3.26E-05 I4.22E-05 I3.13E-05 3.15E-05 1993 1.12E-06 3,16E-05 ]1.39E-04 j3.14E-05 J4.80E-05 J3.1 OE-05 L__.09E-05

The critical organ is the thyroid for the years 1993 to 1997.

The critical age group is the teen for 1997 and the child for 1993 to 1996.

Rev. No. 9 Rev. o. 9Page B-46 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(I tL = 8.6E4 sec th = 5.18E6 sec 2

Y" = 2 kg/rn r = 0.2 A,= 4.2E-9 sec~l Aw= 5.73E-7 sec' (DIFLi) = 1 .56E-5 mrem/pCi 2

These values yield an R.factor of 1.12E9 m?-mrem/yr per pCi/sec as listed in Table B-4 of this appendix.

B. Tritium The concentration of tritium in vegetation is based on the airborne concentration rather than the deposition. l~is calculated as follows:

RKK" (U,,' fL + U. fg) (DFLi)a, [0.75 (0.5/H)]

(mrem/yr per tCi/m3 )

Where:

K' = unit conversion constant, 10 pCi/pCi.

K... = unit conversion constant, iO0 gm/kg.

0.75 = the fraction of vegetation which is water (NUREG-QI 33).

0.50 1= the ratio of the specific activity of the vegetation that is water to the atmospheric water (NUREG-01 33).

H = absolute atmospheric humidity, in gm/rrd (Table B-6.3).

All other parameters are as previously defined above.

Rev. No. 9 Rev. o. 9Page B-35 of ODOM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (Fý Example Calculaition For the H-3 child whole body dose factor from exposure due to ingestion of vegetation:

L U2 = 26 kg/yr Ua = 520 kg/yr fg = 0.76 (DFI-), = 2.03E-7 mrem/pCi H = 8 gm/rn3 (NUREG-Ol 33)

These values yield a R~ factor of 4.01 E3 mrem/yr per pCi/rr? as listed in Table B-4 of this appendix.

IV. MEA A. Radioiodines And Eight Day Particulate~

R. =K' QF (UaP) F (r) (DFLf) + -ff)e 1 At (m 2 -mrern/yr per ýtCi/sec)

Where:

Uap = the receptor's meat consumption rate for age (a), in kg/yr (Table B-6.3).

F,= the'stable element transfer coefficients, in days/kg (Table E-1 of Regulatory Guide 1.109).

tf= the transport time from pasture to receptor, in sec (Table B-6.3).

th = the transport time from crop field to receptor, in sec (Table B-6.3).

Rev. No. 9 Rev.No~jPage B-36 of ODCM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(F YP= the agricultural productivity by unit area of pasture feed grass, in kg/ni (Table B-6.3).

Y,= the agricultural productivity by unit area of stored feed, in kg/ni (Table 13-6.3).

fp = fraction of the year that the cow is on pasture (Table 13-6.3).

f, = fraction of the cow feed that is pasture grass while the cow is on pasture (Table B-6.3).

Qf= the cow's consumption rate, in kg/day (wet weight). See Table B-6.3.

All other parameters were defined previously.

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of meat:

Uap = 41 kg/yr Ff = 1.3E-2 days/kg th = 7.78E6 sec

= 1 .73E6 sec fp ~= 6/12 =0.5 (DFLi)a, = 1.56E-5 mrem/pCi 2

YP = 0.7 kg/in 2

YS = 2.0 kg/in QF = 50 kg/day These values yield a RI factor of 1.37E8 rrf-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

Rev. No. -9 B-37 of ODOM Rev. o. 9Page

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS (11ý B. Tritium The concentration of tritium in meat is based on the airborne concentration rather than the deposition. R.is calculated as follows:

R. = K1 K"' Ff QF Uap (DFL), [0.75 (0.5/H)]

(mrem/yr per p.CiIM 3 )

Example Calculation:

All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of meat. Substituting values into the preceding equation, results in a Fý- factor of 2.33E2 mrem/yr per pCi/iT? as listed in Table B-5 of this appendix.

V. COW'S MILK A. Radioiodines and Eight Day Particulates For the cow's milk pathway, 1`3 is calculated as follows:

R.K'QF(UaP) DFp 0' 4) e e (A+k) Fm ia P 1r (M 2 -mrem/yr per ýtCi/sec)

Where:

Uap = the receptor's milk consumption rate for age (a), in liters/yr (Table 8-6.3).

= the transport time from pasture to cow, to milk, to receptor in sec (Table B-6.3).

Fm = the stable element transfer coefficients, in days/liter (from Regulatory Guide 1.109, Table E-1).

All other parameters were defined previously.

Rev. No. 9 B-38 of ODOM Rev. o. 9Page

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(I Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of cow's milk:

= 1.73E5 sec Ua = 330 I/yr Fm = I .OE-3 days/I These values yield a R,factor of 8.52E7 m?-mrem/yr 2 per pCi/sec as listed in Table B-5 of this appendix.

B. Tritium The concentration of tritium in cow's milk is based on the airborne concentration rather than the deposition. R~ is calculated as follows:

Ri= K' K... FM QF Uap (DFLi)a, [0.75(0.5/H)]

(mrem/year per p~Ci/M 3 )

Example Calculation:

All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of cow's milk. Substituting values into the preceding equation, results in a R. factor of 1.57E3 mrem/yr per pCi/rr? as listed in Table B-5 of this appendix.

Vi. GOATS MILK A. Radioiodines and Eight Day Particulates For the goat's milk pathway, R~ is calculated as follows:

(1ý)0-fpf4) -eth 1 ________

a1p- F (r) (DFLA' ýf + e, e (m 2 -mrem/yr per jiCi/sec)

Rev. No. 9 Rev. o. 9Page B-39 of ODOM

TABLE B-6.2 (Continued)

DERIVATION OF GASEOUS DOSE FACTORS(i Where:

tf = the transport time from pasture to goat, to milk, to receptor in sec (Table B-6.3).

Fm = the stable element transfer coefficients. For the radionuclide in question, use Table E-2 of Regulatory Guide 1.109. If the radionuclide is not listed in Table E-2, use Table E-1 (i.e., the same value used for the cow's milk pathway).

All other parameters were defined previously.

Example Calculation:

For the Co-60 child whole body dose factor from exposure due to ingestion of goat's milk:

QF = 6 kg/day (wet weight)

Fm = I .OE-3 days/I tf= 1.73E5 sec 2

These values yield a F~factor of 1.02E7 m?-mrem/yr per pCi/sec as listed in Table B-5 of this appendix.

B. Tritium The concentration of tritium in goat's milk is based on the airborne concentration rather than the deposition. Rý is calculated as follows:

R. = K' K"' Fm QF Uap (DFL1 ) [0.75(0.5/H)]

(mrem/yr per gi~lm3 )

Example Calculation:

All parameters have been defined in the previous sections for the H-3 child whole body dose factor from exposure due to ingestion of goat's milk. Substituting values into the preceding equation, result in a R~factor of 3.20E3 mrem/yr per pCi/nf as listed in Table B-5 of this appendix.

Rev. No. 9 B-40 of ODCM Rev.No.9Page

TABLE B-6.3 PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE REFERENCE TABLE U~, (liters/yr)-cow's milk/

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 Uap (liters/yr)-goat's milk!

- infant 330 R.G. 1.109 E-5

- child 330 R.G. 1.109 E-5

- teen 400 R.G. 1.109 E-5

- adult 310 R.G. 1.109 E-5 L

Ua (kglyr)-vegetationl

- infant 0 R.G. 1.109 E-5

- child 26 R.G. 1.109 E-5

- teen 42 R.G. 1.109 E-5

-adult 64 R.G. 1.109 E-5 6a (kglyr)-vegetationl

- infant 0 R.G. 1.109 E-5

- child 520 R.G. 1.109 E-5

- teen 630 R.G. 1.109 E-5

- adult 520 R.G. 1.109 E-5 U2a, (kglyr)-meatl

- infant 0 R.G. 1.109 E-5

- child 41 R.G. 1.109 E-5

- teen 65 R.G. 1.109 E-5

- adult 110 R.G. 1.109 E-5 (BR). (m3!yr)-inhalationf

- infant 1400 R.G. 1.109 E-5

- child 3700 R.G. 1.109 E-5

- teen 8000 R.G. 1.109 E-5

- adult 8000 R.G. 1.109 E-5 Rev. No. -9 B-41 of ODOM Rev. o. 9Page

TABLE B-6.3 (Continued)

PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMETERS VALUE, REFERENCE TABLE r (dimensionless) 1.0 for R.G. 1.109 E-15 Radioiodine 0.2 for R.G. 1.109 E-1 5 Particulates f, (dimensionless) 1.0 R.G. 1.109 E-1 5

f. (dimensionless) 0.76 R.G. 1.109 E-15 tL (sec)-vegetation 8.6E4 R.G. 1.109 E-1 5 th (sec)-vegetation 5.18E6 R.G. 1.109 E-1 5 (IDFAi)a (mrem/pCi)- Each R.G. 1.109 E-7 to inhalation Radionuclide E-1 0 DES, (mrem/hr r~er DCi/rr?)-Each R.G. 1.109 E-6 ground plane Radionuclide SF (dimensionless) 0.7 R.G. 1.109 E-1 5 t (sec)-ground plane 4.73E8 R.G. 1.109 E-1 5 QF (kg/day)-cow milk 50 R.G. 1.109 E-3 QF (kg/day)-goat milk 6 R.G. 1.109 E-3 yp (kg/rn 2) 0.7 R.G. 1.109 E-15 Y, (kg/in 2) 2.0 R.G. 1.109 E-1 5 (DFLi)a (mrem/pCi)- Each R.G. 1.109 E-1 1 to meat/milk/vegetation Radionuclide E-1 4 X~(sec 1l) 5.73E-7 R.G. 1.109 E-1 5 tf(sec)-cow milk/ 1.73 E5 R.G. 1.109 E-1 5 goat milk th (sec)-cow milk! 7.78E6 R.G. 1.109 E-1 5 goat milk Y, (kg/rn 2 ) 2.0 R.G. 1.109 E-1 5 K

Rev. No. 9 Rev. o. 9Page B-42 of ODOM

TABLE B-6.3 (Continued)

PARAMETER FOR THE GASEOUS EFFLUENT PATHWAY PARAMEITFIRS VAI LIE REFERENCE TABLE VALH fp (dimensionless) 0.5 site specific f, (dimensionless) 1.0 NUREG-0133 page 33 Fm (days/liter) Each R. G. 1.109 E-1 Radionuclide Ef (days/kg) Each R.G. 1.109 E-1 Stable Element (sec)-meat 1.73E6 R.G. 1.109 E-1 5 th (sec)-meat 7.78 E6 R.G. 1.109 E-15 H (gmftms) 8.0 NUREG-01 33 page 34 Rev. No. -9 B-43 of ODCM Rev. o. 9Page

TABLE B-6.4 JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT r

PATHWAY JUSTIFICATION FOR USAGE I1. NOBLE GAS EXPOSURE (GAMMA)

a. Whole body This pathway is used in the ODOM to calculate dose rates only. This pathway is required by Part I (REC) and NUREG-Ol 33.

b. Gamma Air This pathway is used in the ODOM. This pathway is required by Part 1 (REC) and NUREG-0133.

2. NOBLE GAS EXPOSURE (BETA)

a. Skin This pathway is used in the ODOM to calculate dose rates only. This pathway is required by Part 1 (REC) and NUREG-O1 33.

b. Beta Air This pathway is used in the ODOM. This pathway is required by Part 1 (REC) and NUREG-01 33.

3. GROUND PLANE This pathway is used in the ODOM to calculate dose DEPOSITION only. It is not used to calculate dose rates. This pathway is required for use in dose calculation by Part K, 1 (REC). Part 1 (REC) does not require it to be used for dose rate calculations.

4. INHALATION This pathway is used in the ODOM to calculate dose and dose rates. This pathway is required for use in dose and dose rate calculations by the Part I (REC) and NUREG-0133.

5. VEGETATION This pathway is used in the ODOM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-01 33. Part 1 (REC) and NUREG-01 33 do not require it to be used for dose rate calculations. The calculation of dose factors for stored fruit and vegetables and fresh is combined in one equation in both the ODCM and NUREG-Ol 33.

Rev. No. 9 B-44 of ODOM Rev.No.9Page

TABLE B-6.4 (Continued)

JUSTIFICATION FOR GASEOUS PATHWAYS USED TO ASSESS DOSE AT THE J. A. FITZPATRICK NUCLEAR POWER PLANT PATHWAY JUSTIFICATION FOR USAGE

6. MEAT This pathway is used in the ODOM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-0133. Part 1 (REC) does not require it to be used for dose rate calculations. The calculation of dose factors for Meat Contaminated Feed and Meat Contaminated Forage is combined in one equation in both the ODCM and NUREG-0133.

7. COW'S MILK This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-QI 33. Part 1 (REC) does not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the ODCM and NUREG-Ol 33.

8. GOAT'S MILK This pathway is used in the ODCM to calculate dose only. It is not used to calculate dose rates. This pathway is required for use in dose calculations by NUREG-01 33. Part 1 (REC) and NUREG-01 33 do not require it to be used for dose rate calculations. The calculation of dose factors for Milk Contaminated Feed and Milk Contaminated Forage is combined in one equation in both the ODCM and NUREG-Ol 33.

Rev. No. -9 Rev. o. 9Page B-45 of ODOM

TABLE B-6.5 ORGAN DOSES FOR GASEOUS RELEASES (INHALATION PATHWAYS)-

_____ ____ ____ _____ ____ADULT _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

I BONE) ILIVER THYROID KIDNEY ] LUNG GI-LLI jT. BODY YEAR j (rm mrm _______ (mrem) j (mrem) __Lre j (mrem) 1997 1996 1.89E-07 5.06E-07 7.25E-04 1.88E-04 II2.84E-04 7.34E-04 I 7.25E-04 I 7.27E-04 I1 .89E-04 I1.91 E-04 7.25E-04 1.88E-04 17.25E-04 I.88E-04 1

1995 7.91 E-07 5.34E-05 I1.51 E-04 I5.37E-05 I5.65E-05 5.34E-05 I5.28E-05 1994 7.63E-07 6.17E-05 I2.53E-04 I6.23E-05 7.46E-05 6.19E-05 I6.10E-05 1993 1.05E-06 6.07E-05 1.32E-04 6.07E-05 J 8.13E-05 6.11 E-05 [6.OOE-05

__ __ __ __ __ _ _ __ _ _ EEN ___ ............. _

BONE) LIVER THYROID KIDNEY LUNG) GI-LLI T. BODY YEAR [j re (me)(rm n(rm 1997 1996 2.68E-07 7.11 E-07 7.31 E-04 1.91 E-04 II3.15E-04 7.42E-04 I 7.31 E-04 I 7.34E-04 I1. 91 E-04 I1.95E-04 7.31 E-04 1.90E-04 I7.331 I1.90EE-04 E-04 1995 7.04E-07 5.40E-05 I 1.84E-04 5.46E-05 5.91 E-05 5.40E-05 55.3333E-05 1994 1.07E-06 6.26E-05 I3.09E-04 I6.35E-05 I8.17E-05 6.24E-05 E66.116EE -0 5 1993 6.56E-07 6.16E-05 J 1.55E-04 6.16E-05 J 9.21 E-05 6.15E-05 6.06E-05 BOE IVR TYRID~[ KID NEY ~f LUNG 1 GI-LLI T. BODY YEAR j (mrem) j mrem) I~ n me) me) j~

I (mrem) 1997 1996 1I9.69E-073.67E-07 6.44E-04 1.68E-04 6.59E-04 3.20E-04 II 6.44E-04 1.68E-04 II1.71 6.47E-04 16.44E-04 I6.44E-04 E-04 I1 .67E-04 I1 .67E-04 1995 I1.53E-06 4.78E-05 2.08E-04 I4.82E-05 I5.19E-05 I4.72E-05 I4.71 E-05 1994 I1 .44E-06 5.53E-05 3.52E-04 5.61 E-05 I7.07E-05 5.44E-05 5.45E-05 1993 J 1.96E-06 5.44E-05 1.72E-04 5.43E-05 J 7.92E-05 [ 5.36E-05 5]..36E-05

________ ________INFANT_ _ _ _ _ _ _ _ __ _ _ _ _

I BONE) [ LIVER THYROID I INY I LUNG [ ILI IT. BOD YEAR J (mrem) (mrem) (mrem) (mrem) J (mrem) j (mrem) j~(mrem) 1997

-1996 I2.50E-07 I7.13E-07 3.72E-04 9.71 E-05 3.85E-04 2.37E-04 I 3.72E-04 9.72E-05 II9.96E-05 3.74E-04 I 3.72E-04 I3.72E-04 I9.66E-05 I9.68E-05 1995 I9.91 E-07 2.79E-05 1.74E-04 2.79E-05 I3.09E-05 I2.72E-05 I2.72E-05 1994 I1.09E-06 3.25E-05 3.04E-04 I3.26E-05 I4.22E-05 I3.13E-05 I3.15E-05 1993 1.12E-06 3.16E-05 1.39E-04 3.14E-05 J 4.80E-05 3.1IOE-05 3.09E-05

The critical organ is the thyroid for the years 1993 to 1997.

The critical age group is the teen for 1997 and the child for 1993 to 1996.

Rev. No. 9 Rev. o. 9Page B-46 of ODCM

APPENDIX C METEOROLOGICAL INDEX Rev. No. 9 C-I of ODOM Rev. o. 9Page

APPENDIX C METEOROLOGICAL INDEX The atmospheric dispersion and deposition tables presented in this Appendix were prepared using 8 years' worth of hourly meteorological data (at 10 m and 61 m above grade) collected on site by Niagara Mohawk during the period 1985 through 1992. The tables include the following:

(a) Long-term annual average concentration (X/Q)s, finite-cloud gamma (X/Q)s, and (DIQ)s for the main stack, the four building vents, and unmonitored ground-level releases (site boundary and offsite receptors) [Tables C-I through C-8, C-18, and C-20],

(b) Long-term grazing season concentration (X/Q)s and (D/Q)s for the main stack, the four building vents, and unmonitored ground-level releases (offsite receptors excluding the site boundary) [Tables 0-9 through C-1 3, 0-22 and C-24],

(c) Short-term 85th percentile hourly plume centerline concentration (X/Q)s and (D/Q)s for unmonitored ground-level releases, based on year-round meteorological data (site boundary and offsite receptors) [Tables C-1 5, 0-1 6, 0-1 7 and C-1 9],

(d) Short-term 85th percentile hourly plume centerline concentration (XIQ)s and (D/Q)s for unmonitored ground-level releases, based on meteorological data for the grazing season (offsite receptors excluding the site boundary [Tables 0-21 and C-23],

(e) Critical receptor long-term dispersion and deposition parameters for vent and elevated releases, year-round and grazing season averages [Table 0-14].

The receptors of interest include the site boundary (SB) and various offsite locations in each sector at distances out to 45 miles. Note the following:

(1) The long-term annual average concentration (X/Q)s and finite-cloud gamma (XIQ)s which were based on the sector-average model, are for use in assessing the air doses (gamma and beta), total body and skin dose, and doses due to inhalation from the various release points. The long-term annual average (DIQ)s are for assessing the radiation exposures due to ground plane deposition of radioactivity.

(2) The long-term grazing season concentration (X/Q)s and (D!Q)s are for use in assessing the radiation exposures for the ingestion pathway. Based on census data, the grazing season was taken to be six months (May through October).

Rev. No. -9 Rev. o. C-2 9Pageof ODOM

(3) The 85th percentile hourly concentration (XIQ)s and (DIQ)s were based on the plume-centerline model and are for use in conjunction with short-term releases, as described in Section 4.4.3 of the ODCM. The selected percentile (85%) is applicable for the assessment of intermittent releases; it implies that the probability of exceeding the calculated hourly dispersion and deposition values is only 15%.

(4) The dispersion and deposition parameters for the stack were based on the "elevated plume" model (with plume rise effects, and terrain features, but without building wake effects), and the meteorological data collected on the 61-in elevation of the meteorological tower. The dispersion and deposition parameters for the building vents (reactor building, refuel floor, turbine building, and radwaste building) were based on the "mixed-mode" release (with plumne rise and building wake effects), and the data collected on the 10-in elevation of the tower. Unmonitored ground-level releases made use for the "ground release" model (with building wake effects, but without plume rise) and the meteorological data collected on the 10-in elevation of the tower.

(5) For vent releases and unmonitored ground-level releases, the equations for gamma air dose, total body dose, and the gamma portion of skin dose make use of the concentration (X/Q) (i.e., the semi-infinite cloud model). For stack releases, on the other hand, the equations for the said exposures make use of the finite-cloud gamma (X/Q). By definition, the gamma (X/Q) is the equivalent relative concentration of radioactivity in a semi-infinite cloud that would yield the same radiation exposure as a finite cloud aloft; it accounts for the actual plume dimensions, elevation above the receptor, and gamma radiation spectra.

Complete details on the definition of the dispersion and deposition values presented in this appendix may be found in Reference 6.10.

Rev. No. 9 Rev. o. 9Page 0-3 of ODOM

APPENDIX C METEOROLOGICAL DATA TABLE ITITLE PAGE C-1 Concentration X/Q Values for Site Boundary Determined From C-7 Annual Average Meteorological DataI C-2 Finite Cloud Gamma X/Q Values for Site Boundary Determined C-8 From Annual Average Meteorological Data C-3 Deposition DIQ Values for Site Boundary Determined From C-9 Annual Average Meteorological Data 0-4 Sector Average Dispersion And Deposition Values For Reactor 0-10 Vent Determined From Annual Average Meteorological Data 0-5 Sector Average Dispersion And Deposition Values For Refuel C-I 2 Floor Vent Determined From Annual Average Meteorological Data C-6 Sector Average Dispersion And Deposition Values For Turbine 0-14 Vent Determined From Annual Average Meteorological Data 0-7 Sector Average Dispersion And Deposition Values For Radwaste C-1 6 Vent Determined From Annual Average Meteorological Data 0-8 Sector Average Dispersion And Deposition Values For The Stack 0-18 Determined From Annual Average Meteorological Data 0-9 Sector Average Dispersion And Deposition Values For Reactor C-19 Vent Determined From Grazing Meteorological Data 0-1 0 Sector Average Dispersion And Deposition Values For Refuel C-20 Floor Vent Determined From Grazing Meteorological Data C-Il1 Sector Average Dispersion And Deposition Values For Turbine 0-25 Vent Determined From Grazing Meteorological Data 0-1 2 Sector Average Dispersion And Deposition Values For Radwaste 0-27 Vent Determined From Grazing Meteorological Data 0-1 3 Sector Average Dispersion And Deposition Values For The Stack 0-29 Determined From Grazing Meteorological Data Rev. No. -9 Rev. o. 9Page C-4 of ODOM

APPENDIX C METEOROLOGICAL DATA (CONTINUED)

TABLE TITLE PAGE C-14 Critical Receptor Dispersion And Deposition Parameters For Vent C-32 And Elevated Releases C-1i5 85th Percentile Hourly Plume Centerline Dispersion Values and C-33 Annual Sector Average Dispersion Values For Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-1 6 85th Percentile Hourly Plume Centerline Deposition Values and C-34 Annual Sector Average Deposition Values For Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1 992) (For Use With Short Term Releases)

C-1 7 85th Percentile Hourly Plume Centerline Dispersion Values For C-35 Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1 992) (For Use With Short Term Releases)

C-18 Sector Average Dispersion Values For Unmonitored Ground Level C-36 Releases Determined From Annual Average Meteorological Data (1985-1 992) (For Use With Long Term Releases)

C-1 9 85th Percentile Hourly Plume Centerline Deposition Values For C-37 Unmonitored Ground Level Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-20 Sector Average Deposition Values For Unmonitored Ground Level C-38 Releases Determined From Annual Average Meteorological Data (1985-1992) (For Use With Long Term Releases)

C-21 85th Percentile Hourly Plume Centerline Dispersion Values For C-39 Unmonitored Ground Level Releases Determined From Grazing Meteorological Data (1985-1 992) (For Use With Short Term Releases)

Rev. No. -9 Rev. o. 9Page C-5 of ODCM

APPENDIX C METEOROLOGICAL DATA (CONTINUED)

TABLE TITLE PAGE C-22 Sector Average Dispersion Values For Unmonitored Ground Level C-40

.Releases Determined From Grazing Meteorological Data (1985-1 992) (For Use With Long Term Releases)

C-23 85th Percentile Hourly Plume Centerline Deposition Values For C-41 Unmonitoredi Ground Level Releases Determined From Grazing Meteorological Data (1985-1992) (For Use With Short Term Releases)

C-24 Sector Average Deposition Values For Unmonitored Ground C-42 Level Releases Determined From Grazing Meteorological Data (1985-1992) (For Use With Long Term Releases)

Rev. No. -9 0-6 of 00CM Rev. o. 9Page

TABLE C-I CONCENTRATION XJQ VALUES FOR SITE BOUNDARY DETERMINED FROM ANNUAL AVERAGE METEROLOGICAL DATA (1985 To 1992)

Sector Average Concentration XIQ (seclm3 )

Turbine Ref uel Radwaste Reactor Unmoni to red Distance Building Floor Building Building Ground Level Re-jr qtae-k Vent Vent Vent Vent Relan-N w 225 1.05E-10 3.81E-06 4. 65E-06 5.75E-06 4.*6 53-06 3.50E-05 NNE w .225 3.581-11 1.68E-06 2.05E-06 2.60E-06 2.05E-06 1.7 8E-05 NE w 354 7.52E-10 6.53E-07 8.02E-07 1. 12E-06 8.02E-07 5.*34E-0 6 ENE w 563 1.51E-08 7.82E-07 9.21E-07 1.35E-06 9 .21H-07 3.43E-06 E 1 950 1.64E-08 3.19E-07 3.58E-07 5.39E-07 3.58E-07 1.051-06 1 1030 1.7 8E-08 1.7 8E-07 1.97E-07 3.02E-07 1.97E-07 5.86E-07 ISE 1 1110 1. 94E-08 1.22E-07 1.33E-07 2.28E-07 1.331-07 4.17E-07 SSE 1 1754 1.5 7E-08 4.749-08 4.94E-08 9.17E-08 4.94E-08 1.73E-07 S 1 2205 1.79E-08 4 .71E-08 4.80E-08 8. 30E-08 4.80E-08 1.36E-07 S SW 1 2269 2.19E-08 6.11E-08 6.25E-08 1.14E-07 6.25E-08 2.001-07 SW 1 2382 1.64E-08 7.97E-08 8.17E-08 1.60E-07 8.17E-08 3.14E-07 wWS w 1867 3.559-09 4.081-08 4.52E-08 1.23E-07 4. 52E-08 4.14E-07 W w 644 1.33E-09 9.17E-08 1.43E-07 2 .48E-07 1.43E-07 2.68H-06 wWN w 370 1.87E-09 6. 82H-07 9.99E-07 1.37E-06 9 .99E-07 1.3 9E-05 NW w 306 2 . 50E-09 1.77E-06 2.37E-06 3.09E-06 2.37E-06 2.60E-05 w 241 3.96E-10 2.98E-06 3.85E-06 4. 81E-06 3.85E-06 3.68E-05 1 =land w = water Rev. No. 9 Q-7 of ODOM Rev. o. 9Page

TABLE C-2 FINITE CLOUD GAMMA X/Q VALUES FOR SITE BOUNDARY DETERMINED FROM ANNUAL AVERAGE METEROLOGICAL DATA (1985 To 1992)

Finite Cloud Gamma XIQ (sec/rn 3 )

Distance Direction Stack N 225 1. 32H-07 NN2E 225 1.06E-07 NE 354 1.12R-07 ENE 563 1. 82E-07 E 950 1.169-07 ESE 1030 7.*7lE -08 SE 1110 6 .23R-08 SSE 1754 3. 34E-08 S 2205 3. 02E-08 SSW 2269 3.*89E-08 SW 2382 3 .45E-08 WSW 1867 2 .20E-08 W 644 5 .43E-08 WNW 370 8.40E-08 NW 306 1.38E-07 NNW 241 1.38E-07 1 = land w = water Rev. No. -9 Rev. o. 9Page 0-8 of ODCM

TABLE C-3 DEPOSITION DIQ VALUES FOR SITE BOUNDARY DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(DIQ), Sector Average Deposition (l/rnf)

SEGMENT BOUNDARIES IN MILES Turbine Ref uel Radwaste Reactor Uanmon itored Distance Building Floor Building Building Ground Level It?, 0. IT. 4- 'JI, XT- . za nfl ..

Direction (ml Stack w 225 2.95H-10 2.27E-08 2.65E-08 3.63E-08 2.651-08 1.33E-07 NI w 225 9.26E-11 1.02E-08 1.18E-08 1. 65E-08 1.18E-0 8 7.09E-08 w 354 9.30H-11 6.21E-09 7 .301-09 1.05E-08 7 .301-09 3 .003-08 REN w 563 1. 651-09 1.40E-08 1.55E-08 2.001-08 1.551-08 3.231-08 1 950 1.73E-09 9.03E-09 9.49E-09 1.111-08 9.49E-09 1. 35E-08 1 1030 1.70E-09 6.22E-09 6.49E-09 7.431-09 6.49E-09 8.7'61-09 ESE 1 1110 1.6 1E-09 4 .37E-09 4.54E-09 5.42E-09 4.54E-09 6.461-09 SE 1 1754 7.57E-10 1.16E-09 1. 191-09 1.39E-09 1.19E-09 1. 85H-09 SSE 1 2205 5.52E-10 9.151-10 9.311-10 1.06E-09 9.311-;10 1. 41H-09 SW 1 2269 6.50E-10 7.66E-10 7.761-10 9.33E-10 7.76E-10 1. 37E-09 1 2382 3 .23E-10 7.- 0E-l0 7.091-10 9.001E-10 7 .091-10 1. 511-09 WSW w 1867 9.10E-11 2.97E-10 3.08E-10 4.6 8E-10 3 .081-10 1.25E-09 w 644 7.43E-11 7 .58R-10 9.151-10 1.591-09 9.15E-10 7.79E-09 lW w 370 1.891-10 4.56E-09 5.561-09 8.40E-0 9 5. 56E-09 4.101-08 w 306 4.28E-10 1.22E-08 1. 45E-08 2.08E-08 1.45E-08 8.55E-08 NNW w 241 3.63E-10 1.71E-08 2.03E-08 2.80E-08 2.03E-08 1.143-07 I2= land w = water Rev. No. 9 C-9. of ODOM Rev. No.9Page

TABLE C-4

(

SECTOR AVERAGE DISPERSION VALUES FOR REACTOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentration X/Q (sec/n?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.667E-07 3 .319E-07 2.409B-07 1.596E-07 9.3803-08 6.472E-08 NNE 2.6003-07 1.591E-07 1.1983-07 8.2353-08 4.960E-08 3.446E-08 NE 2.2 96E-07 1.4 109-07 1.048E-07 7.034E-08 4.129E-08 2.830E-OS ENE 5.479E-07 3. 185E-07 2.2603-07 1.4 52E-07 7.962E-OS 5.2 87E-08 4.5283-07 2.6013-07 1.808E-07 1.13 2E-07 5.918E-OS 3 .843E-08 ESE 2.804E-07 1.63113-07 1. 142E-07 6.935E-08 3 .941E-08 2 .559E-08 SE 1. 991E-07 1.2 043-07 8.7153-08 5.609E-OS 3.276E-08 2.602E-08 SSE 1. 071E-07 6.936K-0S 5.348E-0S 3.911E-08 2.8353-08 2.013E-08 S 1.150E-07 7.388K-OS 5. 963H-O8 4.379E-08 3.2183-08 2.223E-08 S SW 1.3 88E-07 9.*086E-OS 7.603B-OS 5.*888K-OS 3.860E-OS0 2.786E-OS SW 1. 68SE-O7 1.12 9E-07 1.094E-07 8.073E-OS 5.2903-08 3.5763-08 WSW 8 .263E-08 5.5513-08 4.795E-OS 4.949E-OS 3 .369E-08 2.4303-OS w 1.04 0Z-07 6 .463E-08 5.213E-08 4.115X-08 2.881E-OS 2.1513-OS WNW 2. 926E-07 1.7 54E-07 1.326E-07 9.420E-08 5.9553-08 4.2603-08 NW 5.036E-07 3.0053-07 2 .226E-07 1.52 0H-07 9.183E-08 6.416E-0 8 5.247E-07 3. 0413-07 2.202E-07 1.468E-07 8.737E-08 6.082E-08 4.5 7.5 15.0 25.0 35.0 45.0 K 4 .865K-OS 2.687K-OS 1.186E-08 6.640E-09 4.4583-09 3 .915E-09 2 .595K-OS 1.428K-O8 6.212E-09 4.9453-09 3.183E-09 2 .299E-09 NNE 2.li0E-08 1.138K-OS 5.166E-09 3.3383-09 2 .130E-09 1.53 0B-09 KNE 3.5870E-08 2.034E-OS 1.024E-08 5.223E-09 3.362E-09 2 .43 0B-09 2 .779K-08 1.440K-OS 7.309E-09 3.751E-09 2.434E-09 .1.772H-09 ESE 1.849E-O8 1.133K-OS 4.571E-09 2.357E-09 1. 53 53-09 1.121E-0 9 1.833K-OS 9.16 5E-09 3.6933-09 1.922E-09 1. 261H-09 9.2703-10 SE 1.438E-0S 7.159E-09 2.869E-09 1.492E-09 9.784E-10 7 .185E-10 SSW 1.5953-08 7 .922E-09 3.182E-09 1.659E-09 1.0913-09 8.025E-10 SW 2 .231K-OS 1.089E-OS 4.2783-09 2.156E-09 1. 385E-09 1.0023-09 SWw 2.896K-OS 1.667K-OS 6.450E-09 3.3573-09 2.135E-09 1.532E-09 SW 1.856E-OS 1.029K-0S 4.799E-09 2.500E-09 1.783E-09 1.393E-09 WSW 1.690E-OS 9.922E-09 4.586E-09 2.552E-09 1.729E-09 1.294E-09 NW 3.276E-OS 1.885K-OS 8.746E-09 4.942E-09 3 .391E-09 2.562E-09 4.862E-OS 2.733E-OS 1.241E-08 6.932E-09 4 .729E-09 3 .560E-09 4 .607E-08 2.596H-O8 1.186E-08 6.657B-09 4.554E-09 3 .433E-09 K

Rev. No. 9 . Rev. C-1 o.9Page of ODOM

TABLE C-4 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REACTOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(DIQ) Sector Average Deposition (1/nif)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 K 4.951H-09 2.8563-09 1.927E-0 9 1.0651-09 4.7771-10 2.7563-10 NNE 2.3483-09 1.42 1E-09 9.-951E-10 5.692E-10 2.6191-10 1.52 8E-10 NE 2.456E-09 1.458E-09 1. 004E-09 5.6541-10 2.-556E-10 1.477E-10 ENE 9.540B-09 5.276E-09 3.429H-09 1. 83 51-09 8.0301-10 4.5951-10 R 1. 212E-08 6.587E-09 4.219E-09 2.2248-09 9. 594E-10 5.450E-10 ESE 9.330E-09 5.097E-09 3.260E-09 1.7071-09 7.4281-10 4.2191-10 SI 7.1653-09 3.997B-09 2.587E-09 1.37 8Z-09 6.0783-10 3.'4731-10 SSE 3.529E-09 2.047E-09 1.3481-09 7.357R-10 3.353Z-10 1.9263-10 S 3 .7911-09 2.2191-09 1.4779-09 8.098E-10 3.7231-10 2.1421-10 SW 2.906E-09 1.760H-09 1-231E-09 7. 0821-10 3.3221-10 1.9501-10 SW 2 .421B-09 1.564E-09 1.1851-09 6.9601-10 3.3403-10 1.972E-10 WSW 6.780E-10 4.656E-10 3 .626E-10 2.3681-10 1.1883-10 7.2063-11 W 7.119E-10 4.*615E-10 3 .455E-10 2.100Z-10 1. 0413-10 6.2823-11 WNW 2.-129E-09 1. 329E-09 9.5671-10 5.6173C-10 2.648E-10 1. 5613-10 NW 4.192E-09 2.500E-09 1.73 51-09 9.8473-10 4.5141-10 2.6293-10 NNw 4 .2513-09 2.462E-09 1. 669E-09 9.2703-10 4.1863-10 2 .4231-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.805H-10 7 .499E-11 2 .350E-11 1.0001-11 5.7313-12 5.3093-11 1NN3 1.006E-10 4.197E-11 1. 303E-11 1. 958H-11 9.0643-12 5.1883-12 9.6811-11 4 .014E-11 1. 237H-11 9.9093-12 5.3161-12 3.2913-12 ENE 2.998E-10 1.245E-10 9.570E1-1 2.2563-11 1. 2103-11 7.4963-12 3 .539E-10 1.462E-10 6.-692H-11 2.1921-11 1.17 61-11 7 .2871-12 2 .738E-10 1.133E-10 4.6361-11 1. 6513-11 8.7771-12 5.439E-12 ESE 2.252E-10 9.507E-11 3 .796H-11 1.493H-11 7.9281-12 4 .7653-12 SE 1.2663-10 5.6351-11 2.578E-11 1.*172E-11 4.6053-12 2.8111I-12 SSE 1.434E-10 6 .420H-11 2 .776E-11 1.37 0H-11 5.1493-12 3.-1371-12 1.27 9E-10 5.527E-11 3 .0741-11 1.119R-11 5. 8823-12 3.1291-12 SSW 1.3183-10 5.5753-11 3 .290E-11 1.5413-11 7 .8003-12 4.5963-12 WSW 4 .828E-11 2 .055E-11 6.4503-12 2 .997E-12 2.3233-11 2.8073-12 4.194E-11 1.7803-11 5.6153-12 2.4183-12 1.3843-12 9.0381-13 1.0323-10 4.323H-11 1.338H-11 5.6703-12 3.2073-12 2.-0823-12 WNW 1.730E-10 7.212E-11 2.-2461-11 9.5343-12 5.4051-12 3.-5201-12 WNW 1.590H-10 6 .621E-11 2.-081H-11 8.887E-12 5.062E-12 3.309E-12 Rev. No. 9 C-1 I of ODOM Rev. o. 9Page

TABLE C-5 SECTOR AVERAGE DISPERSION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentration X/Q (seclrri')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.6671-07 3.319E-07 2.409E-07 1.596E-07 9.380E-08 6.472E-08 NNE 2.600E-07 1.5911-07 1.19 8E-07 8.2351-08 4.9601-08 3.4463-08 NE 2.296E-07 1.4103-07 1. 0481-07 7.034B-08 4.129E-08 2 .830E-08 5.479E-07 3 .1851-07 2.2601-07 1. 452E-07 7.9621-08 5.2 87E-08 4.528E-07 2 .601E-07 1.8081-07 1.13 29-07 5.9181-08 3.843E-08 2 .804E-07 1.631E-07 1.142E-07 6.9351-08 3.941E-08 ý2.5591-08 ISE 1.991E-07 1.204E-07 8.715E-08 5. 6091-0r8 3.276E-08 2.602B-08 SI 1.0711-07 6.9361-08 5.3481-08 3.9118-08 2.8351-08 2.013E-08 SSW 1.1501-07 7 .388E-08 5.9631-08 4.379E-08 3.218E-08 2.223E-08 SW 1.388E-07 9.086E-08 7.603E-08 5.8881-08 3.8601-08 2.786E-08 sWS 1.688E-07 1.12 9E-07 1.094E-07 8. 073E-08 5.290E-08 3.5763-08 SW 8.263E-08 5.5511-0 8 4.7951-08 4.949B-08 3.369E-08 2.430E-08 WNW 1.040R-07 6.463E-08 5.213E-08 4.1151-08 2.8811-08 2.151E-08 NW 2.926E-07 1.7 54E-07 1. 326B-07 9.420E-08 5.*955H-08 4.2601-08 KmW 5.036E-07 3 .005E-07 2 .226E-07 1.52 0E-07 9.183H-08 6.4161-0 8 5.247E-07 3.0411-07 2 .2021-07 1.468E-07 8.737E-08 6.082E-08 4.5 7.5 15.0 25.0 35.0 45.0 x 4.865E-08 2.687E-08 1. 18 6E-08 6.640H-09 4.4581-09 3.915E-09 NNE 2.5951-08 1. 42 81-08 6.212E-09 4.9451-09 3 .183E-0 9 2.299E-09 NE 2.1103-08 1.13 8E-08 5.166E-09 3.3383-09 2.13 0E-09 1.5301-09 ENE 3 .870H-08 2.034E-08 1.024E-08 5.223E-09 3.3621-09 2.430E-09 3 2.779E-08 1.440H-0 8 7.3091-09 3 .751E-09 2.434E-09 1.772E-09 ESE 1. 849E-08 1.133E-08 4. 5711-09 2.357E-09 1. 535E1-09 1. 121B-09 SE 1.833E-08 9.1651-09 3.693E-09 1. 922E-09 1. 261E-09 9.270R-10 SSE 1.438E-08 7.1591-09 2.8693-09 1. 492E-09 9.784E-10 7.18 5B-10 S 1.595E-08 7.922E-09 3.182E-09 1.659E-09 1. 0911-09 8.025E-10 SSW 2 .231E-08 1.0891-08 4.278E-09 2.156E-09 1.3 85E-09 1.002E-09 SW 2.896E-08 1.6673-08 6.4501-09 3.357E-09 2.135E-09 1.53 23-09 WSW 1.856E-08 1.029E-08 4.799E-09 2.5001-09 1.7 83E-09 1.393E-09 W 1.6901-08 9 .9221-09 4.586E-09 2.5521-09 1.729E-09 1.2 94E-09 WNW 3.276E-08 1.8853-08 8.746E-09 4.942E-09 3 .391R-09 2.562E-09 NW 4. 862E-08 2.733E-08 1. 241E-08 6.9323-09 4.729E-09 3.560E-09 NNW 4.607E-08 2.596E-08 1.186E-08 6.657E-09 4.554E-09 3 .433E-09 Rev. No. -9 Rev. o. 9Page C-I 2 of ODCM

/ TABLE C-5 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(DIQ) Sector Average Deposition (1/0f)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.9511-09 2 .856E-09 1.9271-09 1. 0651-09 4.777E-10 2.756B-10 2.348E-09 1.42 1E-09 9.951E-10 5.692E-10 2.619E-10 1.52 8E-10 NNE 2.4561-09 1.458E-09 1. 004E-09 5. 654H-10 2.556E-10 1.477E-10 INX 9.540E-09 5.276E-09 3.4291-09 1. 835E-09 8.030E-10 4. 595E-10 ESI 1.212E-08 6.5871-09 4.219B-09 2.224E-09 9.594B-10 5.450E-10 9.330E-09 5. 097E-09 3 .2603-09 1. 7071-09 7.428E-10 4.219E-10 ESE 7.1651-09 3.997E-09 2.587R-09 1. 37 8E-09 6.07 8E-10 3.4731-10 SSE 3.529E-09 2.047E-09 1.348E-0 9 7. 357E-10 3.353E-10 1.926E-10 SS 3 .791E-09 2.219E-09 1. 47 7E-09 8.0981-10 3 .723E-10 2.-142E-10 SW 2.906E-09 1. 760E-09 1.2312-09 7 .082H-10 3.322E-10 1.950H-10 SSW 2.421H-09 1.564E-09 1.1851-0 9 6. 960E-10 3 .340E-10 1.972E-10 WSw 6.7801-10 4.656B-10 3.626B-10 2.368H-10 1. 1881-10 7.206E-11 W 7.119E-10 4. 615E-10 3.4551-10 2.100E-10 1.0411-10 6.282H-11 WNW 2 .129E-09 1.329E-09 9.5671-10 5.617E-10 2.6481-10 1.5 61H-10 NW 4.192E-09 2.500E-09 1. 735E-09 9.847E-10 4.5141-10 2.629E-10 NNW 4 .251R-09 2.462E-09 1. 669E-09 9 .270E-10 4.186E-10 2.423E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.8051-10 7.4991-11 2.350E-11 1.0 0OO-11 5.731E-12 5. 309E-11 1.006Z-10 4.197E-11 1.3 03E-11 1.958E-11 9.064E-12 5.1881-12 NNE 9.681E-11 4. 014E-11 1.2371-11 9.909E-12 5.316E-12 3.-291E-12 INE 2.9981-10 1.245E-10 9.5701-11 2.-2561-11 1. 210E-11 7.496E-12 3.539E-10 1.. 462E-10 6. 692X-11 2.192E-11 1.17 6E-11 7.287E-12 ESE 2 .738E-10 1.133E-10 4.636R-11 1.6513-11 8.777E-12 5.43 91-12 SH 2.252E-10 9.507E-11 3.796E-11 1.493E-11 7.928E-12 4 .7653-12 SSE 1. 266E-10 5.6351-11 2.578E-11 1. 172E-11 4.605E-12 2 .811E-12 4 S 1.4 34E-10 6 .420E-11 2.776E-11 1. 370E-11 5.149E-12 3.137E-12 SSW 1. 27 9E-10 5. 527E-11 3 .074E-11 1.1191-11 5.8821-12 3 .12 9E-12 SW 1.3 18E-10 5.57 SE-il 3 .290R-11 1. 541E-11 7.8001-12 4.5961-12 WSW 4. 828R-11 2 .0551-11 6.450E-12 2. 997E-12 2.323E-11 2.-807H-12 W 4.194H-11 1.780E-11 5.615E-12 2.418E-12 1.3 84E-12 9.038E-13 WNW 1. 032E-10 4.323E-11 1.3381-11 5.670E-12 3 .2071-12 2.082E-12 NW 1. 730R-10 7.212E-11 2.246E-11 9.534E-12 5.405E-12 3 .520R-12 1-5901-10 6.621H-11 2-.0811-11 8.887E-12 5.062E-12 3.-309H-12 Rev. No. 9 Rev No 9Page 0 -13 of ODOM

TABLE C-6 I, SECTOR AVERAGE DISPERSION VALUES FOR TURBINE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentratio~n XJQ (seclni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.7451-07 2.863E-07 2.1351-07 1.4551-07 8.729E-08 6. 072E-08 NNE 2.1851-07 1.3 91R-07 1.0801-07 7.646B-08 4.692E-08 3.283E-08 NE 1.908E-07 1.216E-07 9.320E-08 6.460R-08 3. 878E-08 2.680E-08 ENE 4.6851-07 2 .784E-07' 2 .016E-07 1.333E-07 7.437E-08 4.972E-08 H 4.*004E-07 2.349E-07 1.660E-07 1.0 65E-07 5.6191-08 3.664E-08 ESE 2.4951-07 1.4 933-07 1.063E-07 6.567E-08 3.806E-08 2.477E-08 SE 1.7861-07 1.116E-07 8.218E-08 5.383E-08 3.1903-08 2.5541-08 SSE 9.5851-08 6.4929-08 5.1103-08 3.8201-08 2.809E-08 1.9881-08 S 1.0 34E-07 6 .930R-08 5.7451-08 4.300E-08 3.197E-08 2.199E-08 S SW 1.2 151-07 8.3501-08 7 .256E-08 5.7 67E-08 3 .8151-08 2.758E-08 SW 1.416E-07 1.007E-07 1.047E-07 7.883E-08 5.2151-08 3 .523H-08 WSW 5.908E-08 4.4281-08 4. 183E-08 4. 757E-08 3.288E-08 2.378E-08 W 6 .826E-08 4.6921-08 4.159E-08 3.599E-08 2.653E-08 2.013E-08 WNW 2.0871-07 1.3451-07 1. 079E-07 8.132E-0 8 5.342E-08 3 .877E-08 NW 3 .914E-07 2.4581-07 1.897E-07 1.34 9E-07 8.370H-08 5.9091-08 NNW 4.173E,-07 2 .514H-07 1.883E-07 1.3001-07 7.933E-08 5.580E-08 4.5 7.5 15. 0 25.0 35.0 45.0 H 4.584E-08 2.550E-08 1.134E-0 8 6.384E-09 4.294E-09 3.8151-09 NNE 2.4811-08 1.372E-08 5.996E-09 4.8451-09 3.117E-09 2.252E-09 NE 2.007E-08 1.0899-08 4.994E-09 3.2501-09 2.074E-09 1.4891-09 ENE 3.653E-08 1.93 0H-08 9.903E-09 5.042E-09 3.2451-09 2.346E-09 2.656B-08 1.3 81E-08 7.100E-09 3.641E-09 2 .362E-09 1.72 0E-09 ESE 1.792E-08 1.10 8E-08 4.459E-09 2 .297E-09 1.4 96E-09 1. 093E-09 SE 1.797E-08 8.964E-09 3.6051-09 1. 87 51-09 1. 23 0E-09 9.044E-10 SSE 1. 416E-08 7.035E-09 2.-816H-09 1.463E-09 9.5981-10 7.048E-10 S 1.5711-0 8 7.792E-09 3.126E-09 1.6291-09 1.071E-09 7 .8801-10 SSW 2 .205E-08 1.074E-08 4.204E-09 2.118Z-0 9 1.360E-09 9.842E-10 SW 2.862E-08 1.648E-08 6.362E-09 3.3001-09 2 . 098E-09 1.506H-09 WSW 1.817E-08 1.008E-08 4 .723E-09 2.459E-09 1.757E-09 1.3 681-09 W 1.593E-08 9 .451R-09 4 .406E-09 2 .462E-09 1.6729-09 1.253E-09 WNW 3.006E-08 1. 752E-08 8.236E-09 4.686E-09 3.228E-09 2.445E-09 NW 4.505E-08 2.5581-08 1.174E-08 6 .598E-09 4.516E-09 3.407E-09 4.254E-08 2 .422E-08 1.119E-08 6.323E-09 4.3403-09 3 .279E-09 Rev. No. -9 Rev. o. 9Page 0-14 of ODOM

TABLE C-6 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR TURBINE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(DIQ) Sector Average Deposition (l1rr?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.S 3.5 N 4.471lE-09 2 .622E-09 1.788E-09 9.981E-10 4 .499E-10 2.6011-10 NNE 2 .162E-09 1.33 53-09 9 .453E-10 5.4 62E-10 2 .521E-10 1.472B-10 NE 2.186E-09 1.329E-09 9.286E-10 5.298E-10 2.409E-10 1.3 953-10 ENE 8.763E-09 4.896E-09 3 .204E-09 1.729E-09 7 .6053-10 4.363E-10 E 1.1481-08 6 .289E-09 4.047E-09 2.149E-0 9 9.307E-10 5.2993-10 ESE 8.909E-09 4.906E-09 3 .151E-09 1. 660E-09 7 .258H-10 4.1303-10 SE 6 .876E-09 3.*8581-0 9 2.503E-09 1.3411-09 5.*9371-10 3.397E-10 SSE 3 .429E-09 1. 9953-09 1. 315E-09 7.210E-10 3 .289E-10 1.890E-10 S 3.698E-09 2.171E-09 1. 4471-09 7 . 965E-10 3.662E-10 2.1083-10 SSW 2.822Z-09 1.722E-0 9 1. 20 9E-09 6 .997E-10 3.281E-10 1.923E-10 SW 2.314E-09 1.520B-09 1. 164E-09 6 .882B-10 3 .299E-10 1.9453-10 WSW 6.0701-10 4.358E-10 3.469E-10 2.3103-10 1. 15 9-10 7.0213-11 W 6.082E-10 4.138E-10 3.183E-10 1.97 7E-10 9.874E-11 5.972E-11 WNW 1. 87 0E-09 1.209E-09 8.870E-10 5.293B-10 2 .5113-10 1.4 83E-10 NW 3 .749E-09 2 .290E-09 1.6 11E-09 9.262E-10 4 .269E-10 2 .492E-10 NNW 3.807Z-09 2.246E-09 1. 54 0E-09 8.652E-10 3 .928E-10 2 .280B-10 4.5 7.5 15.*0 25.0, 35.0 45.0 N 1.706E-10 7.094E-11 2.218E-11 9.588E-12 5.7363-12 8.525H-11 NNE 9.706E-11 4. 050E-11 1. 253H-11 1. 916R-11 8 .919H-12 5.1223-12 NE 9.157H-11 3 .7993-11 1.1751-11 9.911E-12 5.318E-12 3 .2921-12 ENE 2.851E-10 1.186E-10 9 .504E-11 2.256E-11 1.2 113-11 7 .499E-12 3.447E-10 1.427E-10 6.7353-11 2 .192E-11 1.177E-11 7 .290E-12 2.684E-10 1.124E-10 4.674E-11 1.6459-11 8.781E-12 5.44 03-12 SE 2.212E-10 9 .493E-11 3.784E-11 1.485E-11 7 .867E-12 4.731E-12 SSE 1. 257E-10 5.742E-11 2.530E-11 1.1041-11 4.586E-12 2.812H-12 S 1.444E-10 6.569E-11 2.721E-11 1.2 89H-11 5.120E-12 3.138E-12 SSW 1.262E-10 5.539E-11 2. 941E-11 1.1033-11 5.812-122 3.129E-12 SW 1.299E-10 5.523H-11 3 .711E-11 1.54 81-11 7 .792E-12 4.577E-12 WSW 4.707E-11 2.*001E-11 6 .249E-12 3 .103E-12 3 .3953-11 2 .7903-12 W 3.996E-11 1.697E-11 5.314E-12 2.295E-12 1.321E-12 8.6903-13 WNW 9.827E-11 4.117E-11 1.267E-11 5.391E-12 3 .075E-12 2.019E-12 NW 1.642E-10 6.851E-11 2.125E-11 9.0753-12 5 .220R-12 3.464E-12 1.49 8E-10 6. 246E-11 1.9583-11 8.42 6E-12 4 .8853-12 3 .267E-12 Rev. No. 9 C-15 of ODOM Rev.No.9Page

TABLE C-7 SECTOR AVERAGE DISPERSION VALUES FOR RADWASTE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentration XIQ (secln?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 9.2 89E-07 6.007E-07 4.440E-07 2.832E-07 1. 5673-07 1.0523-07 NNE 4 .6683-07 3 .155E-07 2 .371B-07 1. 529E-07 8 .435E-08 5.617E-08 NE 4.087E-07 2.683E-07 1.97 8E-07 1.247E-07 6 .6983-08 4.381E-08 8.420E-07 5.096E-07 3.592B-07 2.227E-07 1.1423-07 7.324E-08 ENE 6.787E-07 3 .900E-07 2.660E-07 1.626E-07 8.118E-08 5.1583-08 SE 4.270E-07 2.5253-07 1.727E-07 1.002E-07 5.512E-08 3.4673-08 ESE 3.397E-07 2.050E-07 1.413E-07 8.476E-08 4.6073-08 3.077E-08 SE 1.996E-07 1.413E-07 1.017E-07 6.6203-08 3.908E-08 2.419E-08 S SE 2.112E-07 1.498E-07 1.138B-07 7.3603-08 4.3103-08 2.6603-08 SW 2. 970E-07 2.024E-07 1.587E-07 1.052E-07 5.857E-08 3.8313-08 SSW 3.696R-07 2.716E-07 2.542E-07 1.569E-07 8.631R-08 5.441E-08 SW 1.93 93-07 1. 634E-07 1. 376E-07 1.185E-07 6.5003-08 4.262E-08 2.0883-07 1.643E-07 1. 369E-07 9.847E-08 5.9583-08 4.143E-08 WNW 5.250B-07 3.657E-07 2.8453-07 1.925B-07 1.13 5E-07 7.9003-08 8.757E-07 5.846E-07 4.4023-07 2.869E-07 1.6 34E-07 1.12 03-07

~NW 4.144E-07 2.6853-07 1. 531E-07 1.051E-07 8.5603-07 5.557E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 7.785E-08 4.199E-08 1.805E-08 9.939E-09 6 .584E-09 5.508E-09 N~NE 4.127E-08 2.189E-08 9.1953-09 5.947E-09 3.828E-09 2.766E-09 NE 3 .177E-08 1. 6423-08 7 .167E-09 3.976E-09 2 .538E-09 1.823E-09 ENE 5.250E-08 2.6703-08 1.1913-08 6.030E-09 3.8793-09 2 .803E-09 E 3. 6813-08 1. 8683-08 8.3703-09 4.283E-09 2.7783-09 2. 022H-09 ES3 2.458E-08 1. 32 6E-08 5.225E-09 2.684E-09 1. 747E-09 1.276E-09 SE 2 .154E-08 1.063E-08 4.246E-09 2 .2053-09 1. 44 6E-09 1.062E-09 SSE 1. 695E-08 8.373E-09 3 .340B-09 1.733E-09 1. 13 6E-09 8.3353-10 S 1.865E-08 9.222E-09 3.6903-09 1.920E-09 1. 26 1E-09 9 .272E-10 SSW 2.696E-08 1. 300E-08 4.993E-09 2. 515E-09 1.6153-09 1.16 83-09 SW 4.155E-08 2 .103E-08 7 .964E-09 3.960E-09 2.520E-09 1. 809E-09 WSW 3.087E-08 1. 587E-08 6.862E-09 3.473E-09 2 . 331R-09 1.6 813-09 W 3 .1253-08 1. 729E-08 7 .572E-09 4 .088E-09 2.722E-09 2.012E-09 WNW 5.992E-08 3.374E-08 1.518E-0 8 8.361E-09 5.637E-09 4.2 01E-09 N1W 8.418E-08 4.6783-08 2 .083E-08 1.141E-08 7 .675E-09 5.711E-09 NNW 7 .914E-08 4.414E-08 1. 974E-08 1. 0853-08 7 .307E-09 5.443E-09 K

Rev. No. -9 Rev. o. 9Page C-1 6 of ODOM

TABLE C-7 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR RADWASTE VENT DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

(DIQ) Sector Average Deposition (I1/rT?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3..5 7 .139E-09 3 .957H-09 2 .509E-09 1.308E-09 5.4891-10 3.0531-10 NE 3.697E-09 2.1201-09 1.363E-09 7.217E-10 3.0461-10 1. 697E-10 3.7381-09 2.1001-09 1. 337E-09 6.993E-10 2.9301-10 1. 6251-10 ENE 1.197E-08 6 .3951-09 3.9981-09 2.058E-09 8.649E-10 4.8341-10 1.42 9E-08 7.542E-09 4.691E-09 2 .4001-09 1.00 61-09 5.6 16H-10 1.0881-08 5 . 771E-09 3.5901-09 1. 833E-09 7.7331-10 4 .331E-10 8.853E-09 4.728E-09 2. 9411-09 1. 5101-09 6.4101-10 4.70911-10 SI 4.668E-09 2.551E-09 1.593E-09 8.2771-10 3.8871-10 3.18 91-10 SSW 5.074E-09 2.781E-09 1.752E-09 9.1211-10 4.4479-10 3.4481E-10 Sw 4.3951-09 2.459E-09 1.5851-09 8.439E-10 3.627E-10 2.3801-10 WSW 4.104E-09 2.423E-09 1.653E-09 8.807E-10 3 .7721-10 2.1071-10 SW 1.3 14E-09 8.3551-10 5.716E-10 3.3151-10 1. 429E-10 8.0301-11 WNW 1.257E-09 7.732E-10 5.19 8E-10 2. 8771-10 1.2481-10 7.0471-11 NW 3 .526E-09 2.0771-09 1.355E-09 7.280E-10 3.0941-10 1.7271-10 6.4401-09 3 .665E-09 2.353E-09 1.242E-0 9 5.23 9E-10 2.917E-10 6.1613-09 3.436E-09 2.187E-09 1.1441-09 4.8171-10 2.6831-10 4.5 7.5 15.0 25.0 35.0 45.*0 N 1.9601-10 8.595E-11 1.32 9E-10 3 .272E-10 3 .8241-10 2.1861-11 NNE 1.0891-10 4.740E-11 6.689E-11 1.2181-11 6.5261-12 4.0371-12 NE 1.040E-10 4.4331-11 5.931E-11 9.8991-12 5.3061-12 3.2831-12 ENE 3.114E-10 1.326E-10 8.260E-11 2.2 54H-11 1.2 09E-11 7.4841-12 E 3 .613E-10 1.508E-10 6.296E-11 2 .1901-11 1.1751-11 7.*278E-12 ESE 2 .7951-10 1.5651-10 4.4901-11 1.6351-11 8.7701-12 5.4321-12 SE 3.152E-10 1.2 83E-10 3 .658E11l 1.3 82E-11 7.4131-12 4 .5901-12 SSE 2.167E-10 8.427E-11 2.3621-11 8.8101-12 4. 5341-12 2 .8051-12 S 2.195E-10 8.754E-11 2.582E-11 9.909E-12 5.0601-12 3.1301-12 SSW 2.8851-10 1.221E-10 2. 6851-11 9.4181-12 5. 0471-12 3.1221-12 SW 1.53 6E-10 1.603H-10 4.5031-11 1.117E-11 5.9441-12 3.6691-12 WSW 5. 191E-11 2.346E-11 3.8391-11 4.1261-11 4 .6591-12 1.9 63E-12 W 4.561E-11 1. 917E-11 2.377H-11 8 .0371-11 1.2 04E-10 1.255E-10 WNW 1.1101-10 4.715E-11 6.492E-11 1.9551-10 2 .7501-10 2 .7771-10 NW 1.873E-10 8. 094E-11 1.1731-10 3 .1451-10 4.1761-10 4.0991-10 NNW 1.72 51-10 7.523E-11 1.182E-10 3.151E-10 4 .133E-10 4.02 51-10 Rev. No. -9 Rev. o. 9Page C-I 7 of ODOM

TABLE C-8 SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Concentration X/Q (sec/rn')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.304E-09 7.537E-09 9.6003-09 1. 38 2E-08 1.5 04E-08 1.366E-08 NNE 2.263Z-09 3 .378E-09 5.419E-09 9.466E-09 1.092E-08 1.011E-08 NE 1.092E-09 2.089E-09 4.269E-09 8.509E-09 1.005E-08 9.366E-09 ENE 1.2601-08 1.222E-08 1.454B-0 8 2.1003-08 2.117E-08 1.845E-08 9 1.547B-08 1.816E-08 2 .136E-08 2.978E-08 2.6551-08 2.1501-08 ESE 1.8881-08 1. 9 14E-08 2.056E-08 2.174E-0 8 2.283E-08 1.73 7E-08 SE 2.187E-08 1. 933E-08 1. 9931-08 2 .243E-08 2.0281-08 2.229E-08 SSE I..833Z-08 1. 56 0-08 1.566E-08 1.73 1E-08 2.077E-08 1.817E-08 S 1.747E-08 1. 44 01-08 1. 54 01-08 1.730H-08 2.2113-08 1. 90 01-08 SSW 1.689E-08 1.47 9E-08 1.724E-08 2.180E-08 2.270E-08 1.996E-08 SW 6.8663-09 6.874E-09 1.247E-08 1.67 53-08 1.7 89E-08 1.442E-0 8 WSW 1.163E-09 1. 723E-09 2.8111-09 6 .821E-09 7.244E-09 6.4141-09 W 1.151E-09 1.393E-09 2.274E-09 4 .102E-09 4.796E-09 4.483E-09 WNW 2.266E-09 3.0773-09 4.8903-09 8.276E-09 9.17 1E-09 8.2623-09 NW 5.561E-09 6 .833E-09 9.696E-09 1. 511E-08 1. 64 8E-08 1. 4 81E-08 NNW 6.602E-09 7.476Z-09 9.456E-09 1.3653-08 1.4983-08 1.37 01-08 4.5 7.5 15.0 25.0 35.0 45.0 N 1. 190E-08 7.9903-09 4.005E-09 2.317E-09 1. 57 2E-09 1. 34 83-09 8.882E-09 6.0463-09 3 .081H-09 4.716E-09 3.041E-09 2.2003-09 NNE 8.2703-09 5.697E-09 3 .376E-09 5.591E-09 3.622E-09 2.629E-09 1.5693-08 1.021E-0 8 8.735E-09 6 .410E-09 4.1213-09 2.977E-09 1.748E-08 1. 059E-08 7 .444E-09 4.667E-09 2.974E-09 2.137E-09 1.362E-08 1. 06 6E-08 4.756E-09 3.0003-09 1. 917E-09 1.3 81E-09 ESE 1.624B-08 8.6783-09 3 .802E-09 2.2823-09 1.4 64E-09 1.0591-09 SE 1.42 1E-08 7.626E-09 3 .217E-09 1.770E-09 1.263E-09 9 .154E-10 S SW 1.632E-08 8.545E-09 3.558E-09 1.953E-09 1.440E-09 1.0451-09 SW 1.910E-08 1.011E-08 4.8453-09 2.8351-09 1.813E-09 1.30 6E-09 SWs 1.354E-08 9.554E-09 4.078E-09 2.987E-09 1.946E-09 1.454E-09 SW 5.511E-09 3 .659E-09 2 .100E-09 1.197E-09 9.790E-10 1 . 201E-09 WSqW 3 .977E-09 2.773E-09 1.47213-09 8.742E-10 6.133E-10 4.701E-10 NW 7.1353-09 4 .716E-09 2.3353-09 1.322E-09 9.004E-10 6.765E-10 W4NW 1.277E-08 8.409E-09 4.115E-09 2.2983-09 1.548E-09 1. 15 2E-09 1.198E-08 8.121E-09 4.120E-09 2.355E-09 1. 6083-09 1. 207E-09 Rev. No. 9 Rev. o. 9Page C-1 8 of ODOM

TABLE C-8 (CONTINUED)

SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

Sector Average Finite Cloud Gamma XIQ (seclrd)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.6 2.5 3.5 N 1. 056E-07 7.326E-08 5.707E-08 4.0483-08 2.-615E-08 1. 9303-08 NNE 8.423E-08 5.8301-08 4.543E-08 3 .233E-08 2.1001-08 1.554E-08 NE 8.669E-08 5.979E-08 4. 651E-08 3 .304E-08 2.144E-08 1.588E-08 ENE 1.35 9E-07 9.3883-08 7.314E-08 5.381H-08 3.443E-08 2.522E-08 E 1.3453-07 9.409E-08 7.3523-08 5.582E-08 3.486E-08 2.500E-08 9 .666B-08 6.962E-08 5.419E-08 3.7853-08 2.627E-08 1.84 93-08 ISE 8.156E-08 5.7861-08 4.497E-08 3.227E-08 2.186E-08 1.9193-08 SSE 6 .370E-08 4.642E-08 3.607E-08 2.673E-08 2.041E-08 1.5739-08 S 6 .367E-08 4.638E-08 3 .736E-08 2.774E-08 2.192E-08 1.668E-08 S SW 8.747E-08 6.029E-08 4.886E-08 3 .679E-08 2.549E-08 1.9583-08 SW 7.8053-08 5.421E-08 4.798E-08 3.4123-08 2.313E-08 1. 662E-08 WSW 4. 633E-08 3.206E-08 2.4 983-08 2 .009E-08 1. 2898-08 9.455E-09 W 4.390E-08 3-020E-08 2.344E-08 1.660E-08 1. 074E-08 7 .954E-09 WNW 6. 518E-08 4.519E-08 3.531E-08 2.520E-08 1.636E-08 1.207E-08 NW 1.07 51-07 7 .471E-08 5.846E-08 4.177E-08 2.713B-08 2.002E-08 1.0903-07 7.544E-08 5.873E-08 4.163E-08 2.689B-08 1.987E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 1.520E-08 9.085E-09 4.282E-09 2.428E-09 1.640E-09 1. 343E-09 NNE 1. 22 8E-08 7.377E-09 3.5103-09 3.242E-09 2.1403-09 1.574E-09 NE 1.2553-08 7.577E-09 3.9 903-09 3 .674E-09 2.441E-09 1. 803E-09 ENE 1. 97 53-08 1.168E-08 7.533E-09 4.588E-09 3.017E-09 2.213E-0 9 E 1. 92 SE-OS 1.103E-08 6.332E-09 3 .583E-09 2.-329E-09 1. 69 53-09 ESE 1.4053-08 9.511E-09 4.144E-09 2.3393-09 1.522E-09 1. 1103-09 SE 1.411E-08 7.582E-09 3.268E-09 1. 80 93-09 1.181E-09 8.637E-10 SSE 1.197E-08 6.451E-09 2 .751E-09 1. 48 5E-09 1.0113-0 9 7 .413E-10 S 1.317E-08 7.027E-09 2 .988E-09 1.616E-09 1.1163-0 9 8 .202E-10 S SW 1.669E-08 8.946E-09 4 .02.5E-09 2.212E-09 1. 44 1E-09 1.051R-09 SW 1.405E-08 8.902E-09 3.815E-09 2.323E-09 1. 522E-09 1.125E-09 WSW 7 .417E-09 4.409E-09 2.259E-09 1.259E-09 9.433E-10 8.792E-10 w 6 .295E-09 3.815E-09 1.849E-09 1. 0613-09 7.-318E-10 5.5453-10 WNW 9.503E-09 5.659E-09 2 .658E-09 1. 4853-09 1.006E-09 7.5363-10 1.574E-08 9.343E-09 4.349E-09 2 .405E-09 1.617E-09 1.203E-09 NNW 1.567E-08 9.395E-09 4.454E-09 2 .499E-09 1.696E-09 1.269E-09 Rev. No. -9 Rev. o. 9Page 0-19 of ODCM

TABLE C-8 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR THE STACK DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985 To 1992)

I I (DIQ) Sector Average Deposition (l1rd)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.867E-10 5.512E-10 5.2 98E-10 3 .807E-10 2.3031-10 1.49 6E-10 2.220E-10 2.564E-10 2.787E-10 2.1731-10 1.3 74E-10 9.0291-11 NNE 1.569E-10 2.2541-10 2.6921-10 2.210E-10 1.434E-10 9.4 84E-11 1.440E-09 1.2 19E-09 1.0781-09 7 .247E-10 4.209E-10 2.7081-10 1.8681-09 1.566E-09 1.37 8E-09 9.226E-10 5.3431-10 3.4331-10 SE 1.. 9701E-09 1.546E-09 1.277E-09 8. 0701-10 4.4931-10 2. 8571-10 ESE 2.009E-09 1.513E-09 1.1951-09 7.2151-10 3 .9201-10 2 .6751-10 SE 1.472E-09 1.088E-09 8.4011-10 4. 9521-10 2.7821-10 1.7831-10 SSE 1.4321-09 1. 0621-09 8.226E-10 4.8641-10 2 .765E-10 1.7581-10 SW 1.448E-09 1.1451-09 9.4991-10 6.029E-10 3 .3981-10 2 .2271-10 4.816E-10 4 .5771-10 4.4241-10 3.1911-10 1.9341-10 1.2 58E-10 WSW 7 .953H-11 9.1051-11 9.8521-11 7.6571-11 4.8341-11 3.1751-11 W 7.5961-11 8.732E-11 9.4531-11 7.3491-11 4. 6411-11 3.0491-11 WNW 2.2598-10 2.5481-10 2.7331-10 2.1141-10 1.3 31E-10 8.739E-11 NW 5.672E-10 5.729E-10 5.7701-10 4.285E-10 2.6401-10 1.724E-10 NNW 6.313E-10 5.7 55E-10 5.4081-10 3. 8201-10 2 .288E-10 1.4831-10 4.5 7.5 15. 0 25.0 35.0 45.0 N 1.02 4E-10 4 .512E-11 1.49 91-11 6.6341-12 3.864E-12 2.538E-12 NNE 6.1871-11 2 .717E-11 8.9361-12 1. 0791-11 1.8771-11 2.3311-11 NE 6. 504E-l1 2 .852E-11 9.3331-12 1. 9221-11 7.686E-12 4.7621-12 ENE 1. 851E-10 8. 1911-11 2.723R-11 2.5891-11 1.390E-11 8.6 13E-12 2 .345E-10 1. 038E-10 3.4391-11 2.4431-11 1. 312E-11 8.1281-12 1.949E-10 9 .0971-11 2.9051-11 1.009E-10 9 .0571-12 5.6131-12 SE 1.804E-10 7 .8051-11 2.518E-11 1.5641-11 3 .6461-11 5.6919-11 S SE 1.212E-10 5.2281-11 1.7 001-11 7 .7641-12 1.0781-11 3 .1481-12 S 1.2 03E-10 5.1621-11 1.6751-11 7.661E-12 2 .38191-11 3 .375E-12 S SW 1.5811-10 6.827E-11 2.1741-11 2.1201-11 3.0211-11 5.0821-12 SW 8.713E-11 3. 9761-11 1.252E-11 5.2661-12 3 .020E-12 2 .782E-12 WSW 2.1751-11 9.5481-12 3.137E-12 1.3621-12 7 .6781-13 5.268E-13 W 2.0891-11 9.1761-12 3.0181-12 1.312E-12 7 .520E-13 4.9061-13 WNW 5.9881-li 2 .6311-11 8 .6651-12 3.7751-12 2 .1681-12 1.417E-12 NW 1.181E-10 5.1971-11 1.72 0E-11 7.5611-12 4.3781-12 2 .873E-12 1.014E-10 4.4751-11 1.490E-11 6.6281-12 3.876E-12 2 .556E-12 Rev. No. -9 Rev. o. 9Page 0-20 of ODOM

TABLE C-9 SECTOR AVERAGE DISPERSION VALUES FOR REACTOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Concentration XIQ (secln?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.872E-07 3.876E-07 2.760E-07 1.*809E-07 1.07 0E-07 7 .473E-08 NNE 2.7843-07 1. 6183-07 1.187E-07 8.049E-08 4.922E-08 3 .490H-08 NE 2'.1461-ý07 1.2939-07 9.6371-08 6.593E-08 4.0101-08 2. 814E-08 ENS 5.379E-07 3.161E-07 2.287E-07 1.517E-07 8.544E-08 5.754E-08 4.3493-07 2.511E-07 1.7813-07 1.161E-07 6.271E-08 4.151E-08 2 .237E-07 1.316E-07 9.5171-08 6 .077E-08 3.752E-08 2.507E-08 SE 1.4 04B-07 8.5551-08 6.434E-08 4 .391E-08 2.7611-08 2.379B-08 SSE 8.4663-08 5.3433-08 4.2519-08 3.290E-08 2.6251-08 1. 947E-08 S 1.1383-07 7.142E-08 5.844E-08 4.397E-08 3.334E-08 2.3401-08 SSW 1.19 53-07 7.622E-08 6.4181-08ý 5.096E-08 3.474E-0 8 2.567E-08 SW 1.568E-07 1. 021H-07 9.798E-08 7.350E-08 4.952E-08 3.388E-08 WSW 8.303E-08 5.439E-08 4.638E-08 4.813E-08 36323E-08 2.418E-08 W 1.023B-07 6.109E-08 4.808E-08 3 .752E-08 2.6751-08 2.039E-08 2.768E-07 1. 563B-07 1.144E-07 8.024E-08 5.180E-08 3.796E-08 WNW 4.819E-07 2.733E-07 1.974E-07 1. 33 6E-07 8.207E-08 5.850E-08 5.8363-07 3.2553-07 2.311E-07 11. 52 5E-07 9.119E-08 6 .4151-08 4.5 7.5 15.0 25.0 35.0 45.0 5.6821-08 3.229E-08 1.487E-0 8 8.630E-09 5.900E-09 5.432E-09 NE 2.674E-08 1.527E-08 6.9813-09 6.259E-09 4.0651-09 2.9551-09 2 .133E-08 1.186E-08 5.6531-09 3.842E-09 2.467E-09 1. 77 8E-09 ENE 4.249E-08 2.266E-08 1.191E-08 6.123E-09 3.960E-09 2.*874E-09 3.039E-08 1. 6101-08 8.670B-09 4.499E-09 2.939E-09 2.1511E-09 1.846E-08 1.219E-08 5.018E-09 2.620E-09 1.719E-09 1. 262E-09

1. 691E-08 8.600E-09 3.531E-09 1.859E-09 1.229E-09 9 .077E-10 SSE

1. 408E-08 7 .122E-09 2.909E-09 1.533E-09 1.014E-09 7 .489E-10 SS 1.694E-08 8.538E-09 3.497E-09 1.849E-09 1.227E-09 9 .083E-10 SS 2 .096E-08 1.036E-08 4.152E-09 2.119E-09 1.372E-09 9.979E-10 SsW 2.774E-08 1.607E-08 6.287E-09 3.2853-09 2.100E-09 1. 512E-09 WSW 1.858E-08 1.043E-08 5.006E-09 2.642E-09 1.930E-09 1. 538E-09 WNW 1.628E-08 9.896E-09 4.77 8E-09 2.735E-09 1.8853-09 1. 426E-09

2. 983E-08 1. 804E-08 8.977E-09 5.317E-09 3.751E-09 2. 887E-09 NW 4 .517E-08 2 .656E-08 1. 29 0E-08 7.554E-09 5.303E-09 4. 069E-09 NNW 4.913E-08 2 .849E-08 1.3632-08 7.907E-09 5.5193-09 4.2183-09 Rev. No. -9 ý Rev. o. 9Page C-21 of ODCM

TABLE C-9 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REACTOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

(DIQ) Sector Average Deposition (Ilnf)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.293E-09 3. 001E-09 1.993B-09 1.084E-09 4.833E-10 2.7 88E-10 NNE 2.213E-09 1. 282E-09 8.6721-10 4.796E-10 2.178E-10 1.26 8E-10 NE 1.943E-09 1. 129E-09 7.661E-10 4.253E-10 1. 923E-10 1.114H-10 ENE 9.5671-09 5.374B-0 9 3.526E-09 1.908E-09 8.486E-10 4.*910E-10 E 1.195E-08 6.594E-09 4.262E-09 2.273E-09 9.946E-10 5.7051-10 ESE 7 .360E-09 4.0981-09 2.647E-09 1.400E-09 6 .2001-10 3.559E-10 SE 4.567E-09 2.616E-09 1.713E-09 9.208E-10 4.141E-10 2.3951-10 SSE 2.349E-09 1. 404E-09 9.335E-10 5.0951-10 2.3741-10 1.3 85E-10 S 3.6801-09 2 .178E-09 1.449E-09 7.904E-10 3.6608-10 2 .123E-10 SSW 2.5521-09 1.5391-09 1. 06 5-09 6.032E-10 2.8351-10 1.674E-10 SW 2.2501-09 1.407E-09 1.024E-09 5. 859E-10 2.7951-10 1.6 553-10 4.5871-10 3.426E-10 2.133E-10 1. 06 0Z-10 6.42 03-11 (.

WSW 7.0021-10 W 6.9601-10 4.315E-10 3.101E-10 1. 811E-10 8.844E-11 5.324H-11 WNW 1. 63 0R-09 9'.674E-10 6.706E-10 3. 802E-10 1.774E-10 1.04 5E-10 NW 3.128E-09 1. 814E-09 1. 23 2E-09 6.840E-10 3.116E-10 1.814E-10 NNW 4.161E-0 9 2.3 81E-09 1.5953-09 8.757E-10 3.947E-10 2.289E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.827E-10 7.623E-11 2.436E-11 1.0571-11 6.134E-12 5.692E-11 8.343E-11 3.499E-11 1.1191-11 2.150E-11 9 .7891-12 5.547E-12 NNE 7.311E-11 3. 048E-11 9.592E-12 9 .504E-12 5 .097B-12 3.154E-12 ENE 3.22 5E-10 1.353E-10 1.15 6E-10 2.576E-11 1.3 82H-11 8 .5571-12 3.727E-10 1. 553B-10 7.770E-11 2.423E-11 1.30 0E-11 8.052E-12 EB 2.326E-10 9.743H-11 4.546E-11 1. 50 81-11 7 .942E-12 4.919E-12 ESE 1.56 6E-10 6.774E-11 3.081E-11 1.184E-11 6 .303E-12 3 .709E-12 S SE 9.207H-11 4.261H-11 2.281E-11 1.017E-11 3 .707E-12 2.214E-12 S 1.42 6E-10 6.463E-11 2 .960B-11 1.496E-11 5.34 9E-12 3.211E-12 SSW 1. 104H-10 4.819E-11 2.963E-11 1.05 91-11 5.586E-12 2.816E-12 SW 1.10 9E-10 4.7443-11 3.118E-11 1.5511B-11 7.8183-12 4. 584E-12 WSW 4.303E-11 1.8431-11 5.936E-12 2.825E-12 2.461E-11 2.913E-12 W 3.5561-11 1.52 0B-11 4. 937E-12 2.1881-12 1.2 80E-12 8.473E-13 WNW 6. 913H-11 2.912H-11 9.300E-12 4.0461-12 2.335E-12 1.5353-12 NW 1.193E-10 4.9983-11 1.589E-11 6.8651-12 3 .941E-12 2.584E-12 NNW 1.504E-10 6.293E-11 2 .015E-11 8.774E-12 5.073E-12 3 .346E-12 K

Rev. No. -9 Rev. o. 9Page C-22 of ODOM

.TABLE C-1O0 SECTOR AVERAGE DISPERSION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Concentration X/Q (sec/nid)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 6.872E-07 3.876E-07 2 .760E-07 1.809E-07 1.07 0E-07 7 .473E-08 NNE 2 .784E-07 1.6 18E-07 1.187E-07 8.049E-08 4 .922E-08 3.4903-08 NE 2.*146E-07 -1.293E-07 9.637E-08 6.593E-08 4 .0103-08 2.8143-08 5.379E-07 3.161E-07 2.287E-07 1. 517E-07 8.544E-0 8 5.7543-08 ESE 4.3499-07 2.511E-07 1.7 81E-07 1. 16I13-07 6.271E-08 4.151E-08 2 .237E-07 1.3 16E-07 9.517E-08 6.077E-08 3 .752E-08 2.507E-08 ESE 1.404E-07 8.5553-08 6.434H-08 4 . 3913-08 2.761E-08 2.379E-08 SSE 8.4663-08 5.343E-08 4 .2513-08 3 .290E-08 2.6253-08 1.947E-0 8 S 1.1383-07 7 .142E-08 5.844E-08 4.397E-08 3 .334E-08 2.3403-08 SSW 1.195E-07 7 .622E-08 6.418E-08 5.096E-08 3 .474E-08 2.567E-08 SW 1.5683-07 1. 021E-07 9 .798E-08 7.3503-08 4. 952E-08 3.388E-08 WSW 8.303E-08 5.439E-08 4.*63 8E-08 4.813E-08 3 .3233-08 2.4183-08 W 1.023E-07 6.1093-08 4 .808E-08 3.752E-08 2 .6753-08 2.039E-08 WNW 2.7683-07 1.563E-07 1.144E-07 8.024E-08 5.180E-08 3.796E-08 NW 4.819E-07 2 .733E-07 1.974E-07 1.33 6E-07 8.207E-08 5.850E-08 NNW 5.836E-07 3 .255E-07 2 .311E-07 1.525E-07 9 .119E-08 6.4153-08 4.5 7.5 15 .0 25.0 35.0 45.0 N 5.682E-08 3 .229E-08 1. 487E-08 8 .630E-09 5.9003-09 5.4 32E-09 NNE 2.674E-08 1. 52 7E-08 6.981E-09 6.259E-09 4 .065E-09 2 .9553-09 NE 2.1333-08 1.186E-08 5.653H-09 3.842E-09 2 .467E-09 1.778E-09 ENE 4.249E-08 2 .266E-08 1. 19 1E-08 6 .123E-09 3 .960E-09 2 .874E-09 H 3 .039E-08 1.6103-08 8.670E-09 4 .499E-09 2.939E-09 2.1513-09 ESE 1.846E-08 1.219E-08 5.018E-09 2.620E-09 1.719E-09 1.26 2E-09 SEB 1. 691E-08 8.600E-09 3. 531E-09 1. 85 9E-09 1.229E-09 9.077E-10 SSE 1. 408E-08 7 .122E-09 2.909E-09 1.533E-09 1.014E-09 7.489E-10 S 1.694E-08 8 .538E-09 3 .497E-09 1.849E-09 1.227E-09 9.083E-10 SSW 2.096E-08 1.036E-08 4.152E-09 2.119E-09 1.372E-09 9.979E-10 SW 2.774E-08 1.607E-08 6.287E-09 3.285E-09 2.100E-09 1.512E-0 9 WSW 1.858H-08 1.043E-08 5.006E-09 2.642E-09 1.930E-09 1.538E-09 W 1.628E-08 9.896E-09 4.778E-09 2.7353-09 1.8853-09 1.426B-09 WNW 2. 983E-08 1.804E-08 8.977E-09 5.317E-09 3.751E-09 2.887E-09 NW 4.517E-08 2.656E-08 1.2903-08 7.5549-09 5.303E-09 4 .069E-09 NNW 4 .913E-08 2.849E-08 1.363E-08 7.907E-09 5.519E-09 4.218E-09 Rev. No. -. 9 Rev. o. 9Page C-23 of ODOM

TABLE C-10 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR REFUEL FLOOR VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

(D/Q) Sector Average Deposition (1/nf)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 5.2931-09 3.0011-09 1.993E-09 1.084E-09 4.833E-10 2.788H-10 NE 2.213E-09 1.282E-09 8.6721-10 4.796E-10 2.178k-10 1.268E-10 1.9431-09 1.12 9E-09 7.661E-10 4.253E-10 1.923E-10 1. 114E-10 ENS 9.567E-09 5.374E-09 3 .526E-09 1.9081-09 8.48 6E-10 4.910E-10 E 1.195B-08 6.594E-09 4.262B-09 2.273E-09 9.946E-10 5.7051-10 151 7.3602-09 4.09 8E-09 2.647E-09 1.4001-0 9 6.20 01-10 3.559E-10 SE 4.567E-09 2.616E-09 1.713E-09 9 .208E-10 4 .141E-10 2.3951-10 SSE 2.349E-09 1. 404E-09 9.3351-10 5.095E-10 2.374E-10 1.3 851-10 S 3.680E-09 2.178E-09 1.44 9E-09 7.904E-10 3 .660R-10 2 .123E-10 SSW 2.552E-09 1. 53 9E-09 1.065E-09 6.032E-10 2.8351-10 1.6 74E-10 SW 2.2501-09 1.407E-09 1.024E-09 5.859E-10 2.795E-10 1.655E-10 WSW 7.0021-10 4.5871-10 3.4261-10 2.133E-10 .1.0601-10 6.420E-11 W 6.9601-10 4.3151-10 3.101E-10 1. 811H-10 8.844E-11 5.324E-11 (:..

WNW 1. 630R-09 9 .674E-10 6.706E-10 3.802E-10 1.77 4E-10 1.0451-10 NW 3.128E-09 1. 814E-09 1.232E-09 6.840H-10 3.116E-10 1. 814H-10 NNW 4.161E-09 2. 381E-09 1.595E-09 8.7571-10 3.947E-10 2.*289E-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.827E-10 7.623E-11 2.436E-11 1.057E-11 6.134E-12 5.692E-11 NNE 8.343E-11 3.499E-11 1.1191-11 2 .150E-11 9.789E-12 5. 547E-12 NE 7.311E-11 3.048E-11 9.592E-12 9.504E-12 5.097E-12 3.154E-12 INI 3.2251-10 1. 353E-10 1.15 61-10 2 .576E-11 1.382E-11 8.557E-12 3.727E-10 1.553E-10 7.770E-11 2.423E-11 1.3001-11 8.052E-12 2.326E-10 9.743H-11 4.546E-11 1.5081-11 7 .942E-12 4. 919H-12 SE 1. 566E-10 6.774E-11 3 .081E-11 1.184E-11 6 .3031-12 3.709E-12 9.207E-11 4.261E-11 2.281E-11 1. 0171-11 3 .7071-12 2.214E-12 S 1. 426E-10 6.463E-11 2 .960E-11 1. 49 61-11 5.349B-12 3 .211E-12 1.104E-10 4. 819E-11 2.963E-11 1.059E-11 5.5861-12 2 .816E-12 Ssw

1. 109E-10 4.744E-11 3.118E-11 1. 551E-11 7 .8181-12 4 .584E-12 WSW 4.303E-11 1.843E-11 5.936E-12 2. 825E-12 2 .461E-11 2 .913E-12 WNW 3. 556E-11 1.520E-11 4 .937E-12 2.1881-12 1.2801-12 8.473E-13 NW 6.9131-11 2. 912H-11 9 .300E-12 4. 046E-12 2 .3351-12 1.5351-12 1.193E-10 4 .998E-11 1.589E-li 6.865E-12 3.9411-12 2 .584E-12 NNW 1.504E-10 6.293E-11. 2.0151-11 8.774E-12 5.073E-12 3 .346E-12 (

Rev. No. 9 Rev. o. 9Page 0-24 of ODOM

TABLE C-1Il SECTOR AVERAGE DISPERSION VALUES FOR TURBINE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Concentration XJQ (sec/ni')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.709E-07 3.3051-07 2.4121-07 1.6251-07 9.8181-08 6 .9211-08 NNE 2.2851-07 1.37 2E-07 1.0371-07 7.2751-08 4.562E-08 3.268E-08 NE 1.7 64E-07 1.102E-07 8.47 7E-08 6.015E-08 3.7551-08 2.661E-08 ENE 4.6161-07 2.776E-07 2.055E-07 1.405E-07 8.0501-08 5.457E-08 I 3.792E-07 2.246E-07 1.62 5E-07 1.0 91E-07 5. 960E-08 3.964E-08 ESE 1.9651-07 1.194E-07 8.826E-08 5.753E-08 3.635E-08 2.434E-08 SE 1. 272E-07 7.992E-08 6.120E-08 4.254E-08 2.712E-08 2.351E-08 SSE 7.646E-08 5.020E-08 4.085E-08 3 .235E-08 2.618E-08 1. 93 3E-08 S 1.036E-07 6.737Z-08 5.658E-08 4.3351-08 3.322E-08 2.3201-08 SSW 1.*046E-07 6.974E-08 6.111E-0 8 4.9951-08 3.438E-08 2.5451-08 SW 1.3 143-07 9.022E-08 9.323E-08 7.163E-08 4.882E-08 3.339B-08 WSW 5.9581-08 4.293E-08 4.003E-08 4.609E-08 3.238E-08 2 .363E-08 W 6.396E-08 4.183E-0 8 3.639E-08 3.164E-08 2.412E-08 1.880E-08 WNW 1.777E-07 1.07 51-07 8.434E-08 6.407E-08 4. 390E-08 3 .3011-08 NW 3.558E-07 2.118E-07 1.59 8E-07 1.134E-07 7.213E-08 5.224E-08 NNW 4.537E-07 2 .623E-07 1.924E-07 1.315E-07 8.0851-08 5 .761E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 5.294E-08 3.037E-08 1.413E-08 8.267E-09 5.666E-09 5.296E-09 2.518E-08 1.451E-0 8 6.687E-09 6.127E-09 3.978E-09 2.891E-09 NNE 2.028E-08 1.13 5E-08 5.477E-09 3 .750E-09 2.407E-09 1.735E-09 INN 4.044E-08 2 .168I-08& 1.15 8E-08 5.9451-09 3.845E-09 2.790E-09 2.910E-08 1.547E-08B 8.448E-09 4.380E-09 2.862E-09 2.094E-09 1.794E-08 1.196E-08 4.909E-09 2 .560E-09 1.680E-09 1.233E-09 ESE 1.669E-08 8.467E-09 3 .468E-09 1.826E-09 1.207E-09 8.915E-10 SSE 1.392E-08 7.028E-09 2 .868E-09 1.511E-09 9 .9971-10 7.383E-10 S 1.673E-08 8.418E-09 3 .4451-09 1.821E-09 1.20 82-09 8.947E-10 S SW 2 .0751-08 1.023E-08 4.085E-09 2.083E-09 1.349E-09 9.812E-10 SW 2 .742E-08 1.588E-08 6 .199E-09 3 .229E-09 2.064E-09 1.486E-09 WSW 1.818E-08 1.022E-08 4.932E-09 2.603E-09 1.9051-09 1.512E-09 W 1.518E-08 9.366E-09 4.5781-09 2.636E-09 1.821E-09 1.3 81E-09 WNW 2 .633E-08 1.6329-08 8.318E-09 4 .9881-09 3.541E-09 2.735E-09 NW 4 .074E-08 2.438E-08 1.207E-08 7.141E-09 5.039E-09 3.879E-09 NNW 4.450E-08 2 .6201-08 1.274E-08 7 .463E-09 5.234E-09 4 .013E-09 Rev. No. 9 C-25 of ODOM Rev.No.2Page

TABLE C-Il (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR TURBINE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

(DIQ) Sector Average Deposition (llrrf)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 4.847E-09 2.779E-09 1. 860E-09 1. 02 0B-09 4.566E-10 2 .639E-10 NNE 2.032E-09 1.194E-09 8. 146E-10 4.5481-10 2.0751-10 1. 2 10-10 NE 1.740H-09 1.03 0H-09 7.073E-10 3.9721-10 1.8061-10 1.0491-10 ENE 8. 906E-09 5.042E-09 3.3251-09 1.8121-09 8.095E-10 4.694E-10 1.133B-08 6.*299E-09 4.*0901-09 2 .1991-09 9.6621-10 5.5541-10 ESE 7 . 0611-09 3.955E-09 2.563E-09 1. 364E-09 6.0631-10 3 .486E-10 SE 4 .447E-09 2.551E-09 1. 6711-09 9.0251-10 4.0671-10 2.3529-10 SSE 2.3281-09 1. 388E-09 9.215E-10 5.0511-10 2 .3501-10 1.369E-10 S 3.6341-09 2 .1481-09 1. 4281-09 7.8211-10 3.6171-10 2.0971-10 SSW 2.4961-09 1.510E-09 1.047E-09 5. 9681-10 2.8031-10 1.6 53E-10 SW 2.157E-09 1.3 62E-09 1.0011E-09 5.7661-10 2.7501-10 1.6281-10 WSW 6.331E-10 4.276E-10 3.252E-10 2 .0631-10 1.0261-10 6.2181-11 W 5.976E-10 3 .834E-10 2.*817E-10 1.6 801-10 8.2841-11 5. 0 07-11

1. 388E-09 WNW 2.777E-09 8 .480E-10

1. 6411-09 5.993E-10

1. 128E-09 3 .462E-10 1.6321-10 9.657E-11

(

NW 6.3461-10 2 .9091-10 1.699E-10 3 .765E-09 2.185E-09 1.477E-09 8.1921-10 3 .7121-10 2.1581-10 4.5 7.5 15.0 25.0 35.0 45.0 N 1.732E-10 7.23 6E-11 2.311E-11 1.013E-11 6. 02 6E-12 8.8481-11 7.973E-11 3.3471-11 1.0681-11 2.1031-11 9 .625E-12 5.4701-12 NNE 6.8961-11 2.87 8E-11 9.085E-12 9.5061-12 5. 098E-12 3 .1561-12 INE 3.089E-10 1.29 8E-10 1.14 0E-10 2.5771-11 1.3 821-11 8.5591-12

3. 636E-10 1.5181-10 7.743E-11 2.4241-11 1. 30 0E-11 8.054E-12 ESE 2.282E-10 9.6721-11 4.575SE-11 1.498E-11 7.9463-12 4 .9201-12 SE 1.544E-10 6.793E-11 .3.047E-11 1.1741-11 6.2171-12 3 .6551-12 SSE 9 .1651-11 4.3521-11 2.187E-11 9.4461-12 3.6701-12 2 .2151-12 S 1.43 51-10 6.6061-11 2.8831-11 1.384E-11 5.2971-12 3 .2121-12 SSW 1.090E-10 4.8351-11 2 .8011-11 1.04 1E-11 5.5071-12 2 .8161-12 SW 1.090B-10 4.6911-11 3.6013-11 1.5571-11 7.8131-12 4.5621-12 WSW 4.1711-11 1.7 84E-11 5.7291-12 2.9351-12 3.6391-11 2 .9151-12 W 3.353H-11 1.43 5E-11 4.643E-12 2 .0681-12 1.2 17E-12 8.1001E-13 6 .407E-11 2.7051-11 8.6121-12 3 .7721-12 2.1961-12 1.4571-12 NW 1.120E-10 4. 6971-11 1.490E-11 6.476E-12 3.7511-12 2 .4851-12 1.420OE-10 5. 952E-11 1. 904E-11 8.344E-12 4.874E-12 3 .254E-12 K

Rev. No. -9 Rev. o. 9Page 0-26 of 00CM

TABLE C-12 SECTOR AVERAGE DISPERSION VALUES FOR RADWASTE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Concentration XJQ (seclni)

SEGMENT BOUNDARIES IN MILES Directioni 0.5 0.75 1.0 1.5 2.5 3.5 N 1.033E-06 6 .607E-07 4.934E-07 3.221E-07 1.851E-07 1.27 51-07 NNE 4.455E-07 2.9871-07 2.2851-07 1.52 5E-07 8.827E-08 6.054E-08 NE 3 .6251-07 2 .4681-07 1.879E-07 1.232E-07 6.884E-08 4. 598E-08 ENE 8 .475E-07 5.272E-07 3.7941-07 2.4161-07 1. 263E-07 8.178H-0 8 6.881E-07 4 .030E-07 2.806E-07 1.77 8E-07 9 .089E-08 5.854E1-08 3.6371-07 2 .260E-07 1.6049-07 9.717E-0 8 5.730R-08 3.661E-08 SE 2.507E-07 1.591E-07 1.1371-07 7.166E-08 4.147E-08 2.8711-08 SSE 1.52 8E-07 1.153E-07 8.6311-08 5.956E-08 3 .7781-08 2.3651-08 S 2.033B-07 1.4 62E-07 1.1361-07 7.515E-08 4.5171-08 2.8141-08 SSW 2.465E-07 1.710E-07 1.3783-07 9.433E-08 5.423E-08 3.604B-08 SW 3 .232E-07 2.419E-07 2.3491-07 1.473E-07 8.2251-08 5.213E-08 WSW 1.847E-07 1.571E-07 1.341E-07 1.183E-0 7 6.589E-08 4.363E-08 W 1.9251-07 1. 49 6E-07 1.2661-07 9.4001-08 5.9351-08 4.234E-08 WNW 4.533E-07 3 .100E-07 2.455E-07 1.7 32E-07 1.090H-07 7.925E-08 7.620E-07 5.042E-07 3.8628-07 2 .611E-07 1. 583E-07 1.133E-07 8.83 6E-07 5.647E-07 4.242E-07 2.807E-07 1.666E-07 1.178E-07 4.5 7.5 15.0 25.0 35.0 45.0 IT 9.616E-08 5.366E-08 2.3981-08 1.359E-08 9.122E-09 7.874B-09 NNEX 4.539E-08 2.496E-08 1.093E-08 7.546E-09 4.900E-09 3.562E-09 NE 3.379E-08 1. 787E-08 8.096E-09 4.598E-09 2.952E-09 2.12 81-09 ENE1 5.900E-08 3.037E-08 1.3 95Eý08 7 .112E-09 4.597E-09 3 .334E-09 H 4.216E-0 8 2.1751-08 1.0091-08 5.213E-09 3.404E-09 2 .490H-09 ESE 2.622E-08 1.462E-08 5.848E-09 3.039E-09 1.992E-09 1.462E-09 SH 2 .025E-08 1.013E-08 4 .110E-09 2.159E-09 1. 42 6E-09 1.053E-09 SSE 1. 670E-08 8.369E-09 3 .400E-09 1.788E-09 1. 1811-09 8.7 13E-10 S 1.986E-08 9.9 511-09 4.056E-09 2.139E-09 1.4 17E-09 1.048E-0 9 S SW 2.557E-08 1.2469-08 4 .8611-09 2.477E-09 1.603E-09 1.166E-09 SW 3.986E-08 2.0259-08 7.746E-09 3 .8811-09 2 .481H-09 1.78 6E-09 WSW 3.183E-08 1.658E-08 7.3801-09 3.775E-09 2.571E-09 1.863E-09 W 3 .249E-08 1.853E-08 8.383E-09 4.616E-09 3.108E-09 .2.313E-09 WNW 6.191E-08 3. 6711-08 1.744E-08 9 .907E-09 6.7951-09 5.122E-09 NW 8.779E-08 5.149E-08 2.428E-08 1.376E-08 9.4251-09 7.099E-09 NNW 9.054E-08 5.244E-08 2 .444E-08 1.37 6E-08 9.398E-09 7 .065E-09 Rev. No. 9 Rev. o. 9Page C-27 of ODOM

TABLE C-12 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR RADWASTE VENT DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

(DIQ) Sector Average Deposition (1/ni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 7 .161E-09 3.9103-09 2.4683-09 1.2 81E-09 5. 3993-10 3.-016H-10 3 .098E-09 1.7253-09 1.1003-0 9 5.7853-10 2.454E-10 1.37 53-10 NNE 2.767E-09 1. 54 6E-09 9.859E-10 5.1683-10 2.179E-10 1.2 153-10 1.236E-08 6.6203-09 4 .148E-09 2.151E-09 9 .130E-10 5.142E-10 ENE 1.471R-08 7.7753-09 4 .841E-09 2.489E-09 1. 051E-09 5. 9013-10 SE 8. 980E-09 4.777B-09 2 .9753-09 1. 52 7E-09 6.496E-10 3.6613-10 ESE 5. 951H-09 3.1763-09 1.973E-09 1.018E-09 4.362E-10 3.7583-10 SE 3.184E-09 1. 73 4B-09 1.082E-09 5. 670E-10 2.7953-10 2.748E-10 S SE 4.939B-09 2.682B-09 1.686E-09 8.791E-10 4.*358E-10 3.566E-10 SW 3.731E-09 2.062E-09 1.3253-09 7. 054E-10 3.056E-10 2.0653-10 3.4913-09 2.008E-09 1.354E-09 7.203E-10 3. 1081H-10 1. 753E-10 SW 1.2163-09 7.473E-10 5 .065E-10 2.908E-10 1.2 623-10 7 .139E-11 (

WSW 1.108E-09 6.5523-10 4.355E-10 2.3913-10 1.04 53-10 5.'9443-11 NW 2 .417E-09 1. 3823-09 8 .9573-10 4.786B-10 2.0493-10 1.152E-10 4.435E-09 2.485E-09 1.59 0Z-09 8.3773-10 3. 5513-10 1.988E-10 NNW 5.741E-0 9 3.164E-09 2.007E-09 1.04 9E-09 4.437E-10 2 .484E-10 4.5 7.5 15.0 25.0 35.0 45.0 K 1.944E-10 8. 685E-11 1.6503-10 4.42 3E-10 5.2 52E-10 2 .758H-11 NNE 8.880H-11 3.942E-11 7.0983-11 1. 2193-11 6.530E-12 4.038E-12 NE 7 .813E-11 3 .4243-11 6.8833-11 9.492E-12 5.086E-12 3 .146B-12 ENE 3 .330E-10 1.4 373-10 9. 824E-11 2.573E-11 1.3 803-11 8.541E-12 E 3 .813E-10 1.608E-10 7.197E-11 2.421E-11 1.2 98E-11 .8 .039E-12 ESE 2 .378E-.10 1.543E-10 4.2943-11 1.480E-11 7 .934E-12 4. 911E-12 SE 2.575E-10 1.053E-10 2.854E-11 1.03 3E-11 5.5403-12 3.428E-12 S SE 1.9093-10 7 .321E-11 1.9693-11 7 .139E-12 3.573E-12 2 .208E-12 S 2.2953-10 9.154E-11 2.687E-11 1.03 2E-11 5.181E-12 3 .203E-12 2.750E-10 1.17 6E-10 2.497E-11 8 .477E-12 4. 541E-12 2.-807E-12 SSW 1.329E-10 1. 642E-10 4.6053-11 1. 0413-11 5. 525H-12 3.393E-12 WSW 4. 643H-11 2 .1563-11 4.157E-11 4.604H-11 4.839E-12 1.971E-12 W 3 .868E-11 1.646E-11 2.3933-11 8.590E-11 1.3 03E-10 1.3653-10 mWN 7 .449E-11 3 .222E-11 6.113H-11 2.097E-10 3. 048E-10 3.1203-10 NW 1. 282E-10 5. 677E-11 1.156E-10 3 .505E-10 4 .802E-10 4 .7753-10 1.602E-10 7 .077E-11 1.317E-10 3.775E-10 5.0513B-10 4.961E-10 Rev. No. -9 Rev. o. 9Page C-28 of ODOM

TABLE C-13 SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Concentration X/Q (sec/ni')

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 x 1.027E-08 1.0 97E-08 1.194E-0 8 1.411E-0 8 1.486E-08 1.33 9E-08 NNE 3 .203E-09 4.104E-09 5.36I3-09 7.7403-09 9.169E-09 8.589E-09 NE 1.541R-09 2.147E-09 3 .601E-09 6.4143-09 8.3653-09 8.0953-09 ENE 2.136E-08 1. 920E-08 2 .0803-08 2 .654E-08 2.6433-08 2.296E-08 2.418E-08 2.669E-08 2.929E-08 3.752E-08 3.256E-08 2.619E-08 ESE 2 .565E-08 2.362E-08 2.317E-08 2.243E-08 2.257E-08 1.729E-08 SE 2 .484E-08 1.862E-08 1.761E-08 1.750E-08 1.669E-08 1.992E-08 SSE 2 .207E-08 1. 569E-08 1.47 6E-08 1. 572E-08 1.921E-0 8 1.773E-08 S 2.327E-08 1.668E-08 1.63 0E-08 1.732E-08 2.2153-08 1.961E-08 S SW 1.9293-08 1.592E-08 1.76 5E-08 2.163E-08 2.276E-08 2.047E-08 SW 7.5253-09 6.805E-09 1.138E-08 1. 499E-08 1.706E-08 1.411E-08 WSW 1.477E-09 1.939R-09 2.783E-09 6.039E-09 6.782E-09 6.122E-09 W 1.6213-09 1.537E-09 2.124E-09 3 .344E-09 4.143E-09 3 .951E-09 WNW 3.121E-09 3.4563-09 4 .222E-09 5.6563-09 6.317E-09 5.765E-09 NW 7.262E-09 7.526E-09 8.766E-09 1.12 7B-08 1.242E-0 8 1.13 0Z-08 9.840E-09 1.0353-08 1. 12 6E-08 1.3253-08 1.394E-08 1.25 9E-08 4.5 7.5 15 .0 25.0 35.0 45.0 N 1.166E-08 7 .912E-09 4.057E-09 2.4003-09 1.6513-09 1.47 3E-09 NNE 7 .654E-09 5.395E-09 2.899E-09 5.9593-09 3.873E-09 2.818E-09 NE 7 .362E-09 5.3853-09 3.568E-09 7 .949E-09 5.187E-09 3.784B-09 ENE 1.956E-08 1.2 84E-08 1.2113-08 9.552X-09 6.177E-09 4.4803-09 3 2 .126E-08 1.2 91E-08 9 .490E-09 6.183E-09 3 .959E-09 2.853E-09 1.3 67E-08 1.137E-08 5.359E-09 3 .641E-09 2 .3483-09 1.702E-09 1.483B-08 8 .319E-09 3 .902E-09 2.516E-09 1.633E-09 1.18 9E-09 SSE 1.426E-08 7.*927E-09 3 .472E-09 1.969E-09 1.44 5E-09 1.052E-09 S 1.720E-08 9 .1693-09 3 .894E-09 2.1703-09 1. 617E-09 1. 17 8E-09 SSW 2.008E-08 1.080E-08 5.377E-09 3 . 251B-09 2 .089E-09 1.5103-09 SW 1.3 68E-08 1.015E-08 4 .452E-09 3 .4883-09 2 .294E-09 1. 73 0E-09 WSW 5.337E-09 3.643E-09 2.196E-09 1.283E-09 1.101E-09 1. 497E-09 W 3 .568E-09 2.5883-09 1.451E-09 8.966E-10 6 .449E-10 5. 031E-10 5.053E-09 3 .461E-09 1. 8053-09 1.063E-09 7 .4403-10 5.702E-10 WNW 9 .8813-09 6 .7053-09 3 .423E-09 1. 972E-09 1.3 56E-09 1.024E-09 NNW 1.100E-08 7 .528E-09 3 .920E-09 2.292E-09 1.590E-09 1.208E-09 Rev. No. -9 0-29 of 00CM Rev. o. 9Page

TABLE C-13 (CONTINUED)

(

SECTOR AVERAGE DISPERSION VALUES FOR THE STACK DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

Sector Average Finite Cloud Gamma XIQ (seclni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.158E-07 8.009E-08 6.19 8E-08 4 .3381-08 2 .763E-08 2.0311-08 1NNE 8. 837E-08 6.084E-08 4.7 071-08 3.3051-08 2.1191-08 1.565E-08 1.0 04E-07 6.8721-08 5.3003-08 3 .714E-08 2.383E-08 1.764E-08 ENE 1.844E-07 1.26 8E-07 9.832E-08 7 .168E-08 4.5511-08 3 .3281-08 EN 1.7 19E-07 1.19 9E-07 9.332E-08 7.016E-08 4.346E-08 3.109E-08 1.0541-07 7.510E-08 5.799E-08 3.997E-08 2.7481-08 1. 9391E-08 ISE 7.5181-08 5.213E-0 8 4.029E-08 2.868E-08 1.9541-08 1.7801-08 SI 6.3101-08 4.479E-08 3 .474E-08 2.569E-08 1. 9951-08 1. 5741-08 S SW 6.7 69E-08 4. 821E-08 3.859E-08 2. 8451-08 2.262E-08 1.744E-0 8 SW 9.202E-08 6.303E-08 5.0951-08 3.824E-08 2.660E-08 2 .061E-08 WSW 8 .132E-08 5.613E-08 4.944E-08 3.5033-08 2.387E-08 1.7251-0 8 SW 5.017E-08 3.457E-08 2 .681E-08 2.139E-08 1.3671-08 1.004E-0 8 WNW 4.869E-08 3.326E-08 2.566E-08 1. 797E-08 1. 151E-08 8.5211-09 NW 5.77 9E-08 3.977E-08 3.077E-08 2.159E-08 1. 37 9E-08 1. 015E-08 9.748E-08 6.725E-08 5.218E-08 3.674E-08 2.357E-08 1.737E-08 NNW 1.133E-07 7.823E-08 6.053E-08 4.2351-08 2.696E-08 1.9 82E-08 4.5 7.5 15 .0 25.0 35.0 45.0 N 1.5991-08 9 .594E-09 4.587E-09 2.642E-09 1.803E-09 1.510E-09

1. 23 8E-08 7 .517E-09 3.669E-09 3 .858E-09 2.576E-09 1.909E-09 NNE 1.400E-08 8.577E-09 4.739E-09 4 .937E-09 3 .317E-09 2.468E-09 2.608E-08 1.550E-08 1.0481-08 6.589E-09 4.3651-09 3 .218E-09 liE 2.393E-08 1.373E-08 8.069E-09 4 .645E-09 3.0351-09 2 .2171-09

1. 48 0E-08 1.035E-08 4.652E-09 2.723E-09 1.792E-09 1.316E-09 ESE 1.326E-08 7.323E-09 3.289E-09 1.896E-09 1.256E-09 9 .271R-10 1.216E-08 6.6983-09 2.936E-09 1. 621E-09 1. 123 3-09 8.2951-10 S 1.392E-08 7.524E-09 3 .256E-09 1. 7 85-09 1.244E-09 9.1901-10 1.778E-.08 9.626E-09 4.425E-09 2.476E-09 1.623E-09 1.189E-09 SSW 1.478E-08 9.614B-09 4 .201E-09 2 .647E-09 1.750E-09 1.302E-09 WSW 7.897E-09 4.7401-09 2.495E-09 1. 413E-09 1.0853-09 1.056E-09 W 6 .758E-09 4.136E-09 2 .051E-09 1.2009-09 8.395E-10 6.423E-10 WNW 8.007E-09 4.832E-09 2.340E-09 1.344E-09 9.281E-10 7 .043E-10 NW 1.369E-08 8.224E-09 3.930E-09 2.224E-09 1.520E-09 1.143E-0 9

1. 561E-08 9.393E-09 4.520E-09 2.573E-09 1.765E-09 1.331E-0 9 K

Rev. No. -9 Rev. o. 9Page C-30 of ODOM

TABLE C-13 (CONTINUED)

SECTOR AVERAGE DEPOSITION VALUES FOR THE STACK DETERMINED FROM GRAZING METEOROLOGICAL DATA (May-Oct., 1985 To 1992)

(DIQ) Sector Average Deposition (Ilni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 8.12 0H-10 6.726E-10 5. 859E-10 3 .891E-1.0 2.241E-10 1.437E-10 2.594E-10 2.4251-10 2.3241-10 1.666E-10 1.006E-10 6 .5371-11 NNE 1.367E-10 1.617E-10 1. 77 89-10 1. 39 6E-10 8. 856E-11 5.825E-11 2 .061E-09 1.641E-09 1. 37 3E-09 8.7 82E-10 4.932E-10 3.1451-10 2.344E-09 1.893E-09 1. 6111-09 1.048E-09 5.954E-10 3 .804E-10

1. 916E-09 1. 44 6E-09 1. 1481-09 6.978E-10 3 .772E-10 2.37 8E-10 ESE 1.509E-09 1.111E-09 8.5361-10 5.0011E-10 2. 6471-10 1.7 88E-10 S SE 1.3 81E-09 9.953E-10 7.4441-10 4.225E-10 2.2821-10 1.4 51R-10 S 1.637E-09 1.173E-0 9 8.706E-10 4.899E-10 2. 6441-10 1.6 64E-10 1.380E-09 1.068E-09 8.670E-10 5.3851-10 2 .9851-10 1.94 6E-10 SSW

4. 653E-10 4.167E-10 3.854E-10 2.688E-10 1.598E-10 1.034E-10 WSW 8 .735E-11 8.6981-11 8.6851-11 6.410E-11 3.936E-11 2.568E-11 W 8.824E-11 8.612R-11 8.467E-11 6. 182E-11 3 .773E-11 2.4591-11 WNW 2.513E-10 2.214E-10 2.02 51-10 1. 401E-10 8.281E-11 5.3 51E-11 NW 5.753E-10 4 .944E-10 4.434E-10 3.018E-10 1.766E-10 1.13 8E-10 8.411E-10 6.830E-10 5.837E-10 3.811E-10 2.1701-10 1. 388E-10 NN 4.5 7.5 15 .0 25.0 35.0 45.0 9.813E-11 4. 342E-11 1.4581-11 6.584E-12 3.899E-12 2.583E-12 4.471E-11 1. 970E-11 6. 541E-12 1.0891-11 2.064E-11 2.6101-11 NNE

3. 992E-11 1.7531-11 5.75919-12 2.237E-11 8.3931-12 5.198E-12 ENE 2.147E-10 .9. 5301-11 3.198E-11 3.184E-11 1.7 09H-11 1.0591-11 2.596E-10 1.151E-10 3.834E-11 2.707E-11 1. 453E1-11 9.002E-12 E SE 1.6201-10 7.545E-11 2.442E-11 1.053E-10 7 . 9071-12 4.8971-12 SE 1.206E-10 5.231E-11 1.7111-11 1.248E-11 3.737E-11 6.7061-11 SSE 9. 856E-11 4.268E-11 1.416E-11 6.581E-12 1.193E-11 2.7891-12 S 1.13 6E-10 4. 896E-11 1.630E-11 7.617E-12 2.8121-11 3.3961-12 S SW 1. 379E-10 5.96713-11 1. 9161-11 2.19 8E-11 3.347E-11 4.991E-12 SW 7.147E-11 3.262E-11 1.0361-11 4.400E-12 2 .543E-12 2.7591-12 WSW 1.757E-11 7.7301-12 2.554E-12 1.121E-12 6 .388E-13 4. 550E-13 W 1.6841-11 7. 414E-12 2.457E-12 1.084E-12 6.291E-13 4 .13OR- 13 3.659E-11 1.616E-11 5.394E-12 2 .412E-12 1.417E-12 9.3621-13 WNW 7.779E-11 3.4381-11 1.1511-11 5.17 0E-12 3 .048E-12 2.0181-12 9.4721-11 4. 197E-11 1.413E-11 6.421E-12 3. 821E-12 2 .541E-12 Rev. No. 9 Rev. o. 9Page C-31 of 00CM

TABLE C-14 CRITICAL RECEPTOR DISPERSION AND DEPOSITION PARAMETERS FOR VENT AND ELEVATED RELEASES DISPERSION PARAMETER DESCRIPTION RECEPTOR Annual Average X/Q - Total Body; Stack Site Boundary Annual Average X/Q - Skin; Stack Site Boundary*

Annual Average X/Q - Ganuna Air; Stack Site Boundary Annual Average X/Q - Beta Air; Stack Site Boundary*

Annual Average X/Q - Dep. Inhal.; Stack Resident Annual Average D/Q - GPD; Stack Resident Grazing D/Q - SFV & FFV; Stack Garden Grazing D/Q - Cow; Stack Milk Animal Grazing D/Q - Goat; Stack Milk Animal Grazing D/Q - Meat; Stack Meat Animal Annual Average X/Q - Total Body; Vent Site Boundary Annual Average X/Q - Skin; Vent Site Boundary Annual Average X/Q - Ganmia Air; Vent Site Boundary Annual Average X/Q - Beta Air; Vent Site Boundary Annual Average X/Q - Dep. Inhal.; Vent Resident Annual Average D/Q - GPD; Vent Resident Grazing D/Q - SFV & FFV; Vent Garden Grazing D/Q - Cow; Vent Milk Animal Grazing D/Q - Goat; Vent Milk Animal Grazing D/Q*- Meat; Vent Meat Animal

The highest X/Q is located beyond the site boundary.

Rev. No. 9 Rev. o. 9Page 0-32 of 00CM

TABLE C-15 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES AND ANNUAL SECTOR AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH SHORT TERM RELEASES)

Concentration X/Q (sec /m')

Site Hourly Annual Boundary Plume Cent. Sector Ave.

Distance Conc. (X/Q) Conc. (X/Q) Slope in 3

Direction (sec/fin) (SeC/rn )

225 N w 1.2 84E-03 3.496B-05 -0.3970 225 w 1. 061E-03 1.7751-05 -0.4506 NNE w 354 4. 704E-04 5.342E-06 -0.4933 ENE w 563 1.6501-04 3.429E-06 -0.4267 ENE 950 4.960E-05 1.054E-06 -0.4243 SE 1030 3.611E-05 5.8621-07 -0.4539 ESE 1110 3.204E-05 4.16 8E-07 -0.4783 1754 2.213E-05 1.732E-07 -0.5343 SE 1

SSE 2205 1. 640E-05 1. 3631-07 -0.5277 1

SW 2269 2. 610E-05 2.0031-07 -0.5365 1

2382 3 .489E-05 3.1411-07 -0.5189 WSW 1867 7.570E-05 4.1411-07 -0.5737 W w 644 3.3381-04 2.683E-06 -0.5314 WNW 370 8.355E-04 1.389E-05 -0.4513 w

NW 306 9.082E-04 2.5961-05 -0.3916 241 1.3 95E-03 3.6841-05 -0.4003 (Refer to Section 4.4.3)

Rev. No. -9 0-33 of ODCM Rev. o. 9Page

TABLE C-16 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES AND ANNUAL SECTOR AVERAGE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH SHORT TERM RELEASES)

Depoeition (D/Q) (1/M2)

Site Hourly Annual Boundary Plume Cent. Sector Ave.

Distance (D/Q) (D/Q) Slope m Direction 225 N w 3.819E-06 1.3 31E-07 -0.3698 225 NNE w 3.549E-06 7.094E-08 -0.4310 NE w 354 1.840R-06 3.000E-08 -0.4534 ENE w 563 1.166E-06 3.2351-08 -0.3949 E 950 4.777E-07 1.3523-08 -0.3927 ESE 1030 3.797E-07 8.757E-09 -0.4152 SE 1110 3.096E-07 6.4563-09 -0.4263 SSE 1754 1. 560E-07 1.852E-09 -0.4884 1

S 2205 1.083E-07 1.409E-09 -0.4783 1

SSW 1 2269 1.300E-07 1.371E-09 -0.5014 SW 2382 1.36 6E-07 1.507E-09 -0.4965 WSW 1867 2.155E-07 1. 247E-09 -0.5676 W w 644 1. 008E-06 7.7 94E-09 -0.5356 WNW 370 2 .080E-06 4.097E-08 -0. 4326 w

NW 306 2.5881-06 8.5461-08 -0.3757 INNW 241 3.727E-06 1.13 9E-07 -0.3842 (Refer to Section 4.4.3)

Rev. No. 9 0-34 of ODOM Rev. o. 9Page

TABLE C-17 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES)

Plume Centerline Concentration X/Q (sec/ni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.6 99E-04 1.076B-04 7.986E-05 4.929E-05 3 . 382E-05 2.338E-05 1.6 07E-04 1.04 6E-04 7.674E-05 4 .790E-05 2.9411-05 2.237E-05 NNE 1.443E-04 8.9101-OS 6 .364E-05 3 .787E-05 2.3531-05 1.62 8B-05 ENE 9.691E-0S 6.042X-O5 4.3001-05 .2.4583-OS 1.431B-O5 9. 546E-06 6.170E-05 3 .762B-05 2.673E-O5 1. 457E-05 8. 4 88-06 5. 543B-06 ESE 4.999E-05 2.937Z-05 2 .013E-05 1. 07 9E-05 5.9581-06 3 .790H-06 SE 4. 934E-05 2.8561-05 1.944E-05 1.003E-05 5.6983-06 3 .529E-06 SSE 6.206E-05 3.660E-05 2.469E-05 1.349E-05 7.6223-06 4.850E-06 S 6.4151-05 3 .732E-05 2 .483E-05 1.356E-05 7. 6811-06 4.949E-06 S SW 1.018E-04 5.889E-05 4.124E-05 2.228E-05 1.3 341-05 9.017E-06 Sw 1.254E-04 7.730E-05 5.343E-05 3 .173E-05 1. 959E-05 1.331E-05 WSW 1.937E-04 1.217E-04 9.179E-05 5.636E-05 3.5651-05 2.610E-05 W 2 .334E-04 1.519E-04 1. 1312-04 7.255E-05 4. 8371-05 3.588E-05 2.266E-04 1. 507E-04 1.154E-04 7.694E-05 4.8671-05 3.613E-05 WNW 2.062E-04 1. 305E-04 9.9101-05 6.428E-05 4.403B-05 3 .137E-05 1.9 501-04 1.25 1E-04 9.5651-05 6.064E-05 4.107E-05 3 .028E-05

4. 5 Miles .7 .5 Miles 15. 0 Miles 25.0 Miles 35.0 Miles 45.0 Miles N 1. 787E-05 1.0 84E-05 5 .123E- 06 3.189B-06 2.5061-06 2 .232E-06 NNE 1.64 0E-05 9.724E-06 4.242E-06 2.665E-06 2.1971-06 1.946E-06 NE 1.202E-05 6 .775E-06 3 .149E-06 2.2401-06 1.7 63B-06 1.658E-06 ENK 7. 0559-06 3.816E-06 1.880E-06 1.244E-06 1.024E-06 9.608E-07 E 3.976E-06 2.256E-06 1.239E-06 8.773E-07 7.968E-07 7.4103-07 ESE 2.708E-06 1. 508E-06 8.402E-07 6 .951E-07 6.563E-07 6 .136E-07 SE 2.529E-06 1. 446E-06 9.104E-07 7 .173E- 07 6.712E-07 6.380E-07 SSE 3 .487E-06 1.8553-06 1.336E-06 1. 005E-06 9.1521-07 8.714E-07 S 3.617E-06 1. 977E-06 1.347E-06 9 .941E-07 8. 840E-07 8.540E-07 S SW 6.567E-06 3.3773-06 1. 965E-06 1.4 912-06 1.15 8E-06 1. 10 2E-06 SW 9.5551-06 5.304R-06 2. 844E-06 2 .096X-06 1.49 0R-06 1.505E-06 WSW 2.0151-05 1. 1441C-0 5 6 .078E-06 3.816E-06 2.8243-06 2.563E-06 W 2 . 801E-05 1.656E-05 8. 601E-06 5.208E-06 4.0801-06 3 .717E-06 WNW 2 .841E-05 1.784E-05 8.792E-06 5.2681-06 4.0151-06 3.663E-06 NW 2 .484E-05 1.399E-05 7.019E-06 4.387E-06 3.446E-06 3 .20SE-06 NNW~ 2.416E-05 1.525E-05 7 .180E-06 4. 311E-06 3 .235E-06 3.083E-06 Rev. No. 9 C-35 of ODOM Rev. o. 9Page

TABLE C-18

(

SECTOR. AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH LONG TERM RELEASES)

Sector Average Concentration XIQ (seclrd)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 3.9481-06 2.078E-06 1.3481-06 7 .608E-07 3.8001-07 2.415E-07 NNE 2 .048E-06 1.-091E-06 7. 116E-07 3 .9951-07 1.969E-07 1. 241E-07 NE 1.427E-06 7.723E-07 5.060E-07 2.8251-07 1.373E-07 8.575E-08 NEX 1.9851-06 1.0701-06 6.9928-07 3 .889Z-07 1.8841-07 1.17 6E-07 1.3751-06 7.2491-07 4.692E-07 2.593E-07 1.2 54E-07 7.83'8E-08 ESE 8.717E-07 4.596E-07 2.977E-07 1.63 9E-07 7.877E-08 4.911E-08 SE 6.983E-07 3.671E-07 2 .384E-07 1. 3151-07 6.3331-08 3.958E-08 SSE 5.*6971-07 3.018E-07 1.9681-07 1.089E-07 5.258E-08 3.2891-08 S 6.334E-07 3.339E-07 2.169E-07 1.1951-07 5.752E-08 3.595E-08 S SW 9.6251-07 5.1481-07 3 .3381-07 1.8283-07 8.685E-08 5.3 621-08 SW 1.6011-06 8.6401-07 5.612E-07 3 .081E-07 1.4651-07 9.029E-08 WSW 1.457E-06 7 .8911-07 5.157E-07 2.866E-07 1.3851-07 8.613E-08 W 1.881E-0 6 9.925E-07 6.4 611-07 3 .645E-07 1.8151-07 1.150E-07 WN~W 3.7 57E-06 1.944E-0 6 1.254E-06 7 .106E-07 3.5931-07 2.3001-07 5.025E-06 2.605E-06 1.6781-06 9.490E-07 4.7891-07 3.0631-07 N~W 4.607E-06 2.382E-06 1.534E-0 6 8.699E-07 4.408E-07 2.826E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 1.72 6E-07 8.781E-08 3 .565E-08 1.8551-08 1.212E-0 8 8.843E-09 NNE 8.811E-08 4.427E-08 1.769E-08 9.098E-09 5.9011-09 4.285E-09 NE 6.049E-08 2.998E-08 1.176E-08 5.962E-09 3.832E-09 2.764E-09 ENE 8.299E-08 4.122E-08 1.627E-0 8 8.305E-09 5.365E-09 3.887E-09 E 5.540E-08 2.769E-08 1.109E-08 5.7342-0 9 3 .740E-09 2.731E-09 ESE 3 .465B-08 1.728E-08 6.916E-09 3 .581E-09 2.339E-09 1. 711E-09 SE 2.799E-08 1.402E-08 5.659E-09 2.952E-09 1.939E-09 1.42 5R-09 S SE 2.326E-08 1.164E-08 4.686E-09 2 .438E-09 1.59 81-09 1. 17 2E-09 S 2 .541E-08 1.272E-08 5.133E-09 2 .678E-09 1.759E-09 1. 293E-09 SSW 3 .755E-08 1.840R-08 7.1661-09 3.633E-09 2 .341E-09 1.696E-09 SW 6.312E-08 3.078E-08 1.186E-08 5.954E-09 3 .807E-09 2 .741R-09 WSW 6. 060E-08 2.988E-08 1.16 5E-08 5.884E-09 3.7733-09 2 .718E-09 W 8.207E-08 .4.159E-08 1.680E-08 8.704E-09 5.673E-09 4 .133E-09 WN~W 1. 653E-07 8.4951-08 3.494E-08 1.834E-08 1. 206E-08 8.836B-09 NW 2.199E-07 1.130R-07 4.643E-08 2.436E-08 1.601E-08 1.173E-08 NNW 2. 033E-07 1.048E-07 4 .324E-08 2 .2751-08 1.498E-08 1.099E-08 Rev. No. -9 Rev. o. 9Page C-36 of ODOM

TABLE C-19 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH SHORT TERM RELEASES)

(DIQ) Plume Centerline Deposition (1/ni)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 8.196E-07 4 .879E-07 3.2351-07 1.74 5E-07 7.6801-08 4.389E-08 1NNE 7.499E-07 4 .421E-07 2.918E-07 1.568E-07 6.8891-08 3.9331-08 NE 7.015E-07 4.084E-07 2.680E-07 1.434E-07 6.279E-08 3.582E-08 ENE 7 .513E-07 4.265B-07 2.758E-07 1.458E-07 6.3481-08 3.618E-08 6 .0001-07 3 .392E-07 2.1981-07 1.164E-07 5. 0951-08 2.906E-08 ESE 5.379B-07 2.-994E-07 1.925E-07 1.013E-07 4.402B-08 2.510E-08 SE 4.9201-07 2 .729E-07 1.756E-07 9.24 8E-08 4.022E-08 2.294E-08 S SE 4.987E-07 2.787E-07 1. 793E-07 9.3901-08 4. 076E-08 2.322E-08 S 5. 035E-07 2.780E-07 1.784E-07 9. 367E-08 4.0641-08 2.3151-08 S SW 6.1501-07 3.456E-07 2 .231E-07 1.17 8E-07 5. 12 5E-08 2 . 924E-0 8 SW 6.826E-07 3.-885E-07 2.522E-07 1.337E-07 5. 8311-08 3 .312E-08 WSW 7 .002E-07 4.1011-07 2.698E-07 1.446E-07 6.339E-08 3.617E-08 W 7 .821E-07 4.647E-07 3 .077E-07 1. 658E-07" 7.294E-08 4.168E-08 WNW 8.673E-07 5.222E-07 3.4801-07 1.8 86E-07 8.325E-08 4.764E-08 8.526E-07 5.116E-07 3 .4031-07 1.841E-07 8.119E-08 4.643E-0 8 8.945H-07 5.382E-07 3.586E-07 1.9431-07 8.572E-08 4.903E-08 4.5 7.5 15.0 25.0 35.0 45.0 N 2.868E-08 1.216E-08 4.258E-09 1.853E-09 1. 097E-09 8.646E-10 NNE 2.569E-08 1.087E-08 3.874E-09 1.831E-09 1. 092E-09 8.632E-10 NE 2.339B-08 9.896E-09 3.6531-09 1.815E-09 1.0911-09 8. 6611-10 ENE 2.344E-08 9.-104E-09 3.470E-09 1. 77 9E-09 1.102E-09 8. 689E-10

1. 884E-08 8.362E-09 3.407E-09 1.768E-09 1. 099E-09 8.723E-10 1.644E-08 7. 454E-09 3.210E-09 1.772E-09 1.094E-09 8.726E-10 ESE 1.522E-08 7.432E-09 3.238E-09 1.752E-09 1. 098E-09 8.714E-10 SSE 1.524E-08 7.294E-09 3.216E-09 1.725E-09 1. 093E-09 8. 703E-10 S 1. 518B-0-8 7.268E-09 3 .248E-09 1. 760E-09 1.092E-09 8. 686E-10 1.909E-08 7.815E-09 3 .324E-09 1. 801E-09 1.089E-09 8. 654E-10 SSW 2 .164E-08 8. 873E-09 3.386E-09 1. 767E-09 1.086E-09 8.6251-10 WSW 2.362E-08 1.002E-08 3.516E-09 1. 747E-09 1.0811-09 8.607Z-10 W 2 .724B-08 1.15 6E-08 3.953E-09. 1. 818E-09 1. 082E-09 8.582E1-20 3 .117E-08 1.32 5E-08 4.389E-09 1.856B-09 1.088E-09 8.598E-10 WNW 3 .035E-08 1. 288E-08 4.349E-09 1.863E-09 1.0911-09 8.632E-10 N~W 3.206E-08 1.348E-08 4.593E-09 1.8951-09 1.094E-09 8.638E-10 Rev. No. 9 0-37 of 00CM Rev. o. 9Page

TABLE C-20 SECTOR AVERAGE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM ANNUAL AVERAGE METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH LONG TERM RELEASES)

(DIQ) Sector Average Deposition (Ilrnf)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 1.937E-08 9.969E-09 6 .130H-09 3 .059E-09 1.2 57E-09 6.930E-10 NNE 1. 032F-08 5. 308E-09 3 .2641-09 1.62 9E-09 6 .689E-10 3.688E-10 HE 8. 393E-09 4.317E-09 2.654E-09 1.3241-09 5.436E-10 2.996E-10 ENE 1. 845E-08 9.552E-09 5.8991-09 2.962E-09 1.227E-09 6.800E-10 E 1.7 64E-08 9 .1611-09 5.670E-09 2.8561-09 1.187E-09 6.*598E-10 ESE 1.2 94E-08 6.744E-09 4.184E-09 2.114E-09 8.826E-10 4.9201-10 SE 1.076E-08 5.627E-09 3.4993-09 1.774E-0 9 7.439E-10 4.158E-10 SSE 6.557E-09 3.433E-09 2 .137E-09 1. 08$Z-09 4 .555E-10 2.*548E-10 S 7.306E-09 3.827E-09 2.383E-09 1. 210E-09 5.0841-10 2.845E-10 SSW 7. 6251-09 3 .959E-09 2 .450R-09 1.234E-09 5.1251-10 2.848E-10 SW 9.231E-09 4.768E-09 2.940E-09 1.47 3E-09 6 .079E-10 3.363E-10 WSW 5.073B-09 2. 6111-09 1.606E-09 8.0181-10 3.294E-10 1. 8161-10 W 5.456E-09 2.807E-09 1.7251-09 8. 6081-10 3 .534E-10 1. 947E-10 (

WNW 1.224B-08 6.296E-09 3.870E-09 1.9301-09 7 .922E-10 4.365E-10 NW 1. 930F-08 9.928E-09 NNW 1.8271-08 9.403E-09 6.1031-09 5.782E-09 3.044E-09 2.886E-09 1.250E-09 1.1851-09 6.8881-10 6.535E-10

(

4.5 7.5 15.0 25.0 35.0 45.0 N 4.42 0E-10 1.789E-10 5. 648E-11 2 .279E-11 1. 219E-11 7.527E-12 NNE 2. 352E-10 9. 517E-11 3 .004E-11 1. 212E-11 6 .481E-12 4.0 01E-12 NE 1.9111-10 7.733E-11 2 .442E- 11 9. 857E-12 5.274E-12 3.258E-12 ENE 4.346E-10 1. 76 0E-10 5.*563E-11 2.248E-11 1. 204E-11 7.44 9E-12 R 4.221E-10 1. 70 9E-10 5.*406E-11 2 .186E-11 1. 172E-11 7.255E-12 ESE 3.150E-10 1.276E-10 4.035E-11 1. 6321-11 8.7501-12 5.416E-12 SE 2.665E-10 1.079E-10 3.412E-11 1. 3791-11 7 .393E-12 4.574E-12 SSE 1. 634E-10 6. 612E-11 2.089E-11 8.43 3B-12 4.514B-12 2 .789E-12 S 1.824E-10 7.383E-11 2.332E-11 9 .4131-12 5. 038E-12 3.112E-12 SSW 1. 821E-10 7.369E-11 2.327E-11 9.3851-12 5.020E-12 3.099E-12 SW 2.147E-10 8.686E-11 2.74 0E-11 1.1041-11 5. 9001-12 3.639E-12 WSW 1.15 8E-10 4.6821-11 1.474E-11 5. 924E-12 3.156E-12 1. 941E-12 W 1.241E-10 5.017E-11 1.579E-11 6.346E-12 3.381E-12 2.079E-12 WNW 2.7 83E-10 1. 126E-10 3.548E-11 1.42 8E-11 7.624E-12 4.697E-12 NW 4.392E-10 1.777E-10 5 .606R-11 2.2591-11 1.2 07E-11 7.446E-12 NNW 4.1681-10 1.686E-10 5.321E-11 2 .145E-11 1.147E-11 7.074E-12 K

Rev. No. -9 Rev. o. 9Page 0-38 of ODOM

TABLE C-21 85TH PERCENTILE HOURLY PLUME CENTERLINE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES)

Plume Centerline Concentration XIQ (seclrd)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 2 .035E-04 1.319E-04 9.688E-05 6. 511E-05 4.4731-05 3 .234E-05 NE 1.87 9E-04 1.27 0R-04 9 .123E-0 5 5.931E-05 3 .831E-05 2.7401-05

1. 632E-04 1.030H-04 7.4651-05 4.782E-05 2.8951-05 1. 998E-05 ENE 1.029E-04 6.4141-05 4.529E-05 2 .778E-05 1.533E-05 1.037E-05 6.347E-05 3.8711-05 2.645E-05 1.643E-05 8.6801-06 5.704E-06 5.5291-05 3.284E-05 2.249B-05 1.3441-05 7.2311-06 4.554E-06 ISE

5. 878E-05 3.449E-05 2 .322E-05 1.327E-05 7.155E-06 4.5301-06 SSE

7. 662E-05 4.653E-05 3.199E-05 1.929E-05 1.0171-05 6.744E-06 S 6.387E-05 3.657E-05 2.530E-05 1.454E-05 7.813E-06 5.065E-06 SSW 1.002E-04 6.046E-05 4.342E-0 5 2 .548E-05 1.416E-05 9.655E-06

.sw 1.271E-04 7. 949E-05 5.718E-0 5 3 .660E-05 2.*001E-05 1. 42 0B-05 WSW 2 .173E-04 1.416E-04 1.0171-04 7.04 01-05 4.171E-0 5 3 .095E-05 W 2.657E-04 1.6951-04 1.2 82E-04 8.955E-05 5.926E-05 4.564E-05 WNW 2.947E-04 1.962E-04 1.530E-04 1.115E-04 7.065E-05 5.353E-05 NW 2.589E-04 1.711E-04 1.2 94E-04 9.394E-05 5.940E-05 4.747E-05 NNW 2.2401-04 1.457E-04 1.122E-04 7.873E-05 5.2171-05 4.167E-05 4.5 7.5 15.0 25.0 35.0 45.0 N 2.466E-05 1. 477E-05 7 .229E-06 4.548E-06 3.2581-06 2.939E-06 NNE 2 .146E-05 1. 237E-05 5.954E-06 3.551E-06 2.874E-06 2.5551-06 NE 1.4 801-05 8.449E-06 4.107E-06 2.76 0E-06 2.172E-06 1.9431-06 ENE 7 .7231-06 4. 094E-06 2.113E-06 1. 43 1E-06 1. 19 4E-06 1. 080H-06 4 .203E-06 2.4501-06 1.5209-06 1.093E-06 9.532E-07 9.103E-07 ESE 3 .277E-06 2.083E-06 1. 212E-06 8.868E-07 9.226E-07 9.234E-07 SE 3.284E-06 2 .108E-06 1. 223E-06 9.083E-07 9.658E-07 9.015E-07 SSE 4 .949E-06 3 .255E-06 1. 759E-06 1.451E-06 1.200E-06 1. 12 51-06 S 3 .595E-06 2 .290B-06 1.634E-06 1.226E-06 1. 05 1E-06 9.739E-07 S SW 7.015E-06 3. 692E-06 2.072E-06 1.640B-06 1.361E-06 1. 212E-06 SW 1.059E-05 5.604E-06 2.972E-06 2 .285E-06 1. 926E-06 1.784E-06 WSW 2 .380E-05 1.346E-05 6.594E-06 4.291E-06 3.372E-06 3 .081E-06 W 3.488E-05 2.109E-O5 1.008E-05 6.435E-06 5.014E-06 4.5151-06 4.291E-05 2 .492E-05 1.284E-05 8.174E-06 5. 922E-06 5.432E-06 NWI 3.796E-05 2.309E-05 1.2 001-05 7.419E-06 4 .994E-06 4 .573E-06 NNW 3.380E-05 2.018E-05 9.8381-06 5.947E-06 4.413E-06 4.003E-06 Rev. No. 9 Rev. o. 9Page C-39 of ODOM

TABLE C-22 i

SECTOR AVERAGE DISPERSION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1 992)

(FOR USE WITH LONG TERM RELEASES)

Sector Average Concentration XIQ (seclrrf)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 5.3001-06 2.743E-06 1.774E-0 6 1.0101-0 6 5.1251-07 3.291E-07 NNE 2.423E-06 1.273E-06 8.309E-07 4.714E-07 2.3651-07 1.507E-07 NE 1.607E-06 8.669E-07 5.697E-07 3.202E-07 1.572E-07 9.8741-08 ENE 2.342E-06 1.257E-06 8.224E-07 4.586E-07 2. 232E-07 1.3989-07 E 1.6509-06 8.651E-07 5.6041-07 3.111E-07 1.517E-07 9.540R-08 ESE 9.686E-07 5.088E-07 3 .309E-07 1.837B-07 8 .941E-08 5.61919-08 SE 6. 517E-07 3.422E-07 2 .237E-07 1.2501-07 6 .131E-08 3.8781-08 SSE 5.53 1R-07 2 .919E-07 1.915E-07 1.0721-07 5.2651-08 3.3321-08 S 6.636E-07 3 .486E-07 2 .274E-07 1.2 62E-07 6 .142E-08 3 .8701-08 SSW 8.999B-07 4.813E-07 3.136E-07 1.73 13-07 8.3101-0 8 5.169E-0 8 SW 1.540E-06 8.3 57E-07 5.447E-07 2.-999E-07 1.4301-07 8.8411-0 8 WSW 1.549E-06 8.3551-07 5.4 52E-07 3 .0391-07 1.479E-07 9.2433-08 W 2.1001E-06 1.097E-0 6 7.13 8E-07 4.055SS-07 2.043E-07 1.3051-07 WNW 4.454E-06 2.2631-06 1.452E-06 8.306E-07 4.280E-07 2 .7awE-07 NW 6.109E-06 3 .1021-06 1.987E-06 1.1351-06 5.847E-07 3.7871-07 NNW 5.8491-06 2 .971E-06 1.903E-06 1.087E-06 5.5931-07 3 .621E-07 4.5 7.5 15.0 25.0 35.0 45.0 N 2 .369E-07 1.223E-07 5.0551-08 2 .663E-08 1.753E-0 8 1.2869-08 1.079E-07 5.507E-08 2 .2451-08 1. 171E-08 7.663E-09 5.598E-09 N3!

6.998E-08 3 .501E-08 1.389E-08 7.107E-09 4.592E-09 3.324E-09 ENE 9.892E-08 4.941E-08 1.967E-08 1.0111-0 8 6.559E-09 4.768E-09 6.774E-08 3.416E-08 1.385E-08 7.224E-09 4.739E-09 3.4751-09

3. 988E-08 2.010E-08 8.1651-0 9 4.2702-09 2.807E-09 2.062E-09 SE 2.764E-08 1.4051-0 8 5.767E-09 3.044E-09 2.013E-09 1.48 61-09 SSE 2.376B-08 1.207E-08 4.950E-09 2.609E-09 1.724E-0 9 1.2729-09 S 2.753E-08 1.3951-08 5.723E-09 3.022E-09 2.002E-09 1.48 0E-09 S SW 3.639E-08 1.802E-08 7.121E-0 9 3.649E-09 2.367E-09 1.72 3E-09 SW 6.194E-08 3.035E-08 1.178E-0 8 5.946E-09 3 .814E-09 2.7501-09

'WSW 6.527E-08 3 .245E-08 1.279E-08 6.514E-09 4.2001-09 3.037E-09 W 9.357E-08 4.793E-08 1.962E-08 1.0261-08 6.727E-09 4.920E-09

2. 008E-07 1.049E-07 4.398E-08 2.339E-08 1.5501-08 1.142E-0 8 WNW 2 .744E-07 1.433B-07 6.013E-08 3.200E-08 2 .120E-08 1.563E-08 2.622E-07 1.369E-07 5.743E-08 3.056E-08 2.025E-08 1.493E-08 K

Rev. No. -9 Rev. o. 9Page C-40 of ODOM

TABLE C-23 85TH PERCENTILE HOURLY PLUME CENTERLINE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH SHORT TERM RELEASES)

(DIQ) Sector Average Deposition (11w?)

SEGMENT BOUNDARIES IN MILES Direction 0.5 0.75 1.0 1.5 2.5 3.5 N 9.063B-07 5.4711-07 3.6361-07 1.966E-07 8.6661-08 4.9521-08 8.251E-07 4. 868E-07 3.-215E- 07 1. 72 8E-07 7.592E-08 4.3 341-08 NNE 7.357E-07 4.2 851-07 2.7711-07 1.4 82E-07 6.503E-08 3.7183-08 7 .139E-07 4.059E-07 2.6331-07 1. 3901-07 6.056E-08 3.4551-08 EIT 5.942E-07 3 .352E-07 2.1741-07 1.145E-0 7 4.-9863-08 2.8431-08 5.161E-07 2 .898E-07 1.8729-07 9.833B-08 4 .282E-08 2.4431-08 ESE 5.089E-07 2 .831E-07 1.82 01-07 9.577E-08 4.1611-08 2.37219-08 SE 5.281E-07 2 .921E-07 1.8551-07 9.735E-08 4.2231-08 2.4063-08 SSE 4.9711-07 2 .7801-07 1.7951-07 9 .481E-08 4.129E-08 2.356E-08 SW 6.017E-07 3.342E-07 2.1501-07 1.132E-07 4.9161-08 2.8023-08 6.7353-07 3 .808E-07 2.4593-07 1.297E-07 5.6291-08 3.210E-08 WSw 7.454E-07 4 .299E-07 2.8121-07 1.5 01E-07 6.569E-08 3.75019-08 W 8.2 55E-07 4.942E-07 3.2 84E-07 1.7751-07 7.813E-08 4.*4619-08 WNW 9.768E-07 5 .984E-07 4.019E-07 2.191E-07 9.*6 94E-08 5.5421-08 NW 9.-981E-07 6 .144E-07 4 .117E-07 2 .241E-07 9.9111-08 5.6671-08 9 .449E-07 5 .713E-07 3.826E-07 2 .082E-07 9.2 051-08 5.2651-08 4.5 7.5 15.0 25.0 35.0 45.0 N 3.236E-08 1.356E-08 4.621E-09 1. 89 7B-09 1.0981-09 8.6461-10 NNE 2.831E-08 1.195B-0 8 4.113E-09 1.839E-09 1.092E-09 8.*6223-10 NIT 2.433E-08 1.035E-08 3-679E-09 1.802E-09 1.0911-09 8.6361-10 ENE 2 .2481-08 8.997E-09 3.623E-09 1.79 8E-09 1.1003-09 8.6721-10 1- 850E-08 8.152E-09 3.457E-09 1.792E-09 1.096E-09 8.7051-10 ESE 1. 618E-08 7.794E-09 3.226E-09 1.746E-09 1.0 94E-09 8.7 181-10 SI 1.571E-08 7 .2551-09 3.1601-09 1.74 8E-09 1. 0911-09 8.*694E-10 S SE 1.606B-08 7.248E-09 3.154E-09 1- 790E-09 1. 087E-09 8 .633E-10 S 1.556E-08 7 .412E-09 3.-201E-09 1.7 65-09 1.089B-09 8.651E-10

1. 833E-08 7 .403E-09 3.328E-09 1.773E-09 1.086E-09 8.*637B-10 SSW 2.098E-08 8.312E-09 3.-361E-09 1.789E-09 1.083E-09 8.6061-10 WSW 2.451E-08 1. 0611-08 3 .5943-09 1. 728E-09 1.078E-09 8.604E-10 W 2.912E-08 1.229E-08 4.144E-09 1.869E-09 1.0811-09 8. 576E-10 3 .619E-08 1.527E-08 5.019E-09 1.940E-09 1. 0881-09 8.569E-10 WNW 3.702E-08 1.563E-08 4.880E-09 1. 9141-09 1.092E-09 8.605E-10 3 .440E-08 1.450E-08 4.799E-09 1.929E-09 1. 096E-09 8.631E-10 Rev. No. 9 0-41 of ODCM Rev.No.9Page

TABLE C-24 SECTOR AVERAGE DEPOSITION VALUES FOR UNMONITORED GROUND LEVEL RELEASES DETERMINED FROM GRAZING METEOROLOGICAL DATA (1985-1992)

(FOR USE WITH LONG TERM RELEASES)

(DIQ) Sector Average Deposition (/I Ir)

SEGMENT BOUNDARIES IN MILES Direction 0'.5 0.75 1.0 1.5 2.5 3.5 N 2.2651-08 1.167E-08 7.177E-09 3 .585N-09 1.474E-09 8.1321-10 1NNE 1.028E-08 5.2951-09 3 .258E-09 1.627E-09 6. 691E-10 3.6911-10 8.034E-09 4.134E-09 2.542E-09 1. 269E-09 5.213E-10 2.874E-10 ENE 2.078E-08 1.079E-08 6 .675E-09 3.3611-09 1.3 97E-09 7.7621-10 E 1.924E-08 1.002E-08 6.213E-09 3 .138E-09 1.309E-09 7.2931-10 ESE 1.159E-08 6.054E-09 3.762E-09 1.906E-09 7.979E-10 4.4 56E-10 SE 7.983E-09 4.184E-09 2.6051-09 1.324E-09 5.5631-10 3.114E-10 SSE 5.1241-09 2.690E-09 1.677E-09 8.5341-10 3.5931-10 2.0141-10 S 7.383E-09 3.8801-09 2.421E-09 1.2331-ý09 5.1981-10 2.9161-10 S SW 6 .769E-09, 3.5251-09 2.186E-09 1.104E-09 4.6021-10 2 .5631-10 SW 8.471R-09 4. 384E-09 2.7061-09 1.3 581-09 5.6191-10 3.1131-10 WSW 5.062E-09 2.608E-09 1. 6051-09 8.0191-10 3.2981-10 1.8201-10 W 5.392E-09 2.777E-09 1.708E-09 8.5291-10 3.506E-10 1.9331-10 1.123E-08 5.780E-09 3.5551-09 1.774E-09 7.2891-10 4.019E-10 N~W 1.792E-08 9 .223E-09 5 .671E-09 2.8301-09 1.1621-09 6.4081-10 NNW 1.976E-08 1. 018E-08 6.260E-09 3.126E-09 1.285E-09 7.0911-10 4.5 7.5 15.0 25.0 35.0 45.0 N 5.188E-10 2.099E-10 6.626E-11 2. 672E-11 1.42 9E-11 8.8201-12 2 .355E-10 9.527E-11 3.006E-11 1. 212E-11 6.4761-12 3.9951-12 NNE

1. 833E-10 7.418E-11 2. 341E-11 9.442E-12 5.0481-12 3 .1161-12 ENE 4.965E-10 2 .0101-10 6.352E-11 2.5651-11 1.3741-11 8 .4931-12 4.6693-10 1.890B-10 5.976E-11 2.4 151-11 1.294R-11 8.006E-12 2.855E-10 1.156E-10 3 .653H-11 1.476E-11 7.9051-12 4.8881-12 ESE 1.997E-10 8.083E-11 2.5531-11 1. 031E-11 5.516E-12 3.4081-12 SSE 1.2 92B-10 5.225E-11 1.648E-11 6.6431-12 3 .550E-12 2.189E-12 S 1.871E-10 7.570E-11 2 .390E-11 9. 637E-12 5.1531-12 3.-1811-12 SSW 1.6411-10 6.6371-11 2 .0C94E-11 8.4421-12 4. 5121-12 2.7831-12 SW 1.9881-10 8.0421-11 2 .536E-11 1. 0211-11 5.4531-12 3 .361E-12 WSW 1.161E-10 4. 6911-11 1.47 6E-11 5.9301-12 3.1581-12 1.942E-12 W 1.233E-10 4. 981E-11 1.567E-11 6 .292E-12 3.349E-12 2 .058E-12 WNW 2.562E-10 1. 03 6E-10 3 .262E-11 1.3 11E-11 6. 9901-12 4.-301E-12 NW 4.086E-10 1. 652E-10 5.209E-11 2.0971-11 1.1191-11 6 .8941-12 4.523E-10 1.830R-10 5.771E-11 2.3251-11 1.24 2E-11 7. 660E-12 Rev. No. 9 0-42 of ODOM Rev. o. 9Page

APPENDIX D LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS Rev. No. -9 Rev. o. 9Page D-1 of ODOM

APPENDIX D LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS TABLE TITLE PAGE D-1 Calculation of Total Cl/yr Releases for Liquids D-5 D-2 Organ Doses For Liquid Releases D-6 0-3 Dose Contribution to the Adult's Whole Body From the D-8 Freshwater Fish Pathway D-4 Dose Contribution to the Teenager's Liver from the D-9 Freshwater Fish Pathway D-5 Dose Contribution to the Adult's Whole Body from the 0-1 0 Potable Water Pathway 0-6 Dose Contribution to the Teenager's Liver from the D-1 1 Potable Water Pathway 0-7 Dose Contribution to the Adult's Whole Body and to D-12 the Teenager's Liver from the Lake Shoreline Deposits Pathway D-8 Dose Contribution to the Adult's Whole Body and to D-1 3 the Teenager's Liver from the Swimming and Boating Pathways Rev. No. 9 Rev. o. D-2 of 00CM

~Page

LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS The radioactive liquid effluents for the years 1980 through 1987 (from the JAFNPP Semi-Annual Effluent release reports) were evaluated to determine the critical pathways, organs, age groups, and nuclides which contributed to environmental doses. The liquid release nuclide distribution used in this analysis is shown in Table D-1. This analysis Was performed to develop a limited dose analysis for determination of liquid effluent environmental doses.

Limiting the dose calculation to a few selected nuclides that contribute the majority of the dose, along with the application of an appropriate conservatism factor to compensate for variations in isotopic mixtures, provides a simplified method of determining compliance with the dose limits of Technical Specification 2.3.

Tables D-2 through D-8 show the results of this evaluation. Table D-2 presents the dose for 8 organs and 4 age groups from all available pathways. The adult's whole body and teenager's age groups (adult, teenager, child, and infant) and all organs (bone, liver, kidney, thyroid, lung, skin, and GI-LLI). The dominant pathway contribution to these doses is freshwater fish ingestion. Table D-3 presents the percent of the adult's whole body dose contribution by the major radionuclides through the dominant pathway, ingestion of freshwater fish. Table D-4 presents the same data for the teenager's liver dose. The data in Tables D-3 and D-4 show that the fish pathway contributes at least 92% to the adult's whole body dose and at least 80.9%

to the teenager's liver dose from all pathways considered. The data in the tables also show that du'ring 1980-1987 the radionuclides Cs-134, Cs-137, Zn-65, Co-60, and Mn-54 contributed over 91 % of the total dose to the whole body and over 80% of the total liver dose via the freshwater fish ingestion pathway.

The data in Tables D-5 and D-6 show that the potable water pathway contributed no more than 1% to the adult's whole body dose and no more than 0.5% to the teenager's liver dose. This pathway is necessary to demonstrate compliance with 1IOCFR50 as specified in Sections 4.2 and 4.3.1 of NUREG-01 33. As mentioned in Appendix A, Table A-4.3, this pathway is considered for all required analysis.

Table D-7 shows that 17.9% of the teenager's dose to the liver in 1984 was from the lake shoreline deposits pathway. The lake shoreline pathway contributed 5.7% of the adult's whole body dose in 1984. This pathway contributed 9.3% of the teenager's liver dose in 1986 and 2.8% of the adult's whole body dose in 1986. The lake shoreline deposits pathway is second to the freshwater fish pathway when the concentrations of Cs-I 34, Cs-I 37, Zn-65, Co-60, and Mn-54 are low as in 1984 and 1986.

Rev. No. 9 0-3 of ODOM Rev. o. 9Page

LIMITED ANALYSIS APPROACH DOSE ASSESSMENT FOR LIQUID RADIOACTIVE EFFLUENTS (Continued)

Table D-8 shows that the swimming and boating pathways, combined, contribute no more than 1.5% to the adult's whole body dose and no more than 0.8% to the teenager's liver dose from 1980 to 1987. The swimming and boating pathways are not used in the ODOM since their dose contributions are very small.

A conservatism factor of 0.8 is introduced into the equation (i.e., calculated doses using this approach should be divided by 0.8) to compensate for any unexpected variability in nuclide and pathway dose contribution. Therefore, the dose commitment to the adult's whole body and teenager's liver due to radioactive material in liquid effluents can be reasonably estimated by limiting the dose calculation to these 5 nuclides and the fish and potable water pathways, which cumulatively contribute the bulk of the total dose calculated by accounting for all nuclides and all pathways.

Rev. No. -9 Rev. o. 9Page D-4 of ODOM

1ABL,. D-1 CALCULATION OF TOTAL Ci/yr RELEASES FOR LIQUIDS (Based on Semi-Annual Effluent Release Reports for the Years 1980 through 1987)

I.:sOTOPE 1980 198 1982_____________1983 19M4 1985. i3i: 1986 j 98 jA/EFy\

H-3 2.81 E 00 4.112E 00 6.55E-01 2.72E 00 4.77E 00 4.20E 00 5.OOE 00 2.48E 00 3.34E 00 Ag-lI Om 1.12 E-04 2.212E-04 1.15E-05 9.49E-05 2.66E-05 5.34E-06 --- 5.90E-05 Cu-64 3.42E-02 -- -- -- -- -- 4.28E-03 Cs-1 34 7.30E-02 8.00E-02 5.47E-02 5.11 E-02 2.19E-04 8.71 E-03 6.68E-05 1.47E-03, 3.37E-02 Cs-137 1,06E-01 1.26E-01 6.96E-02 7.77E-02 8.80E-04 1.27E-02 1.012E-03 6.65E-03 5.012E-02 1-131 2.77E-02 4.50E-02 9.05E-04 1.95E-03 4.73E-05 2.32E-05 -- -- 9.45E-03 Ba/La-140 4.61 E-04 1.12E-03 1.82E-03 4.49E-04 5.86E-04 5.55E-04 2.61 E-06 2.58E-05 6.27E-04 Co-58 1 .07E-01 2.08E-01 2.94E-02 2.49E-02 3.23E-03 6.82E-03 -- 2.90E-03 4.78E-02 Co-60 8.03E-01 1.40E 00 3.66E-01 4.86E-01 3.99E 02 9.96E-02 I1.56E-02 4.32E 02 4.07E-01 Fe-59 1.31 E-02 1.10E-02 3.46E-03 4.40E-03 3.21 E-04 .2.79E-04 -- 3.49E-04 4.112E-03 Zn-65 3.11 E-02 4.57E-02 9.812E-03 5.27E-03 1.29E-03 6.14E-03 7.20E-04 4.67E-04 1.26E-02 Mn-54 2.10E-01 3.44E-01 .6.76E-02 1.04E-01 1.02E-02 2.86E-02 7.30E-04 1.60E-02 9.76E-02 Cr-51 4.63E-02 4.79E-02 2.77E-03 2.83E-03 8.30E-04 1.51 E-04 2.95E-05 -- 1.26E-02 Sb-124 4.87E-03 3.83E-03 5.37E-04 7.62E-04 1.87E-05 - -- 1.27E-04 1.27E-03 Mo-99 1.41 E-02 6.44E-04 I1.22E-04 7.612E-04 -- 2.32E-04 2.07E-06 -- 1.98E-03 Tc-99m 1.81 E-04 1.67E-03 3.17E-05 2.40E-04 1.38E-04 1.94E-05 3.10E-07 -- 2.85E-04 Ce-141 1.72E-05 6.99E-05 3.83E-05 1.03E-04 1.23E-04 1.32E-04 1.53E-06 -- 6.06E-05 Zr/Nb-95 2.14E-03 2.54E-04 5.50E-05 1.45E-04 1.74E-04 7.02E-05 1.20E-06* -- 3.55E-04 Ce-1 44 6.33E-05 6.58E-04 2.46E-05 5.68E-05 1.88E-05 6.87E-04 1.27E-04 -- 2.04E-04 1-133 1.22E-03 5.35E-03 1.03E-03 2.16E-03 1.08E-04 9.72E-06 1.67E-06 -- 1.23E-03 Na-24 1.79E-02 3.77E-02 1.70E-03 2.01 E-03 2.02E-04 2.22E-05 -- 2.78E-04 7.48E-03 As-76 2.46E-04 2.08E-04 8.67E-05 3.40E-06 2.89E-04 2.24E-05 1---I.07E-04 Np-239 2.24E-03 4.29E-02 1.88E-02 3.55E-03 2.02E-03 2.45E-04 ---- 8.72E-03 Xe-1 33 9.65E-03 3.98E-02 1.05E-02 6.81 E-04 2.82E-03 5.29E-03 1.82E-04 4.51IE-05 8.62E-03 Xe-1 35 3.28E-03 5.85E-02 1.01E-02 7.03E-04 3.31 E-02 9.86E-03 6.67E-04 -- 1.45E-02 Kr-85m~ 2.88E-04 7.28E-06 7.14E-05 3.52E-05 5.40E-05 --- -5.70E-05 1-135 4.97E-05 2.47E-03 1.45E-04 6.20E-04 ---- -4.11 E-04 Sr-89 --- 5.76E-04 --- -- -7.20E-05 Sr-90 3.47E-05 1.27E-04 1.88E-04 1.38E-04 - -- -6.10E-05 Fe-55 ---- -2.19E-03 -- 6.78E-03 1.12E-03 Co-57 --- -- -1.29E-05 -- 1.61 E-06 Zr-97 ---- ---- 2.26E-04 -- 2.83E-05 Nb-95m ---- ---- 4.32E-06 -- 5.40E-07 W-187 -- -- I--3.42E-05 4.28E-06 Rev. No. 9 Page D-5 of ODCM

TABLE D-2 ORGAN DOSES FOR LIQUID RELEASES (ALL PATHWAYS)

ADULT I SKIN 1 BONE I LIVER W.BODY ITHYROID KIDNEY I LUNG I GI-LLI YEAR j (mrem) (mrem) (mrem) (mrem) (mrem) (mrem) j (mrem) j (mrem) 1980 4.94E-03 7.82E-02 1.31 E-0 1 5.58E-02 6.52E-03 4.67E-02 2.OOE-02 1.50E-02 1981 8.05E-03 8.97E-02 1.48E-01 6.43E-02 1.05E-02 5.45E-02 2.44E-02 1.97E-02 1982 2.28E-03 5.17E-02 8.75E-02 3.71 E-02 2.10E-03 3.03E-02 1.27E-02 5.67E-03 1983 2.92E-03 5.37E-02 8.86E-02 3.74E-02 2.74E-03 3.10OE-02 1.34E-02 6.94E-03 1984 2.01 E-04 6.08E-04 9.56E-04 4.94E-04 1.86E-04 4.64E-04 2.63E-04 6.44E-04 1985 6.46E-04 9.98E-03 1.68E-02 7.18E-03 5.79E-04 6.07E-03 2.55E-03 1.82E-03 1986 8.21 E-05 5.31 E-04 7.48E-04 3.29E-04 7.58E-05 3.17E-04 1.56E-04 1.71 E-04 1987 7.35E-04 1.05E-02 1.54E-02 6.24E-03 6.57E-04 5.62E-03 2.54E-03 1.83E-03 TEENA.E YEAR J I (mrem)

SKIN Ij BONE (mrem)

LIVER (mrem)

W.BODY (mrem)

ITHYROID (mrem)

Ij KIDNEY (mrem)

I LUNG (mrem)

I GI-LLI (mrem) 1980 4.94E-03 7.82E-02 1.31 E-01 5.58E-02 6.52E-03 4.67E-02 2.OOE-02 1.50E-02 1981 8.05E-03 8.97E-02 1.48E-01 6.43E-02 1.05E-02 5.45E-02 2.44E-02 1.97E-02 1982 2.28E-03 5.17E-02 8.75E-02 3.71 E-02 2.10E-03 3.03E-02 1.27E-02 5.67E-03 1983 2.92E-03 5.37E-02 8.86E-02 3.74E-02 2.74E-03 3.1IOE-02 1.34E-02 6.94E-03 1984 2.01 E-04 6.08E-04 9.56E-04 4.94E-04 1.86E-04 4.64E-04 2.63E-04 6.44E-04 1985 6.46E-04 9.98E-03 1.68E-02 7.18E-03 5.79E-04 6.07E-03 2.55E-03 1.82E-03 1986 8.21 E-05 5.31 E-04 7.48E-04 3.29E 7.58E-05 3.17E-04 1.56E-04 1.71 E-04 1987 7.35E-04 1.05E-02 1.54E-02 6.24E-03 6.57E-04 5.62E-03 2.54E-03 1 .83E-03 Rev. No. 9 Page D-6 of 00CM

TABLE D-2 (Continued)

ORGAN DOSES FOR LIQUID RELEASES (ALL PATHWAYS)

CHILD YEAR j I (mrem)

SKIN) BONE (mrem)

LIVER (mrem)

TW. BODY (mrem)

THYROID (mrem)

KIDNEYLUGI-I (mrem) (mrem) (mrem) 1980 1.03E-03 9.27E-02 1.12E-01 2.22E-02 3.64E-03 3.68E-02 1.34E-02 4.86E-03 1981 1.68E-03 1.04E-01 1.25E-01 2.56E-02 4.7911-03 4.16E-02 1.53E-02 5.95E-03 1982 4.77E-04 6.18E-02 7.48E-02 1.43E-02 5.58E-04 2.43E-02 8.87E-03 1.74E-03 1983 6.09E-04 6.39E-02 7.57E-02 1.43E-02 7.70E-04 2.46E-02 9.13E-03 2.12E-03 1984 4.20E-05 5.96E-04 7.16E-04 2.13E-04 4.76E-05 2.78E-04 1.09E-04 2.01 E-04 1985 1.35E-04 1.17E-02 1.42E-02 2.89E-03 1.41 E-04 4.75E-03 1.69E-03 5.58E-04 1986 1.72E-05 5.89E-04 6.16E-04 1.38E-04 1.81 E-05 2.24E-04 8.23E-05 4.99E-05 1987 1.53E-04 1.24E-02 1.33E-02. 2.42E-03 1.60E-04 4.40E-03 1 .66E-03 5.55E-04 INFANT IJ IW. BODY ITHYROID IKIDNEY I LUNG YEAR JI (mrem)

SKIN BONE (mrem)

LIVER (mrem) j (mrem) (mrem) (mrem) I(mrem')

GI-LLI (mrem) 1980 0 4.12E-04 5.60E-04 2.58E-04 1.16E-03 2.58E-04 1.93E-04 2.34E-04 1981 0 5.45E-04 7.24E-04 4.08E-04 1.84E-03 3.69E-04 2.95E-04 3.83E-04 1982 0 2.52E-04 3.26E-04 1 .20E-04 1.01 E-04 1.32E-04 9.22E-05 1.01 E-04 1983 0 2.67E-04 3.54E-04 1.47E-04 1.59E-04 1.52E-04 1.12E-04 1.27E-04 1984 0 7.73E-06 1.38E-05 1.31 E-05 1.16E-05 1.06E-05 1.01 E-05 1.34E-05 1985 0 5.14E-05 7.43E-05 3.61 E-05 2.38E-05 3.57E-05 2.78E-05 3.38E-05 1986 0 3.78E-06 8.99E-06 7.81 E-06 6.50E-06 7.07E-06 6.70E-06 7.83E-06 1987 0 5.64E-05 7.85E-05 4.16E-05 2.78E-05 4.OOE-05 3.28E-05 3.90E-05 Rev. No. 9 D-7 of ODOM Rev. o. 9Page

TABLE D-3 DOSE CONTRIBUTION TO THE ADULT'S WHOLE BODY FROM THE FRESHWATER FISH PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984 1985 1986 1987 Cs-134 52.7 50.3 56.5 52.2 .25.2 52.1 9.2 26.8 Cs-i 37 45.2 46.8 42.4 46.8 59.7 44.9 82.5 71.5 Zn-65 1.3 1.7 0.6 0.3 8.5 2.1 .5.7 0.5 Co-60 0.6 0.9 0.4 0.5 4.5 0.6 2.1 0.8 Mn-54 0.2 0.3 0.1 0.2 1.7 0.2 0.1 0.4 The percentage (%) 100 100 100 100 99.6 99.9 99.6 100 of the whole body dose from five nuclides in the fish pathway The percentage (%) 98.8 98.3 99.2 98.9 92.0 98.8 95.6 98.4 of the total dose to the adult's whole body from the fish pathway The percentage(% 98.8 98.3 99.2 98.9 91.6 98.7 95.2 98.4 (

of the total dose to the adult's whole body from the five nuclides in the fish pathway K..

Rev. No. 9 Q-.8 of ODOM Rev. o. 9Page

TABLE D-4 DOSE CONTRIBUTION TO THE TEENAGER'S LIVER FROM THE FRESHWATER FISH PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984 1985 1986 1987 Cs-134 46.2 43.8 50.2 45.9 20.0 45.5 7.3 22.0 Cs-137 50.8 52.2 48.4 52.9 60.9 50.2 83.5 75.5 Zn-65 2.0 2.5 0.9 0.5 11.9 3.3 8.0 0.7 Co-60 0.2 0.3 0.1 0.2 1.3 0.2 0.6 0.2 Mn-54 0.8 1.1 0.4 0.6 5.6 0.9 0.5 1.4 The percentage(% 100 99.9 100 100 99.7 100 99.9 99.8 of the liver dose from five nuclides in the fish path-way The percentage(% 96.5 95.0 97.6 97.0 80.9 96.4 89.9 95.6 of the total dose to the teen's liver from the fish pathway

-he percentage(% 96.5 94.9 97.6 97.0 80.7 96.4 89.8 95.4 ijf the total dose

.to the teen's liver orn the five nuclides in the fish pathway Rev. No. 9 Rev. o. 9Page Q-9. of ODOM

TABLE D-5 DOSE CONTRIBUTION TO THE ADULT'S WHOLE BODY FROM THE POTABLE WATER PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984* 1985 1986 1987 Cs-134 41.5 35.7 47.5 41.9 3.29 35.7 1.18 15.5 Cs-i 37 35.6 33.2 35.7 37.6 7.82 30.7 10.5 41.5 Zn-66 1.01 1.2 0.5 0.25 1.11 1.44 0.73 0.28 Co-60 17.8 24.4 12.4 15.5 23.4 15.9 10.8 17.8 Mn-54 0.86 1.1 0.4 0.61 1.10 0.84 0.09 1.22 The percentage (%) 96.8 95.6 96.5 95.9 36.7 84.6 23.3 76.3 of the whole body dose from the nuclides from the potable water pathway The percentage(% 0.16 0.18 0.15 0.15 0.89 0.18 0.94 0.21 the total dose to the adult's whole body from the potable water pathway The percentage (%) 0.15 0.17 0.14 0.14 0.33 0.15 0.22 0.16 of the total dose of the adult's whole body from the five nuclides in the potable water pathway

Tritium was the major contributor to the potable water pathway for 1984.

Rev. No. 9 D-10 of 00CM Rev. o. 9Page

TABLE D-6 DOSE CONTRIBUTION TO THE TEENAGER'S LIVER FROM THE POTABLE WATER PATHWAY (PERCENT)

ISOTOPE 1980 1981 1982 1983 1984* 1985 1986 1987 Cs-i 34 40.9 37.0 47.0 41.7 4.87 36.9 1.74 16.1 Cs-I 37 45.0 44.2 45.3 48.0 14.8 40.8 19.9 55.3 Zn-65 1.8 2.14 0.85 0.44 2.90 2.63 1.90 0.52 Co-60 6.43 9.25 4.49 5.66 12.7 6.03 5.8 6.77 Mn-54 3.5 4.76 1.73 2.54 6.77 3.62 0.57 5.24 The percentage() 97.6 97.4 99.4 98.3 42.0 90.0 29.9 83.9 of the liver dose from the nuclides from the potable water pathway The percentage (%) 0.12 0.13 0.12 0.12 0.38 0.14 0.44 0.15 of the total dose to the teen's liver from the potable water oathway Che percentage N% 0.11 0.12 0.11 0.11 0.16 0.13 0.13 0.12 ofthe total dose

.the teen's liver from the five nuclides in the potable water pathway Tritium was the major contributor to the potable water pathway for 1984 Rev. No. 9 Rev. o. 9Page 0-1 1 of 00CM

TABLE D-7 DOSE CONTRIBUTION TO THE ADULT'S WHOLE BODY AND TEENAGER'S

(

LIVER FROM THE LAKE SHORELINE DEPOSITS PATHWAY 1980 1981 1982 1983 1984 1985 1986 1987 The percentage(% 0.83 1.22 0.56 0.72 5.68 0.85 2.79 1.12 of the total dose to the adult's whole body from the lake shoreline deposits pathway Maximum percentage from 1980 to 1987 - 5.68%

Average percentage from 1980 to 1987 - 1.72%

The percentage (%) 3.22 4.62 2.22 2.80 17.91 3.27 9.33 4.04 of the total dose to the teenager's liver from the lake shoreline deposits pathway

(

K Maximum percentage from 1980 to 1987 - 17.9%

K' Average percentage from 1980 to 1987 - 5.93%

Rev. No. 9 Rev. o. 9Page D-12 of ODCM

TABLE D-8 DOSE CONTRIBUTION TO THE ADULT'S WHOLE BODY AND TEENAGER'S LIVER FROM THE SWIMMING AND BOATING PATHWAYS 1980 1981 1982 1983 1984 1985 1986 1987 Percentage (%)of 0.21 0.31 0.13 0.17 1.39 0.20 0.62 0.27 the total dose to the Adult's whole body from the swimming and boating pathways Maximum percentage from 1980 to 1987 - 1.39%

Average percentage from 1980 to 1987 - 0.41%

Percentage (%) of 0.14 0.21 0.09 0.12 0.78 0.14 0.37 0.18 the total dose to the teenager's liver from the swimming and

-boating pathways

--Maximum percentage

)m 1980 to 1987 - 0.78%

Average percentage from 1980 to 1987 - 0.25%

Rev. No. 9 Rev. o. Q-1

~Page 3 of ODCM

APPENDIX E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS Rev. No. -9 E-1 of ODOM Rev. o. 9Page

APPENDIX E TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS TABLE TITLE PAGE E-1 Effective Dose Factors for Noble Gases - Whole Body Effective E-6 Dose (K~ff)

E-2 Effective Dose Factors for Noble Gases - Air Doses (K~ff) and (Neff) E-7 E-3 Effective Dose Factors for Noble Gases - Skin Effective Dose E-8 (L + 1.1 M)eff and (Leff)

E-4 Tables of Source Terms Used for Development of Effective Dose E-9 Transfer Factors (Elevated Release)

E-5 Tables of Source Terms Used for Development of Effective Dose E-1O0 Transfer Factors (Vent Release)

E-6 Radionuclide Distribution of Vent and Elevated Releases E-1 1 Rev. No. -9 Rev. o. 9Page E-2 of ODOM

TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS The evaluation of doses due to releases of radioactive material to the atmosphere can be simplified by the use of effective dose transfer factors, instead of using dose factors which are radionuclide specific. These effective factors, which are based on the typical radionuclide distribution in the releases, can be applied to the total radioactivity released to approximate the dose in the environment, i.e., instead of having to sum the isotopic distribution multiplied by the isotope specific dose factor, only a single multiplication (Kff, Leff, Meff or Neff) times the total quantity of radioactive material released, would be needed. This approach provides a reasonable estimate of the actual dose while eliminating the need for a detailed calculating technique.

Determination of Effective Dose Factors The effective dose transfer factors are based on past operating data. The radioactive effluent distribution for the past years can be used to derive single effective factors by the following equations.

E-1 n

Keff :" EK -f Where:

Keff =the effective whole body dose factor due to gamma emissions from all noble gases released.

=the whole body dose factor due to gamma emissions from each noble gas radionuclide Tireleased.

f= the fractional abundance of noble gas radionuclide Tiis of the total noble gas rad ion ucl ides.

A Kef is calculated for elevated releases and also for vent releases.

n Leff= LLI .f 1 Where:

Leff =the effective skin dose factor due to beta emissions from all noble gases released.

Rev. No. -9 Rev. o. 9Page E-3 of.ODOM

TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)

=, the skin dose factor due to the beta emissions from each noble gas radionuclide Tireleased.

For ease of calculation, Lff is calculated for elevated releases and (L + 1.1Miff is calculated for vent releases.

E-2 n

(L + 1.1 M)eff ~E (Li + 1.1 M1) .f.

ki1 Where:

(L + 1.1 M)eff = the effective skin dose factor due to beta and gamma emissions from all noble gases released from the vents.

(Li + 1.-1 M) = the skin dose factor due to beta and gamma emissions from each noble gas radionuclide Tireleased from the vents.

E-3 n

Meff = EL M.Ifi HI Where:

Meff = the effective air dose factor due to gamma emissions from all noble gases released.

Mi = the air dose factor due to gamma emissions from each noble gas radionuclideT' released.

A M~ff is calculated for elevated releases and also for vent releases.

Rev. No. 9 Rev. o. 9Page E-4 of 00CM

TECHNICAL BASES FOR EFFECTIVE DOSE FACTORS (Continued)

E-4 n

Neff '= ENi If 1 Where:

Neff = the effective air dose factor due to beta emissions from all noble gases released.

Ni = the air dose factor due to beta emissions from each noble gas radionuclide 'i' released.

A NOf is calculated for elevated releases and also for vent releases.

To determine the appropriate effective factors to be used and to evaluate the degree of variability, the atmospheric radioactive effluents for the years 1985 through 1991 have been evaluated. Tables E-1, E-2, and E-3 present the results of this evaluation.

To compensate for any unusual variability in the radionuclide distribution, 3 sigma was added to the average K~ff, Meff, Neff, Leff, and (L + 1.1 M)eff values. This added conservatism(

provides additional assurance that the evolution of doses by the use of a single effective factor will normally overestimate actual doses in the environment, and any underestimation will be of insignificant magnitude.

Rev. No. -9 Rev. o. 9Page E-5 of ODOM

TABLE E-1 (continued)

EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

WHOLE BODY EFFECTIVE DOSE

[K~ff]

ELEVATED STACK RELEASE

[mrem/sec per jiCilm 3]

YEAR Whole Body Effective Dose Factor Keff 1999 2.34E-04 2000 2.29E-04 2001 2.41 E-04 2002 2.11 E-04 6q 0~

2003 2.47E-04 mean +/- a 2.32E-04 +/- 1.38E-05 mean + 3a 2.73E-04 Rev. No. -9 Rev. o. 9Page E-7 of ODCM

TABLE E-1 EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

WHOLE BODY EFFECTIVE DOSE

[K6 ff]

VENT RELEASE

[mrem/sec per pCi/rn3 ]

YEAR Whole Body Effective Dose Factor K.,f 1985 4.32E-05 1986 1.42E-04 1987 4.34E-05 1988 1.08E-04 1989 1.64E-04 1990 8.80E-05 1991 6.03E-05 mean +/- a 9.27E-05 +/-4.78 E-05 mean + 3a 2.36E-04 Note: The years 1985 through 1991 were selected as representative of historical noble gas releases from the vents. Calculated Kff values based on the 1985 through 1991 data produce a more conservative result providing inclusion (bounding) of K,,f values that may be encountered if a fuel failure occurs. An evaluation of current vent release data (i.e. 1999 through 2003) resulted in non-conservative K~ff values.

Rev. No. -9 Rev. o. 9Page E-6 of 00CM

TABLE E-2 EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

AIR DOSE

[M~ff & Njff YEAR VENT RELEASE ELEVATED RELEASE

[mrad/sec per pCilrr?] [mradlsec per pCi/ni 3 ]

Gamma-Air Beta-Air Gamma-Air Beta-Air Effective Effective Effective Effective Dose Factor Dose Factor Dose Factor Dose Factor Meff Neff Meff Neff 1985 4.57E-05 6.78E-05 2.06E-04 I1.26E-04 1986 1 .49E-04 1.14E-04 2.28E-04 1.30E-04 1987 4.66E-05 5.21 E-05 1.13 E-04 6.58E-05 1988 1.13E-04 7.25E-05 1.17E-04, 7.49E-05 1989 1.71 E-04 7.30E-05 1.81 E-04 I1.52E-04 1990 9.29E-05 8.87E-05 1 .25E-04 1.39E-04 1991 6.41 E-05 6.30E-05 1.31 E-04 9.02E-05 mean +/-0a 9.75E-05 7.59E-05 1.57E-04 1.11 E-04

+/-4.95E-05 +/-2.01IE-05 +/-4.70E-05 +/-3.37E-05

,mean + 3a 2.46E -04 1.36E-04 2.98E-04 2.12E-04 Rev. No. -9 E-8 of ODOM Rev. o. 9Page

TABLE E-3 EFFECTIVE DOSE FACTORS FOR NOBLE GASES -

SKIN EFFECTIVE DOSE YEAR VENT RELEASE ELEVATED RELEASE

[mrem/sec per pCilrnf] [mrem/sec per pCi/er]

Total Skin Effective Skin Effective Dose Factor Dose Factor (L 4- 1.1M)8 ff 1.8ff 1985 9.87E-05 1 .09E-04 1986 2.37E-04 1.13E-04 1987 8.44E-05 4.57E-05 1988. 1.77E-04 5.51 E-05 1989 2.43E-04 1.34E-04 1990 1.58E-04 I1.20E-04 1991 1.04E-04 7.08E-05 mean +/- a 1.57E-04 9.25E-05

+/-6.54E-05 +3.47E-05 mean +3a 3.54E-04 1.97E-04 K.

Rev. No. -9 E-9 of ODOM Rev. o. 9Page

TABLE E-4 TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE DOSE TRANSFER FACTORS (Based on Semi-Annual Effluent Release Reports for the years 1985 through 1991)

ELEVATED RELEASE (Curies)

RADIONUCLIDE 1985 1986 1987 1988 Ar-41 4.34E+01 3.65E+01 6.90E+01 1.34E+01 Kr-83m Kr-85m 3.47E+02 7.48E+01 6.66E+02 3.85E+02 Kr-85 Kr-87 1.57E-'03 2.15E+02 8.39E+0 1 1.59E+02 Kr-88 1.13E+03 3.32E+02 4.60E+02 5.18E+02 Kr-89 Kr-90 Xe-I 31 m 8.51 E+02 7.79E+00 2.30E+00 Xe-i 33m 9.92E+00 2.73E-01I 5.88E+00 Xe-I 33 2.77E+02 1.01 E+02 1.63E+03 1.13E+03 Xe-I 35m 1.76E+03 2.03E+02 9.13E+01 3.69E+01 Xe-135 2.22E+03 3.34E+02 2.35E+02 I .OOE+03 Xe-I 37 3.86E+01 Xe-138 5.59E+03 7.45E+02 2.26E+02 I1.53E+01 TOTAL 1.38E+04 2.1IOE+03 3.47E+03 3.27E+03 RADIONUCLIDE 1989 1990 1991 Ar-41 1.73E+01 3.68E+01 I1.57E+01 Kr-83m Kr-85m I1.28E+01 7.78E+01 1.94E+02 Kr-85 Kr-87 9.26E+00 3.85E+01 7.30E+0.1 Kr-88 Kr-89 2.20E+01 1.17E+02 2.99E+02 Kr-90 Xe-I 31 m 7.41 E+00 1.88E+01 1.16E+02 Xe-I 33m 3.38E+00 5.23E+00 Xe-133 7.17E+00 2.97E+02 4. 74E+02 Xe-I 35m 6.09E+00 2.99E+01 2.38E+01 Xe-I 35 2.49E+01 1.40E+'02 4.OOE+02 Xe-137 2.40E+01 1.87E+02 7.22E+01 Xe-i 38 2 .04E+0 1 1.01 E+02 7.55E+01 TOTAL 1.51 E+02 1.05E+03 1.75E+03 Rev. No. -9 Rev. o. 9Page E-10 of 00CM

TABLE E-5 TABLES OF SOURCE TERMS USED FOR DEVELOPMENT OF EFFECTIVE DOSE TRANSFER FACTORS (Based on Semi-Annual Effluent Release Reports for the years 1985 through 1991)

VENT RELEASE (Curies)

RADIONUCLIDE 1985 1986 1987 1988 Ar-41 Kr-83m Kr-85m 3.35E+01 6.42E+01 3.14E+01 Kr-85 4.36E+02 Kr-87 8.95E+00 4.61 E+01 1.38E+01 7.78E+00 Kr-88 I1.45E+01 7.25E+01 4.81 E+01 4.1 3E+01 Kr-89 Kr-90 Xe-I 31 m 1.44E+02 1.24E+02 1.19E+0-1 I1.26E+01 Xe-I 33m 2.81 E+01 4.65E+01 4.37 E+02 5.33E+01 Xe-133 6.29E+01 4.91 E+01 5.06E+02 2.75E+02 Xe-I 35m 9.66E+00 I1.33E+01 3.39E+01 1.48E+01 Xe-I 35 1.68E+02 3.54E+01I 1.31 E+02 5.14E+01 Xe-I 37 3.10OE+01 Xe-I 38 7.27E+01 I1.06E+02 3.18E+01 I1.35E+02 TOTAL 9.44E+02 5.57E+02 1.28E+03 6.23E+02 RADIONUCLIDE 1989 1990 1991 Ar-41 3.35E-01 9.02E-01 4.70E-01 Kr-83m Kr-85m 7.08E+01 I1.77E+01 I1.74E+01 Kr-85 Kr-87 3.68E+00 1.13E+01 3.72E+00 Kr-88 1.01E+02 I1.36E+01 1.63E+01 Kr-89 Kr-90 Xe-1 31 m 5.57E+01 I1.67E+01 1.IIE+02 Xe-i 33m 5.05E+01 8.95E+01 I1.70E+01 Xe-1 33 4.03E+01 5.54E+01 7.19E+01 Xe-I 35m 1.53E+01 8.81 E+00 1.35E+01 Xe-i 35 2.62E+01 3.27E+01 2.39E+01 Xe-1 37 1.11IE+01 7.85E+00 Xe-i 38 4.42E+01 4.57E+01 1.74E+01 TOTAL 4.08E+02 3.04E+02 3.01 E+02 Rev. No. 9 E-1 1 of O0CM Rev. o. 9Page

TABLE E-6 RADIONUCLIDE DISTRIBUTION OF VENT AND ELEVATED RELEASES (Based on Semi-Annual Effluent Release Reports for the years 1985 through 1991)

Fraction of Total Vent Release RADIONUCLIDE 1985. 1986 1987 1988 1989 1990 1991 Ar-41 -- -- -- -- 8.21 E-04 2.97E-03 1.57E-03 Kr-83m -- - -- -- --

Kr-85m -- 6.01 E-02 5.03E-02 5.04E-02 1.73E-01 5.83E-02 5.80E-02 Kr-85 4.62 E-01 -- - -- --

Kr-87 9.48E-03 8.27E-02 1.08E-02 1.25E-02 9.02E-03 3.73E-02 1.24E-02 Kr-88 1 .53E-02 1.30E-01 3.76E-02 6.63E-02 2.48E-01 4.48E-02 5.43E-02 Kr-89 - -- -- --

Kr-90 ----- --- -

Xe-131m 1.52E-01 2.23E-01 9.32E-03 2.02E-02 1.36E-01 5.51 E-02 3.70E-01 Xe-i 33m 2.97E-02 8.34E-02 3.42E-01 8.56E-02 1.24E-01 2.95E-01 5.67E-02 Xe-1 33 6.66E-02 8.80E-02 3.96E-01 4.42E-01 9.87E-02 1.82E-01 2.39E-01 Xe-1 35m 1,02E-02 2.39E-02 2.65E-02 2.37E-02 3.74E-02 2.90E-02 4.49E-02 Xe-i 35 1 .78E-01 6.35E-02 1.02E-01 8.26E-02 6.42E-02 1.08E-01 7.97E-02 Xe-i 37 -- 5.56E-02 --- - 3.65E-02 2.61 E-02 Xe-1 38 7.70E-02 1.89E-01 2.49E-02 2.17E-01 1.08E-01 1.51 E-01 5.78E-02 FRACTION OF TOTAL ELEVATED RELEASE RADIONUCLIDE 1985 1986 1987 1988 1989 1990 1991 Ar-41 3.15E-03 1.74E-02 1.99E-02 4.09E-03 l1.4E-01 3.52E-02 8.97E-03 Kr-83m - -- -- --

Kr-85m 2.52E-02 3.56E-02 1.92E-01 1.18E-01 8.45E-02 7.44E-02 1.11E-01 Kr-85 - -- -- --

Kr-87 1.14E-01 1.03E-01 2.42E-02 4.85E-02 6.12E-02 3.68E-02 4.17E-02 Kr-88 8.17E-02 1.58E-01 1.33E-01 1.58E-01 1.45E-01 1.12E-01 1.71E-01 Kr-89 -

Kr-90 -- ---------

Xe-1 31 m 6.18E-02 3.71 E-03 6.64E-04 -- 4.90E-02 1.79E-02 6.62E-02 Xe-133m -- 4.73E-03 7,88E-05 1.80E-03 -- 3.23E-03 2.99E-03 Xe-1 33 2.01 E-02 4.83E-02 4.71 E-0 1 3.47E-01 4.74E-02 2,84E-01 2.71 E-01 Xe-135m 1.27E-01 9.68E-02 2.63E-02 1.13E-02 4.03E-02 2.86E-02 1.36E-02 Xe-135 1.61 E-01 1.59E-01 6.78E-02 3.06E-01 1.65E-01 1.33E-01 2.28E-01 Xe-1 37 -- 1.84E-02 -- -- 1.59E-01 1.79E-01 4.13E-02 Xe-1 38 4.06E-01 3.55E-01 6.51 E-02 4.67E-03 1.35E-01 9.62E-02 4.32E-02 Rev. No. -9 Rev. o. 9Page E-1 2 of ODOM

APPENDIX F EFFLUENT MONITOR SAMPLING LOCATIONS AND DESCRIPTIONS Rev. No. -9 F-i of ODCM Rev. o. 9Page

APPENDIX F EFFLUENT MONITOR SAMPLING LOCATIONS AND DESCRIPTIONS TABLE TITLE PAGE F-I Atmospheric Gaseous Release Point Data F-3 F-2 Effluent Monitoring System Data F-4 FIGURE F-I Gaseous Release Points Building Elevations F-6 F-2 Gaseous Release Points Plant Yard Layout -F-7 F-3 Liquid Release Point F-8 F-4 Gaseous Effluent Release Paths F-9 F-5 Liquid Effluent Release Paths F-I 0 F-6 Solid Radwaste Treatment System F-Il1 F-7 Standby Gas Treatment System F-1 2 Rev. No. -9 Rev. o. 9Page F-2 of ODOM

TABLE F-I JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

ATMOSPHERIC GASEOUS RELEASE POINT DATA RELEASEI POINT STACK REACTOR*

BUILDING I TURBINE BUILDING I RAD WASTE.......REFU.EL*

..BUILDING FLOOR Height Above 385 172 172 ill 172 Grade (feet)

Release Mode Elevated Roof Top Vent Roof Top Vent Roof Top Vent Roof Top Vent Effluent Turbine Gland Secondary Turbine Waste Disposal Refuel Floor Source Seal Condenser and Auxiliary Building Building Exhaust Gases Mechan- Building Exhaust Ventilation Ventilation ical Vacuum Exhaust Ventilation Pump Exhaust Ventilation Steam Jet Air Ejector Exhaust

The Refuel Floor and Reactor Building vent is a combined release point.

Rev. No. 9 Page F-3 of ODCM

TABLE F-2 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

EFFLUENT MONITORING SYSTEM DATA MONITOR SAMPLING DETECTION I j CONTROL

}ALARM SETPOINT REFERENCE CALIBRATION.

DESCRIPTION LOCATION j TYPE .RANGE FUNCTIONS USED SOURCE Main steam Located near the main 4-gamma 100-lO'mR/hr Closure of main Yes Victoreen Cs"3 line monitor steam lines downstream sensitive steam line drain gamma dose rate of the outboard ion chambers motor operated source MSIV's in the valves, mechanical steam tunnel vacuum pump line isolation valve, recirculation loop sample valves, and initiates a trip of the mechanical vacuum pump.

Off-gas Turbine 252' 2-gamma 10'-l1O'm R/hr Initiate closure Yes Gas sample radiation west sensitive of off-gas system counted on monitoring ion chambers isolation valves Ge(Li) system Off-gas pipe -Stack Scintillation 10-1-10' cps Indicate and record Yes Gas vent (Stack) detectors rate of release of marinelli monitor radioactive material counted on to the environment Ge(Li)

Process liquid Rad Waste - RW 272' Scintillation 10-1_1 06 Monitor for leaks Yes Representative radiation Service H20 detectors cps of closed systems. liquid sample monitors Monitor normal re- counted on Ge(Li)

Heater Bay 252' lease of radio-active material to the environment TABLE F-2 Rev. No. 9 Rev. o. 9Page F-4 of ODCM

(Continued)

EFFLUENT MONITORING SYSTEM DATA MONITOR SAMPLING DETECTION j CONRO SETPQO%4Tj_.CALIBRATION Plant stack & Turbine - MG Set GM Detectors I01-106 CPM Provide isolation Yes Gas marinelli vent noble 300' of potentially counted on Ge(Li) gas monitors Reactor - RX 344' contaminated Refuel - RX 369' systems Radwaste - TB 300' Scintillation 10-1_106 CPS Stack Detector Drywell Reactor 300' Scintillation 10-1_106 CPM Monitor airborne Yes Gas marinelli continuous south side detectors radioactivity in counted on Ge(Li) air monitor Drywell during normal operation Containment Drywell 2-ion chamber 100-10" R/hr Accident control Yes Victoreen Cs-I 37 high range penetrations detectors and initiates isolation gamma dose rate monitors X1 1OC and X1 QOD source High range Stack, Turbine 2-ion chamber 10-'-10' mR/hr Accident control Yes Victoreen Cs-137 effluent Radwaste detectors and initiates isolation gamma dose rate monitors source Rev. No. 9 Rev. o. 9Page F-5 of ODCM

I POWT~

4 NI Q':-0ON IL 424'-#

I POWs I CAST ELEVATION I, OFF. SITE DOSE CALCULATION MANUAL A 56 -TOPFIGURE, F- I nr-~ jGASEOUS'RELEASE POINTS er__-4 BUILDING ELEVATIONS

~. IJames

~ ~ ~ A.FItzPairlck NAPP 3Ag MAT Entergy Nuclear Operations (AST(L VAnO PoylNorlhfievation Rev. No. 9 -n i-aye -L-_6 OT UUUM

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ALLILCAIIOP *310 0 *11(1FIGURE F-3 OFF-SITE DOSE CALCULATION MANUAL LIQUID EFFLUENT RELEASE POINTS DISCHARGE TUNNEL PLAN & PROFILE J. A. FITZPATRICK N.P.P. ENTERGY NUCLEAR Rev. No. 9 Page F-8 of ODOM

FIGURE F-4 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

GASEOUS EFFLUENT RELEASE PATHS RM RM Release Pioints 1& 2 Turbine Building RM R RM RM Reactor Building Refueling Floor Release Point 3 RM RM Waste Disposal HPA Filterý K.

Building Stack Release Point 4 RM RM Main Condensor Air Extractor K

Rev. No. 9 F-9. of ODOM Rev. N.1....Page

FIGURE F-5 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

LIQUID EFFLUENT RELEASE PATHS To Errnrnnmt

RM-Padiaiion Monitor POTENTIAL LIQUID EFFLUENT PATHS R e a cto r B u lid in g P a r am 9 ter S um p T unnflel S o uth0 S um p W est Storm Drain (>Lake O ntario Auxiliary B oiler O il/W a ter S e p a ra to r B uilding Roof 0 ra in s bcdb6k Treatm ent Plant~ mi East Storm Drain (>Lake O ntario Rev. No. -9 Page F-I 0 of ODOM

FIGURE F-6 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

SOLID RADWASTE TREATMENT SYSTEM Reactor Water Cleanup Phase Separator

-0 Waste Sludge Tank High Volume Compactor Temporary Units On Site Storage Container Filling Area - f ieDsoa Rev. No. 9 F-li1 of ODOM Rev. o. 9Page

FIGURE F-7 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

STANDBY GAS TREATMENT SYSTEM Rev. No. -9 F-1 2 of 00CM Rev. o. 9Page

APPENDIX G UNRESTRICTED AREA MAP Rev. No. 9 Rev. o. 9Page G-1 of 00CM

APPENDIX G UNRESTRICTED AREA MAP FIGURE TITLE PAGE G-1 JAFNPP Site Boundary Map G-3 Rev. No. -9 Rev. o. 9Page G-2 of ODCM

FIGURE G-1 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODCM)

JAFNPP SITE BOUNDARY MAP Lake Ontario NUCLEAR STTICH ob JA NITEARA NUCLEAR h K_

Rev. No. 9 G-3 of ODOM Rev. o. 9Page

NOTES TO FIGURE G-1 (a) NMPI stack (height is 350 feet)

(b) NMP2 stack (height is 430 feet)

(c) JAFNPP stack (height is 385 feet)

(d) Building vents (e) NMPI radioactive liquid discharge (Lake Ontario, bottom)

(f) NMVP2 radioactive liquid discharge (Lake Ontario, bottom)

(g) JAFNPP radioactive liquid discharge (Lake Ontario, bottom)

(h) Site boundary (i) Lake Ontario shoreline Additional Information:

-- NMP2 reactor building vent is located 187 feet above ground level

-- JAFN.PP reactor and turbine building vents are located 173 feet above ground level

-- JAFNPP radwaste building vent is 112 feet above ground level Rev. No. 9 Rev. o. 9Page G-4 of ODCM

APPENDIX H ENVIRONMENTAL SAMPLE LOCATIONS Rev. No. 9 H-i of 00CM Rev. o. 9Page

APPENDIX H ENVIRONMENTAL SAMPLE LOCATIONS TABLE TITLE PAGE H-I Radiological Environmental Monitoring Sampling H-5 Locations H-2 Liquid Effluent Pathway - Water Intake Points H-1 5 Description and Pumpage FIGURE H-i Off-Site Environmental Sample Location Map H-I I H-2 Off-Site Environmental Sample Location Map H-I 2 H-3 On-Site Environmental Sample Location Map H-13 H-4 On-Site Environmental ISESI TLD Locations H-14 H-5 Liquid Effluent Pathway - Water Intake Points H-1 6 Rev. No. 9 H-2 of ODOM Rev. o. 9Page

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 1.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1.1 Sampling Stations/Locations The current sampling locations are specified on Table H-I and Figures H-1, H-2 and H-3. The Radiological Environmental Monitoring Program is a joint effort between the Niagara Mohawk Power Corporation and Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc., the owners and operators of the Nine Mile Point Unit 1, Nine Mile Point Unit 2 and the James A. FitzPatrick Nuclear Power Plant, respectively.

Sampling locations are chosen on the basis of historical'average dispersion or deposition parameters from the three units.

The average dispersion and deposition parameters for the three reactors have been calculated for a five (5) year period, 1978 through 1982 (Reference 6.11 C.T. Main Data). Ingestion sample location evaluations are based on calculations performed by C.T. Main as this report contains grazing season X/Q and D/Q calculations for each of the seven release points in use at the JAF/NMP site. Milk animal locations are evaluated using grazing season D/Qs with the grazing season defined as (April to December). The April through December grazing season is used to coincide with the April through December milk sampling period required by Part 1 (REC)

Specifications. The deposition factor is evaluated at the census locations for each of seven release points (NMP I stack, NMP 2 stack, NMP 2 vent, JAF stack, JAF TB vent, JAF RW vent, and JAF RB vent). An arithmetic average of all release points is calculated and used in the evaluation. If it is determined that a milk sampling location exists at a location that yields a significantly higher (e.g. 50%) calculated D/Q rate, the new milk sampling location will be added to the monitoring program within 30 days. If a new location is added, the old location that yields the lowest calculated DIQ may be dropped from the program after October 31 of that year.

1.2 Interlaboratory Comparison Program Analyses shall be performed on samples containing known quantities of radioactive material that are supplied as part of a Commission approved or sponsored Interlaboratory Comparison Program. Sample analysis shall be only for those media, (e.g. air, milk, water, etc.), that are included inthe Nine Mile Point Environmental Monitoring Program and for which cross check samples are routinely available. The Quality Control sample results shall be reported in the Annual Radiological Environmental Operating Report so that the Commission staff may evaluate the results.

Rev. No. -9 Rev. o. 9Page H-3 of 00CM

Specific sample media analyzed as part of the JAF Cross Check Program include the following:

gamma emitters in air particulate filters

1-131 in milk

gamma emitters in milk

gamma emitters in water

tritium in water

gamma emitters in soil/sediment

1-131 in air particulate cartridges The availability, schedule and subsequent analysis of cross check samples are subject to change as a result of administrative changes within the JAF sampling program and commercial availability of such samples.

1.3 Thermol uminescent Dosimeters Used for Environmental Measurements Thermoluminescent Dosimeters (TLDs) are placed in an inner ring of stations in the general area of the site boundary, and in an outer ring in the 4 to 5 mile range from the site. There are 16 land based sectors in the inner ring and 8 land based sectors in the outer ring. TLDs are also placed in special interest areas such as population centers, nearby residences, schools, Independent Spent Fuel Storage Installation (ISFSI), and control locations.

1.4 Independent Spent Fuel Storage Installation (ISESI) Environmental Monitoring Program The radiological environmental monitoring program implemented at the site pursuant to JAF Technical Specifications Appendix B, contains program elements that satisfy the intent of 10 CFR 72.44(d)(2) and Certificate of Compliance No. 1014 Appendix A, Technical Specifications for the Hi-Storm 100 Cask System, Amendment 0.

Rev. No. -9 Rev. o. 9Page H-4 of ODOM

TABLE H-I RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATION" SAMPLE (FIGURE NO.)

Radioiodine and RI (H-2) Nine Mile Point Road 1.83 mi @92' E Particulates (air) North Radioiodine and R2 (H-3) Co. Rt. 29 & Lake Road 1.06 mi @ 1070 ESE Particulates (air)

Radioiodine and R3 (H-3) .Co. Rt. 29 1.43 mi @ 1340 SE Particulates (air)

Radioiodine and R4 (H-3) Village of Lycoming, NY 1.84 mi @ 145' SE Particulates (air)

Radiolodine and R5 (H-2) Montario Point Road 16.2 mi @ 42' NE Particulates (air)

Direct Radiation (TLD) 75 (H-3) North Fence, NMP-2 486 Ft @ 3560 N Direct Radiation (TLD) 76 (H-3) North Fence, NMP-2 0.12 mi @ 28' NNE Direct Radiation (TLD) 77 (H-3) North Fence, NMP-2 0.17 mi @ 390 NE K

Direct Radiation (TLD) 23 (H-3) North Shoreline Area 0.80 mi @ 740 ENE (H-ONSITE Station)

Direct Radiation (TLD) 78 (H-3) East Boundary, JAFNPP 0.97 mi @ 860 E Direct Radiation (TLD) 79 (H-3) Co. Rt. 29 1.18 mi @ 121 0 ESE Direct Radiation (TLD) 80 (H-3) Co. Rt. 29 1.51 mi @ 1370 SE Direct Radiation (TLD) 81 (H-3) Miner Road 1.66 mi @ 1600 SSE Direct Radiation (TLD) 82 (H-3) Miner Road 1.58 mi @ 1800 S Direct Radiation (TLD) 83 (H-3) Lakeview Road 1.23 mi @ 2030 SSW Direct Radiation (TLD) 84 (H-2) Lakeview Road 1.08 mi @ 2250 SW

See Figures H-I, H-2, H-3 and H-4 for map locations

+ Based on 9 Mile Point Unit 2 Reactor Centerline. Distance and direction determined using Global Positioning System (GPS) readings.

Rev. No. 9 Page H-5 of ODCM

TABLE H-I (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATION+

SAMPLE (FIGURE NO.)

Direct Radiation (TILD) 7 (H-3) Site Meteorological Tower (G ONSITE Station) 0.67 mi @ 2440 WSW Direct Radiation (TLD) 18 (H-3) Energy Information Center 0.44 mi @266'W Direct Radiation (TLD) 85 (H-3) North Fence, NMP-1 0.18 mi @ 2890 WNW Direct Radiation (TLD) 86 (H-3) North Fence, NMP-11 0.13 mi @ 3080 NW Direct Radiation (TLD) 87 (H-3) North Fence, NMP-1 491 Ft @ 332' NNW Direct Radiation (TLD) 88 (H-2) Hickory Grove Road 4.50 mi @ 970 E Direct Radiation (TED) 89 (H-2) Leavitt Road 4.34 mi @ 1120 ESE Direct Radiation (TLD) 90 (H-2) Rt. 104 and Keefe Road 4.20 mi @ 1350 SE Direct Radiation (TLD) 91 (H-2) Co. Rt. 51lA 4.87 mi @ 1570 SSE Direct Radiation (TLD) 92 (H-2) Maiden Lane Road 4.49 mi @ 1830 S Direct Radiation (TLD) 93 (H-2) Co. Rt. 53 4.44 mi @ 2060 SSW Direct Radiation (TLD) 94 (H-2) Co. Rt. I and Kocher Road 4.42 mi @ 2240 SW Direct Radiation (TLD) 95 (H-2) Lake Shore, Alcan West Access Road 3.73 mi @ 2390 WSW Direct Radiation (TLD) 49 (H-2) Phoenix, NY-Control 19.7 mi @ 1680 SSI E Direct Radiation (TED) 14 (H-2) SW Oswego-Control 12.5 mi @ 2270 SW\

Direct Radiation (TED) 96 (H-2) Creamery Road 3.65 mi @ 199' SS~N Direct Radiation (TLD) 58 (H-2) Alcan Aluminum, Rt. 1A 3.04 mi @ 2220 SW Direct Radiation (TED) 97 (H-2) Co. Rt. 29 1.84 mi @ 1450 SE Direct Radiation (TLD) 56 (H-2) New Haven Elem. School 5.22 mi @ 124' SE

See Figures H-11, H-2, H-3 and H-4 for map locations

+ Based on 9 Mile Point Unit 2 Reactor Centerline. Distance and direction determined using Global yPositioning System (GPS) readings.

Rev. No. 9 Rev. o. 9Page H-6 of ODOM

TABLE H-I (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATION+

SAMPLE (FIGURE NO.)

Direct Radiation (TLD) 15 (H-2) West Site Boundary, Bible Camp 0.92 mi @ 2390 WSW Direct Radiation (TLD) 98 (H-2) Lake Road 1.21 mi @ 103" ESE Direct Radiation (TLD) 8 (H-2) Montario Point Road (R5 OFESITE Station-Control) 16.2 mi @ 420 NE Surface Water W8 (H-i) NRG Steam Station Inlet Canal 7.59 mi @ 2370 WSW Surface Water W3 (H-I) JAFNPP Inlet Canal 0.61imi @ 54 0 NE Shoreline Sediment 05 (H-i) Sunset Bay Shoreline 1.43 mi @ 820 E Shoreline Sediment 06 (H-i) Langs Beach-Control 4.78 mi @ 2320 SW Fish F2 (H-i) Nine Mile Point Transect 0.44 mi @290 0 WNW Fish F3 (H-I) FitzPatrick Transect 0.84 mi @ 620 ENE Fish FO (H-i) Oswego Transect 5.93 mi @ 2360 SW Milk 77 (H-i) Milk Location #77-Control Summerville 16.0 mi @ 190' S Food Products ** 01 (H-I) Garden - Cary 1.35 mi @ 840 E (Broad Leaf Vegetation)

See Figures H-1, H-2, H-3 and H-4 for map locations

- Food product samples need not be samples from each locations listed. Two onsite samples will be collected from the location with the highest calculated average DIQ value from which edible or non-edible broad leaf vegetation is available. One control sample will be collected at a location listed from which edible or non-edible broad leaf vegetation is available.

+ Based on 9 Mile Point Unit 2 Reactor Centerline. Distance and direction determined using Global Positioning System (GPS) readings.

Rev. No. 9 Rev. o. 9Page H-7 of ODOM

TABLE H-I (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATIONV SAMPLE (FIGURE NO.)

Food Products ** 79 (H-i) Garden - Nerewski 1.49 mi @ 540 E (Broad Leaf Vegetation)

Food Products

48 (H-i) Garden - Kronenbitter 1.53 mi @ 83' E (Broad Leaf Vegetation)

Food Products ** 133 (H-I) Garden - Culeton 1.56 mi @ 830 E (Broad Leaf Vegetation)

Food Products

77 (H-I) Garden - Vitullo 1.88 mi @ 101 *E (Broad Leaf Vegetation)

Food Products ** 55 (H-I) Garden - Woolson 1.91 mi @132' SE (Broad Leaf Vegetation)

Food Products ** 57 (H-i) Garden - Parkhurst, G. 1.76 mi @ 1260 SE (Broad Leaf Vegetation)

( Food Products ** 422 (H-i) Garden - Parkhurst, C. 2.06 mi @ 1140 ESE

'(Broad Leaf Vegetation)

Food Products

132 (H-i) Garden - Barton 1.99 mi @ 1100 ESE (Broad Leaf Vegetation)

Food Products ** 142 (H-I) Garden - Hall 1.75 mi @ 1430 SE (Broad Leaf Vegetation) NM #49

See Figures H-1, H-2, H-3 and H-4 for map locations

- Food product samples need not be samples from each locations listed. Two onsite samples will be collected from the location with the highest calculated average DIQ value from which edible or non-edible broad leaf vegetation is available. One control sample will be collected at a location listed from which edible or non-edible broad leaf vegetation is available.

+ Based on 9 Mile Point Unit 2 Reactor Centerline. Distance and direction determined using Global Positioning System (GPS) readings.

Rev. No. -9 Rev. o. 9Page H-8 of ODCM

TABLE H-I (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATION"'

SAMPLE (FIGURE NO.)

Food Products **143 (H-i) Garden - Whaley, P. 1.61 mi @ 1380 SE (Broad Leaf Vegetation) NM #54 1/2 Food Products ** 144 (H-I) Garden -Whaley, C. 1.65 mi @ 1400 SE (Broad Leaf Vegetation)

Food Products ** 425 (H-i) Garden - Barsuch 1.81 mi @1440 SE (Broad Leaf Vegetation)

Food Products ** 426 (H-i) Garden - Larroca 1.80 mi @ 1450 SE (Broad Leaf Vegetation)

Food Products C*2 (H-i) Control - Flack 15.4 mi @ 2220 SW (Broad Leaf Vegetation)

Food Products ** 240 (H-I) Garden - Walcott 1.85 mi @ 960 E (Broad Leaf Vegetation)

Food Products 260 (H-I) Garden - Battles 1.71 mi.@98' E (Broad Leaf Vegetation)

Food Products **290 (H-i) Garden - Lee, R. 1.75 mi @ 980 E (Broad Leaf Vegetation)

Food Products 274 (H-i) Garden - Oldenberg 1.43 mi @ 1060 ESE (Broad Leaf Vegetation)

Food Products 343 (H-i) Garden - Fredette/Sheldon 1.82 mi @ 880 ESE (Broad Leaf Vegetation)

See Figures H-i, H-2, H-3 and H-4 for map locations

- Food product samples need not be samples from each locations listed. Two onsite samples will be collected from the location with the highest calculated average D/Q value from which edible or non-edible broad leaf vegetation is available. One control sample will be collected at a location listed from which edible or non-edible broad leaf vegetation is available.

+ Based on 9 Mile Point Unit 2 Reactor Centerline. Distance and direction determined using Global Positioning System (GPS) readings.

(I V

Rev. No. -9 Rev. o. 9Page H-9 of ODOM

TABLE H-I (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING SAMPLING LOCATIONS MAP*

TYPE OF LOCATION COLLECTION SITE LOCATION SAMPLE (FIGURE NO.)

Direct Radiation 1-1 (1-14) ISFSI4 " West Fence, South Direct Radiation 1-2 (HA1) ISFSI++ West Fence, Center Direct Radiation 1-3 (HA4) ISFSI++ West Fence, North Direct Radiation 1-4 (H-4) ISFSI44 North Fence, West Direct Radiation 1-5 (H-4) ISFSI++ North Fence, Center Direct Radiation 1-6 (HA4) ISFSI"+ North Fence, East Direct Radiation 1-7 (H-4) ISFSI`~ East Fence, North Direct Radiation 1-8 (HA4) ISFSI++ East Fence, Center Direct Radiation 1-9 (H-4) ISFSI++ East Fence, South Direct Radiation 1-10 (H-4) ISFSl++ South Fence, East Direct Radiation 1-11 (H-4) ISFSI4 + South Fence, Center

( ect Radiation 1-12 (H-4) ISFSI` South Fence, West See Figures H-1, H-2, H-3 and H-4 for map locations

++ Independent Spent Fuel Storage Installation Rev. No. -9 Rev.

o.9Page H-1 of ODOM

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approximately I1mnle) east of the map deslpgncntloIi I see table H-i lot d~escription

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TABLE H-2 LIQUID EFFLUENT PATHWAY - WATER INTAKE POINTS DESCRIPTION AND PUMPAGE Location of Water lntake Average Water Pumpage Millions of Gallons Per Day

1. At a point between Dennison Creek and Bear 0.80 Creak at a site north of the intersection of lake and Knickerbocker Roads

2. At Puitneyville 1.0

3. At a point north of the village of Sodus 1.0 near the intersection of Shore Road and an extension of Maple Avenue

4. In Sodus Point Village on Lake Road 0.133

5. At east of Port Bay 0.095

6. In the western part of the City of Oswego 20.0 between Sixth and Sheldon Avenues and north of West Schuyler Street

7. At east of the Village of Sackets Harbor 0.30

( 8. In Sawmill Bay at a location on Independence 0.04 Point approximately 0.5 miles south of Chaumont Village's southerly limit

9. Cape Vincent 0.246

10. Township of Pittsburg (Milton) 0.015

11. Township of Pittsburg (Glen Lawrence) 0.015

12. City of Kingston (2 intakes) 9.72

13. Township of Kingston (Pt. Pleasant) 0.705

14. Township of Kingston (Queen's Acres) 0.037

15. Township of Ernestown (Amherstview) 0.270

16. Village of Bath 0.150

17. Town of Picton 0.679

See Figure H-5 for Map Locations Rev. No. 9 Rev. o. 9Page H-14 of ODCM

FIGURE H-4 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (00CM)

On-Site Environmental ISFSI TLD Locations w-.

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FIGURE H-5 JAMES A. FITZPATRICK NUCLEAR POWER PLANT OFFSITE DOSE CALCULATION MANUAL (ODOM)

LIQUID EFFLUENT PATHWAY - WATER INTAKE POINTS Rev. No. 9 H-1 6 of ODOM Rev. o. 9Page

APPENDIX I ODCM

SUMMARY

TABLES Rev. No. -9 1-1 of ODOM Rev. o. 9Page

APPENDIX I ODCM

SUMMARY

TABLES TABLE TITLE PAGE 1-1 Radioactive Effluent Release Limits Summary 1-3 Table

[-2 ODOM Summary 1-4 Rev. No. -9 Rev. o. 9Page 1-2 of ODOM

TABLE I-1 RADIOACTIVE EFFLUENT RELEASE LIMITS -

SUMMARY

TABLE IMONTHLY BODY PERO SKIN (4)

ORGAN J BODY CAL.ENDAR QUARTER.

SKIN ORGAN I

BODY CALENDAR YEAR SKIN ORGAN

______I.(MREM) (IMRAD) (MREM) I(-MREM) (MRAD (MREM) (MVREM) I.(MRAD) (MREM)

Plant Member of Liquid (2) the Public Effluents 0.06 None 0.2 1.5 None 5 3 None 10 Plant Member of the Gaseous (2) None None None 5* 10* 7.5 10* 20* 15 Public Effluents Plant At or Beyond Gaseous (3) None None None None None None 500 3000 1500 Site Boundary Effluents Member of Uranium (4) the Public Fuel Cycle (Site) None None None None None None 25 None 25 (5)

(1) Equipment operability requirements for projected exposures. Refer to Specifications 2.4 (Liquid) and 3.6 (Gaseous).

(2) Plant Liquid and Gaseous release limitations in accordance with Appendix I to 10 CFR 50.

Refer to Part 1, Specifications 2.3 (Liquids), 3.3 (Noble Gases) and 3.4 (lodines and Particulates).

(3) Plant Gaseous release limitations in accordance with dose limits of 10 CFR 20.1001-20.2402. Refer to dose, limits of Part 1, Specification 3.2.

(4) Site Gaseous release limitations in accordance with 40 CFR 190. Refer to Specification 5.0.

(5) Limits to any organ except the thyroid which shall be limited to 75 mrem.

mrad, air dose.

P--v. No. 9 1-3 of ODC'14 ý P'v No 9Page

(- TAFr-`\-2 ODCM

SUMMARY

EFFLUENT PATHWAY IIFREQUENCY PURPOSE OF CALCULATION OF CALCULATION REGULATORY REQUIREMENT I___

Partl1(REC) ~CORRESPONDINGI Part 2

~REQUIREMENT _

1 LIMITING VALE

~(00CM)

SCIN ODCM

~EQUATION UME 1 INPUT

~REQUIEMNTS DATA REPORTING RUIR ENTMICLAOU Liquid Fraction of Each batch 10 times Section 2.2 .ECUs or for Section 3-1 .Discharge Release ECLs, FL release 10CFR20 noble gases 3.2.2 structure exit Permit Appendix 6, 2 x 10" pCi/mI flow Table 2, .Waste tank Column 2 release rate Sample

_________ ________________________ _______concentrations _______

Liquid Minimum Each batch 10 times Section 2.2 ECLs or for Section 3-2 Sample Release required dilution release IOCFR20 dissolved noble 3.2.3 concentrations Permit factor f2/f, min. Appendix B, gases Table 2, 2 x 104 PCi/mI Column 2 _____ ______ ________ ______

Liquid Determination Each batch 10 times Section FL less than or Section 3-3 .FL Input to of effluent release IOCFR20 2.1.2.c.1 equal to 1 when 3.3.2 .Sample operations monitor set- Appendix B, calculating concentrations points Table 2, minimum dilution

________________Column 2 flow_____ ____

Liquid Annual Dose Calendar year UISNRC Section 6.0 N/A Section 3.4a .Site specific Annual Assessment Regulatory 3.4.1 3-4b dose commit- Radiological Guide 1.21 tment factors Effluent Report Previous year's release volumes and curies Site specific dilution &

___________ ____________ ______ _______ingestion ______

Liquid Monthly Dose Calendar IOCFR50 Section 2.3 Whole Body Section 3-5a .Composite dose N/A May use limited Assessment month Appendix I dose - 1.5 3.4.2 3-5b .Duration of analysis mrem/qtr, release approach of 3 mremlyr Organ .Curies released ODCM Section dose - .Volume of 3.4.2 5 mrem/qtr, dilution

__________________110 mrem/yr I___ ___ ______ _____

Rev. No. 9 Rev. o. 9Page 1-4 of 00CM

TABLE 1-2 (Continued)

ODCM

SUMMARY

EFFLUENT PATHWAY PURPOSE OF CALCULATION OF CALCULATION jREGULATORY REQUIREMENT Part I (REC)

REQUIREMENT j LIMITING VALUES I(ODCM)

SECTION 1

EQUATION NUMBER DATA REQUIREMENTS REPORTING REQUIREMENTS IMISCELLANEOUS Liquid Dose projection Prior to N/A Section 2.4 Whole body Section N/A .Number of batch If non-determination release of dose - 0.06 3.5 releases, compliance, of need to unrestricted mremlmonth previous month 30-day NRC operate liquid liquid effluents Organ dose - .2 .Projected number report radwaste mrem/month of releases systems current month Gaseous Determining Calendar IOCFR2O.105 Section Whole body Section 4-1 to .Highest annual N/A May use a instantaneous week 3.2.1.c.1.a dose - 500 4.3.1 4-6 average X/Q limited analysis noble gas mrem/yr for vent and approach of release rates Skin dose - elevated releases ODCM Section 3000 mremlyr .Total body, skin, 4.3.1 to and air dose determine noble factors gas release rate Noble gas release limits rate (pCi/sec)

Effective dose transfer factor for vent releases, fraction of release rate limit 7----.No. 9 7'-> No.9Page 1-5~. of OD'`ý

TA!' -A-7 --'o ntinued)

ODCM

SUMMARY

EFFUEN PATHWAY PUROS CALCULATION FREQUENCY

_ OF

_ _ REGLAOR CALCULATION REQUIREMENT EFFLENT F

Part 1 (REC)

RGULTORYREQIREENT PUROSEOF CORRESPONDING LIITN VALUES LIMTIN IEURMN Part 2 SECTION (0CM)

ODCM NUMBER QUAION INPUT REQUIREMENTS DAT j

_ __EQAINAAREOTN REQUIREMENT EPOTIN MISCELLANEOUS Gaseous Determination of Calendar 10CFR20.105 Section 3.1 and Elevated Release - Section N/A .Maximum Volume Input to effluent monitor month or upon 3.2.l.c.i.a 3.0 x I (ý pCl/sec 4.3.2 release source Operations set-points major operational Vent release -

7.515E+4 x 10'

.Calibration curve (pCi/Cc oqqJ(tf transients (i.e., pCi/sec vs CPM) for power level specified effluent changes and monitor failed fuel) For ground level releases, fraction of release rate limit allocated to specified release point Gaseous Determining Calendar week 100FR20.105 Section 1500 mrem/yr. any Section 4-9 .Long-term N/A radioiodine, 3.2.1.c.1.b organ 4.3.3 4-10 sector average Tritium and 8 concentration day particulate X/Q (Appendix C) instantaneous .Long-term release rates relative deposition value (Appendix C)

Dose factors for applicable environmental pathways (Table B-4 through B-6) lodine,Tritium and 8-day particulate release rate (pCi/sec)

Rev. No. 9 1-6 of ODOM ReV. o. 9Page

TABLE 1-2 (Continued)

ODCM

SUMMARY

PATHWAY CALCULATION FREQUENCY CALCULAT10N fPart REQUIREMENT I (REC) CORRESPONDING VALUES Part 2 SECTION ODCM NUMBER INPUT REQUIREMENTS I

REQUIREMENT MISCELLANEOUS Gaseous Annual Dose Calendar Year USNRC Section 6.1 N/A Section 4-11 to .Previous Annual Assessment Regulatory 4.4.1 4-19 year's annual Radioactive Guide 1.21 average DIQl Effluent Report and X/Q Activity released (pCi/yr) for the previous year from vent and elevated releases Gaseous Monthly Dose Calendar 10CFR5O, Section Gamma air Section 4-20 .Gamma Air Dose Assessment Month Appendix I 3.3.2.c.1 Dose - 5 mrad/qtr 4.4.2 4-23 factors, M

-Gamma air 10 mrad/yr .Beta Air Dose Dose Beta air Dose - factor, N

-Beta air 10 mrad/qtr .Highest annual Dose 20 mrad/yr average XICQ for vent and elevated releases Noble Gas curies released during the month Gaseous Monthly Dose Calendar IOCFR5O, Section Any Organ - Section 4-24 to N/A May use limited

-radioiodine Month Appendix I 3.4.2.c.1 7.5 mremlqtr 4.4.2 4-27 analysis tritium and 15 mremlyr approach of 8-day ODCM Section particulate 4.4.2.c

-w.No. 9 K~> '~> Page -L-7 of ODC" A.,

(.

TA---- -- I-.' _ontinued) 00CM

SUMMARY

FREQUENCY CORRESPONDING Part 2 00CM INPUT PATHWAY CALCULATION CALCULATION IREQUIREMENT I _ _ _

REQUIREMENT VALUES

___ 1SECTION

_ _1 NUMBER

.1_ REQUIREMENTS

_ _ S REQUIREMENT MISCELLANEOUS Gaseous Dose Projection Prior to release N/A Section 3.5 0.2 mrad gamma Section 4-20 .Gamma and Beta If non- May use a limited Determination of of unprocessed 0.4 mrad beta 4.5 4-31 air dose and compliance, 30 analysis need to operate gaseous 0.3 mremn organ particulate, iodine, day NRC report approach of off gas treatment effluents and tritium organ ODCM Section system dose during the 4.5.2 quarter to date Number of days the plant is projected to be operational during the coming month Liquid Demonstrate Calendar year 40CFRI90 Section Whole Body or Section 3-4 .Actual compliance with if liquid 4.1.1.c.1 any organ 5.2 dilut~ion annual fuel/cycle releases (except thyroid) ingestion dose exceed 3 - 25 mremlyr factors (fish commitment mrem, total thyroid - 75 and potable limits body, or 10 mrem/yr water) mrem, any .Radiological organ Environmental Monitoring Program Results Rev. No. 9 Rev. o. 9Page 1-8 of ODCM

TABLE 1-2 (Continued)

ODCM

SUMMARY

EFFLUENT PURPOSE OF OF REGULATORY REQUIREMENT LIMITING (ODCM) EQUATION DATA REPORTING PATHWAY CALCULATION CALCULATION REQUIREMENT VALUES SECTION NUMBER REQUIREMENTS REQUIREMENTMICLAEU

___~~~ _ _ _ _ ~ I _ S_ _

Gaseous Demonstrate Calendar year, 400FRI90 Section Whole Body or Section Equation Current data, 30 day NRC Substitute the compliance with if gaseous 4.1.1.c.1 any organ 5.3 Section including: actual Report total body dose annual fuel releases (except thyroid) 4-4 location of real factor (Ki) for the cycle dose exceed 10 - 25 mremlyr. individuals, gamma air dose commitment mrads gamma thyroid - meteorological factor (Mi) limits air dose, 15 75 mremlyr. conditions, and mremn thyroid or consumption of food any organ (e.g. milk, meat, and vegetation)

Direct Demonstrate Calendar year, 40CFR190 Section Whole Body - Section N/A .Shielding Radiation compliance with if liquids or 4.1.1 .c.1 25 mrem/yr. 5.4 calculations annual gases exceed .TLD results fuel/cycle dose dose limits from commitment indicated above environmental limits program l_-.No. 9 Page 1-9 of ODC&4.,

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