ML20211C331
| ML20211C331 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle  |
| Issue date: | 04/30/1999 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| References | |
| PROC-990430, NUDOCS 9908250213 | |
| Download: ML20211C331 (100) | |
Text
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August 16,1999 IO X244 ALL t
D, Document Control Desk I
Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington DC 20555 Enclosed are revisions to the Generic Offsite Dose Calculation Manual (ODCM). Also included is a change summary for your information. Please update your manual as follows:
Remove: Insert:
Table of Contents Rev.1.1 Dated July Table of Contents Rev. 2.0 Dated April 1994 1999 )
Chapter 1 Rev.1.1 Dated July 1994 Chapter 1 Rev. 2.0 Dated April 1999 Chapter 2 Rev.1.1 Dated July 1994 Chapter 2 Rev. 2.0 Dated April 1999 Chapter 3 Rev.1.1 Dated July 1994 Chapter 3 Rev. 2.0 Dated April 1999 Chapter 4 Rev.1.1 Dated July 1994 J A Chapter 4 Rev. 2.0 Dated April 1999 Chapter 5 Rev.1.1 Dated July 1994 Chapter 5 Rev. 2.0 Dated April 1999 Chapter 6 Rev.1.1 Dated July 1994 Chapter 6 Rev. 2.0 Dated April 1999 Chapter 7 Rev.1.1 Dated July 1994 Chapter 7 Rev. 2.0 Dated April 1999 !
Appendix A Rev.1.1 Dated July 1994 Appendix A Rev. 2.0 Dated April 1999 Appendix B Rev.1.1 Dated July 1994 Appendix B Rev. 2.0 Dated April 1999 Appendix C Rev.1.1 Dated July 1994 Appendix C Rev. 2.0 Dated April 1999 Please sign and date this form ani retum to:
Comed Procedures Clerk 1400 Opus Place 4* Floor Downers Grove, IL 60515
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Name Date 1 9908250213 PDR 990430 W ADOCK 05000010 PDR t I
s Change Summary ODCM, Generic Sedion Revision 2.0
. Note:
The changes to the ODCM Generic section summarized below will maintain the level of radioactive effluent control required by 10CFR20.1302,40CFR190,10CFR50.36a, and Appendix I to 10CFR50 and not adversely impact the accuracy of effluent, dose or set point calculationsE i
Cover Page, Table of Contents Paoe or Section Chanoe Description Cover Page Added station names to docket numbers.
. Updated page numbers in entire T.O.C. Updated changes to section headings, chapters and appendices throughout T.O.C.
. Removed page and revision summary from T.O.C. Individual pages are no longer updated.
. Combined the entire generic section Chapters' table of contents.
. Added a note to the T.O.C. to indicate cha.nges made to chapters and i appendices.
. Clarified in T.O.C. that Chapters 8 and 9 as well as Appendix D and E have intentionally been left blank e Deleted list of abbreviations and acronyms O l 1
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Change Summary
, ooCu, Generic sed 6on Revision 2.0 Pace or Section Qhence Description
. Throughout chapter one and all the generic section chapters, the majority of the information that was provided as backgrou6d and did not specifically address the Comed offsite dose program was deleted.
. Throughout entire generic section, changed CECO to Comed.
. Throughout entire generic section, deleted reference to chapters 8 and 9.
. Updated page numbers throughout generic section.
Chapter 1 Pace or Section Chance Description Introduction Numbered as Section 1.0.
Deleted first four paragraphs and last three paragraphs. Reworded parts of the remainder.
Added statement indicating that manual calculations may be performed in lieu of computer program Changed reference to Radiological Effluent Technical " Specifications" to
" Standards" 1.1,1.1.1,1.1.2, Deleted, this same information is already included in Chapter 4.
1.1.3 1.2.1 Reworded and moved to section 2.1.
O 1.2.2 1.2.3 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
Deleted. This information is descriptive / educational but is not required to be J
included in the manual for the ODCM.
1.2.4 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
1.3 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
1.4 Renumbered 1.1. Reworded to reflect changes to chapters and appendices.
Added fourth paragraph to address the new ODCM Bases and Reference Document (old Appendix E).
Table 1-1,1-2, These tables were deleted and a new table, Table 2-1 was created to contain the same 1-3,1-4 & 1-5 information.
Figure 1-1 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
Figure 12 Reformatted and renamed Figure 2-1. Footnote 1; deleted first sentence defining monthly.
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ODCM, Generic 8edian i d
Revision 2.0 Chapter 2 RR \
Q Eggg_gr Section Chance Description Added introduction to Chapter 2 "~ {
1 2.1.1 ' Removed the 10CFR20 effective dates. Deleted Chapter 1 reference and updated table number, 2.1.1.1 - 2.1.1.4 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
2.1.1.5 Combined with 2.1.1 and added reference to Table 2-1, 2.1.2 - Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
2.1.2.1 Renumbered 2.1.2, deleted last two paragraphs.
2.1.2.2
- Renumbered 2.1.3, deleted last sentence of the second paragraph. i l 2.1.3 Renumbered 2.1.4.
2.1.4 Renumbered 2.1.5. Deleted the number and the specific stations listed in parenthesis. Deleted last sentence of last paragraph.
Added paragraph that references Generic Letter 79-041 which gives the basis for 1
compliance with 40CFR190 requirements, i
2.2 Removed ' specifications' from the section heading. Changed RETS to stand for l Standards. Reworded; deleted reference to (pending approval), deleted reference to acronym recognition.
l 2.2.1 Deleted section and paragraphs related to Standard RETS.
2.2.2 and Deleted; redundant to station annex.
(2.2.2.1 - 2.2.2.5) 2.4 Reworded to emphasize the fact that 10CFR50 provides design 4 objectives, not limits. Also combined with the old 2.5 and both numbered as 2.4.
(2.4.1 - 2.4.4) Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
i O 2.5 2.6 Renumbered 2.4. Reworded first sentence of second paragraph to clarify intent.
Updated table references.
Renumbered 2.5 and renamed section. Changed table references. Reworded to k
improve grammar.
Table 2-1 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM. Created new Table 2-1 ' Regulatory Dose Limit Matrix'. Reformatted footnotes to numbers instead of asterisks; added footnote 3 which relates the fact that 10CFR50 provides design objectives, not limits. Added additional requirement (and limits) to calculate total body and skin dose if air dose is exceeded.
Table 2-2 Deleted. Redundant wording.
Table 2-3 Renamed and Renumbered Table 2-2 Under Reference equation comments, added Col.2" to the 10CFR20 Appendix B reference.
Table 2-4 Renumbered Table 2-3. Reformatted footnotes to numbers instead of asterisks.
Figure 2-1 Reformatted old Figure 12. Footnote 1, deleted first sentence defining yearly and quarterly since they are spelled out now. Footnote e; changed to Table A-3.
Added footnotes 3 and 4 for clarification. Exposure pathways example figure is now incorporated into Figure 3.1 1
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- Chan0e Summary ODCM, Generic Section Revision 2.0 Chapter 3 ym Paae or Section Chanae Description Introduction Numbered as Section 3.0. Updated figure reference. Reworded first sentence to clarify. Reworded last paragraph to clarify.
3.1 Updated figure number. Replaced the words 'The nuclear power stations' with
' Comed' in the second to last sentence. Reworded last sentence to clarify.
3.2 Updated figure number. Reworded first bullet to clarify meaning. In bullets c*,anged ' plant' to ' station'. Reworded and changed reference to ' Appendix E' to
'ODCM Bases and Reference Document'.
Added new paragraph between last two paragraphs to discuss dredging of the rivers near the nuclear stations. Modified last paragraph to clarify that concentrations for noble gases are contained in station Radiological Effluent Technical Standards (RETS).
3.3 Changed reference from Appendix E to ODCM Bases document. Added statement for an example.
Added emphasis that contained radioactive material stored onsite produces doses that are negligible in comparison with applicable limits due to BWR skyshine and potential doses due to radioactive waste storage.
Figures 3-1, Combined the three figures into one; numbered as Figure 3-1; bolded pathways in Figure 3-1 that Comed considers in its calculations; under Liquid Effluents, added a block depicting the pathway of exposure to radioactivity in water from recreational activities.
3-2 and 3-3 I
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Change Summary ODCM, Generic Sedion Revision 2.0
\ f. Chapter 4 Epae or Section Chance Description 4.0 Removed reference to Appendix C.
4.1.1 Reworded section to clarify meaning.
4.1.2 Reworded first sentence to clarify intent of this section. Deleted ' drinking' from second to last paragraph, redundant wording.
4.1.3 Renamed the section. Reworded to clarify meaning. Deleted 'On' at beginning of second two bullets.
Changed radio-iodine to " radioactive iodine" 4.1.4 Minor rewording to clarify meaning.
4.1.5 Changed Appendix D reference to Appendix C. Deleted Table 4-3 reference.
Deleted, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Reworded to clarify meaning.
4.1.6 Reworded to clarify meaning. Deleted equation and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Deleted the three bullets, unnecessary.
4.1.7 Deleted equation and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. In first paragraph, changed 'and, of to 'and/of. j 4.1.8 Changed table reference to Table 4-2.
4.2 Deleted text, redundant wording.
4.2.1 Deleted entire section, this information is descriptive / educational but is not required to be included in the manual for the ODCM.
4.2.1.1 Renumbered 4.2.1. Deleted equation and parameter definitions, this information O
D is descriptive / educational but is not required to be included in the manual for the ODCM. Minor wording changes.
4.2.1.2 Renumbered 4.2.2. Deleted equation and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Changed Appendix D reference to Appendix C. Minor rewording to clarify meaning.
4.2.1.3 Renumbered 4.2.3. In section on ' Dose' deleted the four bullets; redundant.
Renamed section on ' Dose' to *Whole Body Dose' and renamed ' Dose Rate'.
Updated section reference. 'Whole Body Dose Rate'. Minor rewording to clarify !
meaning (clarified the meaning of "whole body dose factor"). l 4.2.1.4 Renumbered 4.2.4. Renamed 2 paragraph headers ' Dose and Dose Rate Skin i
Dose and Skin Dose Rate'. Minor rewording to clarify meaning.
4.2.2 Renumbered 4.2.5. Deleted equations and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Reworded Comment to clarify meaning.
4.2.3 Renumbered 4.2.6. Deleted equation and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Reworded section on 'the inhalation dose commitment factor' to improve clarity, created two bullets. Deleted 'now'in last sentence of Dose Commitment section, redundant wording. 4.2.4 Renumbered 4.2.7. Deleted equations and parameter definitions, this information is descriptive / educational but is not required to be included in the manual for the ODCM. Reworded section to improve clarity. l t
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1 Change Summary ODCM, Generic Section
- i Revision 2.0 1
4.2.4.1, 4.2.4.2 Deleted sections, redundant to Appendix A.
v/ and 4.2.4.3 4.3 Deleted equations and parameter definitions, this infoimation is i descriptive / educational but is not required to be included in the manual for the ODCM, Data is also included in the Appendix A.
Minor rewording for clarity. Changed Figure 3-3 reference to Figure 3-1.
Changed Appendix D reference to Appendix C.
4.4 and 4.4.1 Combined and re-titled ' Contained Sources of Radioactivity". Reworded to improve clarity; added " rad material" to last sentence of second paragraph.
4.4.1.1 Renumbered 4.4.1. Minor rewording for clarity. Added sentence to indicate that the addition of hydrogen can increase the dose rate due to skyshine up to a factor of 10 times expected levels depending on injection rates and power levels. Added reference 39.
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4.4.1.2 Renumbered 4.4.2. Minor rewording to clarify management of facilities. Retitled '
section to "Onsite RadWaste and Rad Material Storage Facilities". Removed site specific information. Added butler buildings / warehouses under DAW Storage Facilities and added bullet for Rad Material Storage Facilities which i includes replaced steam generator storage facilities. Site specific details exist in !
Appendix A.
4.5 (new) New section heading numbered 4.5 to include information on total dose requirements.
4.4.2 Renumbered 4.5.1. Minor rewording for clarity. Deleted second and third j sentences, this information is descriptive / educational but is not required to be included in the manual for the ODCM. ,
4.4.3 Renumbered 4.5.2; fourth bullet reworded to end, ". . if applicable".
Table 4-1 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
O Table 4-2 Table 4-3 Renumbered Table 4-1. Added second footnote 'a'to state that stations are not required to calculate for carton-14. Old footnote "a"is now footnote "b" Renumbered Table 4-2 Chsnged Table references nomenclature to match renumbering for dose commitment factors.
Figure 4-1 Deleted. This information is descriptive / educational but is not required to be included in the manual for the ODCM.
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Change Summary oDCM, Generic Section l Revision 2.0 '
Chapter 5 Paoe or Section Chance Description 5.1 Deleted all but the first paragraph, redundant and informational but is not ,
required to be included in the manual for the ODCM. Minor rewording for clarity. 1 5.2 Minor rewording for clarity. Deleted last sentence, this information is descriptive / educational but is not required to be included in the manual for the ODCM.
5.3 Minor rewording for clarity. Remainder of section, after the fourth sentence, was deleted, informational and redundant. The information is out-of-date and not appropriate for all stations. i 5.3.1 Deleted last two sentences, all Comed sites are now on UREMP. Minor '
rewording for clarity, Removed the capitalization from the words 'interlaboratory comparison program
- to keep the statements generic in nature since the NRC (EPA) no longer provides or requires approval of the program.
Chapter 6 Paae or Section Chanae Descriptior' 6.0 Deleted old Chapter 6 as it was redundant to Site Annex. Previous Chapter 8 was renumbered as Chapter 6.
6.1 Minor rewording.
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Chapter 7 Paae or Section Chance Description e Deleted chapter. Redundant to station annex. I e incorporated References Section into a new Chapter 7 and added reference 103, "U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17,1979.
Chapter 8 Paae or Section Chanae Description l
Chapter 8 was renumbered as Chapter 6.
Introduction Deleted all but the first paragraph, redundant and informational but is not required to be included in the manual for the ODCM.
8.1 Renumbered 6.1. Deleted last two sentences of the first paragraph, redundant material Minor rewording to improve clarity. Clarified responsibility for distribution of the AREOR.
8.2 Renumbered 6.2. Minor rewording to clarify responsibilities. Deleted ' optional'.
8.3 Renumbered 6.3 and re-titled 'REMP Contractor'. Updated department nomenclature to references.
8.4 Renumbered 6.4. Updated department nomenclature to references. Minor rewording to clarify responsibil.;;es.
Chapter 9 IO 7
9 Change Summary ooCu, Generic section Revision 2.0 Chapter 9 has been deleted. The basic program requirements for each station have been relocated into A Chapter 12 (Section 12.5) of each station's annex.
References ~
Egge or Section Chanae Description
. References are no longer a separate section, the references have been reformatted into the new ODCM Chapter 7.
- 1 Deleted reference 1. Procedure no lon0er exists.
- 42 Deleted reference 42. Procedure no longer exists.
- 80 Added reference 80. Changed CECO to Comed.
- 94 Deleted reference 94. This letter was never issued and is no longer necessary since stations have implemented the improved Technical Specifications. 1
- 101 New reference. This document is the old ODCM Appendix E.
- 102 New reference. This document was added to show that increases in the hydrogen injection rates will increase the offsite and onsite doses even higher j than current levels. j 1
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o Change Summary ODCM, Genwie Section Revision 2.0 Appendix A 10 V Paae or Section Chanae Descriotion Updated references to ODCM sections and appendices throughout AppendbrA.
T.O.C. Revised Table listing.
A.0 Revised Table numbers.
A.1.1 A.1.2.1 Added the requirement for the determination projected dose contributions in this section as well as sections A.1.2.2, A.1.4 and A.2.1.
Changed the word ' symbol
- to ' letter. Revised Table number.
A.1.2.2 Updated section and, or appendix references in parameter Li , l idefinitions.
Deleted 'of this manual'.
A.1.2.3 Updated section references in parameter SiiV iG definition. Revised Table number.
A.1.2.4 Updated section and, or appendix references in parameter t.i definition.
A.1.3.1 Deleted reference to proposed generic letter (never issued). Minor rewording in last sentence.
A.1.3.2 Deleted reference to proposed generic letter (never issued).
A.1.4 Deleted 'of this manual'.
A.1.4.1 Updated appendix references in parameter DFG i i, t ,,li definitions.
A.1.4.2 Updated appendix references in parameter R. definitions. Updated Dose Factor references in parameter DFA, definition.
A.1.4.3 Updated Dose Factor references in parameter DFI, definition. Corrected Equation A-22 to read 'i$. = U', C$ '. Updated appendix references in parameter definitions.
A.1.4.3.1 Updated appendix nomenclature references in parameter definitions.
A.1.4.3.2 Updated appendix nomenclature references in parameter definitions.
A.1.4.3.3 Updated appendix nomenclature references in parameter definitions.
C) A.1.5 A.1.6 Deleted reference to proposed generic letter (never issued).
Added the four age groups after ' member of the public' for clarity.
A.2.1 Updated appendix nomenclature references in parameter definitions. Updated Dose Factor references in parameter DFlo definition. Deleted 'of this manual'.
A.2.2 Deleted last sentence of ' Requirement' discussion; Tech Specs are approved.
Changed acronym DWC to ECL. Added sentence at end of 'ECL,' definition to clarify noble gas concentration limits.
Changed reference nomenclature from A.5.3 to A.5.1.
A.3 Added ' types of' and (N'6) for clarity.
i A.3.1 Replaced ' nitrogen-16 (N-16)' with ' N a . Reworded the second paragraph to improve clarity. Additional minor rewording to improve clarity.
A.3.2 Re-worded A.3.2 to remove site specific information. Deleted date reference.
Site specific information is not appropriate for the generic section. Also indicated that waste *may" be stored at the sites since not all sites actually have or store waste in a particular storage facility. Added verbiage to reflect the project that is underway for Byron and Braidwood to have an onsite building to house the old steam generators after they are removed for Byron-1 and Braidwood-1. This information is being added to ensure that the proper dose evaluations be performed once these facilities are constructed and in use.
A.4 Added ' Limits' to section title. Minor rewording to improve clarity. !
A.4.2 Updated reference nomenclature in definition of parameter Wr. Updated appendix nomenclature references.
A.4.3 Deleted 'Ho + Hef,o ' to eliminate appearance of the unnecessary second equation.
A.S.1 Added two paragraphs in the ' Requirement'section to address the ' member of O Appendix A (cont.)
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Change Summary oocu, Generte sodion Revlelon 2.0 Pace or Section Chance Descriotion A.S.2 Minor rewording to improve clarity. "~
A.S.3 Revised Table nomenclature numbers.
A.6.2 Revised Table nomenclature number.
Table A-1 Deleted, redundant to Table 2 3.
Table A-2 Renumbered Table A-1.
Table A-3 Deleted, redundant to Table 2-2.
Table A-4 Renumbered Table A 2.
Table A-5 Renumbered Table A-3.
Table A-6 Renumbered Table A-4.
Figure A-1. Deleted.
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e Change Summary
' oocu, Genede section Revision 2.0 Appendix B Pace or Section Chance Description This revision to Appendix B was expanded to incorporate Appendix C. Added 'Section 1' and 'Section 2' to separate the appendix into airbome and liquid effluents.
B.1 Reworded to improve clarity. Updated appendix reference.
B.1.1 Updated appendix nomenclature reference.
B.2 Deleted '(see Figure B-1)' and '(see Figures B-2 through B-4)'.
B.2.1 Deleted '(see Figure B-4)' twice and deleted '(see Figure B-3)'
B.3.1 Updated appendix nomenclature reference. .
B.3.2 Updated appendix nomenclature reference.
B.4.1 Deleted reference to figures in Appendix D.
B.4.2 Deleted reference to figure in Appendix D.
i B.S.1 Updated appendix nomenclature reference.
B.7 Updated appendix nomenclature reference.
B.8 Updated appendix nomenclature reference.
B.9 Deleted reference to Appendix D.
B.10 Deleted reference to Appendix D.
B.12 Updated appendix nomenclature reference.
B.13 Updated appendix nomenclature reference.
Appendix C Pace or Section Chance Descriptio_q Incorporated entire Appendix C into Appendix B as Section 2.
4 C.0 Renumbered B.14. Updated section nomenclature references.
v C.1 Renumbered B.15.
C.1.1 Renumbered B.15.1. Renumbered equation (A-27) as (A-30). Deleted reference to Figure C-1. In second bullet, added (with 1/M s; 1) to show that dilution is a multiplier. Renumbered l
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Change Summary ooCM, Generic section i Revision 2.0 p Appendix D U Paoe or Section Chanoe Description ~
Renamed Appendix D as Appendix C. Renumbered all sections and tables with the 'C' designation.
D.1 Renumbered C.1. Added two sentences to improve clarity of scope and content of this appendix.
D.2 Renumbered C.2. Reworded section to incorporate the reference to the R.G.1.109 for the dose commitment factors addressing 10CFR50 compliance calculations.
New Section Created Section C.3; this section incorporates the reference to FGR#11 for the dose commitment factors addressing 10CFR20 compliance calculations. Also included description to illustrate how the dose factors were derived from FGR#11.
Table D-1 Deleted; table values were directly taken from the R.G.1.109 and FGR#11.
Through D-8 Table D-9 Renumbered Table C 1.
Table D-10 Renumbered Table C-2. Added reference statement after the table. The value of Ra for the teenager in the manual was incorrectly indicated as 3700. The value is being revised to the correct value of 8000 to be consistent with Reg. Guide 1.109 and the ODCM software. Only the value listed in the manual was (
incorrect, the software database does contain the proper value of 8000.
Table D-11 Renumbered Table C-3.
Table D-12 Renumbered Table C-4. Added reference statement after the table.
Table D-13 Renumbered Table C 5.
Table D-14 Renumbered Table C-6. ;
Table D-15 Renumbered Table C-7. '
Table D-16 Renumbered Table C-8.
Table D-17 Renumbered Table C-9.
Table D-18 Renumbered Table C-10. !
Table D-19 Renumbered Table C 11.
Table D-20 Deleted table of intake to dose conversion factors which are found in FGR-11.
Table D-21 !
Deleted table of intake to dose conversion factors which are found in FGR-11.
Figures D-1 Deleted as redundant, direct copies from the R.G.1.109.
through D-8 Appendix E Pace or Section Chanoe Description Appendix E was deleted from the generic section of the ODCM. The appendix was converted to a generic section bases and reference document which will be treated as a reference and will not be included as part of the ODCM. This information is descriptive / educational but is not required to be included in the manual for the ODCM; it is now reference #101.
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o Comed Oftsite Dose O Calculation Manual Docket Numbers:
l Dresden 50-10, 50-237, 50-249 Quad Cities 50-254, 50-265 ;
Zion 50-295, 50-304 i LaSalle 50-373, 50-374 {
Byron 50-454, 50-455 l Braidwood 50-456, 50-457 l
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I Revision 2.0 i April 1999 OFFSITE DOSE CALCULATION MANUAL (j TABLE OF CONTENTS Part 1: GENERIC SECTIONS TABLE OF CONTENTS PAGE Chapter 1 Introduction 1 j i
Chapter 2 Regulations and Guidelines 2 Chapter 3 Pathways 12 Chapter 4 introduction to Methodology 15 l
Chapter 5 Measurement 29 )
Chapter 6 Implementation of Offsite Dose Assessment Program 31 Chapter 7 References 33 l
Chapter 8 Intentionally Left Blank Chapter 9 Intentionally Left Blank I
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Q Appendix A Compliance Methodology A-i Appendix B Models and Parameters for Airborne and Liquid Effluent Calculations B-i Appendix C Generic Data C-i Appendix D Intentionally Left Blank _
Appendix E Intentionally Left Blank _
Part 2: SITE SPECIFIC SECTIONS Chapter 10 Radiological Effluent Treatment and Monitoring Chapter 11 Radiological Environmental Monitoring Program Chapter 12 Radiological Effluent Technical Standards Appendix F Station Specific Data Note: Previous Chapter 6 was deicted anc pmv Ns Chapter 8 was renumbered as Chapter 6.
l Previous Chapter 7 was deleted cnd replaced by the references section.
Previous Chapter 9 was deleted.
Previous Appendix B and C have been combined into Appendix B.
Previous Appendix D has been revised into Appendix C.
Previous Appendix E has been deleted and is Reference 101.
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Revision 2.0 April 1999 OFFSITE DOSE CALCULATION MANUAL eG h TABLE OF CONTENTS (Continued)
CHAPTER 1 INTRODUCTION PAGE
1.0 INTRODUCTION
1 1.1 STRUCTURE OF THIS MANUAL 1 )
J CHAPTER 2 REGULATIONS AND GUIDELINES 2
2.0 INTRODUCTION
2 2.1 CODE OF FEDERAL REGULATIONS 2 1, 10CFR20, Standards for Protection Against Radiation 2 l
- 2. Design Criteria (Appendix A of 10CFR50) 2 l
- 4. 40CFR190, Environmental Radiation Protection -
Standards for Nuclear Power Operations 3 J
- 5. 40CFR141, National Primary Drinking Water Regulations 3 2.2 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS / STANDARDS 3
- 1. Categories 4 2.3 OFFSITE DOSE CALCULATION MANUAL 4 2.4 OVERLAPPING REQUIREMENTS 5 2.5 DOSE RECEIVER METHODOLOGY 5 CHAPTER 3 EXPOSURE PATHWAYS 12
3.0 INTRODUCTION
12 3.1 AIRBORNE RELEASES 12 3.2 LIQUID RELEASES 12 l 3.3 RADIATION FROM CONTAINED SOURCES 13 l
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Revision 2.0 April 1999 OFFSITE DOSE CALCULATION MANUAL \
/~'%
(/ TABLE OF CONTENTS (Continued)
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PAGE CHAPTER 4 METHODOLOGY 15
4.0 INTRODUCTION
15 j 4.1 IMPORTANT CONCEPTS AND PARAMETERS 15
- 1. Dose and Dose Commitment 15 4
- 2. Exposure Pathways 15
- 3. Categories of Radioactivity 16
- 4. Release Point Classifications 16
- 5. Historical Average Atmospheric Conditions 17
- 6. Relative Concentration Factor X/O 18
- 7. Relative Deposition Factor D/O 18
- 8. Dose Factors 19 4.2 AIRBORNE RELEASES 19
- 1. Gamma Air Dose 19
- 2. Beta Air Dose 19
- 3. Whole Body Dose and Dose Rate 20
- 4. Skin Dose and Dose Rate 21
- 5. Ground Radiation 21
- 6. Inhalation 22
- 7. Ingestion 22
'd 4.3 LIQUID RELEASES 23 4.4 CONTAINED SOURCES OF RADIOACTIVITY 24
- 1. BWR Skyshine 24 l
- 2. Onsite Radwaste Storage Facilities 24 4.5 TOTAL DOSE REQUIREMENTS 25
- 1. Total Effective Dose Equivalent Limits of 10CFR20 25
- 2. Total Dose for Uranium Fuel Cycle 25 CHAPTER 5 MEASUREMENT 29
5.0 INTRODUCTION
29 5.1 EFFLUENT AND PROCESS MONITORING 29 I 5.2 METEOROLOGICAL MONITORING 29 5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 29
- 1. Interlaboratory Comparison Program 29 O
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Revision 2.0 April 1999 OFFSITE DOSE CALCULATION MANUAL TABLE OF CONTENTS (Continued)
PAGE CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT 31 6.1 NUCLEAR POWER STATION 31 6.2 METEOROLOGICAL CONTRACTOR 31 6.3 REMP CONTRACTOR 31 6.4 CORPORATE DEPARTMENTS 31 CHAPTER 7 REFERENCES 33 1
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Revision 2.0 April 1999 l , OFFSITE DOSE CALCULATION MANUAL LIST OF TABLES FOR TIIE ODCM GENERIC SECTIONS l SECTION TABLE NUMBER TITLE Chapter 2 2-1 Regulatory Dose Limit Matrix 2-2 Dose Assessment Receivers 2-3 Dose Component / Regulation Matrix l
Chapter 4 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways 4-2 Radiation Dose Factors Appendix A A-1 Compliance Matrix A-2 Release Point Classifications A-3 Nearest Downstream Community Water Systems A-4 40CFR190 Compliance Appendix C C-1 Miscellaneous Dose Assessment Factors Environmental Parameters C-2 Miscellaneous Dose Assessment Factors -
Consumption Rate Parameters C-3 Stable Element Transfer Data C-4 Atmospheric Stability Classes C-5 Vertical Dispersion Parameters
, C-6 Allowable Concentrations of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste C-7 Radiological Decay Constants (A,) in hr' C-8 Bio-accumulation Factors B, to be Used in the Absence of Site-Specific Data C-9 Beta Air and Skin Dose Factors for Neble Gases C-10 External Dose Factors for Standing on Contaminated Ground C-11 Sector Code Definitions C-12 Exposure to Dose Conversion Factors for Inhalation C-13 Exposure to Dose Conversion Factors for Ingestion l
l LIST OF FIGURES FOR TIIE ODCM GENERICSECTIONS l
l SECTION FIGURE NUMBER TITLE l Chapter 2 2-1 Simplified Flow Chart of Offsite Dose Calculations Chapter 3 3-1 Radiation Exposure Pathways to Humans l
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Revision 2.0 April 1999 CHAPTER 1 1.0 Introduction The Offsite Dose Calculation Manual (ODCM) presents a discussion of the following:,
. The basic concepts applied in calculating offsite doses from nuclear plant effluents.
- The regulations and requirements for the ODCM and related programs
. The methodology and parameters for the offsite dose calculations used by the nuclear power stations to assess impact on the environment and compliance with regulations.
The methodology detailed in this manualis intended for the calculation of radiation doses during routine (i.e., non-accident) conditions. The calculations are normally performed using a computer program.
Manual calculations may be performed in lieu of the computer program.
The dose effects of airborne radioactivity releases predominately depend on meteorological conditions (wind speed, wind direction, and atmospheric stability). For airbome effluents, the dose calculations prescribed in this manual are based on historical average atmospheric conditions. This methodology is appropriate for estimating annual average dose effects and is stipulated in the Bases Section of the '
Radiological Effluent Technical Standards (RETS) of all Comed nuclear power stations.
1.1 STRUCTURE OF THIS MANUAL This manualis the ODCM for all Comed nuclear power stations. It is divided into two parts. The material in the first part is generic (applicable to more than one station) and consists of Chapters 1 through 7 and Appendices A through C. The materialin the second part is station (or site) specific.
Therefore, there are six separate sets of station-specific sections each containing three chapters I (chapters 10,11,12) and an appendix (App. F).
The chapters of the generic section provide a brier introduction to and overview of Comed's offsite dose calculation methodology and parameters. The generic section appendices, Appendices A and B, provide detailed information on specific aspects of the methodology. Appendix C contains tables of values of the generic parameters used in offsite dose equations.
The station-specific section provides specific requirements for the treatment and monitoring of radioactive effluents, for the contents of the Radiological Environmental Monitoring Program (REMP) and the Radiological Effluent Technical Standards (RETS). These three programs are detailed in ODCM Chapters 10,11 and 12 respectively. Appendix F contains tables of values for the station-specific parameters used in the offsite dose equations. References are provided as required in each station-specific chapter and appendix.
An ODCM Bases and Reference Document (see Reference 101) provides description of the bases for the methodology and parameters discussed in the generic section of the ODOM. This is a stand-alone document and is not considered to be a part of the ODCM.
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Revision 2.0 April 1999 CHAPTER 2 CT t
REGULATIONS AND GUIDELINES V' ""
2.0 INTRODUCTION
I This chapter of the ODCM serves to illustrate the regulations and requirements that define and are applicable to the ODCM. Any information provided in the ODCM concerning specific regulations are not a substitute for the regulations as found in the CFR or Technical Specifications.
2.1 CODE OF FEDERAL REGULATIONS Various sections of the Code of Federal Regulations (CFR) require nuclear power stations to be designed and operated in a manner that limits the radiation exposure to members of the public. These I sections specify limits on offsite radiation doses and on effluent radioactivity concentrations and they also require releases of radioactivity to be "As Low As Reasonably Achievable". These requirements I are contained in 10CFR20,10CFR50 and 40CFR190. In addition,40CFR141 imposes limits on the l concentration of radioactivity in drinking water provided by the operators of public water systems. I 2.1.1 10CFR20, Standards for Protection Against Radiatior' This revision of the ODCM addresses the requirements of 10CFR20. The 10CFR20 dose limits are summarized in Table 2-1.
2.1.2 Design Criteria (Appendix A of 10CFR50)
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'v Section 50.36 of 10CFR50 requires that an application for an operating license include proposed Technical Specifications. Final Technical Specifications for each station are developed through negotiation between the applicant and the NRC. The Technical Specifications are then issued as a part of the operating license, and the licensee is required to operate the facility in accordance with them.
Section 50.34 of 10CFR50 states that an application for a license must state the principal design criteria of the facility. Minimum requirements are contained in Appendix A of 10CFR50.
2.1.3 ALARA Provisions (Appendix I of 10CFR50)
Sections 50.34a and 50.36a of 10CFR50 require that the nuclear plant design and the station RETS have provisions to keep levels of radioactive materials in effluents to unrestricted areas "As Low As Reasonably Achievable"(ALARA). Although 10CFR50 does not impose specific limits on releases, Appendix 1 of 10CFR50 does provide numerical design objectives and suggested limiting conditions for operation.
According to Section I of Appendix I of 10CFR50, design objectives and limiting conditions for operation, conforming to the guidelines of Appendix l "shall be deemed a conclusive showing of compliance with the "As Low As Reasonably Achievable" requirements of 10CFR50.34a and 50.36a."
An applicant must use calculations to demonstrate conformance with the design objective dose limits of Appendix 1. The calculations are to be based on models and data such that the actual radiation exposure of an individualis "unlikely to be substantially underestimated"(see 10CFR50 Appendix 1, Section Ill.A.1).
The guidelines in Appendix I call for an investigation, corrective action and a report to the NRC whenever the calculated dose due to the radioactivity released in a calendar quarter exceeds one-half of an annual design objective. The guidelines also require a surveillance program to monitor releases, monitor the environment and identify changes in land use.
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Revision 2.0 April 1999 2.1.4 40CFR190, Environmental Radiation Protection Standards for Nuclear Power Operations
/N Under an agreement between the NRC and the EPA, the NRC stipulated to its licensees in Generic Letter h 79-041 that " Compliance with Radiological Effluent Technical Specifications (RETS), NUREG-0472 (Rev.2) for PWR's or NUREG-0473 (Rev.2) for BWR's, implements the LWR provisicIns to meet 40CFR190". (See Reference 103 and 49.)
The regulations of 40CFR190 timit radiation doses received by members of the public as a result of operations that are part of the uranium fuel cycle. Operations must be conducted in such a manner as to provide reasonable assurance that the annual dose equivalent to any member of the public due to radiation and to planned discharges of radioactive materials does not exceed the following limits:
e 25 mrem to the whole body e 75 mrem to the thyroid e 25 mrem to any other organ An important difference between the design objectives of 10CFR50 and the limits of 40CFR190 is that 10CFR50 addresses only doses due to radioactive effluents. 40CFR190 limits doses due to effluents and also to radiation sources maintained on site. See Section 2.4 for further discussion of the differences between the requirements of 10CFR50 Appendix 1 and 40CFR190.
2.1.5 40CFR141, National Primary Drinking Water Regulations The following radioactivity limits for community water systems were established in the July,1976 Edition of 40CFR141:
. Combined Ra-226 and Ra-228: 5 5 pCi/L.
. Gross alpha (particle activity including Ra-226 but excluding radon and uranium): 515 pCi/L.
. The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annual dose equivalent to the whole body d or any internal organ greater than 4 mrem /yr.
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The regulations specify procedures for determining the values of annual average radionuclide concentration !
which produce an annual dose equivalent of 4 mrem. Radiochemical analysis methods are also specified.
The responsibility for monitoring radioactivity in a community water system falls on the supplier of the water.
l However, some of the Comed stations have requirements related to 40CFR141 in their specific RETS. For i calculational methodology, see Section A.6 of Appendix A.
2.2 RADIOLOGICAL EFFLUENT TECHNICAL STANDARDS The Radiological Effluent Technical Standards (RETS) were formerly a subset of the Technical Specifications. They implement provisions of the Code of Federal Regulations aimed at limiting offsite radiation dose. The NRC published Standard Radiological Effluent Technical Specifications for PWRs (Reference 2) and for BWRs (Reference 3) as guidance to assist in the development of technical !
specifications. These documents have undergone frequent minor revisions to reflect changes in plant design and evolving regulatory concerns. The Radiological Effluent Technical Specifications have been removed from the Technical Specifications and placed in the ODCM as the Radiological Effluent Technical Standards (RETS) (see Reference 90). The RETS of each station are similar but not identical to the guidance of the Standard Radiological Effluent Technical Specifications.
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2.2.1 Categories l
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LJ The major categories found in the RETS are the following:
e Definitions "
A glossary of terms (not limited to the ODCM).
. Instrumentation This section states the Operability Requirements (OR) for instrumentation performance as well as the associated Surveillance Requirements. The conservative alarm / trip setpoints ensure regulatory compliance for both liquid and gaseous effluents. Surveillance requirements are listed to ensure ors are met through testing, calibration, inspection and calculation. Also l included are the bases for interpreting the requirements. The Operability Requirement (OR) is l the ODCM equivalent of a Limiting Condition for Operation (LCO) as defined in both the NRC published Standard Radiological Effluent Technical Specifications and the stations' Technical Specifications.
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. Liquid Effluents This section addresses the limits, special reports and liquid waste treatment systems required to substantiate the dose due to liquid radioactivity concentrations to unrestricted areas.
Surveillance Requirements and Bases are included for liquid effluents.
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. Gaseous Effluents !
This section addresses the limits, special reports and gaseous radwaste and ventilation I exhaust treatment systems necessary for adequate documentation of the instantaneous offsite l radiation dose rates and doses to a member of the public. Surveillance Requirements and l Bases are included for gaseous effluents.
. Radiological Environmental Monitoring Program (V) This section details the Radiological Environmental Monitoring Program (REMP) involving sample collection and measurements to verify that the radiation levels released are minimal.
This section describes the annualland use census and participation in an interlaboratory comparison program. Surveillance Requirements and Bases are included for environmental monitoring.
. Reports and Records This section serves as an administrative guide to maintain an appropriate record tracking system. The management of procedures, record retention, review / audit and reporting are discussed.
1 2.3 OFFSITE DOSE CALCULATION MANUAL The NRC in Generic Letter 89-01 defines the ODCM as follows (not verbatim)(see Reference 90):
The Offsite Dose Calculation Manual (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of tne Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports.
Additional requirements for the content of the ODCM are contained throughout the text of the RETS.
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Revision 2.0 April 1999 2.4 OVERLAPPING REQUIREMENTS I p
( In 10CFR20,10CFR50 and 40CFR190, there are overlapping requirements regarding offsite radiation dose and dose commitment to the whole body. In 10CFR20.1301 the total eMective dose equivalent to a member of the public is limited to 100 mrem per calendar year, in addition, Appendix 1 to 10CFR50 establishes design objectives on annual total body dose or dose commitment of 3 mrem per reactor for liquid effluents and 5 mrem per reactor for gaseous effluents (see 10CFR50 Appendix 1, Sections ll.A and ll.B.2(a)). Finally,40CFR190 limits annual whole body dose or dose commitment to a member of the public to 25 mrem due to all uranium fuel cycle operations.
While these dose limits / design objectives appear to overlap, they are different and each is addressed separately by the RETS. Calculations are made and reports are generated to demonstrate compliance to all regulations. Refer to Tables 2-1,2-2 and 2-3 for additional information regarding instantaneous ,
effluent limits, design objectives and regulatory compliance.
2.5 Dose Receiver Methodology Table 2-2 lists the location of the dose recipient and occupancy factors, if applicable. In general the dose receiver spends time in the locations that result in maximum direct dose exposure and inhales and ingests radioactivity at locations that yield maximum pathway doses. Thus, the dose calculated is very conservative compared to the " average" (or typical) dose recipient who does not go out of the way to maximize radioactivity uptakes and exposure.
Finally Table 2-3 relates the dose component (or pathway) to specific ODCM equations and the appropriate regulation.
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1 Revision 2.0 April 1999 Table 2-1
( Regulatory Dose Limit Matrix 1
REGULATION DOSE TYPE DOSE LIMIT (s) ODCM EQUATION Airborne Releases: (quanerty) (annual) 10CFR50 App.13 Gamma Dose to Air due to Noble Gas 5 mrad 10 mrad A-1 Radionuclides (per reactor unit)
Beta Dose to Air Due to Noble Gas 10 mrad 20 mrad A-2 Radionuclides (per reactor unit)
Organ Dose Due to Specified Non-Noble 7.5 mrem 15 mrem A-13 Gas Radionuclides (per reactor unit)
Total Body and Skin Total Body 2.5 mrern 5 mrem A-6 Dose (if air dose is exceeded)
Skin 7.5 mrem 15 mrem A-7 Technical Specifications Whole Body Dose Rate Due to Noble Gas 500 mrem /yr A-8 Radionuclides (instantaneous limit, per '
site)
Skin Dose Rate Due to Noble Gas 3,000 mrem /yr A-9 Radionuclides (instantaneous limit, per site)
(" Organ Dose Rate Due to Specified Non- 1,500 mrem /yr A-28 Noble Gas Radionuclides (instantaneous limit, per site)
Liquid Releases: (quaneriy) (annual) 10CFR50 App.13 Whole (Total) Body Dose 1.5 mrem 3 mrem A-29 (per reactor unit)
Organ Dose (per reactor unit) 5 mrem 10 mrem A-29 Technical Specifications The concentration of radioactivity in liquid Ten (10) times the effluents released to unrestricted areas concentration values A-32 listed in 10CFR20 Appendix B; Table 2, Column 2, Table C-6 of Appendix C for Noble Gases Total Doses ':
l 10 CFR 20.1301 (a)(1) Total Effective Dose Equivalent 100 mrem /yr A-38 10CFR20.1301 (d) Whole Body Dose 25 mrem /yr A-35 and 40CFR190 Thyroid Dose 75 mrem /yr A-37 Other Organ Dose 25 mrem /yr A-37 Other Limits8:
l 40CFR141 Whole Body Dose Due to Dnnking Water 4 mrem /yr A-30 l From Public Water Systems Organ Dose Due to Drinking Water From 4 mremlyr A-30 Public Water Systems i These doses are calculated considenng all sources of radiation and radioactivity in effluents.
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Revision 2.0 April 1999 These lenits are not directly apphcable to nuclear power stations. They are apphcable to the owners or operators of public O g water systems. However, the RETS of some of the Comed nuclear power stations require assessrnent of comphance with these hmits. For additionalinformation, see Section A 6 of Appendix A.
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2 Note that 10CFR50 provides design objectives not limits.
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Revision 2.0 April 1999 TABLE 2 2 f DOSE ASSESSMENT RECEIVERS Location; Occupancy if Dose Component or Pathway Different than 100%
" Instantaneous" dose rates from airborne Unrestricted area boundary location that results in radioactivity the maximum dose rate
" Instantaneous" concentration limits in liquid Point where liquid effluents enter the unrestricted effluents area Annual average concentration limits for liquid Point where liquid effluents enter the unrestricted effluents area Direct dose from contained sources Receiver spends part of this time in the controlled area and the remainder at his residence or fishing nearby; occupancy factor is considered and is site-specific. See Appendix F, Table F-8 for occupancy factors.
Direct dose from airborne plume Receiver is at the unrestricted area boundary ,
location that results in the maximum dose.
Direct dose from radioactivity deposited on the Receiver is at the unrestricted area boundary )
ground location with the highest D/Q.
Inhalation dose from airborne effluents Receiver is at the unrestricted area boundary location that results in maximum dose.
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Ingestion dose from vegetables Receiver eats vegetables from the garden at the nearest residence with the highest D/0 Ingestion dose from milk Receiver drinks milk from the near-site dairy farm with the highest D/O ingestion dose from meat Receiver eats meat produced at the near-site farm with the highest D/Q Ingestion dose from drinking water' The drinking water pathway is considered as an additive dose component in this assessment only if the public water supply serves the community I immediately adjacent to the plant.
Ingestion dose from eating fish The receiver eats fish from the receiving body of water (lake or river)
Total Organ Doses Summation of ingestion / inhalation doses Total Effective Dose Equivalent Summation of above data At present, only the Braidwood and Zion station assessments include the drinking water pathway for 10CFR20 comphance.
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April 1999 l
TABLE 2-3
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DOSE COi..PONENT/ REGULATION MATRIX Regulation in which dose component is utilized Dose Component or Reference equation; 10CFR50 P2thway Comments 10CFR20 40CFR190 App.l l " Instantaneous" dose rates from airbome A-8: Whole body l ridioactivity A-9: Skir. X(2) l A-28: Organ l
" Instantaneous" concentration limits in liquid Ten times the limits of Table 2, affluents Col. 2,10CFR20, Appendix B to X(2)
$$20.1001 - 20.2402 Table C-6 i of Appendix C for Noble Gases l l Annual average concentration limits for liquid 10CFR20, Appendix B to affluents $920.1001 - 20.2402(2) X(3)
Direct dose from contained sources A-34 X X Direct dose from airbome plume A-1: Gamma air dose X A-2: Beta air dose X A-6: Whole body dose X X X A-7: Skin dose X Direct dose from radioactivity deposited on tha ground A-14 X X X
[ Inhalation dose from airborne effluents G A-17 (1) X X X Ingestion dose from vegetables A-23 and A-18 (1) X X X ingestion dose from milk A-25 and A-18 (1) X X X Ingestion dose from meat A-27 and A-18 (1) X X X I
i Ingestion dose from drinking water i A-30 (1) X X X {
ingestion dose from eating fish ;
Total Organ Doses A-13 X X Total Effective Dose Equivalent A-38 X 1
Ingestion / inhalation dose assessment is evaluated for adult / teen / child and infant for 10CFR50 Appendix I compliance l and for an adult for 10CFR20/40CFR100 compliance. Ingestion / inhalation dose factors are taken from Reg. Guide j 1.109 (Reference 6) for 10CFR50 Appendix I compliance and FGR 11 (Reference 93) for 10CFR20/40CFR190 compliance.
2 Technical Specifications for most stations have been revised to allow 10 times the 10CFR20 value or specifically states the maximum instantaneous dose rate limit.
3 Optional for 10CFR20 compliance.
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Revision 2.0 April 1999 Floure 2-1 Simplified Chart of Offsite Dose Calculations 8 1 ,
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Category Radionuclides Pathway Text Receptor Code and Limits Frequency of Section Calculation' Airborne Releases:
Noble Gases: Plume f A 1.3.1 Total Body RETS: As Required by 500 mremlyr Instantaneous Noble Gases. Plume f and p* A.1.3.2 Skin RETS: Station 3000 mrem /yr instantaneous Procedure Noble Gases: Plume f A 1.2.1 10CFR50, 8 5 mrad /qtr,10 mrad /yr i
Noble Gases: Plume p* A.1.2.2 Air d 8 Monthly 10CFR50: l 10 mrad /qtr 20 mradlyr Non-Noble Inhalation
- A.1.5 Adult RETS: As required by )
Gases: (Any Organ) 1500 mrem /yr instantaneous Statio i Procedure Ground Deposition
- A 1.4.1
-. Whole body Non-Noble Inhalation A.1 4.2 Gases 10CFR50: 3 Leafy Vegetables
- A.1.4 3.1 4 Age groups (All Monthly and Organs) Annually Produce
- A.1.4.3.1 7.5 mrem /qtr.15 mrem /yr Milk. A.1.4.3.2 Meat 8 A.1.4 3.3 Liquid Releases:
All Water A 2.2 RETS,10 times 10CFR20 As Required by Appendix B. Table 2; Col 2 Station Table C-6 of Appendix C for Procedure Noble Gases Non-Noble Water' and A.2.1 Whole Body 10CFR50:
3 Gases 7,, 1.5 mrem /qtr 3 mrem /yr Non-Noble Water' and A.2 1 4 Age Groups (All 10CFR50 :
8 Monthly Gases Organs) 5 mrem /qtt 10 mrem /yr Non-Noble Water
- A6 Adult (Whole Body 40CFR141: When Required Gases and all Organs) 4 mrem /yr by RETS Whole Body 40CFR190.
25 mrem /yr Fuel All All releases plus A.3 Thyroid (Adult) 40CFR190. Annually direct radiation 75 mrem /yr Cycle: from contained sources All Other Organs 40CFR190.
(Adult) 25 mremlyr TEDE: All Extemal (DDE) + A43 Total Body + 10CFR20. Annually Internal (CEDE) organs (Adutt) 100 mrem /yr g lodem/genenc/rev2 0/ 10
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Floure 2-1 (Cont'd) l V Notes for Fiaure 2-1: -
- 1. Definition: Monthly means at least once per 31 days or once per month. See station RETS for exact requirements.
- 2. Addmonal Calculations: In addition to the calculations shown in this figure, monthly projections of doses due to radioactive materials are required for gaseous and hquid effluents from ComEo nuclear power stations. See Sections A 1.6 and A.2.5 of Apoendix A.
Also, projections of drinking water doses are required at least once per 92 days for Dresden and Quad Cites. See Section A.7 of Appendix A.
- 3. 10 CFR 50 prescribes design objectives not limits.
- 4. If the air dose is exceeded, doses to the total body and skin are calculated. Total body objectives are 2.5 mrem /qtr and 5.0 mrem / year; the skin dose objectives are 7.5 mrem /qtr and 15 mrem / year.
a Evaluated at the unrestncted area boundary, b Evaluated at the location of maximum offsite X/Q.
c Evaluated at the location of maximum offsite D/O.
d Evaluated for the nearest producer within 5 miles or if there is none a hypothetical producer at 5 miles.
e Evaluated for the nearest downstream community water supply as specifed in Table A-3 of Appendix A. The flow and dilution factors specifed in Table F-1 of Appendix F are used.
f Evaluated for fish caught in the near-feld region downstream of plant using the flow and dilution factors specifed in Table F-1 of Appendix F.
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Revision 2.0 April 1999 CHAPTER 3
/Q EXPOSURE PATHWAYS V
3.0 INTRODUCTION
Figure 3-1 illustrates some of the potential radiation exposure pathways to humans due to routine operation of a nuclear power station. These exposure pathways may be grouped into three categories:
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Airborne Releases Exposures resulting from radioactive materials released with gaseous effluents to the atmosphere.
Liquid Releases Exposures resulting from radioactive materials released with liquid discharges to bodies of water.
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Radiation from Contained Sources Exposures to radiation from contained radioactive sources.
When performing radiation dose calculations, only exposure pathways that significantly contribute (2 10%) to the total dose of interest need to be evaluated. The radiation dose from air and water exposure pathways are routinely evaluated. (see Regulatory Guide 1.109, Reference 6.)
3.1 AIRBORNE RELEASES g For airborne releases of radioactivity (Figure 3-1), the NRC considers the following pathways of ra6a timi exposure of persons:
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- Radiation from radioactivity airborne in the effluent plume.
. Radiation from radioactivity deposited by the plume on the ground.
e Ingestion of radioactivity on, or in, edible vegetation (from direct plume deposition or from
, the transfer of radioactivity deposited on the soil).
. Ingestion of radioactivity that entered an animal food product (milk or meat) because the animal ingested contaminated feed, with the contamination due either to direct deposition on foliage or to uptake from the soil.
e Inhalation of radioactivity in the plume.
Comed considers these same pathways with the exception that the transfer of radioactivity from soil to vegetation is omitted. This pathway was determined to be of minimal significance in relation to the other airborne exposure pathways.
3.2 LIQUID RELEASES For liquid releases of radioactivity (Figure 3-1), the NRC considers the following pathways of radiation exposure of persons:
. Direct exposure to radioactivity in water while engaging in recreational activities such as swimming and boating.
. Exposure to radiation from shoreline sediments contaminated by water containing radioactivity from station liquid discharges.
e ingestion of edible vegetation contaminated by irrigation with water containing radioactivity from station' liquid discharges.
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Revision 2.0 April 1999
. Ingestion of radioactivity from animal food products (milk or meat) resulting from the animal either drinking water contaminated by radioactive liquid effluents or from the animal eating O feed or vegetation contaminated by irrigation with such water.
. ingestion of aquatic food (e.g., fish) obtained from the body of water to which radioactive station effluents are discharged.
. Ingestion (drinking) of potable water contaminated by radioactive liquid effluents discharged from the station.
Comed considers the latter two of these pathways as significant. For the aquatic food pathway, only fish is considered since it is the only significant locally produced aquatic food consumed by humans.
The stations omit the pathways involving irrigation and animal consumption of contaminated water because these pathways were determined to be insignificant. The stations also omit the pathway of radiation exposure from shoreline sediment because this pathway was also found to be insignificant (see ODCM Bases and Reference Document, Section O.3.2).
The stations have also verified that the dose contribution to people participating in water recreational activities (swimming and boating) is negligible. (See ODCM Bases and Reference Document, Reference 101, Tables O-3 and O-4) This pathway was not addressed explicitly in Regulatory Guide 1.109. Thus, the stations also omit dose assessments for the water recreational activities pathway.
Periodically the Illinois Army Corps of Engineers dredges silt and debris from the river beds near Comed nuclear stations. As a part of the land use census, Comed will determine if the Corps performed dredging within one mile of the discharge point. If so, Comed will obtain spoils samples, through it's REMP vendor, for analysis. The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable. j O in addition, to assure that doses due to radioactivity in liquid effluents will be ALARA, concentrations will be limited to ten times (10x) the values given in 10CFR20 Appendix B, Table 2; Column 2. Specific limitations for concentrations of entrained noble gases are contained in the stations' Radiological Effluent Technical Standards (RETS). ]
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3.3 RADIATION FROM CONTAINED SOURCES '
Radioactivity contained within tanks, pipes or other systems and contained radioactive material or waste stored on site can produce radiation at offsite locations. Annual offsite radiation doses near the stations due to such sources were judged to be negligible in comparison with applicable limits except for doses due to BWR turbine skyshine and potential doses due to radioactive waste storage facilities (excludes radioactive material storage). See ODCM Bases and Reference Document, Reference 101. Changes or modifications to the power station that may impact the offsite dose through increases to the direct radiation levels need to be evaluated on a case by case basis and added to Chapter 12 of the station annex to the ODCM when applicable (e g.; the Old Steam Generator Storage Faciinies).
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Revision 2.0 April 1999 Figure 31 Radiation Exposure Pathways to Humans Nuclear Power Plant Radiation from m Contained Sources Llauld Effluents Releases
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P ab a er Airborne Effluents 4 usi Fo m ingestion by ingestion of .
F Anirnals Milk and Meat -
Irngation onto Vegetation 4 ingestion ,
M Irngation of Soil l recreational activities in water I Deposition onto Shoreline Sediment Direct Radiation Exposure r
Humans Inhalation J I
Deposition onto Vegetation l
4 l A Ana als ( g cows) k an at Deposition onto Direct Radiation Soil Exposure Direct Radiation , . .
Exposure - '
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'a Revision 2.0 April 1999 CHAPTER 4
/ METHODOLOGY V]
4.0 INTRODUCTION
This chapter provides an introduction to the methodology used by Comed to calculate offsite radiation doses resulting from the operation of nuclear power stations. Additional explanation and details of the methodology are provided in Appendices A and B. Appendix A discusses each dose limit in the RETS and provides the associated assessment equations. Appendix B describes methods used to determine values of parameters included in the equations.
4.1 IMPORTANT CONCEPTS AND PARAMETERS 4.1.1 Dose and Dose Commitment The dose calculation equations contained in the ODCM are based on two types of evoosure to radiation; external and internal exposure. The first type of exposure is that resulting from radioadwe sources external to the body (including radiation emanating from an effluent plume, radiation emanating from radioactivity deposited on the ground and radiation emanating from contained sources (also referred to as direct radiation)). Exposure to radiation external to the body only occurs while the source of the radioactivity is present. For example, once a plume containing the airbome radioactivity passes by the individual, the external exposure to radiation ends.
The second type of exposure occurs when the source of radioactivity is inside the body, or internal.
Radiation can enter the body by breathing air containing the radioactivity, or by eating food or drinking water containing radioactivity. These latter processes are also referred to as ingesting radioactivity (ingestion). Once radioactivity enters the body and becomes internal radiation, a person will continue to
[S V) receive radiation dose until the radioactivity has decayed or is eliminated by biological processes. The dose from this type of exposure is also termed dose commitment, meaning that the person will continue to receive dose even-though the plume containing the radioactivity has passed by the individual, or even-though the individual is no longer drinking water containing radioactivity.
The regulations addressed by the ODCM may require assessment of either type of exposure to radiation or of both types in summation.
4.1.2 Exposure Pathways All of the exposure pathways are discussed in Chapter 3. This section presents the exposure pathways addressed by Comed nuclear stations in the ODCM and associated software.
For releases of radioactivity in airborne effluents the primary pathways are the following:
. Direct radiation from an effluent plume.
Direct radiation from radioactivity deposited on the ground by a plume.
. inhalation of radioactivity in a plume.
ingestion of radioactivity that entered the food chain from a plume that deposited the radioactivity on vegetation.
For releases of radioactivity in liquid effluents, the exposure pathways considered are human consumption of water and fish.
When determining total doses, as required by 10CFR20 and 40CFR190, the BWR stations also consider O direct radiation due to skyshine from nitrogen-16 (NS) in turbines and associated piping. All nuclear g /odem/generec/rev2 0/ 15
Revision 2.0 April 1999 power stations will consider exposure to radiation emanating from onsite radwaste storage facilities when they are put into operation.
41.3 Categories of Radioactivity Radionuclide content of effluent releases from nuclear power stations can be categorized according to the characteristics of the radionuclides. In evaluating doses associated with a particular pathway, only those categories of radionuclides that significantly contribute to the dose need to be included in the dose calculations (See Section 3.0). The categones of radionuclides considered by the Comed nuclear power stations for each of the airborne pathways are summarized in Table 4-1. Selection of the significant airborne pathways was based on the following:
. The requirements in the RETS (see discussion in Appendix A)
. Applicable regulatory guidance (References 6 and 14), and A study of the potential radiological implications of nuclear facilities in the upper Mississippi River basin (Reference 20).
Calculations were used to determine which radionuclides were significant for a particular pathway. For example, in the case of direct radiation from a plume of airborne radioactivity, it was found that radiation from noble gases is significant and radiation from radioactive iodine was not. The dose rate per unit of airborne radioactivity concentration is about the same for noble gases and radioactive iodine since they emit comparable types and energies of radiation. However, the quantity of noble gas radioactivity (Ci) released in routine nuclear plant operation typically exceeds the quantity of radioactive iodine by a factor of about 10,000.
As another example, consider the inhalation pathway. Here, the calculations showed that the dose commitment due to radioactive iodine was significant but the dose commitment due to radioactive noble gases was not significant and can be excluded from the compliance calculations for the inhalation b
V pathway. This is true despite the fact that a much larger quantity of noble gas radioactivity is released.
The reason for this is that the solubility of noble gas in body tissue is very low, where-as the inhaled radioactive iodine does concentrate in specific body organs such as the thyroid (see the discussion on Pages 228 and 231 to 234 of Reference 38).
4.1.4 Release Point Classifications In the determination of the dose consequence from an airborne release of radioactivity, it is required to know the height of the release of the effluent plume relative to the ground and where the dose recipients are located. This correlation is very important because the radiation dose calculated is greatly impacted by the distance separating the dose recipient and the radioactive plume.
It has been found that the height an effluent plume maintains as it travels above the ground is related to I the elevation of the release point and to the height of structures immediately adjacent as follows: 1 if the elevation of the release point is sufficiently above the height of any adjacent structures, the plume will remain elevated for considerable distances.
If the elevation of the release point is at or below the heights of adjacent structures, the plume is likely to be caught in the turbulence of the wakes created by wind passing over the buildings. The plume elevation would then drop to ground level.
If the elevation of the release point is not significantly above the heights of adjacent structures, then the plume may be elevated or at ground level.
/ For the calculations of this manual, each established release point has been designated as belonging to Q] one of three release point classifications:
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Revision 2.0 .
April 1999 l Stack (or Elevated) Release Points (denoted by the letter S or subsenpt s)
These are release points approximately twice the height of adjacent solid structures.
Releases are treated as elevated releases unaffected by the" presence of the adjacent I structures.
l .
' Ground Level Release Points (denoted by the letter G or subscript g)
These are release points at ground level or lower than adjacent solid structures. l l
Releases are considered drawn into the downwind wake of these structures and are l l treated as ground level releases.
Vent (or Mixed Mode) Release Points (denoted by the letter V or subscript v)
These are release points as high or higher than adjacent solid structures but lower than l twice the structure's heights. These releases are treated as a mixture of elevated and ground level releases. The proportion of the release attributed to either elevated or ground level in a vent release is determined by the ratio of stack exit velocity to the wind speed (see Section B.1.2.4 of Appendix B).
The definitions of these classifications are based on Regulatory Guide 1.111 (Reference 7). A list of the l )
classifications of specific airborne release points for each of the Comed nuclear power stations is '
contained in Table A-2 in Appendix A.
4.1.5 Historical Average Atmospheric Conditions
,m The dispersion characteristics of airborne effluents from a nuclear power station are dependent on
(,b weather conditions. Meteorological factors that directly affect the concentration of airborne radioactivity in a plume include the following:
. Wind Direction The concentration of radioactivity is highest in the direction toward which the wind is blowing. l l
. Wind Speed Greater wind speeds produce more dispersion and consequently lower concentrations of radioactivity.
. Atmosphenc Turbulence The greater the atmosphenc turbulence, the more a plume spreads both vertically and horizontally. For calculations in this manual, the degree of turbulence is classified by use of seven atmospheric stability classes, designated A (extremely unstable) through G (extremely stable). The seven classes and some of their characteristics are listed in Table C-4 of Appendix C.
Meteorological conditions strongly impact the values of various parameters applied in the dose calculations of this manual. These include:
The Relative Concentration Factor X/O (Section 4.1.6)
. The Relative Deposition Factor D/O (Section 4.1.7) a g iodem/genenenen-o/ 17
Revision 2.0 April 1999 e
The Gamma Air Dose Factor (Section 4.2.1) e The Whole Body Dose Factor (Section 4.2.3)
Some bases sections of both the Standard Radiological Effluent Technical Specifications (guidance document) and the RETS specify that dose calculations be based on "historidial average atmospheric conditions". Therefore, this manual provides values for the above parameters that are based on station-specific historical average meteorological conditions. These values were obtained by averaging hourly values of the parameters over a long-term, several-year, period of record. The averaging period was based on calendar years in order to avoid any bias from weather conditions associated with any one season. The period of record is identified in each of the tables providing the values (see Appendix F).
4.1.6 Relative Concentration Factor XIQ i
A person immersed in a plume of airbome radioactivity is exposed to radiation from the plume and may also inhale some of the radioactivity from the plume. The concentration of radioactivity in air near the exposed person must be calculated to adequately evaluate doses resulting from any inhalation. The relative concentration factor X/O (referred to as " chi over Q") is used to simplify these calculations. X/O ,
is the concentration of radioactivity in air, at a specified location, divided by the radioactivity release rate.
X/O has the following units:
)
Units of X/Q = (pCilm') / (pCi/sec) = sec/m' Station-specific values of X/O are provided for each nuclear power station in Table F-5 of Appendix F.
These values are based on historical average atmospheric conditions (fiee Section 4.1.5).
For each of the release point classifications (eg. stack, vent and ground ievel) and for the 16 compass-direction sectors (N, NNE, etc.), Table F-5 provides the maximum value of X/O for locations at or beyond the unrestricted area boundary.
The value of X/Q for each sector reflects the fraction of time that the wind blew into that sector and the distribution of wind speeds and atmospheric stability classes during that time. Note that the value would be zero if the wind never blew into the sector.
The methodology for determining X/O is discussed in detail in Section B.3 of Appendix B.
4.1J Relative Deposition Factor D/Q As a plume travels away from its release point, portions of the plume may touch the ground and deposit radioactivity on the ground and/or on vegetation. Occurrences of such deposition are important to model since any radioactivity deposited on the ground or on vegetation may directly expose people and/or may be absorbed into food products which can ultimately be ingested by people. The relative deposition factor is used to simplify the dose calculations for these pathways.
The relative deposition factor D/O is the rate of deposition of radioactivity on the ground divided by the radioactivity release rate. Its value was determined for specific conditions. In this manualit has the following units:
Units of D/Q = [(pCilsec)/m') / (pCi/sec) = 1/m' The values of D/O are affected by the same parameters that affect the values of X/Q: release characteristics; meteorological conditions and location (see Section 4.1.6). Station-specific values of D/O are provided for each Comed nuclear power station in Appendix F Tables F 5 and F-6. These values are based on historical average atmospheric conditions (see Section 4.1.5).
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)
E -
Revision 2.0 April 1999 I For each release point classification and for each of the 16 compass-direction sectors (N, NNE, etc.),
Table F 5 provides the maximum value of D/O for locations at or beyond the unrestricted area boundary, s in Table F-6, values of D/O are given for the locations of the nearest milk and meat producers within 5 s miles of the nuclear power station. The methodology for determining D/Q is discussed in Section B.4 of Appendix B.
l 4.1.8 Dose Factors Various dose factors are used in this manual to simplify the calculation of radiation doses. These factors 1 are listed in Table 4-2. Definitions of these factors are given in the remainder of this chapter. Methods of determining their values are addressed in Appendix B.
4.2 AIRBORNE RELEASES 4.2.1 Gamma Air Dose The term ' gamma air dose' refers to the component of dose absorbed by air resulting from the absorption of energy from photons emitted during nuclear and atomic transformations, including gamma rays, x-rays, annihilation radiation, and Bremsstrahlung radiation (see footnote on page 1.109-19 of Regulatory Guide 1.109).
The Gamma Air Dose Factor The gamma air dose factor is the gamma air dose rate divided by the radioactivity release rate. The value of the gamma air dose factor is determined by calculating the gamma dose rate to air (at a specific location and corresponding to a given release rate) and dividing that dose rate by the corresponding I release rate:
Gamma Air Dose Factor = [(mradlyr)/(pCi/se))
The methodology for this calculation is discussed in Section B.5 oi Appendix B. The calculation is complex because the dose rate at any given point is affected by the radioactivity concentration and distance. The value of the gamma air dose factor is also affected by all of the psrameters that affect X/Q: release characteristics, meteorological conditions and location (see Section 4.1.6). Additionally, ;
the value is affected by radiological parameters: the distribution of energies and intensities for gamma emissions from each specific radionuclide and the photon attenuation characteristics of air.
In the ODCM, station-specific values of gamma dose factors are provided for each station in Appendix F, Table F-7. These values are based on historical average atmospheric conditions (see Section 4.1.5).
For the release point classification and for each of the 16 compass-direction sectors Table F 7 provides the maximum value of the gamma air dose factor for noble gas radionuclides at the unrestricted area boundary. The value includes a correction for radioactive decay during transport of the radionuclide from the release point to the dose calculation location, i 4.2.2 Beta Air Dose The term ' beta air dose' refers to the component of dose to air dose resulting from the absorption of energy from emissions of beta particles, mono-energetic electrons and positrons during nuclear and atomic transformations (see the footnote on Page 1.109-20 of Regulatory Guide 1.109).
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l Revision 2.0 April 1999 The Beta Air Dose Factor The beta air dose factor is the beta air dose rate divided by the concentration of radioactivity in air at the (A) dose calculation location. Values of the beta air dose factor are different for each radionuclide because of the differences in electron-emission spectra. Values for the beta air dose f5ctors of 15 noble gas radionuclides are provided in Appendix C Table C-9.
The values of beta air dose factors are independent of nuclear power station because the size of a plume, at or beyond the restricted area boundary, is large compared to the range of the beta particle radiation. Therefore, the radioactivity concentration can be assumed to be constant over the entire volume surrounding a given beta dose calculation point. One can then define the beta air dose factor as tile beta dose rate per unit of air radioactivity concentration. This relationship is independent of station-specific parameters. In contrast to this, the gamma air dose may depend on radioactivity concentration hundreds of feet away from the dose calculation point (see Section 4.2.1). Therefore, when determining the value of the gamma air dose factor, the shape of the plumt 'er a large region must be considered. Plume shape does depend on station-specific parameters t 7 o eteorology and release point classification and therefore values of the gamma air dose factor sn-specific.
4.2.3 Whole Body Dose and Dose Rate Whole Body Dose Equation A-6 of Appendix A is used to calculate dose to the whole body from noble gas radionuclides released in gaseous effluents. The deep dose equivalent (DDE) (oi whole body dose) equation is similar to that used to calculate gamma air dose (Equation A-1 of Appendix A).
Whole Body Dose Rate Equation A-8 of Appendix A is used to calculate dose rate to the whole body. The assumptions used for this equation are the same as those used in the calculation of whole body dose (Equation A-6 of Appendix A) except that any shielding benefit (dose attenuation) provided by residential structures is not applied. Since the calculation is for the maximum instantaneous dose rate, the dose recipient may be out of doors when exposed and would not be shielded from the exposure by any structural material.
The Whole Body Dose Factor !
The whole body dose factor is the whole body dose rate divided by the radioactive release rate. Values ,
for the whole body dose factor depend on the same parameters as those that affect the gamma air dose j factor (see Section 4.2.1). The whole body dose factor is a 10CFR50 term that yields a Deep Dose I Equivalent when applied to the radioactive release rate.
]
Station-specific values for the whole body dose factor are provided for each Comed nuclear power station in Appendix F. Table F-7. These values are based on historical average atmospheric conditions ,
(see Section 4.1.5). For each of 15 noble gas radionuclides, for the release point classifications, and for '
each of the 16 compass-direction sectors, Table F-7 provides the maximum value of the whole body dose factor at the unrestricted area boundary. These values include a correction for radioactive decay <
dunng transport of the radionuclide from the release point to the dose calculation location. I The methodology for determining whole body dose factors is addressed in Section B.6 of Appendix B. ;
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1 Revision 2.0 April 1999 4.2.4 Skin Dose and Dose Rate i
Skin Dose v Equation A-7 of Appendix A is used to calculate dose to skin from noble gas Yadionuclides released in gaseous effluents. The skin dose is also referred to as the ' shallow dose equivalent' (SDE). The SDE is the summation of dose to the skin from beta and gamma radiation.
The equation for beta dose to skin is similar to that used to calculate beta dose to air (Equation A-2 of Appendix A) except that beta skin dose factors are used instead of beta air dose factors. The beta skin dose factor differs from the beta air dose factor by accounting for the attenuation of beta radiation by the I dead layer of skin. The dead layer of skin is not susceptible to radiation damage and therefore is not of concern. The beta dose to the skin from non-noble gases is insignificant and is not calculated for the reason described in Section 4.1.3. When calculating the beta contribution to skin dose, no reduction is included in the calculations due to shielding provided by occupancy of residential structures.
l The equation for gamma dose to skin is similar to that used to calculate gamma dose to air except for the following:
. Equation A-7 of Appendix A includes a units conversion factor 1.11 rem / rad to convert from units of gamma air dose (rad) to unds of tissue dose equivalent (rem).
- Equation A-7 of Appendix A includes a dimensionless factor of 0.7 to account for the shielding due to occupancy of residential structures.
Equation A-7 of Appendix A uses gamma air dose factors not gamma whole body dose factors. When calculating gamma dose to skin, no reduction is applied for the attenuation of radiation due to passage through body tissue (dead layer of skin).
Skin Dose Rate Equation A-9 of Appendix A is used to calculate dose rate to skin. The assumptions are the same as those used in the calculation of skin dose (Equation A-7 of Appendix A) except that no credit is taken for shielding of gamma radiation by residential structures. The dose recipient may be outdoors when exposed and the maximum instantaneous dose rate is of concern.
The Skin Dose Factor As with the beta air dose factor, values of the beta skin dose factors are different for different radionuclides but do not vary from station to station. Values of the beta air dose factors and skin dose factors are provided in Table C-9 of Appendix C for 15 noble gas radionuclides.
4.2.5 Ground Radiation Equations A-14 through A-16 of Appendix A are used to calculate the deep dose equivalent (whole body dose) due to non-noble gas radionuclides released in gaseous effluents and deposited on the ground.
Comment Note that if there is no release of radionuclide 'i' during a given time period, then the deposition rate is l zero, the ground plane concentration is zero and the resulting dose due to ground deposition is zero. If there is a release of radionuclide T, the ground concentration is computed as if that release had been occurring at a constant rate for the ground deposition time period.
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Revision 2.0 April 1999 The Ground Plane Dose Conversion Factor I
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i (/
The ground plane dose conversion factor is the dose rate to the whole body per unit of radioactivity l concentration on the ground. Values of the ground plane dose conversion factor that are calculated by assuming constant concentration over an infinite plane are provided for vario*us radionuclides in Table C-10 of Appendix C. The values are the same for all stations. The station-specific aspects of the calculation of ground dose concern the determination of the radioactivity concentration on the ground.
4.2.6 Inhalation Dose Commitment i
Radioactivity from airborne releases of radioactive iodine, particulate, tritium, and carbon-14 can enter {
the body through inhalation. Equation A-17 of Appendix A is used to calculate dose commitment to the whole body or its organs due to inhalation of non-noble gas radionuclides released in gaseous effluents. l This dose component is also referred to as the ' committed dose equivalent' (CDE).
The inhalation Dose Commitment Factor Values for the inhalation dose commitment factor are the same for all Comed stations. The components of this factor are not impacted by station specific parameters. However, the dose commitment factors used for compliance with 10CFR20 and 10CFR50 Appendix l are different as noted below:
. Values of the inhalation dose commitment factor used in the 10CFR50, Appendix l assessment are exactly those listed in Reg. Guide 1.109 (Reference 6) Tables E-7, 8,9 and
- 10. These tables include data for four age groups (adult, teenager, child and infant) and seven body organs.
D . Values of the inhalation dose commitment factor used for determining 10CFR20 and 40CFR190 compliance are exactly those listed in Table 2.1 of Federal Guidance Report No.
11 (FGR 11)(Reference 93). These data are for an adult and are given for all significant organs.
)
l Dose Commitment Rate j The inhalation dose commitment rate is the rate at which dose commitment is accrued by an individual breathing contaminated air. Equation A-28 of Appendix A is used to calculate dose commitment rate to an organ due to inhalation of non-noble gas radionuclides. The assumptions are the same as used in the calculation of inhalation dose commitment (Equation A-17 of Appendix A).
4.2.7 Ingestion Airborne releases of radioactive iodine, particulate, tritium, and carbon-14 can enter the food chain through deposition on, or absorption by, vegetation. The radioactivity can be ingested by humans who consume the vegetation or who consume products (e g., milk or meat) of animals who have fed on the contaminated vegetation. Each Comed nuclear power station considers the following four ingestion pathways:
. Leafy vegetables, e Produce (e.g. non-leafy vegetables, fruit, and grain),
e Milk, and
. Meat.
A Equation A-18 of Appendix A is used to calculate the dose commitment due to ingestion of food containing non-noble gas radionuclides released in gaseous effluents.
o loocnvgenenc/m2 o/ 22 !
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Revision 2.0 April 1999 Values of the ingestion dose commitment factor are the same for each Comed nuclear power station.
The components of this factor are not impacted by station specific parameters. The station-specific
((9
) aspects of the calculation of ingestion dose only concern the quantity of radioactivity ingested. However, the ingestion dose commitment factors used for 10CFR20 and for ' 10CFR50 compliance are different as was noted previously in section 4.2.6. These differences are noted below:
e Values of the ingestion dose commitment factor used in the 10CFR50 Appendix I assessment are exactly those listed in Reg. Guide 1.109 Tables E-11,12,13 and 14.
These tables include data for four age groups and seven organs.
- Values of the ingestion dose commitment factor used in the 10CFR20 assessment are exactly those listed in Table 2.2 of Federal Guidance Report No.11 (Reference 93). These tables include data for an adult and are given for all organs.
The ingested activity is calculated by use of equations A-19 through A-22 of Appendix A. The food product radioactivity concentration is calculated from measurements of radioactivity in station releases.
The different equations used for radioactivity concentration in vegetation, milk, and meat are also discussed in Appendix A.
4.3 LIQUID RELEASES The evaluation of dose and dose iMe due to releases of radioactivity in liquid effluents is required to confirm compliance with the provisions of RETS related to 10CFR50 Appendix 1. ODCM Section 3.2 and Figure 3-1 list some of the pathways by which radioactivity in liquid effluents can impact man. The principal pathways used by Comed to calculate dose from liquid effluents are ingestion by drinking water ]
and by eating fish from the body of water receiving station liquid discharges. The nuclear power stations obtain the dose commitment due to radioactivity in liquid effluent releases by summing the dose O commitments from both the drinking water and fish pathways.
Equations A-29, A-30 and A-31 of Appendix A are used to calculate committed dose equivalent (CDE) for the member of the public due to consumption of drinking water and fish.
The radioactivity concentration in water is obtained by dividing the quantity of radioactivity released by the volume of water in which the release is diluted (e g., the flow is multiplied by the total time of the ,
release in hours). The result is multiplied by the following' !
i e A factor to represent any additional dilution that might occur.
. A factor to account for radioactive decay from the time of release to the time of )
consumption. ;
1 The radioactivity concentration in fish is the product of the radioactivity concentration in water and a bio-accumulation factor. The dilution and radioactive decay factors for fish may be different from those for water. (The fish may be caught at a location different from where drinking water is drawn and the time period from the release of radioactivity to consumption may be different.)
The bio-accumulation factor accounts for the fact that the quantity of radioactivity in fish can build up with time to a higher value relative to the concentration of the radioactivity in the water they consume. The bio-accumulation factor is the equilibrium ratio of the concentration of radionuclide T in fish to its concentration in water. The same values are used for the bio-accumulation factor at each station. These values are provided in Appendix C, Table C-8.
O g lodem/genenc/rev2-0/ 23
Revision 2.0 April 1999 4.4 CONTAINED SOURCES OF RADIOACTIVITY In addition to the whole body, skin and single organ dose assessments previously described, an
'u additional assessment is required. The additional assessment addresses radiation dose due to
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radioactivity contained within the nuclear power station and its structures.
There are presently two types of contained sources of radioactivity which are of concern in offsite radiological dose assessments. The first is that due to gamma rays resulting from nitrogen-16 carry-over to the turbine in BWR steam (skyshine). The second is that due to gamma rays associated with radioactive material contained in onsite radwaste and rad material storage facilities.
4.4.1 BWR Skyshine The most significant dosa component to members of the public produced by " contained sources" is nitrogen-16 (N-16) within the turbine building of BWRs. Although primary side shielding is around the turbine and its piping, N-16 gamma rays scattered by air molecules in the overhead air space above the turbine and piping cause a measurable "skyshine" radiatim dose in the local power plant environs.
Equation A-34 of Appendix A is used to evaluate skyshine dose. A complicating factor in the calculation is the practice at some stations of adding hydrogen to reactor coolant to improve coolant chemistry. The addition of hydrogen can increase the dose rate due to skyshine up to a factor of 10 times expected levels depending on injection rates and power levels (Reference 39). Increasing the hydrogen injection rate will increase the dose rates even further. (See Reference 102) The skyshine dose determined by Equation A-34 of Appendix A depends on the following factors:
. The distance of the dose recipient location from the turbine.
- The number of hours per year that the location is occupied by a dose recipient.
- The total energy [MWe-br] generated by the nuclear power station with hydrogen addition.
p e The total energy [MWe-ht) generated by the nuclear power station without hydrogen addition.
4 4.4.2 Onsite Radwaste and Rad Material Storage Facilities Low level radioactive waste may be stored at any Comed nuclear power station in the following types of l storage facilities:
. Process Waste Storace Facilities
. Interim Radwaste Storage Facility (IRSF) structure
. Concrete vaults containing 48 radwaste liners (Also referred to as "48-pack";) l e DAW Storaae Facilities e Dry Active Waste (DAW) facihties (may include Butler buildings / warehouses) e Replaced Steam Generator Storaae Facilities in addition, Rad Material may be stored in facihties on site:
. Rad Material Storaae Facilities e Contaminated tools and equipment in seavans and/or warehouses Administrative controls are implemented by each station to ensure compliance to applicable regulations.
The impact to the offsite dose will be evaluated on a case by case basis and added to the station annex of the ODCM when applicable. In addition, a 10CFR50.59 analysis may be required for radwaste storage facikties.
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4 s
Revision 2.0 April 1999 4.5 TOTAL DOSE REQUIREMENTS p
4.5.1 Total Effective Dose Equivalent Limits; 10CFR20 and 40CFR190 10CFR20 requires compliance to dose limits expressed as " Total Effective Dose Equivalent"(TEDE).
The TEDE is the sum total of the external dose and the sum of the weighted internal doses. (See Appendix A; Sections A.4.3 and A.S.1) 4.5.2 Total Dose For Uranium Fuel Cycle The nuclear power stations are required to determine the total dose to a member of the public due to all uranium fuel cycle sources in order to assess compliance with 40CFR190 as part of demonstrating compliance with 10CFR20.
The total dose for the uranium fuel cycle is the sum of doses due to radioactivity in airbome and liquid effluents and the doses due to direct radiation from contained sources at the nuclear power station.
When evaluation of total dose is required for a station, the following contributions are summed:
. Doses due to airborne and liquid effluents from the station.
. Doses due to liquid effluents from nuclear power stations upstream.
. Doses due to nitrogen-16 (N) skyshine, if the station is a boiling water reactor.
. Doses due to any onsite radioactive waste storage facilities; if applicable.
Section A.5.2 of Appendix A discusses the details of evaluations.
O Oo gJodem/genenc/rev2-0/ 25
Revision 2.0 April 1999 Table 4-1 Radionuclide Types Considered For Airborne Effluent Exposure Pathways Extemal Radiation intemal Rsdiation Cateoory Plume Ground Inhalation incestion l Noble Gases X 1
Tritium (H-3) X X Carbon-14 (C-14)
- X X lodine' X X X Particulate
- X X X Comed stations are not required to calculate dose due to C". (See ODCM Bases and Reference document, Reference 101; Section O.4.5) 6 l The nuclear power stations are not required to consider all iodine and particulate radionuclides.
For details, see Generic Letter 89-01 and the RETS.
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g lodem/genenc/rev2@ 26
Revision 2.0 April 1999 Table 4-2 Radiation Dose Factors Name and Symbol Units Definition Table Gamma Air Dose mrad /yr Gamma air dose rate per F-7 Factor per unit of radioactivity F-7a S,V,Gi i i pCi/sec release rate for mdio-nuclide i for a stack (Si), vent (V),i or ground level (G i ) release.
Whole Body Dose mradlyr Whole body dose rate per F-7 Factor: per unit of radioactivity F-7a pCi/sec release rate for radio-
_S,V,Gi i i nuclide i for a stack (Si ), vent (Vj), or ground (G i) level release.
Beta Air Dose mrad /yr Beta air dose rate per C-9 Factor Li per unit of radioactivity pCi/m3 concentration for radionuclide i.
Beta Skin Dose mrem /yr Beta skin dose rate C-9 per per unit of radioac-Factor Li_. pCi/m3 tivity concentration for radionuclide 1.
Ground Plane Dose miem/hr Dose rate per unit C-10 ,
k Dose Conversion per of ground radioactivity ]
DFGi pCi/m2 concentration for '
radionuclide i.
Inhalation Dose mrem Dose commitment to RG 1.109 Commitment Factor per organ j of age group 'a' Tables; DFAja i pCi per unit of radio- E-7, E-8, activity inhaled for E-9, E-10 radionuclide i. (see Note 1) ;
i Ingestion Dose mrem Dose commitment to organ RG 1.109 Commitment Factor per j of age group a per Tables; DFlija pCi unit of radioactivity E-11, E 12, ingested for radio- E-13, E 14 nuclide i. (see Note 1)
Inhalation Dose Sv/Bq Dose commitment to organ FGR-11 Commitment Factor j of age group a per unit Table 2.1 DFAja i of radioactivity inhaled for radionuchde I(see Note 1).
Ingestion Dose Sv/Bq Dose commitment to organ FGR-11 Commitment Factor j of age group a per Table 2.2 DFlja i unit of radioactivity ingested for radio-nuclide i(see Note 1).
O g todem/genenchev2@ 27
Revision 2.0 April 1999 Table 4-2 Radiation Dose Factors (cont.)
Note 1: Dose assessments for 10CFR20 and 40CFR 190 compliance are made for*hn adult only using the dose l commitment factors of Federal Guidance Report it (Reference 93). These are given in unns of Severts per l Becquerel. To convert these data to the conventional units of (mrem /pCi) the data must be multcled by l 3.7x108 Dose assessments for 10CFR50 Appendix 1 are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups.
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l g /odem/ generic /rev2-0/ gg
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Revision 2.0 April 1999 i
CHAPTER 5
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v MEASUREMENT
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5.0 INTRODUCTION
Each nuclear station has three measurement programs associated with offsite dose assessment:
. Measurement of releases of radioactivity from the station.
. Measurement of meteorology at the station site.
- Measurement of levels of radiation and radioactivity in the environs surrounding the station.
5.1 I EFFLUENT AND PROCESS MONITORING
]
i Radioactivity in liquid and gaseous effluents is measured in order to provide data for calculating radiation I doses and radioactivity concentrations in the environment of each nuclear power station. Measurement !
of effluent radioactivity is required by 10CFR20.1302 and 10CFR50. The RETS of each nuclear power j station provide detailed requirements for instrumentation, sampling and analysis. Relevant Regulatory Guides are 1.21 (Reference 4) and 4.15 (Reference 13). Chapter 10 of the ODCM includes brief descriptions of effluent monitoring instruments at each nuclear power station. The RETS of each nuclear power station require submission to the NRC of reports of effluent radioactivity releases and i environmental measurements.
l l
5.2 METEOROLOGICAL MONITORING '
Meteorological parameters are measured in the vicinity of each nuclear power station in order to provide l data for calculating radiation doses due to airborne effluent radioactivity. Some nuclear power station's Technical Specifications state applicable requirements (typically under the subheading,
- Meteorological (ov) Instrumentation,"in the instrumentation section). Regulatory guidance is given in Regulatory Guide 1.23 (Reference 5). Wind speed, wind direction and the temperature gradient are measured using instruments at two or more elevations on a meteorological tower at each Comed station. The elevations are chosen to provide meteorological data representative of the elevations of the airborne releases from the station. The Annual Radiological Environmental Operating Report includes a summary of meteorological data collected over the reporting year. These data are used to calculate optional isopleths of radiation dose and radioactivity concentration.
5.3 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)
Each nuclear power station has a REMP that provides representative measurements of radiation and radioactive materialin the environment. The program provides verification that measurable radiological impacts from the power station on the environment are within expectations derived from effluent measurements and calculations. The REMP is required by 10CFR50 (see Appendix 1, Sections IV.B.2 l and IV.B.3). General requirements of the program are prescribed in each station's RETS and more precise details (such as specific monitoring locations) are specified in ODCM Chapter 11.
5.3.1 Interlaboratory Comparison Program The laboratory which performs the REMP analyses is required by the RETS to participate in an interlaboratory comparison program The purpose is to provide an independent check on the laboratory's analytical procedures ant, to alert it to potential problems (e.g. accuracy). In order to assess
! the measurements of radioactivity in environmental media, an independent agency supplies participating l laboratories with samples of environmental media containing unspecified amounts of radioactivity. The
'Q laboratories measure the radioactivity concentrations and report the results to the agency. ' At a later l b/ time, the agency informs the participating laboratories of the actual concentrations and associated g /odem/genenc/rev2-0/ 29
Revision 2.0 April 1999 uncertainties. Any significant discrepancies are investigated by the participating laboratories. A similar process is used to assess measurements of environmental radiation by passive thermoluminescent dosimeters.
O glodem/genenc/rev2-0/ 30 m
Revision 2.0 April 1999 CHAPTER 6 IMPLEMENTATION OF OFFSITE DOSE ASSESSMENT P,R,0 GRAM 6.1 NUCLEAR POWER .6TATION The nuclear power station staff is responsible for effluent monitoring. The staff determines effluent radioactivity concentration and flow rate. This data is used to determine the radioactivity release information required for the Radioactive Effluent Release Report and to perform mon:hly calculatior:s and projections of offsite radiation dose.
The nuclear power station staff is also responsible for control of effluent radioactivity. Procedures are implemented for determining, calculating and implementing setpoints. Liquid and gaseous radwaste treatment systems and ventilation exhaust treatment systems are utilized when appropriate. The nuclear power station staff implements the Process Control Program (PCP) for solid radwaste and measures tank radioactivity and BWR off-gas radioactivity.
The nuclear power station staff maintains instrumentation associated with these activities and demonstrates operability of the instrumentation in accordance with the surveillance requirements of tre RETS. In the event that any RETS requirements are violated, the nuclear power station staff is responsible for taking one of the actions allowed by the RETS and issuing any required reports to the NRC.
The nuclear power station staff assembles and distributes the Radioactive Effluent Release Report.
The nuclear power station staff and/or the Generation Support Radiation Protection Department s (GSRPD) reviews the Annual Radiological Environmental Operating Report prepared by the REMP contractor. The nuclear power station staff distributes the report to the NRC.
6.2 METEOROLOGICAL CONTRACTOR The meteorological contractor operates and maintains the meteorological tower instrumentation at each nuclear power station. The contractor collects and analyzes the data and issues periodic reports. The contractor prepares the meteorological data summary required for the Annual Radiological Environmental Operating Report (AREOR) and also computes and plots isopleths included in the AREOR.
6.3 REMP CONTRACTOR The radiological environmental contractor collects environmental samples and performs radiological analyses as specified in the nuclear power station's REMP (see ODCM Chapters 11 and 12). The contractor issues reports of results to GSRPD and each nuclear station. The contractor participates in an interlaboratory comparison program and reports results in the Annual Radiological Environmental Operating Report. The contractor performs the annualland use census and assembles the Annual Radiological Environmental Operating Report.
6A CORPORATE DEPARTMENTS The Generation Support Radiation Protection Department (GSRPD) administers the offsite dose assessment computer program. The department maintains the generic section of the ODCM. The department oversees the meteorological and REMP contractors through administration of the purchase orders and by receiving and reviewing periodic reports.
O glodem/genenc/rev2-0/ 31
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Revision 2.0 April 1999 A computer support group develops and maintains the computer program used by the nuclear power stations for offsite dose calculation and projection. GSRPD performs validation and verification of the computer code l
I i
glodemigeneric/rev2-0/ 32 ,
1
. 1 Revision 2.0 April 1999 CHAPTER 7 REFERENCES
- 1. Deleted
- 2. U.S. Nuclear Regulatory Commission, Standard Radioloaical Effluent Technical Specifications for Pressunzed Water Reactors, NUREG-0472, Rev. 3, Draft, January 1983 (frequently revised). j
(
- 3. U.S. Nuclear Regulatory Commission, Standard Radioloaical Effluent Technical Specifications for Boilina Water Reactors, NUREG-0473, Rev. 3, Draft, September 1982 (frequently revised),
- 4. U.S. Nuclear Regulatory Commission, Measurina. Evaluatina. and Reportina Radioactivity in Solid Wastes and Releases of Radioactive Materials in Llauid and Gaseous Effluents from Liaht-Water-Cooled Nuclear Power Plants. Reaulatory Guide 1.21. Revision 1, June 1974.
- 5. U.S. Nuclear Regulatory Commission, Onsite Meteoroloaical Proarams, Regulatory Guide 1.23, Safety Guide 23, February 17,1972.
- 6. U.S. Nuclear Regulatory Commission, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluatina Compliance with 10 CFR Part 50 Appendix 1, Regulatory Guide 1.109, Rev.1, October 1977.
- 7. U.S. Nuclear Regulatory Commission, Methods for Estimatina Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Liaht-Water-Cooled Reactors, Regulatory Guide 1.111, Rev.1, July 1977.
O 8. U S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liouid Effluents from Liaht-Water-Cooled Power Reactors, Regulatory Guide 1.112, Rev. 0-R, April 1976; reissued May 1977.
- 9. U.S. Nuclear Regulatory Commission, Estimatina Acuatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of implementina Appendix 1, Regulatory Guide 1.113, Rev.1, April 1977.
- 10. U.S. Nuclear Regulatory Commission, Proarams for Monitorina Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Rev.1, April 1975.
- 11. U.S. Nuclear Regulatory Commission, Preparation of Environmental Reports for Nuclear Power i Stations, Regulatory Guide 4.2, Rev. 2, July 1976. j
- 12. U.S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, Rev.1, December 1975. (See also the related Radiological Assessment Branch Technical Position, Rev.1, November 1979.)
- 13. U.S. Nuclear Regulatory Commission, Quality Assurance for Radioloaical Monitorina Procrams (Normal Operations)-Effluent Streams and the Environment, Regulatory Guide 4.15, Rev.1, February 1979.
- 14. U.S. Nuclear Regulatory Commission, Preparation of Radioloaical Effluent Technical Specifications for Nuclear Power Plants, edited by J. S. Boegli et al. NUREG-0133, October 1978.
O g lodem/genenc/rev2 0/ 33
Revision 2.0 April 1999
- 15. U.S. Nuclear Regulatory Commission, XOODOO Computer Proaram for the Meteoroloaical Evaluation of Routine Effluent Releases at Nuclear Power Stations, J. F. Sagendorf et al.
['N NUREG/CR-2919, PNL-4380, September 1982.
b 16. U.S. Nuclear Regulatory Commission, Radioloaical Assessment, eddbd by J. E. Till and H. R.
Meyer, NUREG/CR-3332, ORNL-5968, September 1983.
- 17. U.S. Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, July 1981.
- 18. U.S. Atomic Energy Commission, Meteoroloav and Atomic Enerav 1968, edited by D. H. Slade, TID-21940, July 1968.
- 19. U.S. Atomic Energy Commission, Plume Rise, G. A. Briggs, TID-25075,1969.
- 20. U.S. Atomic Energy Commission, The Potential Radioloaical Implications of Nuclear Facilities in the Upper Mississippi River Basin in the Year 2000, WASH 1209, January 1973.
- 21. U.S. Atomic Energy Commission, HASL Procedures Manual, Health and Safety Laborabry, HASL-300 (revised annually). ,
I i
- 22. U.S. Department of Energy, Models and Parameters for Environmental Radioloaical !
Assessments, edited by C. W. Miller, DOE / TIC-11468,1984.
{
l
- 23. U.S. Department of Energy, Atmospheric Science and Power Production, edited by D.
Randerson, DOE / TIC-27601,1984.
)
- 24. U.S. Environmental Protection Agency, Workbook of Atmospheric Dispersion Estimates, D. B.
Turner, Office of Air Programs Publication No. AP-26,1970.
(O)
- 25. U.S. Environmental Protection Agency,40CFR190 Environmental Radiation Protection Reauirements for Normal Operations of Activities in the Uranium Fuel Cvele, Final Environmental Statement, EPA 520/4-76-016, November 1,1976.
- 26. U.S. Environmental Protection Agency, Environmental Analysis of the Uranium Fuel Cycle, EPA-520/9-73-003-C, November 1973.
- 27. American Society of Mechanical Engineers, Recommended Guide for the Prediction of the Dispersion of Airborne Effluents,1973.
- 28. Eisenbud, M., Environmental Radioactivity, 3rd Edition, (Academic Press, Orlando, FL,1967).
- 29. Glassione, S., and Jordan, W. H., Nuclear Power and its Environmental Effects (American l Nuclear Society, LaGrange Park, IL,1980). l
- 30. International Atomic Energy Agency, Generic Models and Parameters for Assessina the Environmental Transfer of Radionuclides from Routine Releases, Safety Series, No. 57,1982. l
- 31. National Council on Radiation Protection and Measurements, Radioloaical Assessment-Predictina the Transport. Bioaccumulation. and Uptake by Man of Radionuclides Released to the Environment, NCRP Report No. 76, March 15,1984.
- 32. American National Standards Institute, Guide to Samplina Airborne Radioactive Materials in Nuclear Facilities, ANSI N13.1-1969, February 19,1969.
U) l g lodcm/ generic /rev2-0/ 34
r Revision 2.0 April 1999
- 33. Institute of Electrical and Electronics Engineers, Specification and Performance of On-Site Instrumentation for ContinuousIV Monitorina Radioactivity in Effluents, ANSI N13.10-1974,
/'] September 19,1974.
L)
- 34. American National Standards institute, Testina and Procedural Spec'dications for Thermoluminescence Dosimetry (Environmental ADDI ications), ANSI N545-1975, August 20, 1975.
- 35. American Nuclear insurers Effluent Monitonna, ANI/MAELU Engineering inspection Cnteria for Nuclear Liability insurance, Section 5.1, Rev. 2. October 24,1986.
- 36. American Nuclear insurers, Environmental Monitorina, AN1/MAELU Engineering inspection Criteria for Nuclear Liability insurance, Section 5.2, Rev.1. March 23,1987.
- 37. American Nuclear insurers, Environmental Monitorina Proarams, ANI/MAELU Information Bulletin 86-1, June 9,1986.
- 38. Cember, H., Introduction to Health Physics,2nd Edition (Pergamon Press, Elmsford, NY 1983).
- 39. Electric Power Research institute, Guidelines for Permanent BWR Hydroaen Water Chemistry
) Installations-1987 Revision, EPRI NP-5283-SR-A, Special Report, September 1987.
- 40. Commonwealth Edison Company, Information Relevant to Keepina Levels of Radioactivity in Effluents to Unrestricted Areas As low As Reasonably Achievable. LaSalle County Station.
Units 1 and 2, June 4,1976.
- 41. U.S. Nuclear Regulatory Commission, Branch Technical Position, Radiological Assessment n Branch, Revision 1, November 1979. (This is a brar di position on Regulatory Guide 4.8.)
- 42. Deleted
- 43. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liauid Effluents from Pressurized Water Reactors (PWR-GALE Code),
NUREG-0017, April 1976.
- 44. U.S. Nuclear Regulatory Commission, Calculation of Releases of Radioactive Materials in Gaseous and Liouid Effluents from Boilina Water Reactors (BWR-GALE Code), NUREG-0016, April 1976.
- 45. Sargent & Lundy, N-16 Skyshine from BWR Turbine Systems and Pipina, NSLD Calculation No, D2-2-85, Rev. O,2/1/85.
- 46. Sargent & Lundy Calculation ATD-0138, Rev. O, N-16 Skyshine Ground Level Dose from Dresden Turbine Systems and Pipina. July 14,1992.
- 47. Sargent & Lundy Calculation ATD-0139, Rev. O, N-16 Skyshine Ground Level Dose from LaSalle Turbine Systems and Pipina. July 28,1992.
- 48. Sargent & Lundy Calculation ATD-0140, Rev. O, N-16 Skyshine Ground Level Dose from Quad Cities Turbine Sysms and Pioina. July 28,1992.
- 49. U.S. Nuclear Regulatory Commission, Methods for Demonstratina LWR Compliance with the EPA Uranium Fuel Cvele Standard (40 CFR Part 190), NUREG-0543, February 1980.
fN i l V
glodem/genenc/rev2 0/ 35
e Revision 2.0 e
April 1999
- 50. International Commission on Radiologica' Protection, Report of Committee Two on Permissible Dose for internal Radiation. Recommendations of the Intemational Commission on Radiological Protection, ICRP Publication 2,1959.
- 51. U.S. Nuclear Regulatory Commission, Ace-Specific Radiation Dose Commitment Factort for a One-Year Chronic Intake, Battelle Pacific Northwest Laboratorios, NUREG-0172,1977.
- 52. W. C. Ng, Transfer Coefficients for Prediction of the Dose to Man via the Foraae-Cow-Milk Pathway from Radionuclides Released to the Biosphere, UCRL-51939.
- 53. E. C. Eimutis and M. G. Konicek Derivations of Continuous Functions for the Lateral and Vertical Atmospheric Dispersion Coefficients, Atmospheric Environment 6,859 (1972).
- 54. D. C. Kocher, cditor, Nuclear Decav Data for Radionuclides Occurrina in Routine Releases from Nuclear Fuel Cvele Facilities, ORNL/NUREG/TM-102, August 1977.
- 55. R. L. Heath, Qamma-Ray Spectrum Cataloa, Aerojet Nuclear Co., ANCR-1000-2, third or subsequent edition.
- 56. S. E. Thompson, Concentration Factors of Chemical Elements in Edible Aauatic Oraanisms, UCRL-50564, Rev.1,1972.
- 57. U.S. Nuclear Regulatory Commission, instruction Concernina Risks from Occupational Radiation Exposur,e, Regulatory Guide 8.29, July 1981.
- 58. Dresden Nuclear Power Station, Radioactive Waste and Environmental Monitorina, Annual Report 1987, March 1988.
- 59. Reserved reference number
- 60. Sargent & Lundy Calculation ATD-0173, Rev. O,9/21/92, Annual Dose to Members of the Public Due to the LaSa!Ie IRSF.
- 61. Sargent & Lundy Calculation ATD-0174, Rev. O,9/21/92, Annual Dose to Members uf the Public Due to the Zion IRSF.
- 62. Sargent & Lundy Calculation ATD-0175, Rev. O,9/21/92, Annual Dose to Members of the r ublic Due to the Quad Cities IRSF.
- 63. Sargent & Lundy Calculation ATD-0176, Rev. O,9/21/92, Annual Dose to Members of the Public Due to the Dresden IRSF.
- 64. Reserved reference number
- 65. Sargent & Lundy Calculation ATD-0180, Rev. O,9/25/92, Dose Information Around Braidwood DAW Sea / Land Van Storaae Area.
- 66. Sargent & Lundy Calculation ATD-0181, Rev. O,9/25/92, Dose Information Around Byron DAW Sea / Land Van Storaae Area.
- 67. Sargent & Lundy Calculation ATD-0182, Rev. O,9/25/92, Dose information Around Dresden DAW Sea / Land Van Storace Area.
O 68. Sargent & Lundy Calculation ATD-0183, Rev. O,9/25/92, Dose information Around LaSalle DAW h Sea / Land Van Storace Area.
g:/odem/genenc/rev2-0/ 36
Revision 2.0 e
April 1999
- 69. Catalytic, Inc., Determination of Roof and Wall Shieldina for Onsite and Offsite Radiation Protection from Skyshine. Calculation index Number 70161-19, August 22,1984 (applies to Dresden). ..
- 70. D. C. Kocher, Radioactivity Decay Data Tables. DOE / TIC-11026,1981.
- 71. J. C. Courtney, A Handbook of Radiation Shieldina Data, ANS/SD-76/14, July 1976.
- 72. Commonwea'th Edison Company, Information Relevant to Keepina Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Zion Station. Units 1 and 2, June 4,1976.
- 73. Commonwealth Edison Company, Information Relevant to Keepino Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonably Achievable. Dresden Station. Units 2 and 3, June 4,197.6.
- 74. Commonwealth Edison Company, Information Relevant to Keepina Levels of Radioactivity in Effluents to Unrestricted Areas As Low As Reasonab!v Achievable. Quao Cities Station. Units 1 and 2. June 4,1976.
- 75. Sargent & Lundy, METWRSUM. S&L Program Number 09.5.187-1.0.
- 76. Sargent & Lundy, Comments on CECO ODCM and List of S&L Calculations, Intemal Office Memorandum, P. N. Derezotes to G. R. Davidson, November 23,1988.
- 77. Sargent & Lundy, AZAP. A Computer Proaram to Calculate Annual Averaae Offsite Doses from Routine Releases of Radionuclides in Gaseous Effluents and Postaccident X/O Values, S&L O* Program Number 09.8.054-1.7.
- 78. National Oceanic and Atmospheric Administration, A Proaram for Evaluatina Atmospheric Dispersion from a Nuclear Power Station. J. F. Sagendorf, NOAA Technical Memorandum ERL ARL-42, Air Resources Laboratory, Idaho Falls, Idaho, May 1974.
- 79. G. P. Lahti, R. S. Hubner, and J. C. Golden, Assessment of Gamma-Ray Exposures Due to Finite Plumes, Health Physics 41,319 (1981).
- 80. National Council of Radiation Protection and Measurements, lonizina Radiation Exposure of the Population of the United States. NCRP Report No. 93, September 1,1987.
- 81. Reserved reference number
- 82. W. R. Van Pelt (Environmental Analysts, Inc.), Letter to J. Golden (Comed) dated January 3, 1972.
- 83. Electric Power Research institute, Radioloaical Effects of Hydrocen Water Chemistry, EPRI NP-4011, May 1985.
- 84. U.S. Nuclear Regulatory Commission, Draft Generic Environmental Impact Statement on Uranium Millina. NUREG-0511, April 1979.
- 85. U.S. Environmental Protection Agency, Environmental Analysis cf the Uranium Fuel Cycle. Part I- Fuel Supolv. EPA-520/9-73-003-B, Octobet 1973.
I v
g>odemQenenc/rev2-0/ 37 i I
l 3
e Revision 2.0 4 April 1999
- 86. U.S. Nuclear Regulatory Commission, Final Generic Environmental Statement on the Use of Recycle Plutonium in Mixed Oxide Fuelin Liaht Water Cooled Reactors, NUREG-0002, August 1976.
- 87. U.S. Nuclear Regulatory Commission, Demoaraohic Statistics Pertainina to Nuclear Power Reactor Sites. NUREG-0348, Draft, December 1977.
- 88. Nuclear News 31, Number 10, Page 69 (August 1988).
l
- 89. General Electric Company, Irradiated Fuel Storace at Morns Operation. Operatina Experience l
Report. January 1972 throuah December 1982, K. J. Eger, NEDO-209698.
- 90. U.S. Nuclear Regulatory Commission, Generic Letter 89-01, ' Guidance For The imDiementation of Proarammatic Controls for RETS in The Administrative Controls Section of Technical Specifications and the Relocation of Procedaral Detals of Current RETS to *$e Offsite Dose Calculation Manual or Process Control Proaram", January 1989.
91, " Assessment of the impact of Liould Radioactiye Effluents from Braidwood Station on Proposed Public Water intakes at Wilminato1. lilinois", J.C. Golden, NSEP, January 1990
- 92. NRC Safety Evaluation Report (SER)/ idaho Notional Engineering Laboratory Technical Evaluation Report (TER) of the Commonwealth Edison Offsite Dose Calculation Manual (ODCM), Revision O.A, December 2,1991.
- 93. K. F. Eckerman, et al, Limitina Values of Radionuclide intake and Air Concentration and Dose Conversions Factors for Inhalation. Submersion and Inhalation. Federal Guidance Report No.
11, U.S. Environmental Protection Agency Report EPA-520/1-88-020, September 1988.
- 94. Deleted.
- 95. U.S. Nuclear Regulatory Commission, Standards for Protection Aaainst Radiation (10CFR20).
l
- 96. U.S. Nuclear Regulatory Commission, Licensina of Production and Utilization Facilities 1 (10CFR50). i
- 97. Federal Register, Vol. 57, No.169, Monday, August 31,1992, page 39358.
l
- 98. Miller, Charles W., Models and Parameters for Environmental Radioloaical Assessments, U.S.
Dept. of Energy, DE8102754,1984, pages 32,33,48, and 49.
- 99. Kocher, D. C., Dose-Rate Conversion Factors For External Exposure To Photons and Electrons", Health Physics Vol. 45, No. 3 (September), pp. 665-686,1983.
100. U.S. Department of Health, Education and Welfare Public Health Service, Radioloaical Health Handbook, January 1970.
101. ODCM Bases and Reference Document, rev.0, November,1998.
102. G. Moran, D. Goff, Quad Cities Nuclear Power Station: 1993 Hydroaen Water Chemistry Stress Corrosion Monitorina Test - Unit 2, 9/17-23/93.
103. U.S. Nuclear Regulatory Commission, Generic Letter 79-041, September 17,1979.
O glodem/ generic /rev2-0/ 38
)
Revision 2.0
! April 1999 APPENDIX A O
V COMPLIANCE METHODOLOGY .-
TABLE OF CONTENTS PAGE A.0 INTRODUCTION A-1 l
A.1 AIRBORNE RELEASES A-1
- 1. Release Point Classifications A-1
- 2. Dose Due to Noble Gas Radionuclides A-2
- 1. Gamma Air Dose A-2
- 2. Beta Air Dose A-3
- 3. Total Body Dose A4 )
- 4. Skin Dose A-5
- 3. Dose Rate Due to Noble Gas Radionuclides A-6
- 1. Wnole Body Dose Rate A-6
- 2. Skin Dose Rate A-6
- 4. Dose Due to Non-Noble Gas Radionuclides A-7
- 1. Ground Deposition A-8
- 2. Inhalation A-8
- 3. Food Pathways A-10
- 1. Vegetation A-11
( 2. Milk A-12
- 3. Meat A-15
- 5. Dose Rate Due to Non-Noble Gas Radionuclides A-15
- 6. Operabikty and Use of Gaseous Effluent Treatment Systems A-16 A.2 LIQUID RELEASES A-17
- 1. Dose A-17
- 2. Liquid Effluent Concentrations Requirement A-19
- 3. Tank Discharges A-20
- 4. Tank Overflow A-21
- 5. Operabikty and Use of the Liquid Radwaste Treatment System A-21
- 6. Drinking Water A-21
- 7. Non-routine Liquid Release Pathways A-21 A.3 DOSE DUE TO CONTAINED SOURCES A-21
- 1. BWR Skyshine A-22
- 2. Dose from Onsite Radwaste Storage Facilities A-23 A.4 TOTAL DOSE LIMITS A-24
- 1. Deep Dose Equivalent A-24
- 2. Committed Effective Dose Equivalent A-24
- 3. Total Effective Dose Equivalent A-25 O
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1 Revision 2.0 April 1999 APPENDlX A p, TABLE OF CONTENTS (Cont'd)
O ' ~~
PAGE A.S COMPLIANCE TO TOTAL DOSE LIMITS A-26
- 1. Total Effective Dose Equivalent Limit - 10CFR20 Complience A-26
- 2. Total Dose Due to the Uranium Fuel Cycle (40CFR190) A-26
- 3. Summary of Compliance Methodology A-27 A.6 DOSE DUE TO DRINKING WATER (40CFR141) A-27
- 1. 40CFR141 Restrictions on Manmade Radionuclides A-27
- 2. Application A-28 LIST OF TABLES ;
NUMBER TITLE PAGE A-0 Average Annual Concentrations Assumed to Produce A-28 a Total Body or Organ Dose of 4 mremlyr.
A-1 Compliance Matrix A-29 A-2 Release Point Classifications A-30 A-3 Nearest Downstream Community Water Systems A-31 A4 40CFR190 Compliance A-32 O
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APPENDIX A
) COMPLIANCE METHODOLOGY ,_
A.0 INTRODUCTION This appendix reviews tne offsite radiological hmits applicable to the nuclear power stations and presents in detail the equations and procedures used to assess compliance with these limits. An introduction to the calculational approach used here is given in Chapter 4. The approach incorporates simplifications such as the following:
Use of pre-calculated atmospheric transport parameters based on historical average atmospheric conditions (see Section 4.1.5). These factors, X/O and D/O, are defined in Chapter 4.
Use of pre-calculated dose factors based on historical average atmospheric conditions. For example, a dose factor with units (mradlyr) per (pCi/sec) is used to obtain gamma dose rate in mradlyr from noble gas release rate in pCi/sec.
Values of these parameters are obtained as desenbed in Appendix B.
The equations and parameters of this appendix are for use in calculating offsite radiation doses during routine operating conditions. They are not for use in calculating doses due to non-routine releases (e g., accident releases).
The applicable radiation protection regulations included in 10CFR20,10CFR50 Appendix i, and 40CFR190 each require a different type of radiological dose assessment. In some cases, e g. ingestion and inhalation pathways, the calculations used to demonstrate compliance may be similar, but the reference dose conversion factors differ because of historical regulatory evolution. This section of the ODCM develops, in detail, the evaluation used to determine the individual components of the total dose, and then indicates which are reportable and in some cases combined to demonstrate regulatory compliance.
An overview of the required compliance is given in Tables 2-1,2-2, and 2-3. In Table 2-1, the dose components are itemized and referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in Table 2-3. Additionally, the locations of dose receivers for each dose component are given in Table 2-2.
The following sections detail the required radiological dose calculations.
A.1 AIRBORNE RELEASES A.1.1 Release Point Classifications The pattern of dispersion of airborne releases is dependent on the height of the release point relative to adjacent structures. For the equations of this appendix, each release point is classified as one of the following three i height-dependent types, which are defined in Section 4.1.4:
. Stack (or Elevated) Release Point (denoted by the letter S or subscript s) e Ground Level Release Point (denoted by the letter G or subscript g) e Vent (or Mixed Mode) Release Point (denoted by the letter V or subscript v)
The release point classifications of routine release points at the nuclear power stations are stated in Table A-2.
I g:/odem/ generic / Attar 2-0/ A-1
Revision 2.0 April 1999 A.1.2 Dose Due to Noble Gas Radionuclides A.1.2.1 Gamma Air Dose ,
Requirement RETS limit the gamma air dose due to noble gas effluents released from each reactor unit to areas at arid beyond the unrestricted area boundary to the following:
. Less than or equal to 5 mrad per calendar quarter.
- Less than or equal to 10 mrad per calendar year. I Equation The gamma air dose due to noble gases released in gaseous effluents is calculated by the following expression:
D, = (3.17E4)E{ SA,, + VA , + GA, ) (A1)
The summation is over noble gas radionuclides i.
I D, Gamma Air Dose [ mrad) i Dose to air due to gamma radiation from noble gas radionuclides released in gaseous effluents. 4 3.17E4 Conversion Constant (seconds to years) [yr/sec]
8,, V,, G, Garr.ma Air Dose Factor [(mradlyr)/(pCi/sec)) j O Gamma air dose rate at a specified location per unit of radioactivity release rate for radionuclide 'i' released from a stack, vent, or ground level release point, respectively. See Section 4.2.1, Section B.5 of Appendix B, and Table F-7 of Appendix F.
A,., A,,, A, . Cumulative Radionuclide Release [pCi)
Measured cumulative release of radionuclide 'l' over the time period I of interest from a stack, vent, or ground level release point.
Application RETS require determination of cumulative and projected gamma air dose contributions due to noble gases for the current calendar quader and the current calendar year at least once per 31 days (see Sections 12.4 of each station's RETS or Technical Specifications).
The dose factors in Table F-7 of Appendix F are used for the determinations required by ther,e specifications.
These values were calculated for the unrestricted area boundary in each sector and are judf ;d to be very good approximations to the maximum offsite values. After doses for all sectors are determined, tne highest dose is compared with the RETS limit on gamma air dose.
For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in. ODCM Chapter 10.-
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Revision 2.0 April 1999 A.1.2.2 Beta Air Dose f
i)V Requirement
~
RETS limit the beta air dose due to noble gases in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary to the following:
- Less than or equal to 10 mrad per calendar quarter.
. Less than or equal to 20 mrad per calendar year.
Equation The beta air dose due to noble gases released in gaseous effluents is calculated by the following expression: l D, = (3.17E-8)I{ L,[(X/Q),A',, + (XIQ),A',, + (X/Q),A',,) ) (A-2)
)
The summation is over noble gas radionuclides T.
D, Beta Dose [ mrad]
Dose to air due to beta radiation from noble gas radionuclides released in gaseous effluents.
3.17E-8 Conversion Constant (seconds to years) [yr/sec)
I L. Beta Air Dose Factor [(mradlyr)/(pCi/m')]
Beta air dose rate per unit of radioactivity concentration for radionuclide T. See Section 4.2.2, Section B.7 of Appendix B, and Table C-9 of Appendix C.
v '(X1Q), Relative Concentration Factor [sec/m )
(X/Q),
(XIQ), Radioactivity concentra' ion at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release . See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.
A'i, Cumulative Radionuclide Release, [pCi) j A',, Adjusted for Radiodecay ;
A',
Measured cumulative release of radionuclide T over the time period of interest from a stack, vent, or ground level release point, reduced to account for radiodecay in transit from the release point to the dose point:
A',, = A,, exp(-AR/3600u,) (A-3)
A',, = A,, exp(-AR/3600u,) (A-4)
A',, = A, exp(-AR/3600u,) (A-5)
A, Cumulative Radionuclide Release [pCi)
A,,
A., Defined in Section A.1.2.1.
A Radiological Decay Constant [hr')
O Radiological decay constant for radionuclide T. See U
g:/odem/ generic / Attar 2-0/ A-3
J . j Revision 2.0 l April 1999 l
Table C-7 of Appendix C.
R Downwind Range , , [m]
Distance from the release point to the dose point.
See Tables F-5 F-6, and F-7.
3600 Conversion Constant [sec/hr]
Converts hours to seconds.
J u, Average Wind Speed [m/sec]
u, u, Average wind speed for a stack, vent, or ground level release. See Section B.1.3 of Appendix B and Table F-4 of Appendix F.
Application RETS require determination of cumulative and projected beta air dose contributions due to noble gases for the current calendar quarter and the current calendar year at least once per 31 days (see Section 12.4 of each station's RETS or Technical Specification).
Beta air dose is determined for each sector using the highest calculated offsite value of X/Q for that sector. This value and the distance R to which it pertains are provided in Table F 5 of Appendix F. The highest dose is compared with the limit on beta air dose.
For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.
O A.1.2.3 Total Body Dose V
Requirement The whole body dose, also called the deep dose equivalent (DDE), to any receiver is due, in part, to gamma radiation emitted from radioactivity in airborne effluents. This component is added to others to demonstrate compliance to the requirements of 40CFR190 and 10CFR20.
Equation The whole body dose /DDE component due to gamma radiation from noble gases released in gaseous effluents is I calculated by the following expression: l
~
D. = (0.7)(1.11)(3.17E-8) x I{S,A., + 5/A, + GA,} (A6)
The summatir n is over noble gas radionuclides 'I'.
l D. Whole Body Dose [ mrem)
Dose to the whole body due to gamma radiation from noble ;
gas radionuclides released in gaseous effluents.
' O.7 Shielding Factor; a dimensionless factor that accounts for shielding due to the occupancy of structures.
1.11 Conversion Constant (rads in air to rem in tissue) [ mrem / mrad) 3.17E-8 Conversion Constant (seconds to years) {yr/sec) g:/odem/ generic / Attar 2-0/ A-4
1 Revision 2.0 f April 1999 f'~] 5,, k G, Gamma Whole Body Dose Factor [(mradlyr)/
() .
(pCi/sec))
Gamma whole body dose rate at a specified location per unit of radioactivity release rate for radionuclide 'i' released from a stack, vent, or ground level release point. The attenuation of gamma radiation due to passage through 1 cm of body tissue of 1 g/cm 2 density is taken into account in calculating this quantity. See Section 4 2.3, Section B.6 of Appendix B, and Table F-7 of Appendix F.
A,,, A,,, A,, Cumulative Radionuclide Release [pCi]
Defined in Section A.1.2.1.
Application The whole body dose (deep dose equivalent) is included in the 40CFR190 and 10CFR20 compliance assessments. In some cases, the whole body dose may be required in 10CFR50 Appendix I assessments (See Table 2-1). i 1
A.1.2.4 Skin Dose Requirement There is no regulatory requirement to evaluate skin dose, also referred to as the shallow dose equivalent (SDE).
I However, this component is evaluated for reference as there is skin dose design objective contained in 10CFR50 Appendix 1. Note that in the unlikely event that if beta air dose guideline is exceeded, then the skin dose will g require evaluation.
Equation The part of skin dose due to noble gases released in gaseous effluents is calculated by the following expression:
D. = (3.17E-8)I{ Li [(X/Q),A',, + (X/Q),A',, + (X/Q),A',,) (A 7)
+ (0.7)(1.11)[S,A,, + V,A,, + G,A,,]}
The summation is over noble gas radionuclides *i'.
D. Skin Dose [ mrem]
Dose to the skin due to beta and gamma radiation from noble gas radionuclides released in gaseous effluents.
I., Beta Skin Dose Factor [(mremlyr)/
(pCi/m')]
Beis skin dose rate per un't of radioactivity concentration for radionuciMe 'i'. Attenuation of beta radiation passing through 7 mg/cm2 of dead skin is accounted for. See Section 4.2.4, Section B.7 of Appendix B, and Table C-9 of Appendix C.
The remaining parameters are defined in Sections A.1.2.1 and A.1.2.2.
Application Il The skin dose is calculated for reference only.
d g:/odem/ generic / Attar 2-0/ A-5
.a Revision 2.0
! April 1999 A.1.3 Dose Rate Due to Noble Gas Radionuclides
- A.1.3.1 Whole Body Dose' Rate , ,,.
Requiremoni RETS limit the whole body dose rate (deep dose equivalent rate) due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 500 mrt m/yr at all times. (see Section 12.4 of each station's RETS and Technical Specifications)
Equation The whole body dose rate (deep dose equivalent rate) due to noble gases released in gaseous effluents is calculated by the following expression:
= (1.11)I{S,Q,, + 9,Q,, + G,Q,,} (A-8)
The summation is over noble gas radionuclides 'I'.
D. Whole Body Dose Rate [ mrem /yr)
Dose rate to the whole body due to gamma radiation from noble gas radionuclides released in gaseous effluents.
Q,,,Q,,,Q,, Release Rate [pCi/sec)
Measured release rate of radionuclide 'i' from a stack, vent, or ground level release point.
The remaining parameters have the same definitions as used in the equation for whole body dose in Section A.1.2.3.
Application RETS require the dose rate due to noble gases in gaseous effluents be determitied to be within the above limit in accordance with methodology specified in the ODCM (see Section 12.4 of each station's RETS and Technical Specifications).
To comply with this specification, each station uses an effluent radiatinr. monitor setpoint corresponding to an offsite whole body dose rate at or below the limit (see Chapter 10). In addition, each station assesses compliance by calculating offsite whole body dose rate on the basis of periodic samples obtained in accordance with station procedures.
A.1.3.2 Skin Dose Rate Requirement RETS limit the skin dose rate due to noble gases in gaseous effluents released from a site to areas at and beyond the site boundary to less than or equal to a dose rate of 3000 mrem /yr at all times. (See Section 12.4 of each station's RETS and/or Technical Specifications)
Equation The skin dose rate (shallow dose equivalent rate) due to noble gases released in gaseous effluents is calculated by the following expression:
D = I{ L [(X/Q),Q',,
i + (X/Q),Q',, + (X/Q),Q',,] (A-9)
+ (1.11)[S,Q,, + V,Q,, + Gi Q,,) }
g:/odem/ generic / Attar 2-0/ A-6
Revision 2.0 April 1999 The summation is over noble gas radionuclides i. 1 l
(/ D. Skin Dose Rate , ,_
[ mrem /yr]
Dose rate to skin due to beta and gamma radiation from noble gas radiont.clides released in gaseous effluents.
Q ',, Release Rate, Adjusted for Radiodecay (pCi/sec)
Q', .
O',, Measured release rate of radionuclide 'i' from a stack, vent, or ground level release point, reduced to account for radiodecay in transit from the release point to the dose point:
Q'i, = Q,, exp(-X,R/3600u,) (A 10)
Q',, = Q,, exp( A,R/3600u,) (A-11)
Q'g = Q,, exp(-A,R/3600u,) (A-12)
The parameters Q,,, Q,,, and Q,, are defined in Section A.1.3.1, and the parameters A,, R, u,, u,, and u, are defined in Section A.1.2.2.
The remaining parameters have the same definitions as used in the equation for skin dose in Section A.1.2.4.
)
Application RETS require the dose rate due to noble gases in gaseous effluents to be determined to be within the above limit in accordance with methodology specified in the ODCM. (See Section 12.4 of each station's RETS and Technical Specifications.
To comply with this specification, each station uses an effluent radiation monitor setpoint corresponding to an offsite skin dose rate at or below the limit (see Chapter 10). In addition, each station assesses compliance by calculating offsite skin dose rate on the basis of samples obtained periodically in accordance with station procedures.
A.1.4 Dose Due to Non-Noble Gas Radionuclides Requirement RETS provide the following limits, based on 10CFR50 Appendix 1, on the dose to a member of the public from specified non-noble gas radionuclides in gaseous effluents released from each reactor unit to areas at and beyond the unrestricted area boundary:
Less than or equal to 7.5 mrem to any organ during any calendar quarter.
Less than or equal to 15 mrem to any organ during any calendar year, The individual dose components are also required as part of the 40CFR190 assessments and combined as part of the 10CFR20 assessment (See Section A.4). The deep dose due to radionuclides deposited on the ground is considered to be a component of the deep dose equivalent for 10CFR20 and 40CFR190 compliance and an organ (whcle body) dose component for 10CFR50 Appendix l compliance.
Note that as a result of historical regulation evolution, committed dose equivalent (CDE) assessments for ,
10CFR20 and 40CFR190 compliance are made for an adult using Federal Guidance Report No.11 (Reference
- 93) dose conversion factors; assessments for 10CFR50 Appendix I compliance are made for 4 age groups (adult / teenager / child / infant) using Regulatory Guide 1.109 (Reference 6) dose conversion factors.
J g:/odem/ generic / Attar 2-0/ A-7 l
7 Revision 2.0 April 1999 Equation
\ l'
(),/ The committed dose equivalent (CDE) is calculated for releases in the time period under consideration.
Specifically, the CDE is calculated as the sum of two contributions:
D""83 = D " 3 + D'"d,, (A-13)
D"" , Committed Dose Equivalent (CDE) D:le to Non-Noble Gas [ mrem]
Radionuclides Sum of the committed dose equivalents to organ j of an individual of age group a due to non-noble gas radionuclides released in gaseous effluents dunng a specified time period. i D'"*', inhalation Committed Dose Equivalent (CDE) [ mrem)
CDE to organ j of an individual of age group a due to inhalation of non-noble gas radionuclides released in gaseous effluents. See Equation A-17 in Section A.1.4.2.
D'"d, Food Pathways Committed Dose Equivalent (CDE) [ mrem] ;
CDE due to ingestion via food pathways (leafy vegetables, produce, l milk, and meat) of non-noble gas radionuclides released in gaseous effluents. See Equation A-18 in Section A.1.4.3.
Application RETS require cumulative and projected dose contributions for the current calendar quarter and the current
[d T calendar year for the specified non-noble gas radionuclides in airbome effluents to be determined at least once per 31 days (see Section 12.4 of each station's RETS and Technical Specifications).
To comply with this specification, each nuclear power station obtains and analyzes samples in accordance with the radioactive gaseous waste or gaseous effluent sampling and analysis program in its RETS. For each organ of each age group considered (adult / teenager / child / infant), the dose for each pathway is calcula e d in every sector (except for sectors over water bodies). The calculation is based on the location assumptions Jiscussed below in conjunction with the pathway equations. For each organ of each age group, the doses are summed in each sector over all pathways. The result for the sector with the highest total dose is compared to the limit.
For a release attributable to a processing or effluent system shared by more than one reactor, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.
The CDE evaluated for an adult is also included as part of the 10CFR20 and 40CFR190 assessment (See Section A 4).
A.1.4.1 Ground Deposition The dose due to ground deposition of radioactivity is considered to be a whole body dose (deep dose equivalent) component and is calculated by the following expressions:
D8"' = (24)(0.7)t,I{ DFG,C8,) (A-14)
C8, = (dA)[1 - exp( A,t.)] (A 15)
(D
/
g:/odem/ generic / Attar 2-0/ A8
7-
, s Revision 2.0 1
April 1999 d, = [(1E6)/(24t,)] x [A',,(D/Q), + A',,(D/Q), + A',,(D/Q),] (A 16)
O V The summation is over non-noble gas radionuclides T, ,
D*"' Ground Deposition Deep Dose Equivalent (DDE) [ mrem)
DDE due to ground deposition of non-noble gas radionuclides released in gaseous effluents.
24 Conversion Constant (days to hours) [hr/ day) 0.7 Shielding Factor; a dimensionless factor which accounts for shielding due to occupancy of structures.
t, Release or Exposure Period [ days)
Time period of the calculation (e.g., number of days in the quarter for a calendar quarter calculation).
DFG, Ground Plane Dose Conversion Factor [(mrem /hr)/(pCi/m2 )]
Dose rate to the whole body per unit of ground radioactivity concentration due to standing on ground uniformly contaminated with radionuclide T. See Table C-10 of Appendix C.
CS, Ground Plane Concentration [pCi/m2) I Concentration of radionuclide T on the ground.
- d. Deposition Rate [(pCi/hr)/m2)
Rate at which radionuclide T is deposited onto the ground.
A, Radiological Decay Constant [hr')
Radiological decay constant for radionuclide T. See Table C-7 of Appendix C.
t,, Time Period of Ground Deposition [hr)
Time period during which the radioactivity on the ground is assumed to have been deposited. See Table C-1 of Appendix C.
1E6 Conversion Constant (pCi to pCi) [pCi/pCi] ,
A',, Cumulative Radionuclide [ Ci)
A',, Release, Adjusted for Radiodecay A',,
Measured cumulative release of radionuclide T from a stack, vent, or ground level release point, reduced to account for radiodecay in transit from the release point to the dose point.
See Section A.1.2.2.
(D/Q), Relative Deposition Factor [m 2]
g:/odem/ generic / Attar 2-0/ A-9 L
Revision 2.0 April 1999 (D/Q),
(' -(D/Q), Rate of deposition of radioactivity at a specified location per unit of radioactivity release rate for a stack, vent, or ground level release. See Section 4.1.7, Section B.4 of'Ap#ndir. B, and Table F-5 of Appendix F.
Application The deep dose equivalent (DDE) due to ground deposition is determined for each sector using the highest calculated offsite value of D/Q for that sector. This value and the distance R to which it pertains are provided in Table F-5 of Appendix F. This dose component is included in the calculation of the total DDE (see equation A-35).
A.1.4.2 inhalation The committed dose equivalent (CDE) due to inhalation is calculated by the following expression:
D"3 = (3.17E4)(1E6)(R ) (A-17) x I{ DFA,[(X/Q),A' + (X/Q)A' + (X/Q),A*g] }
The summation is over non-noble gas radionuclides T.
D", inhalation Committed Dose Equivalent (CDE) [ mrem)
CDE to organ j of an individual in age group a due to inhalation of non-noble gas radionuclides released in gaseous effluents.
3.17E4 Conversion Constant (seconds to years) [ yrs /sec) 1E6 Conversion Constant ( Cito pCi) [pCi/pCi]
R, Individual Air Inhalation Rate [m8/yr)
The air intake rate for individuals in age group 'a' See Table C-2 of Appendix C.
DFA, inhalation Dose Commitment Factor [ mrem /pCi)
Dose commitment to organ T of an individual in age group 'a' per unit of activity of radionuclide T inhaled.
Assessment Dose Factor Ace Group 10CFR50 App.I Reg. Guide 1.109 All(four)
Tables E-7 through E-10 l
10CFR20/40CFR190 Federal Guidance Adult only l Report-11: Table 2.1 (average individual) i (X/Q), Relative Effluent Concentration [sec/m')
(X/Q), l (X/Q), Radioactivity concentration at a specified location per unit of radioactivity release rate. See Section 4.1.6, Section B.3 of Appendix B, and Table F-5 of Appendix F.
A',,,A'w,A', Cumulative Radionuclide Release, Adjusted for Radiodecay [ Ci]
g:/odem/ generic / Attar 2-0/ A 10
Revision 2.0
[ April 1999 Measured cumulative release of radionuclide T from a stack, vent, or ground level release point, reduced to account for radiodecay in transit from the release point to the
( dose point. See Section A.1.2.2. ,
Application The CDE due to inhalation is determined for each sector using the highest calculated offsite value of X/O for that sector. This value and the distance R to which it pertains are provided in Table F-5 of Appendix F. This dose component is included within the total CDE from all pathways (see equations A-13 and A-38).
A.1.4.3 Food Pathways The committed dose equivalent (CDE) due to food pathways is calculated by the following expression:
D'***p=(t,/365) x I{DFl.,[i",, + l',, + I",, + l',,) } (A-18)
The summation is over non-noble gas radionuclides T.
D'**d, Food Pathways Committed Dose Equivalent (CDE) [ mrem]
CDE commitment to organ j of an individual in age group a due to ingestion via food pathways (leafy vegetables, produce, milk, and meat) of non-noble gas radionuclides released in gaseous effluents.
t, Time Period of Release or Exposure [ days)
(e g., number of days in a quarter for a calendar quarter calculation).
1/365 Conversion Constant (days to years) [yr/ day)
DFI,, Ingestion Dose Commitment Factor [ mrem /pCi]
Dose commitment to organ 'j' of an individualin age group 'a' per unit of activity of radionuclide T ingested.
Assessment Dose Factor Ane Group 10CFR50 App i Reg. Guide 1.109 All(four) l Tables E-11 through E-14, 10CFR20/40CFR190 Federal Guidance Adult only Report-11; Table 2 2 (average individual)
Ivi ,i',,, Rate of ingestion of Activity [pCi/yr]
I",,,l',, Activity of radionuclide T ingested annually by an individualin age group a from, respectively, the following:
. Leafy vegetables.
. Produce (nonleafy vegetables, fruits, and grain).
- Milk.
Meat (flesh).
Calculated as follows:
IV., = UV, f, CV, (A 19)
I",, = U', f, C"i (A 20) p I" = U", C"i (A-21) d g:!odem! generic / Attar 2-0! A-11
D.
Revision 2.0 April 1999 l'i. = U', C', (A 22)
(g D UV, Food Product Consumption Rat,e ,,
[kglyr]
U. [kglyr]
U". [L/yr]
U'. [kglyr]
Annual consumption (usage) rate of leafy vegetables, produce, milk, or meat, respectively, for individuals in age group 'a'. See Table C-2 of Appendix C.
fy Food Product Affected Fraction f, Fraction of ingested leafy vegetables (V) or produce (P) grown in the garden of interest. See Table C-1 of Appendix C.
CV, Food Product Radioactivity Concentration [pCi/kg]
C', [pCi/kg)
C", [pCi/L]
C's [pCi/kg]
CVi and C', represent, respectively, the average concentration of radionuclide i in leafy vegetables and produce grown in the garden of interest. Calculated from the amount of radioactivity released and the relative deposition factor D/O at the garden of interest.
See Section A.1.4.3.1 below for the equation.
C5 and C', represent, respectively, the average concentration of radionuclide i in milk and meat from the producer of interest.
[dD Calculated from the amount of radioactivity released and the relative deposition factor D/O at the locations of the producers of interest. See Sections A.1.4.3.2 and A.1.4.3.3 below for equations.
Application The dose due to ingestion of leafy vegetables and produce is calculated in each sector for a hypothetical garden assumed to be located at the location of highest offsite D/O (see Table F-5 of Append:x F). The dose due to ingestion of milk and meat is calculated in each sector for the location of the nearest producer as specified in Table F-6 of Appendix F, if there is no actual milk or meat producer within 5 miles of the station, one is assumed to be located at 5 miles (food pathway calculations are not made for sectors in which the offsite regions near the station are over bodies of water).
A.1.4.3.1 Vegetation The radioactivity concentration in leafy vegetables (CV), i produce (C'i), or other vegetation is calculated by the following expression.
C, = [(d,)(r)/(Y,)(Asi)] x [1 - exp(-Aa ,t.)] [exp(-Atn)](f i i) (A-23) {
C, Food Product Radioactivity Concentration [pCi/kg]
Average concentration of radionuclide 'i'in leafy vegetables, produce, or other vegetation. !
1 d, Deposition Rate [(pCi/hr)/m2] l p Rate at which radionuclide 'i' is deposited onto the ground.
l g:/odem/ generic / Attar 2-0! A 12 !
Revision 2.0
- April 1999 Calculated from the amount of radioactivity released and the relative deposition factor D/O at the location of interest. See O' Section A.1.4.1 for an equation. See the Subsection " Application" in Section A.1.4.3 for the loca' tion assumption *iused in determining d,.
r Vegetation Retention Factor Fraction of deposited activity retained on vegetation.
See Table C-1 of Appendix C.
Y, Agricultural Productivity Yield [kg/m2]
The quantity of vegetation produced per unit area of the land on which the vegetation is grown. See Table C-1 of Appendix C.
1,, Effective Decay Constant d
[hr )
Effective removal rate constant for radionuclide 'i' from vegetation:
Agi = A, + ( (A-24)
A. Radiological Decay Constant [hr')
Radiological decay constant for radionuclide 'i'.
See Table C-7 of Appendix C.
( Weathering Decay Constant [hr')
O 7 Removal constant for physical loss by weathering.
See Table C-1 of Appendix C.
t, Effective Vegetation Exposure Time [hr)
Time that vegetation is exposed to contamination during the growing season. See Table C-1 of Appendix C.
t,, Harvest to Consumption Time [hr)
Time between harvest and consumption.
See Table C-1 of Appendix C.
f, Seasonal Growing Factor Factor which accounts for the seasonal growth of vegetation.
It has the value '1' during the growing season, 'O' otherwise.
See Table C-1 of Appendix C.
A.1.4.3.2 Milk The radioactivity concentration in milk is calculated by the following expressions:
C", = F. C', W, exp(-A,t.) (A-25)
C', = f, f, C', + (1 - f.)C', + f,(1 - f,)C', (A 26)
O g:/odem/ generic / Attar 2-0/ A 13
Revision 2.0 April 1999 C", Milk Radioactivity Concentration [pCi/l.]
/ Average concentration of radionuclide T in milk from the producer ofinterest. , ,_
F. Milk Fraction { days /L]
Fraction of an animal's daily intake of radionuclide i which appears in each liter of milk (pCi/L in milk per pCi/ day ingested by the animal). See Table C-3 of Appendix C.
j C', Feed Concentration [pCi/kg]
Average concentration of radionuclide T in animal feed.
W, Feed Consumption (kg/ day]
Amount of feed consumed by the animal each day.
See Table C-1 of Appendix C.
A, Radiological Decay Constant d
[hr]
Radiological decay constant for radionuclide T.
See Table C-7 of Appendix C.
- t. Milk Transport Time
[hr]
Average time from the production of milk to its consumption.
See Table C-1 of Appendix C.
f, Pasture Time Fraction l l l
Fraction of time that animals graze on pasture.
i See Table C-1 of Appendix C.
f, Pasture Grass Fraction ;
i Fraction of daily feed that is pasture grass when animals I graze on pasture. See Table C-1 of Appendix C. !
C', Pasture Grass Concentration [pCi/kg)
{
i Concentration of radionuclide T in pasture grass. Calculated using Equation A-20 with the seasonal growing factor f, = 1 and with parameter values specified for the pasture grass and milk pathways in Table C-1 of Appendix C.
C', Stored Feed Concentration [pCi/kg)
Concentration of radionuclide T in stored feed. Calculated using Equation A-20 for Ci with the seasonal growing factor f, = 1 and parameter values specified for the stored feed and milk pathways in Table C-1 of Appendix C.
O g:/odcm/ generic / Attar 2-0/ A-14
Q Revision 2.0 April 1999 A.1.4.3.3 Meat G
The radioactivity concentration in meat is calculated by the following exp,ression:
C', = F, C', W, exp(-At.) (A-27) l C', Meat Radioactivity Concentration [pCi/kg)
Average concentration of radionuclide T in meat from the producer of interest.
Fr Meat Fraction [ days /kg)
Fraction of an animars daily intake of radionuclide T which appears in each kilogram of flesh (pCi/kg in meat per pCi/ day ingested by the animal). See Table C-3 of Appendix C.
1 C', Feed Concentration [pCi/kg)
Average concentration of radionuclide T in animal feed.
Calculated using the equation for C', in the preceding sub-section with parameter values specified for the meat pathway in Table C-1 of Appendix C.
W, Feed Consumption [kg/ day) f,- Amount of feed consumed by the animal each day.
t See Table C-1 of Appendix C.
U, Radiological Decay Constant d A [hr )
Radiological decay constant for radionuclide T.
See Table C-7 of Appendix C.
t, Time From Slaughter to Consumption [hr) I See Table C-1 of Appendix C.
A.1.5 Dose Rate Due to Non-Noble Gas Radionuclides Requirement RETS limit the dose rate to any organ, due to radioactive materials in gaseous effluents released from a site to areas at and beyond the site boundary, to less than or equal to a dose rate of 1500 mrem /yr (see Section 12.4 of each station's RETS and Technical Specifications).
All stations consider the adult to be the receptor in calculating dose commitment to organs due to inhalation of non-noble gas radionuclides in gaseous effluents.
Equation The dose rate to any adult organ due to inhalation is calculated by the following expression:
D*, = (1E6)(R.)I{DFA,[(X/Q),Q'. + (XIQ),Q',, + (XIQ),Q'J} (A-28) g:/odem/ generic / Attar 2-0/ A-15 i
1 i
Revision 2.0 April 1999 {
The summation is over no 1-noble gas radionuclides 'I'.
O -
D'"'*',
l h inhalation Dose Rate ,
(mrem /yr)
Rate of dose commitment to organ j of an individualin age group a due to inhalation of non-noble gas radionuclides released in gaseous effluents; j and a are chosen to correspond to an edult thyroid.
Q' Radionuclide Release Rate, Adjusted for Radiodecay [pCi/sec) t Q'i, l Q'i, Measured release rate of radionuclide 'i' from a stack, vent, or ground level release point, reduced to account for f
radiodecay in transit from the release point to the dose point. See Section A.1.3.2.
The other parameters are defined in Section A.1.4.2.
Application !
RETS require the dose rate due to non-noble gas radioactive materials in airborne effluents be determined to be within the above limit in accordance with a sampling and analysis program specified in the RETS (see Section 12.4 of each station's RETS and Technical Specifications).
To comply with this specification, each station obtains and analyzes samples in accordance with the sampling and analysis program in its RETS. The adult organ dose rate due to inhalation is calculated in each sector at the location of the highest offsite X/Q. Tne result for the sector with the highest organ inhalation dose rate is compared to the limit.
l A.1.6 Operability and Use of Gaseous Effluent Treatment Systems l
Requirement 10CFR50 Appendix 1 and the station RETS require that the ventilation exhaust treatment system and the waste gas holdup system be used when projected offsite doses in 31 days, due to gaseous effluent releases, from each reactor unit, exceed any of the following limits:
. 0.2 mrad to air from gamma radiation.
. 0.4 mrad to air from beta radiation.
. 0.3 mrem to any organ of a member of the public.
The nuclear power stations are required to project doses due to gaseous releases from the site at least once per 31 days.
Each station calculates doses for all members of the public (adult, teenager, child and infant) and then determines the maximum dose. The member of the public who receives the maximum dose will be reported.
Equation Offsite doses due to projected releases of radioactive materials in gaseous effluents are calculated using Equations A-1, A-2 and A-13. Projected cumulative radionuclide releases are used in place of measured cumulative releases A., A,, and A,,.
I 1
l l
/
g:/odem/ generic / Attar 2-0/ A-16
Q.
Revision 2.0 April 1999 Application For a release attributable to a processing or effluent system shared by rnore than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units siiaring the system. The allocation procedure is specified in Chapter 10 of this manual.
A.2 LlQUID RELEASES A.2.1 Dose Requirement The design objectives of 10CFR50, Appendix 1 and RETS provide the following limits on the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released from each reactor unit to restricted area boundaries:
During any calendar quarter, less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ.
During any calendar year, less than or equal to 3 mrem to the total body and less than or equal to 10 mrem to any organ.
The organ doses due to radioactivity in liquid effluents are also used as part of the 40CFR190 compliance and are j included in the combination of doses to determine the Total Effective Dose Equivalent (TEDE) used to I demonstrate 10CFR20 compliance. (See Section A.4) )
As noted earlier, dose assessments for 10CFR20 and 40CFR190 compliance are made for an adult using Federal ,
Guidance Report No.11 (Reference 93) dose conversion factors. Dose assessments for 10CFR50 Appendix l l compliance are made for four age groups (adult / teenager / child / infant) using Regulatory Guide 1.109 (Reference 6) I dose conversion factors. l Equation The dose commitment from radioactive materials in liquid effluents is calculated for the four age groups considering only the two principal pathways for radiation exposure. The dose commitment to each organ (and to the total body) is obtained as the sum of contributions from consumption of drinking water and fish:
I Da, = D**', + D"'", (A 29) )
i D**3= (1.1E 3)(8760)(U*,M*/F") x I{ A,DFI,,exp(-A,t")} (A-30) l D**", = (1.1E-3)(8760)(U',M'/F') x I{ A,B,DFI,,exp(-A,t')} (A-31)
The summations are over i radionuclides.
D'"', Total organ, and total body, dose commitment (CDE) Due [ mrem) to Radioactivity in Liquid Effluents Dose commitment to organ j (and total body) of age group a consuming water and fish containing radioactivity released in liquid effluents.
D **, Committed Dose Equivalent (CDE) Due [ mrem) to Consumption of Drinking Water O
g:!odem/ generic / Attar 2-0/ A-17
Q, Revision 2.0 April 1999 Dose commitment to organ j of age group a consuming water containing radioactivity released in liquid effluents.
~~
D*", Committed Dose Equivalent ('CDE) Due ' [ mrem) to Consumption of Fish Dose commitment to organ j of age group a consuming fish containing radioactivity released in liquid effluents.
U*,, U', Usage Factor [L/hr, kg/hr)
Consumption rate of water (U*,) or fis lU',). See Table C-2 of Appendix C.
1/M*,1/M' Dilution Factor Measure of dHution prior to withdrawal of potable water or fish.
See Table F-1 of Appendix F.
F* Average Flow Rate (cfs)
Average flow rate of receiving body of water at point where Potable water is taken. See Table F-1 of Appendix F.
F' Near-Field Flow Rate [ cts)
Near field flow rate of receiving body of water (in region where fish are taken). See Table F-1 of Appendix F.
A, Radionuclide Release [pCi]
Measured amount of radionuclide 'i' released in liquid effluents during the time period under consideration.
DFI,3 Ingestion Dose Factor [ mrem /pCi]
Dose commitment to organ j (and total body) of an individual in age group 'a' per unit of activity of radionuclide 'i' ingested.
Assessment Dose Factor Aae Group 10CFR50 App.I Reg. Guide 1.109 Ali(four)
Tables E-11 through E-14.
10CFR20/40CFR190 Federal Guidance Adult Report-11; Table 2.2 (average)
A Decay Constant [hr')
Radiological decay constant of radionuclide 'i'.
See Table C-7 of Appendix C. .
t*, t' Elapsed Time [hr)
O g:/odem/ generic / Attar 2-0/ A-18 i
" ', i Revision 2.0 April 1999 Dose commitment to organ J of age group a consuming water containing radioactivity released in liquid effluents.
d Committed Dose Equivalent C (' DE) Due '
~
D", [ mrem) to Consumption of Fish Dose commitment to organ j of age group a consuming fish i containing radioactivity released in liquid effluents.
)
U",, U', Usage Factor [Uhr, kg/hr)
Consumption rate of water (U",) or fish (U',). See Table C-2 of Appendix C.
1/M",1/M' Dilution Factor Measure of dilution prior to withdrawal of potable water or fish.
See Table F-1 of Appendix F.
F* Average Flow Rate [cfs)
Average flow rate of receiving body of water at point where Potable water is taken. See Table F-1 of Appendix F.
F' Near-Field Flow Rate (cfs)
Near field flow rate of receiving body of water (in region where fish are taken). See Table F-1 of Appendix F.
A, Radionuclide Release [pCi]
Measured amount of radionuclide T released in liquid effluents during the time period under consideration.
DFI, Ingestion Dose Factor [ mrem /pCi)
Dose commitment to organ j (and total body) of an individual in age group 'a' per unit of activity of radionuclide T ingested. l Assessment Dose Factor Aae Group 10CFR50 App.I Reg. Guide 1.109 All(four)
Tables E-11 through E-14.
10CFR20/40CFR190 Federal Guidance Adult Report-11; Table 2.2 (average)
A Decay Constant [hr')
Radiological decay constant of radionuclide T.
See Table C-7 of Appendix C.
t", t' Elapsed Time [hr)
A V
g:/odem/ generic / Attar 2-0/ A-18
Revision 2.0 April 1999 Average elapsed time between release and consumption of potable water or fish. See Table F-1 of Appendix F.
~
' ~
B, Bioaccumulation Factor [L/kg)
Equilibrium ratio of the concentration of radionuclide 'i'in fish (pCi/kg) to its concentration in water (pCi/L). See Table C-8 of Appendix C.
1.1E-3 Conversion Constant [(pCi/ liter) per (pCi/yr)/(cfs))
Factor to convert to pCi/ liter from (pCi/yr)/(cfs).
8760 Conversion Constant (hours per year) [hr/yr)
Application RETS require determination of cumulative and projected dose contributions from liquid effluents for the current calendar quarter and the current calendar year at least once per 31 days. (see Section 12.3 of each station's RETS and/or Technical Specifications).
For a release attributable to a processing or effluent system shared by more than one reactor unit, the dose due to an individual unit is obtained by proportioning the effluents among the units sharing the system. The allocation procedure is specified in ODCM Chapter 10.
A.2.2 Liquid Effluent Concentrations Requirement Requirement O One method of demonstrating compliance to the requirements of 10CFR20.1301 is to demonstrate that the annual average concentr'ations of radioactive material released in gaseous and liquid effluents do not exceed the values specified in 10CFR20 Appendix B, Table 2; Column 2. (See 10CFR 20.1302(b)(2).) However, as noted in Section A.5.1, this mode of 10CFR20.1301 compliance has not been elected.
As a means of assuring that annual concentration limits will not be exceeded, and as a matter of policy assuring l that doses by the liquid pathway will be ALARA; RETS provides the following restriction: i "The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to ten times the concentration values in Appendix B, Table 2, Column 2 to 10CFR20.1001-20.2402."
This also meets the requirement of Station Technical Specifications and RETS.
Equation According to the footnotes to 10CFR20 Appendix B, Table 2; Column 2, if a radionuclide mix of known composition is re' eased, the concentrations must be such that E{C/10 ECLJ 51 (A-32) where the summation is over index i (radionuclides).
C, RaJioactivity Concentration in [ Ci/mL)
, Liquid Effluents to the Unrestricted Area Concentration of radionuclide 'i' in liquid released to the unrestricted area.
b] ECL, Effluent Concentration Limit in Liquid [pCi/mL) g:/odem/ generic / Attar 2-0/ A-19
7 Revision 2.0 1
! April 1999 I Effluents Released to the Unrestricted Area
(
(z The allowable annual average concentration ohadionuclide 'i' in liquid effluents released to the unrestricted area. This concentration is specified in 10CFR20 Appendix B, Table 2; Column 2. Concentrations for noble gases are different and are specified in the stations' Technical Specifications /RETS. I 10 Multiplier to meet the requirements of Technical Specific.ations (if approved).
If either the identity or concentration of any radionuclide in the mixture is not known, special rules apply. These are given in the footnotes in 10CFR20 Appendix B, Table 2; Column 2.
Application The RETS and Technical Specifications require a specified sampling and analysis program to assure that liquid l radioactivity concentrations at the point of release are maintained within the required limits. j l
To comply with this provision, each nuclear power station obtains and analyzes samples in accordance with the radioactive liquid waste (or effluent) sampling and analysis program in its RETS. Radioactivity concentrations in tank effluents are determined in accordance with Equation A-33 in the next section. Comparison with the Effluent ,
Concentration Limit is made using Equation A-32.
A.2.3 Tank Discharges When radioactivity is released to the unrestricted area with liquid discharge from a tank (e.g., a radwaste discharge tank), the concentration of a radionuclide in the effluent is calculated as follows:
A
( ) C, = (C\)(F')/(F' + F') (A-33)
V l l
C, Concentration in Liquid effluent to the unrestricted area. [pCi/mL]
Concentration of radionuclide 'i' in liquid released to the unrestricted area.
C', Concentration in the Discharge Tank [pCi/mL)
Measured concentration of radionuclide 'i' in the discharge tank.
F' Flow Rate. Tank Discharge [cfs)
Measured flow rate of liquid from the discharge tank to the initial dilution stream.
F8 Flow Rate, Initial Dilution Stream [cfs)
Measured flow rate of the initial dilution stream that carries the radionuclides to the unrestricted area boundary (e.g.,
circulating cooling water or blowdown from a cooling tower or lake).
b)
Q g:/odem/ generic / Attar 2-0/ A-2 0
Revision 2.0 April 1999 A.2.4 Tank Overflow (3 I V Requirement ,
l To limit the consequences of tank overflow, the RETS/ Technical Specifications may limit the quantity of radioactivity that may be stored in unprotected outdoor tanks. Unprotected tanks are tanks that are not surrounded by liners, dikes, or walls capable of holding the tank contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system. The specific objective is to provide assurance that in the event of an uncontrolled release of a tank's contents, the resulting radioactivity concentrations beyond the unrestricted area boundary, at the nearest potable water supply and at the nearest surface water supply, will be less than the limits of 10CFR20 Appendix B, Table 2; Column 2.
The Technical Specifications and RETS may contain a somewhat similar provision. For most nuclear power stations, specific numerical limits are specified on the number of curies allowed in affected tanks.
Application '
Table F-1 of Appendix F provides information on the limits applicable to affected stations. The limits are as stated i for some stations in the station Technical Specifications.
A.2.5 Operability and Use of the Liquid Radwaste Treatment System Requirement The design objectives of 10CFR50, Appendix 1 and RETS/ Technical Specifications require that the liquid radwaste treatment system be operable and that appropriate portions be used to reduce releases of radioactivity when projected doses due to the liquid effluent from each reactor unit to restricted area boundaries exceed either of the following (see Section 12.3 of each station's RETS or Technical Specifications);
s e 0.06 mrem to the whole body in a 31 day period.
= 0.2 mrem to any organ in a 31 day period.
(v)
Equation '
Offsite doses due to projected releases of radioactive materials in liquid effluents are calculated using Equation A-29. Projected radionuclide releases are used in place of measured releases A,.
A.2.6 Drinking Water Five nuclear pc wer stations (Braidwood, Dresden, LaSalle, Quad Cities, and Zion) have requirements for calculation of drinking water dose that are related to 40CFR141, the Environmental Protection Agency National Primary Drinking Water Regulations. These are discussed in Section A 6.
A.2.7 Non-routine Liquid Release Pathways Cases in which normally non-radioactive liquid streams (such as the Service Water) are found to contain radioactive material are non-routine will be treated on a case specific basis if and when this occurs. Since each station has sufficient capacity to delay a liquid release for reasonable periods of time, it is expected that planned releases will not take place under these circumstances. Therefore, the liquid release setpoint calculations need not and do not contain provisions for treating multiple simultaneous release pathways.
A.3 DOSE DUE TO CONTAINED SOURCES There are presently two types of contained sources of radioactivity which are of concern in Comed offsite radiological dose assessments. The first source is that due to gamma rays from nitrogen-16 (NS) carried over to the turbine in BWR steam. The second source is that due to gamma rays associated with . radioactive material resident in onsite radwaste storage facilities.
O g:/odem/ generic /AnAr2-0/ A-21
I . ,
Revision 2.0 April 1999 Gamma radiation from these sources contributes to the whole body dose (deep dose equivalent).
v A.3.1. BWR Skyshine The contained onsite radioactivity source which results in the most significant offsite radiation levels at Comed nuclear power stations is skyshine resulting from N decay inside turbines and steam piping at boiling water l reactor (BWRs).
The N that produces the skyshine effect is formulated through neutron activation of the oxygen atoms (oxygen-16, or O) in reactor coolant as the coolant passes through the operating reactor core. The N travels
, with the steam produced in the reactor to the steam driven turbine. While the N is in transport, it radioactively l decays with a half-life of about 7 seconds and produces 6 to 7 MeV gamma rays. Typically, offsite dose points are shielded from a direct view of components containing N, but there can be skyshine radiation at offsite locations due to scattering of gamma rays off the mass of air above the steamlines and turbine.
The offsite dose rate due to skyshine has been found to have the following dependencies:
. The dose rate decreases as distance from the station increases.
. The dose rate increases non-linearly as the power production level increases.
. The dose rate increases when hydrogen is added to the reactor coolant, an action taken to improve reactor coolant chemistry characteristics (see Reference 39).
l To calculate offsite dose in a given time period due to skyshine, a boiling water nuclear power station must track the following parameters:
7
. The total gross energy En produced with hydrogen being added.
. The total gross energy E, produced without hydrogen being added.
l The turbines at BWR sites are sufficiently close to each other that energy generated by the two units at each site may be summed.
An initial estimate of BWR skyshine dose is calculated per the following equation:
D*' *(K) (E, + M.E ) x I{OF,SFuexp(-0.007R,)) (A-34)
The summation is over all locations k occupied by a hypothetical maximally exposed member of the public characterized by the parameters specified in Table F-8. The parameters in Equation A-34 are defined as follows:
D*' Dose Due to N-16 Skyshine [ mrem)
Gamma dose (deep dose equivalent) due to BWR N-16 skyshine for the time period of interest.
K Empirical Constant [ mrem /(MWe-br))
A constant determined by fitting data measured at the each station.
E. Electrical Energy Generated Without Hydrogen Addition [MWe-hr]
Total gross electrical energy generated without hydrogen addition in the time period of interest.
E. Electrical Energy Generated with Hydrogen Addition [MWe-br]
g:/odem/ generic / Attar 2 0/ A-2 2
Revision 2.0 April 1999 g] Total gross electrical energy generated with hydrogen
\g addition in the period ofinterest, ,
M. Multiplication Factor for Hydrogen Addition Factor applied to offsite dose rate when skyshine is present.
Hydrogen addition increases main steam line radiation levels typically up to a factor of approximately 5 (see Page 8-1 of Reference 39).
Mn is station specific and is given in Table F-8 of Appendix F.
OF, Occupancy Factor The fraction of time that the dose recipient spends at location 'k' during the period of interest. See Table F-8 of Appendix F.
SF, Shielding Factor A dimensionless factor that accounts for shielding due to occupancy of structures. SF, = 0.7 if there is a structure at location k; SF, = 1.0 otherwise. See Table F-8 of Appendix F.
0.007 Empirical Constant [m"]
A constant determined by fitting data measured at the Dresden station (see Reference 45).
R. Distance [m]
Distance from the turbine to location 'k'. See Table F-8 of Appendix F.
A.3.2 Dose from Onsite Radwaste Storage Facilities Low level radioactive waste may be stored at any, or all Comed nuclear power stations in the following types of storage facilities:
e Interim Radwaste Storage Facility (IRSF) e Concrete vaults containing 48 radwaste liners (48-Pack) e Dry Active Waste (DAW) facilities e Butler buildings / warehouses e Steam generator storage facilities The 48-Pack" is a shie'ded concrete vault which is designed to hold three tiers of radwaste liners in a four by four array. The outer shell of the "48-Pack" is a three-foot thick concrete wall and a two and one-half foot thick concrete cover stab. The vault is placed on a poured concrete slab. The liners may have an average surface dose rate of fifteen (15) rem per hour (or up to 380 rem /hr if a 50.59 evaluation has been completed).
The DAW facility will contain low-level rs;dioactive waste that would result in dose rates less than the 10CFR20 requirements.
Preliminary locations for the 48-Packs and the DAW facilities have been selected for each station. Preliminary dose assessments, which include site-specific occupancy factors, indicate that the expected doses, to members of the public, when fully loaded, will be well within the 40CFR190 annual limits.
A g:/odem/ generic / Attar 2-0/ A-2 3
Revision 2.0
- April 1999 The dose rates resulting from these radwaste storage facilities will be monitored frequently as they are being
(]
v utilized, and if necessary, a dose calculation model similar to that of Equation A-34 will be developed and placed in the ODCM. ,
I A.4 Total Dose Limits (10CFR20 and 40CFR190)
The regulatory requirements of 10CFR20 and 40CFR190 each require " total" doses to be assembled in an appropriate form. Sections A.1 and A.2 considered organ doses from the gaseous and liquid effluent streams. ,
The regulations of 10CFR20 and 40CFR190 also require consideration of direct radiation exposure from contained !
sources of radioactivity. Section A.3 addresses the direct radiation component. The following sections will describe the methodology of assessing direct radiation dose and then the manner in which the various doses are combined to obtain the appropriate " total" for regulatory compliance purposes.
I Annual dose limits in 10CFR20 are now expressed in terms of Total Effective Dose Equivalent (TEDE) where radiation exposures due to inhalation, ingestion and external sources are appropriately weighted to provide a uniform risk based comparison. As defined in 10CFR20, TEDE is equal to the sum of the deep-dose equivalent from external exposures and the committed effective dose equivalent (CEDE) from internal exposures.
A.4.1 Deep Dose Equivalent The deep dose equivalent, H., is comprised of three parts:
- 1) Whole body dose (deep dose equivalent) due to noble gas radionuclides in gaseous effluents (Section A.1.2),
- 2) Dose due to contained sources (Section A.3) and
- 3) Whole body dose due to radioactivity deposited on the ground (Section A.1.4.1).
Expressed as an equation using the notation used in this appendix, then; H, = D + D*r + D'"' (A-35)
Hs Deep Dose Equivalent (DDE) [ mrem]
Dose equivalent due to external whole-body exposure at a tissue depth of 1 cm.
D. Whole Body Dose, Effluents [ mrem]
DDE due to gamma radiation from noble gas radionuclides released in gaseous effluents. See Equation A-6.
D*' Dose Dua 'o N-16 Skyshine [ mrem]
DDE due to skyshine for the period of interest. See Equation A-34.
D'"d Dose From Ground Deposition [ mrem] l DDE due to ground deposition of non-noble gas radionuclides released in gaseous effluents. See Equation A-14. '
A.4.2 Committed Effective Dose Equivalent (CEDE)
The CEDE for internal exposures (He, )is the sum of the products of the weighting factors applicable to each of the body organs, or tissues, that are irradiated and the committed dose equivalent (CDE) to those tissues.
He, = Er W1Hr,.o (A-36) g:/odem/ generic / Attar 2-0/ A-24
Revision 2.0 April 1999
( Hr . Committed Effective Dose Equivalent
[ mrem]
( The committed effective dose equivalent due to internal exposures.
W7 Weighting Factor The weighting factor for organ or tissue (T) which is the proportion of stochastic effects resulting from the irradiation of that organ or tissue to the total risk of stochastic effects when the whole body is irradiated uniformly. Values of Wr are given in Reference #93, Federal Guidance Report 11and in 10CFR20.
Hr,u Committed Dose Equivalent
[ mrem]
The total dose equivalent to organs or tissues (T) that will be received, after an intake of radioactive material by an individual, over the 50 year period following the intake.
The general methodology for calculating the committed dose equivalents from airborne releases is given in Section A.1.4; and from liquid releases in Section A.2.1. In terms of parameters developed earlier in this I document, then, Hr,w = D""S3 + D'*, (A-37) l
{
D"" 3 CDE Due to Non-Noble Gas Radionuclides (mrem]
The sum of the dose and dose commitment to organ j of an individual of age group 'a' due to non-noble gas radionuclides released in 4 gaseous effluents during a specified period. See Equation A-13.
D'*, CDE for an Adult Due to Radioactivity Released in Liquid Effluents (mrem]
The CDE commitment to organ j of an individual of age group 'a' resulting from consumption water and fish containing radioactivity l released in liquid effluents during a specified period. See Equation A-29.
In order to be consistent with the dose factor data, upon which the current revision of 10CFR20 is based, the CDEs D""Spand D"a 3are now calculated using the dose factor data included in Federal Guidance Report No.11 (Reference 93). The Regulatory Guide 1.109 dose factors (Reference 6 and ODCM, Appendix C) are still used for 10CFR50 Appendix 1 compliance.
A.4.3 Total Effective Dose Equivalent l
The above relationships may then be combined into a single equation for the total effective dose equivalent, TEDE, as follows:
TEDE = H, + He, = D. + D** + D'"' + Er Wr (D""*, + D"a3) (A-38)
TEDE Total Effective Dose Equivalent [ mrem)
The sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
O g:/odem/ generic / Attar 2-0/ A-2 5
l' Revision 2.0 April 1999 l O A.5 COMPl iM'CE TO TOTAL DOSE LIMITS Nj - ...
A.S.1 Total Effective Dose Equivalent Limit - 10CFR20 Compliance '
l Requirement Each station's RETS limits the Total Effective Dose Equivalent (TEDE) to an annual limit of 100 mrem, as required by 10CFR20.1301 (a)(1). The regulations offer licensees the option of demonstrating compliance by one of two
)
l methods 10CFR20.1302 (b)(1) or 10CFR20.1302 (b)(2). The RETS state that the 10CFR20.1302 (b)(1) l l methodology has been selected to demonstrate compliance to 10CFR20.1301 (a)(1). '
1-The general methodology for calculating the TEDE is given in Section A.4.3. In lieu of specific regulatory 1 guidance, this evaluation is conservatively made for an adult living at the nearest residence.
{
in August of 1995, a revision to 10CFR20 was implemented that changed the definition of a member of the public. i As a result, for each nuclear station, estimated doses were calculated for a member of the public who enters the site boundary, but is not authorized for unescorted access to the protected area of the site and does not enter any radiologically posted areas on the site. Realistic assumptions were made for occupancy times and locations visited I while within the site boundary.
t These evaluations indicate that the doses estimated for these members of the public are well within the 10CFR20 I limits. These dose evaluations will be performed annually and if necessary, a model will be developed and included in the ODCM. 1 Equation The TEDE is evaluated using Equation A-38.
i Application I d This evaluation is used to demonstrate compliance to 10CFR20 and satisfy station RETS and Technical Specifications (see Chapter 12).
A.S.2 Total Dose due to the Uranium Fuel Cycle (40CFR190)
Requirement RETS and 40CFR190 limit the annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation frora uranium fuel cycle sources to the following:
. Less than or equal to 25 mrem to the whole body.
- Less than or equal to 25 mrem to any organ except the thyroid.
- Less than or equal to 75 mrem to the thyroid.
Total Dose Components This requirement includes the total dose from operations at the nuclear power station. This includes doses due to radioactive effluents (airborne and liquid) and dose due to direct radiation from non-effluent sources (e.g., sources contained in systems on site). It also includes dose due to plants under consideration, neighboring plants and dose due to other facilities in the uranium fuel cycle.
The operations comprising the uranium fuel cycle are specified in 40CFR190.02(b). The following are included to the extent that they directly support the production of electucal power for public use utilizing nuclear energy:
O e Milling of uranium ore.
( e Chemical conversion of uranium.
t g:/odem/ generic / Attar 2-0/ A-2 6 l l
l l
Revision 2.0 April 1999
. Isotopic enrichment of uranium.
G e Fabrication of uranium fuel.
) =
Generation of electricity by a fight-watered-cooled nuclear po,wer, plant using uranium fuel.
. Reprocessing of spent uranium fuel.
Excluded are:
. Mining operations.
. Operations at waste disposal sites.
. Transportation of any radioactive materialin support of these operations.
The re-use of recovered non-uranium special nuclear and by-product materials from the cycle.
When Compliance Assessment is Required l The calculation of compliance to 40CFR190 regulations is now required as part of demonstration of compliance to 10CFR20 regulations.
Equation The dose due to the uranium fuel cycle is determined with equations A-35 and A-37, sections A.4.1 and A.4.2 respectively.
A.5.3 Summary of Compliance Methodology The required compliance is given in Tables 2-1,2-2 and 2-3. In Table 2-1, the dose components are itemized and i j
referenced, and an indication of their regulatory application is noted. A more detailed compliance matrix is given in j Table 2-3. The locations of dose receivers for each dose component are given in Table 2-2. l j
(m) Further, Table 2-2 states the location of the receiver and occupancy factors, if applicable. In general, the receiver V spends time in locations that result in maximum direct dose exposure and inhales and ingests radioactivity from l l
sites that yield maximum pathway doses. Thus, the dose calculated is a very conservative one compared to the
" average" receiver who does not go out of his way to maximize radioactivity uptakes. Finally, the connection between regulations, the ODCM equations and the station RETS and Technical Specifications is given 4 . Table 12-0.
A.6 DOSE DUE TO DRINKING WATER (40CFR141)
The National Primary Drinking Water Regulations,40CFR141, contain the requirements of the Environmental l Protection Agency applicable to public water systems. Included are limits on radioactivity concentration. Although these regulations are directed at the owners and operators of public water systems, several stations have requirements in their Technical Specifications related to 40CFR141.
A.6.1 40CFR141 Restrictions on Manmade Radionuclides Section 141.16 states the fo!!owing:
(a) The average annual concentration of beta particle and photon radioactivity from man-made radionuclides in drinking water shall not produce an annua! dose equivalent to the total body or any internal organ greater than 4 millirem / year.
(b) Except for the radionuclides listed in Table A-0, the concentration of man-made radionuclides causing 4 mrem total body or organ dose equivalents shall be calculated on the basis of drinking 2 liter of water per day. (Using the 168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> data listed in " Maximum Permissible Body Burdens and Maximum (N Permissible' Concentration of Radionuclides in Air or Water for Occupational Exposure,
) "NBSHandbook 69 as amended August 1963, U.S. Department of Commerce.). If two or more g:/odem/ generic / Attar 2-0/ A-2 7
Revision 2.0
$ April 1999 radionuclides are present, the sum of their annual dose equivalents to the total
(
\
body or any organ shall not exceed 4 millirem / year.
l TABLE A 0 l AVERAGE ANNUAL CONCENTRATIONS ASSUMED TO l PRODUCE A TOTAL BODY OR ORGAN DOSE OF 4 MREM /YR Radionuclide Critical Organ pCl / liter Tritium Total body 20,000 i Strontium-90 ' ' Bone marrow 8.
A.6.2 Application
' The projection or calculation of dose due to the drinking water pathway is made using Equation A-30. Projections are made using projected radionuclides reles.:?< ir, place of measured releases A,. Doses calculated using j Equation A-30 may differ from doses determined by the methodology prescribed in 40CFR141.16.
J When required, a nuclear power station prepares a special report on radiological impact at the nearest community water system. This system is taken as the one listed in Table A-3 of this appendix. The report should include the following:
. The doses calculated by Equation A 30.
. A statement identifying the dose calculation methodology (e.g., a reference to this manual),
e A statement that the doses calculated by the ODCM methodology are not necessarily the same as doses calculated by the methodology prescribed in 40CFR141.16.
e The data used to calculate the doses. This information includes the amounts of radioactivity released and the flow rate and dilution values used (see Table F-1). This information is provided to assist the opercer of the community water system in performing its own dose assessment.
l t
l l-l 1-l 1
i g:/odem/ generic / Attar 2-0/ A-2 8 l
l
Revision 2.0 4
April 1999 1
Table A 1 O
h COMPLIANCE MATRIX ,
Regulation Dose to be compared to limit 10CFR50 . Gamma air dose and beta air dose due to airborne radioactivity in effluent Appendix I plume.
. Whole body and skin dose due to airborne radioactivity in effluent plume are reported only if certain gamma and beta air dose criteria are exceeded.
. CDE for all organs and all four age groups due to iodine and particulate in effluent plume. All pathways are considered.
. CDE for all organs and all four age groups due to radioactivity in liquid effluents.
10CFR20 . TEDE, totaling all deep dose equivalent components (direct, ground and plume shine) and committed effective dose equivalents (all pathways, both airborne and liquid-borne). CDE evaluation is made for adult only using FGR 11 database.
40CFR190 . Whole body dose (DDE) due to direct radiation, ground and plume (now, by reference, exposure from all sources at a station.
also part of 10CFR20
. Organ doses (CDE) to an adult due to all pathways.
A
( ~j RETS/ODCM . " Instantaneous" whole body (DDE), thyroid (CDE) and skin (SDE) dose rates to an adult due to radioactivity in airborne effluents. For the thyroid dose only inhalation is considered.
. " Instantaneous" concentration limits for liquid effluents.
iO Vl g:/odem/ generic / Attar 2-0/ A-2 9
Revision 2.0 4 April 1999 1.
l O Table A-2 Release Point Classifications _,
l 4
Release Release Point Station Point Classification
- Braidwood 1 & 2 Vent Stacks Vent (Mixed Mode)
Byron 1 & 2 Vent Stacks Vent (Mixed Mode) i Dresden 1 Plant Chimney Stack (Elevated) i Dresde.r. 2 & 3 Chimney Stack (Elevated)
, Reactor Building Vent (Mixed Mode) l Ventilation Exhaust Stack LaSalle 1 & 2 Main Station Stack (Elevated)
Vent Stack Standby Gas Stack (Elevated)
Treatment Stack" Quad Cities 1 & 2 Chimney Stack (Elevated)
Reactor Building Vent (Mixed Mode)
Ventilation l Exhaust Stack Zion 1 & 2 Vent Stacks Ground Level 1
"These classifications are based on Sargent & Lundy NSLD Calculation No. CEC-4-88;Rev. O,10/19/88. The definitions of release point classifications (stack, vent and ground level) are given in Section 4.1.4.
- The LaSalle standby gas treatment stack is located inside the main station vent stack.
1 l
O I g:/odem/ generic / Attar 2-0/ A-3 0
Revision 2.0 i April 1999 Table A-3 Nearest Downstream Community Water Systems
~~
Characteristics of Nearest '
Affected Downstream Community Water Supply Comed Nuclear Other Comed Facillties Location Nuclear Stations Upstream of and Upstream of Station Station Distance
- Water Supply Braidwood None Wilmington, None 5 river miles Byron None None within NA*
115 river miles Dresden Braidwood Peoria, Braidwood 106 river LaSalle miles LaSalle Braidwood Peo,ia, Braidwood Dresden 97 river Dresden (sf miles Quad Cities None E. Moline, None 16 river miles Zion None Lake County None intake, 1.4 miles "ODCM Bases and Reference Document (Reference 101) Table O-2 and 0-6 provide the bases of the location and distance data.
- NA = not applicable. For purposes of the calculations in the ODCM, there are no community water supplies affected by liquid effluents from Byron Station. This is based on the absence of community water supplies between the Byron Station liquid discharge to the Rock River and the confluence of the Rock and Mississippi Rivers,115 miles downstream.
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D Revision 2.0 4
April 1999 Table A-4 40CFR190 Compliance , _,
1 l
40CFR190 Dose Annual Limit ODCM Equivalent Dose and Equation Number (mrem)
Whole Body 25 Deep Dose Equivalent; A-35 Thyroid 75 Thyroid Committed Dose Equivalent; A-37 evaluated for thyroid Other Organs 25 Organ Committed Dose Equivalent; A-37 evaluated for all organs except thyroid I
Notes:
- 1. The evaluation is made considering the following sources:
- a. Radioactivity in contained sources within the station;
- b. Radioactivity in station gaseous and liquid effluents.
- 2. Dose contributions from neighboring stations and other facilities in the nuclear fuel cycle.
I g:/odem/ generic / Attar 2-0/ A-3 2 1
i
" Revision 2.0 April 1999 APPENDIX B O MODELS AND PARAMETERS FOR AIRBORNE and LIQUID EFFLUENT CALCULATIONS ,
TABLE OF CONTENTS PAGE SECTION 1: Models and Parameters for AIRBORNE Effluent Calculations .
B.O INTRODUCTION B-1 B.1 METEOROLOGICAL DATA AND PARAMETERS B-1
- 1. Data B-2 ,
- 2. Joint Frequency Distribution B-2
- 1. Downwind Direction Versus Upwind Direction B-2
- 2. Stack JFD B-3
- 3. Ground Level JFD B-3 j
- 4. Vent JFDs B-3 t
- 3. Average Wind Speed B-4 1
- 1. Stack Release B-5 l
- 2. Ground Level Release B-5
- 3. Vent Release B-5 ,
I B.2 GAUSSIAN PLUME MODELS B-6 1
- 1. Mathematical Representation B-6
- 2. Sector-Averaged Concentration B-7 B.3 RELATIVE CONCENTRATION FACTOR XIQ B-7
- 1. Stack Release .
B-8
- 1. Effective Release Height B-9
- 1. Plume Rise B-9 l
- 2. Terrain Effects B-11 1
- 2. Ground Level Release B-11
- 3. Vent Release B-12
- 4. Removal Mechanisms B-12 B.4 RELATIVE DEPOSITION FACTOR D/Q B-12
- 1. Stack Release B-13
- 2. Ground Level Release B-14
- 3. Vent Release B-14 B5 GAMMA AIR DOSE FACTORS (Si, Vi , Gj) B-15
- 1. Stack Release B-15
- 2. Ground Level Release B-17
- 3. Vent Release B-17
(
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- Revision 2.0 April 1999 APPENDIX B Table of Contents (Cont'd)
\
PAGE
~
B.6 WHOLE BODY DOSE FACTORS (SS G,) B-18
- 1. Stack Release B-18
- 2. Ground Level Release B-18
- 3. Vent Release B-19 B.7 BETA AIR AND SKIN DOSE FACTORS (Li, l.i) B-19 B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi B-19 B.9 INHALATION DOSE COMMITMENT FACTOR DFAja i B-20 B.10 INGESTION DOSE COMMITMENT FACTOR DFlja i B-20 B.11 MEASURED RELEASE PARAMETERS B-20 B.12 RADIOLOGICAL DECAY CONSTANTS B-20 B.13 PRODUCTION / EXPOSURE PARAMETERS B-20 SECTION 2: Models and Parameters for LIQUID Effluent Calculations:
B.14 INTRODUCTION B-21 B.15 DOSE B-21
- 1. Drinking Water B-21
- 2. Aquatic Foods (Fish) B-22
- 3. Parameters B-22
- 1. Flow, Dilution, and Transport Time B-22
- 1. River Model B-22
- 2. Lake Michigan Model B-23
- 2. Dose Factors B-23
- 3. Measured Releases B-23
- 4. Radiological Decay B-23
- 5. Consumption B-24 j l
B.16 CONCENTRATION IN TANK DISCHARGES B-24 1 i
O G:/odem/ generic /AttBr2-0/ B-ii
g
- Revision 2.0 April 1999 APPENDIX B
('-
LIST OF TABLES ...
NUMBER TITLE PAGE B-1 Portion of an Example Joint Frequency Distribution B-25 LIST OF FIGURES NUMBER TITLE PAGE B-1 Instantaneous View of a Plume B-26 B-2 A Gaussian Curve B-27 B-3 Effect of Observation Period on Plume Shape B-28 B-4 A Gaussian Plume B-29 B-5 Illustration of Model for Calculating B-30 Dose Due to Radioactivity Release B-6 Illustration of Model for Dilution of B-31 Tank Discharge N
)
O G:/odem/ generic /AttBr2-0/ B-iii
, Revision 2.0 l'
April 1999 SECTION 1: i r~N h MODELS AND PARAMETERS FOR AIRBORNE EFFLUENT CALCULATIONS ~
B.O INTRODUCTION The equations used for calculation of doses due to radioactive airborne effluents are given in Section A.1 of Appendix A. The equations involve the following types of parameters:
- Meteorological Parameters These include X/Q, D/Q, and wind speed. Their values are based on historical average atmospheric conditions at a site for a selected multi-year historical period (see Section 4.1.5).
. Dose Factors These parameters are used to provide a simple way to calculate doses and dose rates due to gamma and beta radiation Some of these parameters are independent of meteorological conditions and therefore generic (i.e., not station-specific). Others have values based on historical average atmospheric conditions for a selected multi-year historical period and are therefore station-specific.
. Measured Release Parameters These are measured values of radioactivity releases and release rates.
- Radiological Decay Constants These are used to account for the radioactive decay between the release of radioactivity to the environment and the exposure of persons to it.
- Production / Exposure Parameters These are parameters characterizing agricultural production (e.g., length of growing season, p transport times) and human exposure patterns (e.g., exposure period, breathing rate, food consumption rates). These parameters affect the quantities of radioactivity to which persons ,
may be exposed. 1 This appendix discusses the methodology used to determine values of these parameters. Section B.1 addresses how the historical meteorology of a site is characterized by use of a function called the joint l frequency distribution. Section B.1 and Sections B.3 through B.6 present equations that use the joint frequency distribution to obtain values for site-specific meteorological and dose parameters. Most of these equations involve a mathematical model of a plume known as the Gaussian plume model. This model is developed in Section B.2. Various genene dose factors are discussed in Sections B.7 through B.10. The other parameters are discussed in the remaining sections.
B.1 METEOROLOGICAL DATA AND PARAMETERS Predicting where airborne effluent will travel requires information on the following:
. Wind speed l
e Wind direction
- Atmospheric turbulence The greater the atmospheric turbulence, the more an effluent plume will tend to broaden and the more dilute the concentration will be. Atmospheric turbulence is affected by the general condition of the atmosphere (e g., the vertical temperature distribution) and by local features (e g., objects that protrude I into the wind stream). A commonly used classification scheme for the degree of atmospheric turbulence '
associated with the general condition of the atmosphere involves seven stability classes:
G:/odem/ generic /AttBr2-0/ B-1
l
)
I
, Revision 2.0 i April 1999 A Extremely Unstable
/^ B Moderately Unstable V}
C Slightly Unstable
- ~
l D Neutral i
l E Slightly Stable l F Moderately Stable {
G Extremely Stable ,
i This classification scheme is based on Reference 5, Table 1. Each class is associated with a particular l range of wind direction fluctuations and of vertical temperature gradients in the atmosphere. These are specified in Table C-4 of Appendix C. {
B.1.1 Data t Historical atmospheric conditions at each nuclear power station were recorded by an instrumented meteorological tower that measured wind speed, wind direction, and temperature at various heights.
Hourly everage values of wind speed, wind direction, and stability class were determined. The difference in temperature between two heights was used to assign an atmospheric stability class based on the l
correlation between temperature gradient and stability class in Table C-4 of Appendix C. i l
In obtaining the data, quality assurance checks and corrections were made. Also, corrections were applied to compensate for the limitations of wind sensors at low speeds. A calm was said to exist if the wind speed was less than that of the threshold of either the anemometer (wind speed meter) or the wind !
direction vane. For calm conditions, a wind speed equal to one-half of the higher threshold was assigned.
For each stability class, the wind directions during calm conditions were assumed to be distributed in proportion to the observed wind direction distnbution of the lowest non-calm wind speed class.
j i
B.1.2 Joint Frequency Distribution l The data for a particular historical period are summarized by developing a joint frequency distribution (JFD). Each such distribution specifies the fraction of time during the historical period that the following l jointly occur:
e Wind speed within a particular range (wind speed class).
i . Downwind direction in one of the 16 sectors corresponding to the 16 principal compass i directions (N, NNE, etc.).
l e Atmospheric conditions corresponding to one of the seven atmospheric stability classes !
discussed in Section B.1. Table B-1 of this appendix displays a portion of an example JFD.
Different JFDs are associated with the different release classifications defined in Section 4.1.4. One JFD is defined for stack releases, and another JFD is defined for ground level releases. Two JFDs are l
associated with vent (mixed mode) releases, one for the portion of the time the release is treated as elevated and the other for the portion of the time the release is treated as ground level.
B.1.2.1 Downwind Direction Versus Upwind Direction Unless otherwise noted, any reference to wind direction in this document represents downwind direction, i.e., the direction in which the wind is blowing toward. This is because the parameters developed in this document are used to calculate radioactivity concentration and radiation dose downwind of a release point. In contrast, it is conventional for meteorologists to provide JFDs based on upwind direction, the direction from which the wind is blowing. For example, the JFDs presented in the annual operating reports of the nuclear power stations are obtained from a meteorological contractor and the directions
, fG specified in the reports are upwind directions. Users of JFDs should always be careful to hscertain V whether the directions specified are upwind or downwind.
G:/odem/ generic /AttBr2-0/ B-2 I
. Revision 2.0 April 1999 B.1.2.2 Stack JFD d For a stack release, the JFD is defined as follows: ~
If s(n,0,c) Joint Frequency Distribution, Stack Release The fraction of hours during a period of observation that all of the following hold:
. The average wind speed is within wind speed class n.
. The downwind direction is within the sector denoted by 0.
. The atmospheric stability class is c.
This function is defined for application to a stack release point (see Section 4.1.4). Its value is based on hourly average wind data obtained at a height representative of the release point height.
The stack JFD is normalized to 1:
E fs(n,0,c) = 1 (B-1)
The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c.
B.1.2.3 Ground Level JFD For a ground level release, the JFD fg(n,0,c) is defined in the same way as for a stack release except that the wind data are obtained at a height representative of a ground level release point. This height is d taken as about 10 meters.
The ground level JFD is normalized to 1: j I f g(n,0,c) = 1 (B-2)
The summation is over all wind speed classes n, all compass direction sectors, and all stability classes c.
B.1.2.4 Vent JFDs in accordance with the approach recommended in Regulatory Guide 1.111 (Reference 7), the plume from a vent release is treated as elevated part of the time and as ground level the rest of the time. Two JFDs are determined:
e fy,,l,y(n,0,c) characterizes the plume during the part of the time that it is considered elevated; e
f v,gnd(n,0,c) characterizes the plume during the part of the time that it is considered ground level.
Their definitions are as follows:
f y,,g,y(n,0,c) Joint Frequency Distribution, Elevated Portion of a Vent Release O
G:/odem/ generic /AttBr2-0/ B-3
- Revision 2.0 April 1999 The fraction of hours during a period of observation that the plume is considered elevated and that all of the following hold:
Os .
The average wind speed is within wind speed class n.
The downwind direction is within the secf6r denoted by 0.
. The atmospheric stsbihty class is c.
fv,gnd(n,0,c) Joint Frequency Distribution, Ground Level Portion of a Vent Release The fraction of hours during a period of observation that the plume is considered ground level and that all of the following hold:
. The average wind speed is within wind speed class n.
. The downwind direction is within the sector denoted by 0. ,
. The atmospheric stability class is c. f The value of fy,,l,y(n,0,c) is based on hourly average wind data at a height representative of the vent release point. Where the measurement height differed considerably from the release height, wind speed data for the release height was obtained by extrapolation. The value of yf ,gnd(n,0,c) is based on hourly average wind data obtained at a height representative of a ground level release point. This is taken as i about 10 meters.
The sum of these two JFDs is normalized to 1:
I{ f y,,i,y(n,0,c) + fv,gnd(n,0,c) } = 1 (B-3) l O The summation is over all wind speed classes n, all compass direction sectors 0, and all stability classes c.
The prescription of Regulatory Guide 1.111 is used in determining the fraction of time that the plume is considered elevated and the fraction of time that it is considered ground level. The fractions are obtained from the ratio of stack exit velocity Woto hourly average wind speed u at the height of the vent release point as follows:
If Wolu > 5, then the plume is considered elevated for the hour. ,
1 if Wolu 51, then the plume is considered ground level for the hour.
if 1 < Wolu 5 5, the plume is considered to be a ground level release for a fraction Gt of the hour and an elevated release for a fraction (1 - Gt ) of the hour where Gt is defined as follows:
Gt = 2.58 - 1.58(W o lu) for 1.0 < Wolu 51.5 (B-4)
Gt = 0.30 - 0.06(Wo lu) for 1.5 < Wolu $ 5.0 (B-5)
B.1.3 Average Wind Speed Using the joint frequency distribution, average wind speeds are obtained for each station. Values are obtained for each downwind direction (N, NNE, etc.) and for various release point classifications (stack, vent, and ground level).
G:/odem/ generic /AttBr2-0/ B-4
- Revision 2.0 l April 1999 B.1.3.1 Stack Release (nj For a stack release, the following formula is used:
us(0) = I{ fs(n,0,c)un}I E(I s(n,0,c) } (B-6) where the summations are over wind speed classes n and stability classes c.
us(0) Average Wind Speed, Stack Release [m/sec)
The average wind speed in downwind direction 0 for a stack release.
un Wind Speed for Class n [m/sec)
A wind speed representative of wind speed class n. For each wind speed class except the highest, unis the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, u n is the lower limit of the wind speed range for the class.
i The parameter f, is defined in Section B.1.2.2.
1 B.1.3.2 Ground Level Release For a ground level release, the following formula is used:
ug(0) = I{ fg(n,0,c)un}/ I{ I g(n,0,c) } (B-7)
( ) where the summations' are over wind speed classes n and stability classes c.
U/ I ug(0) Average Wind Speed, Ground Level Release [m/sec)
The average wind speed in downwind direction 0 for a ground level release. l The parameter fgis defined in Section B.1.2.3.
B.1.3.3 Vent Release j For a vent release, the following formula is used:
uy(0) = I { [f y,eggy(n,0,c) + fv,gnd(n,0,c)]un } IB-8)
/ I{ fy,,gey(n,0,c) + fy,gnd(n,0,c) }
where the summations are over wind speed classes n and stability classes c.
uy(0) Average Wind Speed, Vent [m/sec)
Release The average wind speed in downwind direction 0 for a vent release.
The parameters fy ,,j,y and f ,gnd v are defined in Section B.1.2.4.
~.
l
\.v)
G:/odem/ generic /AttBr2-0/ B-5 ,
1 l l
L
, Revision 2.0 April 1999 B.2 GAUSSIAN PLUME MODELS As a plume of airborne effluents moves away from an elevated release point, the plume both broadens and meanders. It has been found that the time-averaged distribution of matbTialin an effluent plume can be well represented mathematically by a Gaussian function.
B.2.1 Mathematical Representation 4
In a widely used form of the Gaussian plume model, the distribution of radioactivity in a plume is represented mathematically by the equation below:
2 2 2 X(x,y,z) = [Q/(2n oy o z u))exp(-y /2o y) x {exp[-(z-h,)2/2o 2) + exp[-(z+he )2/2o2]} z (B-9)
X(x,y,z) Radioactivity Concentration [pCi/m*]
The concentration of radioactivity at point (x,y,z). The x, y, and z axis are defined as follows:
x Downwind Distance [m]
Distance from the stack along an axis parallel to the wind direction. I I
y Crosswind Distance (m)
Distance from the plume centerline along an axis parallel to the crosswind direction.
z Vertical Distance [m]
Distance from the ground (grade level at the stack) along an axis parallel to the vertical direction.
Q Release Rate [pCi/sec)
Release rate of radioactivity.
cy, cz Horizontal and Vertical Dispersion Coefficients [m]
Standard deviations of the Gaussian distributions describing the plume cross-sections in the y and z directions, respectively. The values of oy andozdepend on several parameters:
. Downwind distance x.
Because a plume broadens and meanders as it travels away from its release point, the values of oy and ozincrease as x increases.
- Atmospheric stability class.
The plume is broadest for extremely unstable atmospheric conditions (Class 1 A) and narrowest for extremely stable conditions (Class G).
. Tim'e period of averaging plume concentration.
G:/odem/ generic /AttBr2-0/ B-6
, Revision 2.0 April 1999 The values of oy and og increase as the averaging period increases.
u Average Wind Speed . [m/sec)
The average wind speed. The average speed of travel of the plume in the x direction.
h, Effective Release Height [m]
The effective height of effluent release above grade elevation.
This mav be greater than the actual release height (see Section B.3.1.1.1).
The two exponential functions of z in the curly brackets of Equation B-9 represent the emitted and reflected components of the plume. The reflected component (represented by the exponential with (z +
h e) in its argument) arises from the assumption that all materialin a portion of the plume that touches ground is reflected upward. This assumption is conservative if one is calculating airbome radioactivity concentration.
B.2.2 Sector-Averaged Concentration Sometimes, it is desired to determine the average concentration of radioactivity in a sector due to release at a constant rate over an extended period of time (e.g., a year). For such a case, it is reasonable to assume that the wind blows with equallikelihood toward all directions within the sector. From Equation B-9, the following equation for ground level radioactivity concentration can be derived:
Xsector = [2.032 f Q/(a 2 z u x)]exp(-h ,/2o2)z (B-10)
Xsector Sector-Averaged Ground Level [pCi/m3)
(j Concentration {
The time-averaged concentration of airborne radioactivity in a sector at ground level at a distance x from the release point.
2.032 A dimensionless constant.
f Sector Fraction The fraction of time that the wind blows into the sector.
Q Release rate of radioactivity. [pCi/sec]
The other parameter definitions are the same as for Equation B-9. 1 B.3 RELATIVE CONCENTRATION FACTOR X/Q I The relative concentration factor X/Q (called " chi over Q") provides a simple way of calculating the ,
radioactivity concentration at a given point in an effluent plume when the release rate is known: l X = Q (XIQ) (B11)
X Concentration of Radioactivity [pCi/m3)
Concentration of radioactivity at point (x,y,z) in the atmosphere.
Q ' Release Rate [' pCi/sec)
G:/odem/ generic /AttBr2-0/ B-7
. Revision 2.0 April 1999 Release rate of radioactivity, f~'
X/Q Relative Concentration Factor ,_ [sec/m3)
Relative concentration factor for point (x,y,z). The airbome radioactivity concentration at (x,y,z) per unit release rate.
Expressions for X/Q based on Gaussian plume models can be obtained from the equations for concentration X in Section B.2 simply by dividing both sides of each equation by the release rate Q. For example, from Equation B-10, we obtain the following expression for the sector-averaged XIQ:
(Xsector/Q) = [2.032 f/(o 2 z u x)]exp(-h ,12o2) z (B-12)
The values of X/Q used in ODCM calculations are both sector-averaged and time-averaged. The time averaging is based on the historical average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is accomplished by use of the joint frequency distribution discussed in Section B.1.2. The formulas used to obtain the time.and sector-averaged XIQ are based on Equation B-12, but vary depending on whether the release is a stack, ground level, or vent release. The three cases are discussed below.
B.3.1 Stack Release For a stack release, the relative concentration factor is designated (X/Q)s. Its value is obtained by the following formula:
(X/Q)s = (2.032/R):E{sf (n,0,c) x [exp (-h 2 ,/2o2 z)]/(u Oz) }
n (B-13) i The summation is over wind speed classes n and atmospheric stability classes c.
(X/Q)s Relative Concentration Factor, [sec/m3)
Stack Release The time- and sector-averaged relative concentration factor due to a stack release for a point at ground level at distance R in downwind direction 0.
2.032 Constant A dimensionless constant.
R Downwind Distance [m]
l The downwind distance from the release point to the point of interest.
f s(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.
h, Effective Release Height [m]
The effective height of an effluent release above grade elevation. For a stack release, h, is obtained by correcting the actual height of the release point for plume rise, terrain effects, and downwash as described in Sectiori B.3.1.1, below.
G:/odem/ generic /AttBr2-0/ B-8
. Revision 2.0 April 1999 oz Standard Vertical Dispersion Coefficient [m]
C A coefficient characterizing vertical plume spread in,[he Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).
l un Wind Speed [m/sec)
A wind speed representative of wind speed class n. For each wind speed class except the highest, unis the average of the upper and lower limits of the wind speed range for the class. For the highest wind speed class, un is the lower limit of the wind speed range for the class.
This expression is recommended by the NRC in Regulatory Guide 1.111 (Reference 7) and is based on a model designated there as the " constant mean wind direction model." in this model it is assumed that the mean wind speed, the mean wind direction, and the atmospheric stability class determined at the release point also apply at all points within the region in which airbome concentration is being evaluated.
B.3.1.1 Effective Release Height For a stack release, the effective height of an effluent plume is the height of the release point corrected for plume rise and terrain effects:
if (hs+ h rp- h ) t< 100 metens, then h=h+hpr e s - ht (B-14)
(~3 If(hs+h pr - h t) > 100 meters, then; V he= 100 meters (B 15) he Effective Release Height [m]
The effective height of an effluent release above grade elevation.
hs Actual Release Height [m]
The actual height of the release above grade elevation.
hr p Plume Rise [m]
The rise of the plume due to its momentum and buoyancy.
(See Section B.3.1.1.1.)
ht Terrain Correction Parameter [m]
l A parameter to account for the effect of terrain elevation on the effective height of a plume. Taken as zero (see Section B.3.1.1.2).
B.3.1.1.1 Plume Rise l
Because nuclear power stations generally have plumes that are not significantly warmer than room I temperature, plume rise due to buoyancy is neglected. The formulas used to calculate plume rise due to (N momentum are given below.
(
G:/odem/ generic /AnBr2-0/ B-9
. Revision 2.0 April 1999 Stability Classes A, B, C, and D For these stability classes (corresponding to unstable and neutral conditionsT hp r is taken as the lesser of two quantities:
hpr = Minimum of [(hpr)1,(hpr)2] (B-16)
(hpr)1 * (144)(Wo/u)2/3(R/d)1/3(d)-hd (B-17)
(hpr)2 = (3)(Wolu)(d) (B-18)
Wo Stack Exit Velocity [m/sec)
The effluent stream velocity at the discharge point.
u Wind Speed [m/sec)
R Downwind Distance [m]
The downwind distance from the release point to the point of interest.
d Internal Stack Diameter [m]
The internal diameter of the stack from which the effluent is released.
hd Downwash Correction [m]
A parameter to account for downwash at low exit velocities.
The parameter h d si calculated by the following equations:
hd = (3)(1.5 - Wo /u)(d)if Wo<1.5u (B-19) hd = 0 if Wa t1.5u (B-20) i Note that (hpr)1 can increase without limit as R increases; thus, the effect of (h pr)2 si to limit calculated l plume nse at large distances from the nuclear power station.
Stability Classes E, F, and G For these stability classes (corresponding to stable conditions), hpr is taken as the minimum of four quantities:
h pr = Minimum of [(hpr)1, (hpr)2, (hpr)3, (hpr)4] (B-21)
(hpr)3 = (4)(F/S)1/4 (B-22)
(hpr)4 = (1,5)(Flu)il3(S)-1/6 (B-23) 4 F Momentum Flux Parameter [m /sec2)
A parameter defined as:
F=Wo2(d/2)2 (B-24)
G:/odem/ generic /AttBr2-0/ B-10
. Revision 2.0 April 1999 O S Stability Parameter (U ~
[1/sec2)
A parameter defined as follows:
Stability Class S E 8.70E-4 F 1.75E-3 G 2.45E-3 The quantities (hpr)1 and (hpr)2 are as defined by Equations B-17 and B-18.
B.3.1.1.2 Terrain Effects Due to general flatness of the terrain in the vicinity of the stations, the terrain correction parameter ht was taken as zero in all calculations of meteorological dispersion and dose parLmeters for this Manual.
B.3.2 Ground Level Release For a ground level release, the relative concentration factor is designated (X/Q)g. Its value is obtained by the following formula:
(X/Q)g = (2.032/R)I{ fg(n,0,c)/(unz S )} (B-25)
The summation is over wind speed classes n and atmospheric stability classes c.
(X/Q)g Relative Concentration Factor, Ground !.evel Release [sec/m3)
The time- and sector-averaged relative concentration factor due to a ground level release for a point at ground level at distance R in downwind direction 0.
f g(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.
Sz Wake-Corrected Vertical Dispersion Coefficient [m]
The vertical dispersion coefficient corrected for building wake effects. The correction is made as described below.
The remaining parameters are defined in Section B.3.1.
Wake-Corrected Vertical Dispersion Coefficient The wake-corrected vertical dispersion coefficient Sz in Equation B-25 is taken as the lesser of two quantities:
Sz = Minimum of [(S z )j,(Sz}2] (B26)
G:/odem/ generic /AttBr2-0/ B-11 l l
l
L ,
, Revision 2.0 April 1999 (Sg), = [o*g + D'/(2n)] (B-27)
(Sg): = (oz )(3 ) . (B-28) 4 Sz Wake-Corrected Vertical Dispersion Coefficient [m] ,
t The vertical dispersion coefficient corrected for building wake effects.
oz Standard Vertical Dispersion Coefficient [m] l l
l The coefficient characterizing vertical plume spread in the Gaussian model for stability class c at distance R (see Table C-5 of Appendix C).
D Maximum Height of Neighboring Structure [m]
j The maximum height of any neighboring structure causing building wake !'
effects (see Table F-2 of Appendix F).
B.3.3 Vent Release For a vent release, the relative concentration factor is designated (X/Q)y. Its value is obtained by the following formula:
(X/Q)y = (2.032/R) I{ fy ,,g,y(n,0,c) (B-29) x [exp(-h*,120*z)]/(un Uz)
+ fv,gnd(n,0,c)/(ungS ) }
The summation is over wind speed classes n and atmospheric stability c, asses c.
(X/Q)y Relative Concentration [sec/m3)
Factor, Vent Release The time and sector averaged relative concentration factor due to a vent release for a point at ground level at distance R in downwind direction 0.
The parameters fy,,l,y(n,0,c) and f v,gnd(n,0,c) are defined in Section B.1.2.4. The parameter Sz is )
defined in Section B.3.2. The remaining parameters are defined in Section B.3.1.
Es.3.4 Removal Mechanisms i in Regulatory Guide 1.111, the NRC allows various removal mechanisms to be considered in evaluating i the radiologicalimpact of airborne effluents. These include radioactive decay, dry deposition, wet l deposition, and deposition over water. Radiological decay is taken into account in the equations of this manual which use X/Q (see Appendix A).
l For simplicity, the other removal mechanisms cited by the NRC are not accounted for in the evaluation or use of X/Q in this manual. This represents a conservative approximation as ignoring removal mechanisms increases the value of X/Q.
B.4 RELATIVE DEPOSITION FACTOR D/Q The quantity D/Q (called "D over Q") is defined to provide the following simple wey of calculating the rate of deposition of radioactivity at a given point on the ground when the release rate t
- own.
G:/odem/ generic /AttBr2-0/ B-12
. Revision 2.0 April 1999
/] d = Q (D/Q) (B-30)
V ~~
l d Deposition Rate [(pCi/m2)/sec)
Rate of deposition of radioactivity at a specified point on the ground.
Q Release Rate of radioactivity. [pCi/sec]
D/Q Relative Deposition Factor [1/m2)
Relative deposition factor for a specified point on the ground. The deposition rate per unit release rate.
The values of D/Q used in this manual are time-averaged. The time averaging is based on the historical l average atmospheric conditions of a specified multi-year time period (see Section 4.1.5) and is l l accomplished by use of the joint frequency distribution described in Section B.1.2. The formulas used to l obtain D/Q vary depending on whether the release is a stack, ground level, or vent release. The three {
cases are discussed below.
B.4.1 Stack Release For a stack release, the relative deposition factor is designated (DlQ)s. Its value is obtained by the following formula:
(D/Q)s = [1/(2nR/16)] I{f,(n,0,c) Dr (c,R,he )) (B-31)
The summation is over wind speed classes n and stability classes c.
O (DlQ), Relative Deposition Factor, Stack Release [1/m2) ;
The time-averaged relative deposition factor due to a stack release for a point at distance R in the direction 0.
2n/16 Sector Width [ radians]
The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle.
R Downwind Distance [m]
The downwind distance from the release point to the point of interest.
f,(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.
Dr(c,R,h.) Relative Deposition Rate, Stack Release [m-1]
The deposition rate per unit downwind distance [pCi/(sec-m)] divided by the source strength [pCi/sec] due to a stack release for stability class c, 1 downwind distance R, and effective release height he. !
O l l
G:/odem/ generic /AttBr2-0/ B-13 i
l 1
l
. Revision 2.0 April 1999 The value is based on Figures 7 to 9 of Regulatory Guide 1.111, which
~T apply, respectively, to release heights of 30,60, and 100 m. Linear (Q interpolation is used to obtain values at intermediate release heights. If the effective release height is greater than 100' meters, then the data for 100 meters are used.
h, Effective Release Height [m]
The effective height of the release above grade elevation.
See Section B.3.1.1.
B.4.2 Ground Level Release For ground level release, the relative deposition factor is designated (D/Q),. Its value is obtained by the following formula:
(D/Q)e = [1/(2nR/16)) D,(R) I{ f,(n,0,c) } (B-32)
The summation is over wind speed classes n and stability classes c.
(DlQ)g Relative Deposition Factor, 2
[1/m )
Ground Level Release The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.
f g(n,0,c) Joint Frequency Distribution, Ground Level Release This function is defined in Section B.1.2.3.
Dr(R) Relative Deposition Rate, Ground Level [m-1)
The deposition rate per unit downwind distance [ Ci/(sec-m)) divided by the source strength [pCi/sec) due to a ground level release for downwind distance R. The value is taken from Figure 6 of Regulatory Guide 1.111 and is the same for all atmospheric stability classes.
l The remaining parameters are defined in Section B.4.1.
B.4.3 Vent Release For a vent release, the relative deposition factor is designated (D/Q)y. Its value is obtained by the following formula:
(D/Q)y = [1/(2nR/16)) x [I{ fy ,,iey(n,0,c) D r(c,R,he) } + D r(R) I{ fv,gnd(n,0,c) }) (B-33)
The summation is over wind speed classes n and stability classes c.
(D/Q)y Relative Deposition Factor, Vent Release [1/m2)
The time-averaged relative deposition factor due to a ground level release for a point at distance R in the direction 0.
G;/odem/ generic /AnBr2-0/ B-14
o
, Revision 2.0 April 1999 The parameters fy,,l,y(n,0,c) and f ,gnd(n,0,c) v are defined in Section B.1.2.4. The remaining parameters are defined in Sections B.4.1 and B.4.2.
(V) ~~
B.5 GAMMA AIR DOSE FACTORS (S;, Vg, G i)
The gamma air dose factors provide a simple way of calculating doses and dose rates to air due to gamma l radiation. For example, using a dose factor DF i, gamma air dose rate may be calculated as follows:
l l
D = IDl (B-34)
Di = I(QgDFg } (B-35)
The summations are over i radionuclides.
1 D Gamma Air Dose Rate [ mrad /yr)
The gamma air dose rate due to all radionuclides released.
Di Gamma Air Dow i sie Due to Radionuclide i [mradlyr)
Qi Release Rate of Radionuclide i [pCi/sec)
DF, Gamma Air Dose Factor for [(mradlyr)/
Radionuclide I (pCi/sec))
. A factor used to calculate gamma air dose or dose rate due to release of radionue;ide i. Gamma air dose rate at a particular location per unit release rate.
Three gamma air dose factors are defined: Si, iV, and G . They are used for stack, vent, and ground level l
releases, respectively. These three release point classifications are defined in Section 4.1.4. The calculation '
of the three dose factors is discussed below.
l l B.S.1 Stack Release For a stack release, the gamma air dose factor Si is obtained by a model similar to that of Equation 6 of Regulatory Guide 1.109 (Reference 6). A sector-averaged Gaussian plume is assumed and the dose factor is evaluated on the basis of historical average atmospheric conditions. The value of Si depends on distance R from the release point and on downwind sector 0.
The following equation is used:
Si = [260/(2xR/16)] x I{f (n,0,c)[exp(-A R/3600u i n)) xEn p (Eg)Ai a 1(h en,u ,c,or ,Ea)/un ) (B-36)
The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.
Si Gamma Air Dose Factor, Stack Release [(mradlyr)/
l (pCi/sec))
l The gamma air dose factor at ground level for a stack release for !
l radionuclide 1, downwind sector 0, downwind distance R from the
! [] release point, and the average atmospheric conditions of a'specified
() historical time period.
G:/odem/ generic /AttBr2-0/ B-1s
. Revision 2.0 April 1999 260 Conversion factor [(mrad-radians-m3-disintegrations)/(sec-MeV-Ci)]
J ~~
Reconciles units of Equation B-36.
2n/16 Sector Width [ radians)
The width of a sector over which the plume direction is assumed to be uniformly distributed (as in the model of Section B.2.2). Taken as 1/16 of a circle.
f.(n,0,c) Joint Frequency Distribution, Stack Release This function is defined in Section B.1.2.2.
Ai Radiological Decay Constant [hr-1)
Radiological Decay Constant for radionuclide I (see Table C-7 of Appendix C).
3600 Conversion Factor [sec/hr]
The number of seconds per hour. Used to convert wind speed in meters /sec to meters /hr.
E. Photon Group Eriergy [MeV/ photon)
An energy representative of photon energy group k. The photons emitted by each radionuclide are grouped into energy groups in order to facilitate analysis.
,/ All photons with energy in energy group k are assumed to have energy E .
b pa(E ) Air Energy Absorption Coefficient [m-1)
The linear energy absorption coefficient for air for photon energy group k. The fraction of energy absorbed in air per unit of distance traveled for a beam of photons of energy En. Distance is measured in units oflinear thickness (meters).
Ani Effective Photon Yield [ photons per disintegration)
The effective number of photons emitted with energy in energy group k per decay of nuclide 1. On the basis of Section B.1 of Regulatory Guide 1.109 (Reference 6), the parameter Ani i s calculated as follows:
Ani = [I(A. E p.(E.)}]/[En pjE=)] (B-37)
The summation in the numerator c over the index m.
Am True Photon Yield (photons per disintegration)
The actual number of photons emitted with energy E.
per decay of nuclide 1.
E. Photon Energy [MeV/ photon)
The energy of the m photon within photon energy group k'.
G:/odem! generic /AttBr2-0! B-16
l I
' Revision 2.0 April 1999
') p.(E.) Air Energy Absorption Coefficient (O [m-1]
l The linear energy absorption coefficient for air for photon energy E..
l(...) i Function l
A dimensionless parameter obtained by numerical evaluation of integrals that arise in the plume gamma dose problem. The value of I depends on the arguments (...) listed in Equation B-36. A specific definition for I is given by Equation F-13 of Regulatory Guide 1.109.
]
The integrals involved in calculating I arise from conceptually dividing up the radioactive plume into small elements of radioactivity and adding up the doses produced at the point ofinterest by all of the small elements. The distribution of radioactivity in the plume is represented by a sector-averagea Gaussian plume I model like that discussed in Section B.2.2.
The parameters R, h., u n, and o, are defined in Section B.3.1. )
B.S.2 Ground Level Release The gamma air dose factor Gi for a ground level release is defined as follows:
Gi Gamma Air Dose Factor, Ground Level Release [(mradlyr)/ )
(pCi/sec)]
The gamma air dose factor at ground level for a ground level release for radionuclide 1, downwind sector 0, downwind q distance R from the release point, and the average atmospheric l
!v) conditions of a specified historical time period. ;
i The value of Gi is obtained by the same equation as used for a stack release, Equation B-36 of Section B.S.1, with the following modifications:
The joint frequency distribution for a ground level release (f, of Section B.1.2.3) is used in place of the one for a stack release (f.).
e in evaluating the i function, the effective release height h. is taken as zero.
This corresponds to use of a finite plume model. This approach differs from that of Regulatory Guide 1.109 in that the regulatory guide has a uniform semi-infinite cloud model to determine dose factors for a ground level release. The approach used here is more realistic than that in the regulatory guide.
B.S.3 Vent Release i For a vent release, the gamma air dose factor is calculated as follows:
Vi = [260/(2nR/16)] x I{f,,..,(n,0,c)[exp(-A R/3600u i n)] x Ani E mp.(E.) 1(h.,un ,c,o,,E6 )/un (B-38)
+ f .ona(n,0,c)[exp( A i R/3600u n)] x Am Exp.(Em) 1(0,un ,c,c,,Ea)/un)
The summation is over wind speed clast,es n, atmospheric stability classes c, and photon group indices k.
Vg Gamma Air Dose Factor, Vent Release [(mradlyr)/
(pCi/sec))
/~N
%s G:/odem! generic /AttBr2-0/ B-17
l
~
Revision 2.0 I April 1999 The gamma air dose factor at ground level for a vent release for radionuclide i,
/'3 downwind sector 0, downwind distance R from the release point, and the V average atmospheric conditions of a specified historical time period.
The parameters f, i.,(n,0,c) and f,,,n (n,0,c) are defined in Section B.1.2.4. The parameter S,is defined in Section B.3.2. The remaining parameters are discussed in Section B.5.1.
B.6 WHOLE BODY DOSE FACTORS (5,9, G i ) 3 The whole body dose factors provide a simple way of calculating doses and dose rates due to gamma irradiation of the whole body. They are similar to the gamma air dose factors (see the discussion at the beginning of Section B.5). The whole body dose factors are defined for stack, vent, and ground level releases, respectively.
B.6.1 Stack Release To obtain the whole body dose factor for a stack release Equation B-36 is modified to account for the attenuation of gamma radiation by 1 cm of tissue with a density of 1 g/m3. The following expression results:
Si = [260/(2nR/16)] x I{ fs(n,0,c)[exp(A iR/3600un)] (B-39) xAki EkPa(En)1(h T e ,un ,c,oz ,Ek ) x [1/un ]exp[-p a(Em)t d l)
The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.
The change is the addition of the factor exp[-pT.(En) ta].
All of the parameters are discussed in Section B.S.1 except the following: l 5, Whole Body Garrma Dose Factor, Stack Release [(mradlyr)/(pCi/sec))
The whole body gamma dose factor at ground level for a stack release for l radionuclide I, downwind sector 0, downwind distance R from the release point, i I
and the average atmospheric conditions of a specified historical time period.
pT(E ) Tissue Energy Absorption Coefficient [cm2fg j j l
The mass energy absorption coefficient for tissue for photon energy group k.
The fraction of energy absorbed in tissue per unit distance of travel for a beam of photons of energy En with distance measured in units of density thickness (g/cm#).
td Tissue Thickness [g/cm2)
An assumed value 2 of tissue thickness used in calculating whole body
- dose.
Taken as 1 g/cm to represent 1 cm of tissue with a density of 1 g/cm .
Accounts for the shielding of the inner more radiosensitive parts of the body by the outer body parts.
B.6.2 Ground Level Release The whole body dose factor G ifor a ground level release is defined as follows:
'Gl Whole Body Gamma Dose Factor, [(mradlyr)/
(, Ground Level Release (pCi/sec)]
G:/odem/ generic /AttBr2-0/ B-18
. Revision 2.0 April 1999 p The whole body gamma dose factor at ground level for a ground level release for radionuclide i, downwind sector 0, downwind distance R ' rom the release point, and the avera'g'e atmospheric conditions of a specified historical time period.
The equation for Gl is obtained from the equation for S i , Equation B-39 of Section B.6.1, by making the two modifications specified in Section B.5.2.
B.6.3 Vent Release To obtain the whole body dose factor for a vent release, Equation B-38 is modified to account for the i attenuation of gamma radiation by 1 cm of tissue with a density of 1 g/cm3. The following expression results:
Vg = [260/(2nR/16)] x E{ [Aki EkPa(Ek)/unl*XP[-P'a(Ek) d t] (B-40) x [exp(-1lR/3600u n )] x [f y ,,ley(n,0,c)l(h,,un ,c,oz,Ek) + fv,gnd(n,0,c)l(0,un ,c,az,Ek )] }
The summation is over wind speed classes n, atmospheric stability classes c, and photon group indices k.
Vi Whole Body Gamma Dose Factor, Vent Release [(mradlyr)/(pCi/sec)]
The whole body gamma dose factor at ground level for a vent release for radionuclide 1, downwind sector 0, downwind distance R from the release point, and the average atmospheric conditions of a specified historical time period.
O The parameters p'a(E k) and td are defined in Section B.6.1. The other parameters are discussed in Section B.5.3.
B.7 BETA AIR AND SKIN DOSE FACTORS (Ll,i.l)
The dose factors Li and i.; provide a simple way of calculating beta air and skin doses and dose rates, just as the gamma air dose factors do (see the discussion at the beginning of Section B.5). Their definitions are as follows:
. L i , discussed in Section A.1.2.2 of Appendix.A, is used to calculate beta air dose due to noble gas radionuclide i and has the following units:
(mradlyr) per (pCi/ m')
. I.l, discussed in Section A.1.2.4 of Appendix A, is used to calculate beta skin dose and dose rate due to noble gas radionuclide i and has the following units:
(mrem /yr) per (pCi/m')
The values used in this manual for Li andi.; are specified in Table C-9 of Appendix C and are taken from Regulatory Guide 1.109. The values are based on a semi-infinite cloud model.
B.8 GROUND PLANE DOSE CONVERSION FACTOR DFGi The ground plane dose conversion facur DFG,is used to calculate dose due to standing on ground g contaminated with radionuclide 1(see Equation A-14 of Appendix A). The units of DFG iare (mrem /hr) per
[v t (pCi/ m').
G:/odem/ generic /AnBr2-0/ B-19
\
, Revision 2.0 April 1999 p
Values are provided (see Table C-10 of Appendix C) for dose to the whole body. The values are taken from Regulatory Guide 1.109 and are based on a model that assumes a uniforml{ contaminated ground plane.
B.9 INHALATION DOSE COMMITMENT FACTOR DFA, The inhalation dose commitment factor DFA, is used to calculate dose and dose rate to organ j of an individual of age group a due to inhalation of radionuclide I(see Equations A-17 and A-28 of Appendix A).
Values of DFA, for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFA, are (mrem) per (pCi inhaled). Values are provided for seven organs, with the whole body considered as an organ (see Tables E-7, E-8, E-9 and E-10 in Reg. Guide 1.109).
Values of DFA, used for 10CFR20 compliance assessments are taken from Table 2.1 of reference 93. l Evaluations are made for the adult only. The units of DFA, are (Sv) per (Bq) inhaled. '
B.10 INGESTION DOSE COMMITMENT FACTOR DFA, The ingestion dose commitment factor DFA, is used to calculate dose to organ j of an individual of age group a due to ingestion of radionuclide I(see Equation A-18 of Appendix A).
Values of DFA, for 10CFR50 compliance are taken from Regulatory Guide 1.109 (Reference 6). The units of DFA, are mrem per pCiingested. In Tables E-11, E-12, E-13 and E-14 of Reg. Guide 1.109, values are provided for seven organs, with the whole body considered as an organ.
Values of DFA, used for 10CFR20 compliance assessments are taken from Table 2.2 of reference 93.
Evaluations are for the adult only. The units of DFA, are Sv per Bq ingested.
O V
B.11 MEASURED RELEASE PARAMETERS Input parameters required for calculations of dose or dose rate due to airborne effluents include measured values of radioactivity release (A.,
i Aw, and A.) or release rate (Q,., Qw, and Q,,)(see Section A.1 of Appendix A). These are obtained per the nuclear power station procedures.
B.12 RADIOLOGICAL DECAY CONSTANTS l Values used for these are obtained from the literature and are specified in Table C-7 of Appendix C.
B.13 FRODUCTION/ EXPOSURE PARAMETERS l These parameters characterize various aspects of agricultural production and human exposure. Values used for generic (site-independent) parameters are specified in Appendix C.
Values of site-specific parameters are given in Appendix F. Many of the values are based on Reg. Guide 1.109, while others are based on site-specific considerations.
O G:/odem/generidAnBr2-0/ B-2 o
, Revision 2.0 April 1999 SECTION 2:
MODELS AND PARAMETERS FOR LIQUID EFFLUENT CALCULATIONS B.14 INTRODUCTION Equations for radiation dose and radioactivity cacentration due to liquid effluents are given in Section A.2 of Appendix A. The equations involve the following types of parameters:
- Flow and Dilution Parameters.
. Dose Factors.
. Measured Release Parameters.
. Radiological Decay Constants.
. Transport / Consumption Parameters.
This section discusses the methodology used to determine these parameters. Section B.15 addresses dose calculations and Section B.16 addresses concentration calculations for tank discharges. For dose calculations, flow and dilution parameters are discussed for two different models; the River Model, which is used for all nuclear power stations except Zion, and the Lake Michigan Model, which is used for Zion.
B.15 DOSE B.15.1 Drinking Water The radiation dose due to consumption of drinking water containing released radioactivity is calculated by Equation A-30 of Appendix A:
D"" = (1.1E-3)(8760)(UW M*/FW) a x I{ AgDFl jai exp(-A i tw)} (A-30 )
The summation is over index i(radionuclides) and the parameters are defined in Section Al2.1 of Appendix A.
This equation can be understood as arising from the following model: I e Release of an amount A of radioactivity over a time period T at a uniform rate A/T into a stream flowing at a constant rate F. [The resulting radioactivity concentration in the flowing stream is (A/T)/F.)
. A fraction of full river flow in which dilution (mixing) occurs is represented by 1/M (with 1/M s; 1).
e The radioactivity decays for a time t with decay constant A.
. Water containing the diluted radioactivity is then consumed at constant rate U for a time period T.
. The dose commitment per unit of ingested radioactivity is DFl.
This modelleads to the following equation for dose commitment:
D = [(A/T)/F) (M) [exp(-At)] (UT) DFl (B 41)
D = U (M/F) A DFl exp(-At) (B-42)
Any set of consistent units can be used for the above parameters. For example, the following would be suitable:
A Released Radioactivity [pCi)
T Period of Release and Consumption [hr)
F Dilution Stream Flow Rate [L/hr) 1/M Additional Dilution Factor [dimensionless)
G:/odem/ generic /AttBr2-0/ B-21
Revision 2.0 April 1999 A Decay Constant
[hr")
t Decay Period ~
[hr)
U Consumption Rate
[Uhr)
DFI Ingestion Dose Commitment Factor [ mrem /pCi]
D Dose Commitment
[ mrem)
In Equation A-30 of Appendix A, units different from the above have been chosen for A and F:
A Released Radioactivity [pCi) l F Dilution Stream Flow Rate [cfs)
With the modified units, Equation B42 takes the following form:
D = KU (M/F) A DFl exp(-At) (843) where K is a units conversion factor which is expressed as follows:
K = [1.1E-3 (pCi/L)(ft'Isoc)/(pCi/yr)] x [8760 hrlyr] (B44)
B.15.2 Aquatic Foods (Fish)
Near the nuclear power stations, the only aquatic food of significance for human consumption is fish. The radiation dose due to consumption of fish containing released radioactivity is calculated by Equation A-31 of V Appendix A:
D f fI
= (1.1E-3)(8760)(U aM /F ) x I{AgBjDFl i jaexp( Ai tf )} (A-31)
The summation is over radionuclides I, and the parameters are defined in Section A.2.1 of Appendix A.
1 The form of this equation is like that used for calculating the dose due to drinking water except for the addition j of the bioaccumulation factor, Bi . This factor is the equilibrium ratio of the concentration of radionuclide iin ;
fish (pCi/kg) to its concentration in water (pCi/L). It accounts for the fact that radioactivity ingested by fish can l accumulate in their bodies to a higher concentration than in the waters in which the fish live.
1 B.15.3 Parameters l B.15.3.1 Flow, Dilution, and Transport Time The values of dilution flow rate F, dilution factor 1/M, and decay period t can differ for water and fish. The ;
dilution and decay parameters for water will depend on where water is drawn, while those for fish will depend on where the fish are caught. Models used to determine these parameters are discussed below. The values used for each station are summarized in Table F-1 of Appendix F. ;
B.15.3.1.1 River Model For the purpose of calculating the drinking water dose from liquid effluents discharged into a river, it is assumed that total mixing of the discharge in the river flow (F") occurs prior to consumption. The measure of dilution used is the parameter 1/M" and may be thought of as the fraction of full river flow in which dilution .
occurs.1/ M* = 1 represents full dilution. il M* less than 1 represents dilution in only a portion of the river, GJodem/ generic /AttBr2-0/ B-22 l
l l l L
. Revision 2.0 April 1999 The river flow is taken as the long-term average (generally 10 years). The time period for decay is based on O the flow time to the nearest potable water intake on the receiving body of water. This location is described in V a footnote to Table F-1 of Appendix F.
For the fish consumption pathway, a near-field dilution flow (F') is used. This is an estimate of the dilution of released radioactivity in the water consumed by fish caught near the station downstream of its discharge. No additional dilution is assumed to occur. The decay time between release of radioactivity and its consumption in fish is taken as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.15.3.1.2 1.ake Michigtn Model Only (Zion) discharges liquid effluents into Lake Michigan. For this nuclear power station, it is assumed that the concentration of radioactivity is diluted initially in the condenser cooling water flow (F*) and then by an additional factor of 60 prior to consumption as potable water (ie; F* = F* / 60). The dilution factor of 60 is the product of the following:
Initial entrainment dilution (factor of 10).
. Plume dilution (factor of 3 over approximately 1 mile).
. Current direction frequency (annual average factor of 2).
For the fish ingestion pathway only, it is assumed that radioactivity is diluted in a hypothetical river of flow F' with dilution il M' = 1.0. To determine F', it was assumed that the near shore lake current constitutes a " river" with the following characteristics:
. Width of 5 miles (based on the observed width of the lake current varying from 2 to 10 miles).
. Deptn of 50 feet (the average lake cepth from shore out to 5 miles near Zion).
. Flow rate of 0.2 miles per hour (the measured, offshore average value). j This results in F' = 4E5 cfs. The decay time between release of radioactivity and its consumption in fish is taken as 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.15.3.2 Dose Factors Equations A-30 and A-31 of Appendix A determine dose due to ingested radioactivity using the same ingestion dose factor DFl ija as used in the evaluation of airborne radioactivity which is ingested with foods.
The units of DFlja i are: -
(mrem) per (pCi ingested)
For 10CFR50 Appendix I compliance, the data of Tables E-1, E-12. E-13 and E-14 of Reg. Guide 1.109, are used for four age groups and for seven organs, with the whole body considered as an organ.
For 10CFR20 compliance, the data of Federal Guidance Report 11 (Reference 93) are used. Data are provided for an adult only, and all organs. Note these data have units of Sieverts per Becquerel ingested and must be multiplied by 3.7x10' to convert to units of (mrem) per ( Ciingested).
B.15.3.3 Measured Releases Calculations of dose due to liquid effluents require measured values of radioactivity release (Ai ) for input.
These release values are obtained per the nuclear power station procedures.
B.15.3.4 Radiological Decay Values used for these constants are obtained from the literature and are listed in Table C-7 of Appendix C.
G:/odem/ generic /AttBr2-0/ B-2 3
, Revision 2.0 {
April 1999 B.15.3.5 Consumption Equations A-30 and A-31 of Appendix A involve consumption rates for water,and fish (UW a anduf).
a The values used are specified for each nuclear power station in Table F-1 of Appendix F. I B.16 CONCENTRATION IN TANK DISCHARGES The concentration of radioactivity in a release to the unrestricted area due to a tank discharge is calculated by Equation A-33 of Appendix A:
Ci = (C t, }(pr)f(pd + pr) (A-33)
The parameters are defined in Section A.2.3 of Appendix A.
The radioactivity concentration released from the tank (Ct at flow rate Fr) is diluted by mixing with the initial dilution stream (with flow rate F') to yield a lower concentration (Ci ) in the combined streams.
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G:/odem/ generic /AttBr2-0/ B 24
Revision 2.0 April 1999 Table B.1 Portion Of Sn Example Jokt Ffeguency -
Distrbution Summary Table of Percent by Direction and Class Cisse N NNE NE ENE E ESC SE SSE 5 A .289 .317 .301 .244 .249 .190 .198 .197 335 5 .190 .187 .178 .158 .125 .065 .079 .130 .193 C .269 .226 .252 .218 .190 .118 .152 .189 .302 D 3.298 2.327 2.338 2.884 1.992 1.334 1.365 2.172 3.012 E 1.466 1.198 .988 1.331 1.661 1.226 1.472 2.553 3.628 F .504 .318 .185 .276 .699 .648 .803 1.293 1.732 G .202 .091 .061 .099 .253 .250 .355 .400 .624 l
Total 6.217 4.663 4.304 5.011 5.169 3.830 4.424 S.933 9.826 l
Summary Table of Percent by Direction and Speed Speed N >#dE NE ENE E ESE SE SSE 5 l l
.078
.45 .098 .099 .030 .009 .000 .014 .032 .046 1.05 .308 .154 .125 .137 ,121 .090 .127
) 2.05 .939 .602 .458 .594 .543
.093
.606
.090
.598 .605 1.008 3.05 1.164 1.030 .779 .981 1.468 1.075 1.093 1.478 1.982 4.05 1.179 1.024 .878 .995 1.243 .831 1.027 1.727 2.110 5.05 .839 .631 .858 .798 .724 .474 .852 1.254 1.636 6.05 .612 .467 .496 .589 .417 .313 .418 .803 1.153 8.05 .755 .437 .612 .695 .310 .313 '.405 .735 1.319 10.05 .253 .157 .183 .165 .032 .093 .103 .180 .374 13.05 .053 .061 .034 .027 .001 .031 .025 .028 .072 18.00 .016 .001 .004 .000 .000 .001 .005 .002 .000 99.00 .000 .000 .000 .000 .000 .000 .000 .000 .000 Total 6.217 4.663 4.304 B.011 5.169 3.830 4.424 6.933 9.826 Summary Table of Percent by Speed and Class Class A B C O E F G 5 peed 45 .004 .001 .000 .095 .257 .275 .346 1.05 .018 .012 .027 .508 1.033 1.080 .780 2.05 .286 .171 .246 3.256 5.028 3.228 1.419 3.05 .744 .428 .616 6.258 7.173 2.272 .985 4.05 .992 .581 .781 8.165 6.404 1.902 .460
- 5.05 .909 .506 .808 7.302 4.357 .607 .077 6.05 .712 .388 .613 6.167 2.938 .164 .013 8.05 .819 .500 .755 7.616 2.734 .081 .011 10.05 .230 .150 .196 2.606 .667 .009 .000 13.05 .075 .032 .055 .755 .161 .001 .000 18.00 .004 .000 .018 .117 .012 .000 .000 99.00 .000 .000 f '
.001 .001 .000 .000 .000
/*
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Revision 2.0 April 1999 Figure B 1 Irstantaneous View of Plume dy Wind m
_ .- f_ .../ _ .a 4,
= =,x b
V) i This figure represents a snapshot of a projection of a plume on the horizontal plane. As it moves downwind, the plume both meanders about the average wind direction and broadens. j (Adapted from Reference 18.) I 1
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Revision 2.0 l April 1999 Figure B-2 i t I
A Gaussian Curve 1.0 -
0.9 -
1 exp 1 z.T 0.8 y , Sc --
2
_ L
- J '_
0.7 -
0.6 -
y .c . 8 0.5 -
0.4 -
0.3 -
0.2 -
0.1 -
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z.T C
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(Adapted from Reference 24 of Chapter 9, Page 81.)
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Reusion 2.0 April 1999 j Figure B-3 O
Effect of Observation Period on Plurne Shah
, y avt='ct #
gos.n avtRaGI P' W e instantutout PLuwt ;
weko tctsga \N _-
vint ut e a_sjs or rsuwt - # > -
A P
/
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,, , ALLAvJwt Co4CENTRefl0W '
b This sketch represents the approximate outlines of a smoke plume observed instantaneously and averaged over periods of 10 minutes and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The diagram on the right shows the i i
s corresponding cross plume distribution patterns. The plume width increases as the period of observation increases (from Reference 18). ,
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Revision 2.0 April 1999 Figure B-4 Z A Gaussian Plume j k
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en x
" (r.-y, Z)
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f s '
'(z.y,0)
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'h* ,
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l This sketch illustrates a plume characterized by Equation B 9. The plume is moving downwind in the x direction. Both the honzontal dispersion parametet o, increase as x increases. The reflected component has been omitted in this itiustration (adapted from Reference 24).
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- Resision 2.0 April 1999 Figure B-5 Illustration of Model for Calculation Dose Due to Radoactrvity Release Release rate Aff pCl/hr 1f.
Flow rate F cfs
)
O f'
Additional There is a time delay i between rolesse 1/M dilution by and consumption factor 1/M II Consumption at rate U Uhr for time period T hours l
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s Reusion 2 0 April 1999 Figure B-6 18ustration of Model for Dilution of Tank Discharge initial Discharge tank 8'l"II'"
stream Radioactivity Flow rate Fd concentration
,,, pc y ,
CI I
~
Flow reta Fd + pr
, Radioactivity Concentration Cg l P' Ca . C i F' + F e
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Revision 2.0 April 1999 APPENDIX C l
GENERIC DATA TABLE OF CONTENTS -
PAGE C.1 INTRODUCTION C-1 C.2 10CFR50 DOSE COMMITMENT FACTORS C-1 C.3 10CFR20 DOSE COMMITMENT FACTORS C-1 l
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LIST OF TABLES NUMBER TITLE PAGE C-1 Miscellaneous Dose Assessment Factors C-3
- Environmental Parameters C-2 Miscellaneous Dose Assessment Factors l - Consumption Rate Parameters C-4 ]
1 l C-3 Stable Element Transfer Data C-5 C-4 Atmospheric Stability Classes C-7 l C-5 Vertical Dispersion Parameters C-8 C-6 Allowable Concentrations of )
l Dissolved or Entrained Noble Gases Released j from the Site to Unrestricted Areas in Liquid '
Waste C-9
- C7 Radiological Decay Constants (A,)in hr" C-10 l ,
C-8 Bioaccumulation Factors B, to be Used in the Absence of Site-Specific Data C-12 C-9 Beta Air and Skin Dose Factors for Noble Gases C-14 C-10 External Dose Factors for Standing on Contaminated Ground C-15 C-11 Sector Code Definitions C-17 l
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Revision 2.0 April 1999 APPENDIX C GENERIC DATA C.1 INTRODUCTION
~
This appendix contains generic (common to one or more of the stations) offsite dose calculation parameter factors, or values. Site specific factors are provided in the station annex Appendix F. The factors described in section C.2 and C.3 are found in the prescribed references and are not repeated in this appendix.
C.2 10CFR50 DOSE COMMITMENT FACTORS The dose commitment factors for 10CFR50 related calculations are exactly those provided in Regulatory Guide 1.109 (Reference 6). The following table lists the parameters and the corresponding data tables in the RG 1.109:
PATHWAY ADULT TEENAGER CHILD INFANT Inhalation RG 1.109: Table E-7 RG 1.109: Table E-8 RG 1.109: Table E-9 RG 1.109: Table E-10 Ingestion RG 1.109: Table E-11 RG 1.109: Table E-12 RG 1.109: Table E-13 RG 1.109: Table E-14 These tables are contained in Regulatory Guide 1.109 (Reference 6). Each table (E-7 through E-14) provides dose factors for seven organs for each of 73 radionuclides. For radionuclides not found in these tables, dose factors will be derived from ICRP 2 (Reference 50) or NUREG-0172 (Reference 51).
C.3 10CFR20 DOSE COMMITMENT FACTORS Dose commitment factors for 10CFR20 related calculations are exactly those provided Federal Guidance
/
Report Number 11 (Reference 93). The following table lists the parameters and the corresponding tables in the RG 1.109:
PATHWAY AVERAGE INDIVIDUAL Inhalation FGR-11: Table 2.1 Ingestion FGR-11: Table 2.2 The factors used in offsite dose calculations are for the seven organs (Gonad. Breast, Lung, R. Marrow, B Surface, Thyroid and Remainder organs) but do not include the Effective (weighted) values. The factors in FGR#11 have units of Sieverts/ Becquerel (Sv/Bq). To convert to traditional units of mrem /pCi multiply the factors by 3.7E+3.
NOTE There are radionuclides listed in FGR-11 that have more than one clearance classification (day, ;
week or year) For these nuclides, a conservative approach was used to pick the dose commitment factors for the dose calculations. For these nuclides, the highest (largest) value was picked for each '
organ no matter which clearance class it belonged to. As a result, for dose calculations involving these nuclides, the resulting calculated dose will be conservatively high when compared to a calculation that uses only the dose commitment factors for the clearance classification with the highest value for the Effective dose conversion factor. For example:
Assume that the radionuclide in question is Mg-28 and the pathway is inhalation. From Table 2.1 in FGR-
- 11. the dose commitment values are:
I Nuclide Class /f. Gonad Breast t.u, n_g R. Marrow B. surface Thyroid Remaindy Effective Mg-28 D 2 91E-10 2 07E-10 2.96E-9 7 96E 10 1.42E-9 1.78E-10 1.04 E-9 916E 10 W 2 59E-10 146E-10 5 92E-9 4 03E 10 6 4E-10 1.07E-10 155E-9 1.33E 9 Mg-28 has two clearance classifications D and W. The clearance class with the highest effective dose conversion factor (the column on the far right) is "W' clearance class. But the actual factors used in the G:/odem/ generic /AttCr2-O' C-1
L Revision 2.0 April 1999 ODCM offsite dosa calcul tions tra picktd from th3 highrst valu3 list:d for sich orgin cs shown in tha bold text in the next table:
O Nuclide gg Goned gry),st g R. Marrow B. Surface '~ Thyroid Romainder Effective Mg-28 0 2.91E-10 2.07E 10 2.96E-9 7.96E 10 1.42E-9 1.78E-10 1.04E-9 9.16E-10 W 2.59E-10 1.46E-10 5.92E-9 4.03E-10 6 4E-10 1.07E-10 1.56E-9 1.33E-9 Since some values are used from each of the classifications (the lung and remainder factors are class W and the gonad, breast, rnarrow, bone surface and thyroid are class D), the actual offsite dose calculation will result in a higher (more conservative) dose than if the organ dose conversion factors corresponding to the highest Effective dose conversion factor were used.
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Revision 2.0 April 1999 Tcble C-1 Miscellaneous Dose Assessment Factors -
Environmental Parameters
, Parameter and Value Basis' f, = 0,76 A fy = 1.0 A tn = 0 for pasture grass (milk and meat pathways) A tn = 24 hr (1 day for leafy vegetables) A tn = 1440 hr (60 days for produce) A in = 2160 hr for stored feed (milk and meat pathways) A
- t. = 720 hr (30 days for milk and meat) A
- t. = 1440 hr (60 days for produce or leafy vegetables) A f, = 1.0 May-October B f, = 0.0 November-April B f, = 0.5 B 1, = 0.0021 hr" A Y, = 2.0 kg/m' for leafy vegetables and produce pathways A Y, = 0.7 kg/m' for milk and meat pathways A t, = 480 hr (20 days) A r = 1.0 (iodines) A
[ = 0.2 (others) A We = 50 kg/ day C
tu = 48 hr (2 days) A to = 175,200 hr (20 years) D f, = 1.0 May-October B f, = 0.0 November-April B Miscellaneous Dose Assessment Factors - Environmental Parameters
- Basis key:
A: Reference 6, Table E-15.
B: Typical for climate of Illinois and vicinity.
C: Reference 6, Table E-3.
D. The parameter to is taken as the midpoint of plant operating life (per Reference 6, Appendix C; Section 1).
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G:/odem' generic /AttCr2-0! C-3
]
Revision 2.0 April 1999 Tabb C-2 Miscellaneous Dose Assessment Factors -
Consumption Parameters Type Variable infant Child Teenager Adult Air R. 1400 3700 8000 8000 (m3/yr)
Milk U "". 330 330 400 310 (Uyr)
Produce U". 0 520 630 520 (Kglyr)
Leafy U ". 0 26 42 64 Vegetables (Kglyr)
Meat U'. 0 41 65 110 (Kglyr)
Water U" (Uhr) 0.038 0.058 0.058 0.083 i
Fish U'. 0 7.9E-4 1.8E-3 2.4 E-3 (Kg/hr)
From Regulatory Guide 1.109, Table E-5.
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Revision 2.0 April 1999 Tcble C-3 Stable Element Transfer Data O Element H
Fe Meat (d/ko) 1.2E-02 Fu(Cow)
Milk (d/L) 1.0E-02 Reference 6
Be 1.5E-03 3.2E-03 Footnote 1 C 3.1 E-02 1.2E-02 6 F 2.9E-03 1.4E-02 Footnote 2 Na 3.0E-02 4.0E-02 6 Mg 1.5E-03 3.2E-03 Footnote 1 Al 1.5E-02 1.3E-03 Footnote 3 P 4.6E-02 2.5E-02 6 Cl 2.9E-03 1.4 E-02 Footnote 2 Ar NA NA NA K 1.8E-02 7.2E-03 16 Ca 1.6E-03 1.1 E-02 16 Sc 2.4E-03 7.5E-06 Footnote 4 Ti 3.4E-02 5.0E-06 Footnote 5 V 2.8E-01 1.3E-03 Footnote 6 Cr 2.4E-03 2.2E-03 6 Mn 8.0E-04 2.5E-04 6 Fe 4.0E-02 1.2E-03 6 Co 1.3E-02 1.0E-03 6 Ni 5.3E-02 6.7E-03 6 Cu 8.0E-03 1.4E-02 6 Zn 3.0E-02 3.9E-02 6 Ga 1.5E-02 1.3E-03 Footnote 3 Ge 9.1 E-04 9.9E-05 Footnote 7 As 1.7E-02 5.0E-04 Footnote 8 O Se Br Kr 7.7E-02 2.9E-03 NA 1.0E-03 2.2E-02 NA Footnote 9 Fe Footnote 2;Fu from Ref.16 NA Rb 3.1E-02 3.0E-02 6 Sr 6.0E-04 8.0E-04 6 Y 4.6E-03 1.0E-05 6 Zr 3.4E-02 5.0E-06 6 Nb 2.8E-01 2.5E-03 6 Mo 8.0E-03 7.5E-03 6 Tc 4.0E-01 2.5E-02 6 Ru 4.0E-01 1.0E-06 6 Rh 1.5E-03 1.0E-02 6 Pd 5.3E-02 6.7E-03 Footnote 10 Cd 3.0E-02 2.0E-02 Footnote 11 in 1.5E-02 1.3E-03 Footnote 3 Sn 9.1 E-04 9.9E-05 Footnote 7 Sb 5.0E-03 2.0E-05 98 Ag 1.7E-02 5.0E-02 6 Te 7.7E-02 1.0E-03 6 1 2.9E-03 6.0E-03 6 Xe NA NA NA Cs 4.0E-03 1.2E-02 6 Ba 3.2E-03 4.0E-04 6 La 2.0E-04 5.0E-06 6 Ce 1.2E-03 1.0E-04 6 Pr 4.7E-03 5.0E-06 6 Nd 3.3E-03 5.0E-06 O 6 G:/odem/ generic /AnCr2-0! C-5 l
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Revision 2.0 April 1999 Tcble C-3 (Cont'd)
Stable Element Transfer Data Fe Fu(Cow)
C Element Meat (d/ko) Milk (d/L) Reference Pm 2.9E-04 2.0E-05 16 Sm 2.9E-04 2.0E-05 16 Eu 2.9E-04 2.0E-05 16 Gd 2.9E-04 2.0E-05 16 Dy 2.9E-04 2.0E-05 16 Er 2.9E-04 2.0E-05 16 Tm 2.9E-04 2.0E-05 16 Yb 2.9E-04 2.0E-05 16 Lu 2.9E-04 2.0E-05 16 Hf 3.4 E-02 5.0E-06 Footnote 5 Ta 2.8E-01 1.3E-03 Fu - Ref.16; Fe -Footnote 6 W 1.3E-03 5.0E-04 6 Re 1,0E-01 1.3E-03 Fu - Ref.16; Fe -Footnote 12 Os 2.2E-01 6.0E-04 Footnote 13 Ir 7.3E-03 5.5E-03 Footnote 14 Pt 5.3E-02 6.7E-03 Footnote 10 Au 1.3E-02 3.2E-02 Footnote 15 Hg 3.0E-02 9.7E-06 Fu - Ref.16; Fe -Footnote 11 Tl 1.5E-02 1.3E-03 Fu - Ref.16; Fe -Footnote 3 Pb 9.1E 04 9.9E-05 98 Bi 1.7E-02 5.0E-04 98 Ra 5.5E-04 5.9E-04 98 Th 1.6E-06 5.0E-06 98 m U 1.6E-06 1.2E-04 98 Np 2.0E-04 5.0E-06 6 Am 1.6E-06 2.0E-05 98 Notes:
- 1. NA = lt is assumed that noble gases are not deposited on the ground.
- 2. Elements listed are those considered for 10CFR20 assessment and comphance.
Footnotes:
There are numerous Fe and Fuvalues that were not found in published literature. In these cases, the penodic table was used in conjunction with published values. The penodic table was used based on a general assumption that elements have similar charactenstics when in the same column of the penodic table. The values of elements in the same column of the periodic table. excluding atomic numbers $8-71 and 90-103, were averaged then assigned to elements missing values located m the same column of the periodic table. This method was used for all columns where there were missing values except column 3A. where there was no data, hence, the average of column 28 and 4A were used.
- 1. Values obtained by averaging Reference 6 values of Ca, Sr. Ba and Ra.
- 2. Fe value obtained by assigning the Reference 6 value for 1. Fu value obtained by averaging l(Ref. 6) and Br (Ref 16).
3 Fe values obtained by averaging Zn (Ref 6) and Pb (Ref. 98); there were novalues for elements in the same column; an average is taken between values of columns 2B and 4A on the periodic table. Fu values obtained by using the value for Tl from Reference 16.
4 Values obtained by averaging Reference 6 values of Y and La.
- 5. Values obtained by assigning the Reference 6 value for Zr.
i 6 Fevalues obtained from Ref. 6 value for Nb. Fu values obtained by averaging values for ND (Ref 6) and Ta (Ref.16)- l
- 7. Values obtained from the Reference 6 values for Pb.
8 Values obtained from the Reference 6 values for Bt 9 Values obtained from the Reference 6 values for Te.
- 10. Values obtained from the Reference 6 values for Ni. ;
- 11. Fevalues obtained from Ref. 6 values for Zn. Fu values obtained by averaging the Reference 6 values for Zn and Hg. I
- 12. Values obtained by averaging Reference 6 values for Mn. Tc. Nd and Reference 98 value for U.
- 13. Values obtained by averaging Reference 6 values from Fe and Ru.
- 14. Values obtained by averaging Reference 6 values from Co and Rh.
- 15. Values obtained by averaging Reference 6 values from Cu and Ag.
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Revision 2.0 April 1999 Tcbie C 4 AtmoSDheric StabilitV Cl8SSet
(
\
Pasquill Stability 'o, Temperature Change with Height Desenotion Class (dearees) (*C/100 m)
Extremely A >22.5 <-1.9 Unstable Moderately B 17.5 to 22.5 -1.9 to -1.7 Unstable Slightly C 12.5 to 17.5 -1.7 to -1.5 Unstable ,
i Neutral D 7.5 to 12.5 -1.5 to -0.5 Slightly E 3.8 to 7.5 -0.5 to 1.5 Stable Moderately F 2.1 to 3.8 1.5 to 4.0 Stable Extremely G 0 to 2.1 >4.0 Stable
'a o is the standard deviation of horizontal wind direction fluctuation over a period of 15 minutes to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
O From Regulatory Guide 1.21, Table 4B.
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n, Revision 2.0 April 1999 Table C-5 Vertical Dispersion Parameters Section i
~~
Vertical Dispersion Parameters e, o, (meters) = aR*+c with o, limited to a maximum of 1000 meters R = downwind range (meters) a, b and c have the valles listed below:
Stability 100 < R < 1000 R > 1000 Class a b g a h g A *
- 0.00024 2.094 -9.6 )
g . . . . . .
C 0.113 0.911 0.0 * *
- D 0.222 0.725 -1.7 1.26 0.516 -13.0 E 0.211 0.678 . -1.3 6.73 0.305 -34.0 F 0.086 0.74 -0.35 18.05 0.18 -48.6 G 0.052 0.74 -0.21 10.83 0.18 -29.2 Basis: Reference 53, except for cases denoted by an asterisk. In these cases, the value of o, is obtained by a polynomial approximation to the data from Reference 53 (see Section 2 of this table). The functions given in Reference 50 are not used because they are discontinuous at 1000 meters.
Section 2 Polynomial Approximation for og o,(meters) = exp [a +o a,P + a2P +2 a3P ) with o, limited to a maximum of 1000 meters S
f-
! P = log.[R(meters))
ao, ai, a sand a3 have the values listed below:
Stability Class Ranae Coefficients A 1005 R 51000 a0 = -10.50 a1 = 6.879 a2 = -1.309 a3 = 0.0957 8 100$ R51000 a0 = -0.449 a1 = 0.218 a2 = 0.112 a3 = -0.00517 B, R > 1000 a0 = 319.148 a1 = -127.806 a2 = 17.093 a3 = -0.750 C R > 1000 a0 = 5.300 aj = -1.866 I
a2 = 0.3509 a3 = -0.01514 O i G:/odcm/ generic /AttCr2-0/ C-8 l l
Revision 2.0 April 1999 Tcble C-6 Allowable Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liould Waste
(~~)
(/ Allowable Concentration , , ,
(pCi/mL)*
Dresden LaSalle Braidwood Quad Cities Nuclide Byron Zion Kr 85m 2E-4 2E-4 Kr 85 2E-4 SE-4 Kr 87 2E-4 4E-5 Kr 88 2E-4 9E-5 Ar41 2E-4 7E-5 Xe 131m 2E-4 7E-4 Xe 133m 2E-4 SE-4 Xe 133 2E-4 6E-4 Xe 135m 2E-4 2E-4 Xe 135 2E-4 2E-4 l
O ' Computed from Equebn 17 of ICRP Publication 2 (Reference 47) adjusted for infinite cloud submersion in water, and R = 0.01 ;em/ week, p = 1.0 gm/cm , and P,/P = 1.0.
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Revision 2.0 April 1999 Tcble C-7 d
Radioloalcal Decay Constants g) in hr Isotope Lambda Isotope Lambda .- Isotope Lambda H-3 6.44E-06 AS-73 3.6E 04 TC 104 273TE+00 BE-7 5.4E-04 AS-74 1.62E-03 RU-97 9.96E-03 C-14 1.38E-08 AS-76 2.63E-02 RU-103 7.34E-04 F-18 3.78E-01 AS-77 1.79E-02 RU-105 1.56E 01 NA-22 3.04E-05 SE-73 9.69E-02 RU 106 7.84E-05 NA-24 4.62E-02 SE-75 2.41 E-04 RH 106 8.33E+01-MG 27 4.39E+00 BR-77 1.21 E-02 PD-109 5.15E-02 MG-28 3.31 E-02 BR-80 2.38E+00 CD-109 6.22E-05 AL-26 1.10E-10 BR-82 1.96E-02 IN 111 1.02E-02 AL-28 1.85E+01 BR-83 2.90E-01 IN 115M 1.59E-01 P-32 2.02E-03 BR-84 1.30E+00 IN-116 7.66E-01 CL-38 1.12E+00 BR-85 1.45E+01 SN 113 2.51E-04 AR-41 3.79E-01 KR-79 1.98E-02 SN-117M 2.12E-03 K 40 6.19E-14 KR-81 3.77E-10 SN-119M 9.85E-05 <
K-42 5.61 E-02 KR-83M 3.79E-01 SB-117 2.48 E-01 l K-43 3.07E-02 KR-85M 1.55E-01 SB-122 1.07E-02 CA 47 6.37E-03 KR-85 7.38E-06 SB-124 4.80E-04 SC-44 1.76E-01 KR-87 5.44E-01 SB-125 2.86E 05 SC-46M 1.33E+02 KR-88 2.44E-01 SB-126 2.33E-03 SC-46 3.44 E-04 KR-90 7.71 E+00 AG-108M 6.23E-07 SC-47 8.44E-03 RB-84 8.78E-04 AG-108 1.75E+01 TI-44 1.67E-06 RB-86 1.55E-03 AG-110M 1.16E-04 V-48 l 1.81 E-03 RB-87 1.67E-15 AG-111 3.87E-03 CR-51 1.04E-03 RB-88 2.33E+00 TE-121M 1.88E-04 MN-52M 1.94E+00 RB-89 2.69E+00 TE-121 1.72E-03 ,
MN-52 5.16E-03 SR-85 4.45E-04 TE-123M 2.41 E-04 MN-54 9.23E-05 SR-87M 2.47E-01 TE 125M 4.98E-04 MN-56 2.69E-01 SR-89 5.71 E-04 TE-125 0.00E+00 FE-52 8.37E-02 SR-90 2.77E-06 TE 127M 2.65E-04 FE-55 2.93E-05 SR-91 7.29E-02 TE 127 7.41 E-02 FE-59 6.47E-04 SR-92 2.56E-01 TE-129M 8.59E-04 CO-57 1.07E-04 Y-86 TE-129 5.96E-01 CO-58 4.08E-04 4.70E-02 L Y-87 8.63E-03 TE 131M 2.31E-02 CO-60 1.50E-05 Y-88 2.71 E-04 TE-131 1.66E+00 NI-63 7.90E-07 Y-90 1.08E-02 TE-132 8.86E-03 NI-65 2.75E-01 Y-91 M - 8.35E-01 TE-134 9.93E-01 CU-64 5.46E-02 Y 91 4.94E-04 l-123 5.28E-02 CU-67 4.67E-04 Y-92 1.96E-01 1-124 6.91 E-03 CU-68 8.31 E+01 Y-93 6.86E-02 1125 4.80E-04 I ZN-65 1.18 E-04 ZR-95 4.51 E-04 l-130 5.61 E-02 ZN-69M 5.04 E-02 ZR-97 4.10E-02 1-131 3.59E-03 ZN-69 7.46 E-01 NB-94 3.90E-09 l-132 3.01 E-01 GA-66 7.37E-02 N B-95 8.00E-03 1-133 3.33E-02 GA-67 8.85E-03 NB-97M 4.15E+01 1-134 7.89E-01 GA-68 6.10E-01 NB-97 5.76E-01 1135 1.CSE-01 GA 72 4.91 E-02 MO-99 1.05E-02 XE-127 7.93E-04 I GE-77 6.13E-02 TC-99M 1.15E-01 XE-129M 3.25E-03 AS-72 2.67 E-02 TC-101 2.92E+00 XE-131M 2.44E-03 O l l
l G:/odem/ generic /AttCr2-O' C-10 l
l
Revision 2.0 April 1999 Ttbl2 C-7 (Crnt'd) d Radioloalcal Decay Constanto (Aj)in hr
/
lsotope Lambda isotoDe Lambda .-
XE-133M 1.32E-02 YB-175 6.89E-03 XE-133 5.51E 03 LU-177 4.30E-03 XE 135M 2.70E+00 HF-181 6.81E-04 XE-135 7.61E-02 TA-182 2.52E-04 XE-137 1.08E+01 TA-183 5.78E-03 XE 138 2.94E+00 W-187 2.91E-02 CS 129 2.16E-02 RE-168 4.08E-02 CS-132 4.46E-03 OS-191 1.88E-03 CS-134 3.84E-05 IR 194 3.62E-02 CS-136 2.19E-03 PT-195M 7.18E-03 CS-137 2.62E-06 PT 197 3.79E-02 CS-138 1.29E+00 AU-195M 8.15E+01 CS-139 4.41 E+00 AU 195 1.58E-04 BA 131 2.45E-03 AU 198 1.07E-02 BA 133M 1.78E-02 AU-199 9.20E-03 BA 133 7.53E-06 HG-197 2.91 E-02 BA 135M 2.41E-02 HG-203 6.20E-04 BA 137M 1.63E+01 TL-201 9.49E 03 BA-137 0.00E+00 T L-206 9.90E+00 BA 139 4.99E-01 TL-208 1.36E+01 BA-140 2.26E-03 PB-203 1.33E-02 BA 141 2.27E+00 PB-210 3.55E-06 BA-142 3.88E+00 PB-212 6.51 E-02 LA 140 1.72E-02 PB-214 1.55E+00 Q(j LA 142 4.35E-01 BI-206 4.63E-03 CE-139 2.10E-04 B1-207 2.37E-06 CE-141 8.ME-04 BI-214 2.09E+00 CE-143 2.10E-02 RA-226 4.94E-08 CE-144 1.02E-04 TH-232 5.63E-15 PR-142 3.62E-02 U-238 1.77E-14 PR 143 2.13E-03 NP-239 1.23E-02 PR-144 2.40E+00 AM-241 1.83E-07 ND 147 2.63E-03 ND-149 4.01 E-01 (A)i = Radiological Decay Constant PM-145 4.47E-06 = 0.693/Ti PM 148M 6.99E-04 PM 148 5.38E-03 Ti . Radiological Half-Life in hours PM 149 1.31 E-02 (from Reference 70).
SM 153 1.48E-02 Except for Cu-68, Tc-104, Ba-137, Ta-183, TL-206. Bi-EU 152 5.82E-06 206 which are from References 100. l EU-154 8.99E-06 EU-155 1.59E-05 GD 153 1.20E-04 DY-157 8.60E-02 ER-169 3.07E-03 ER-171 9.22E-02 TM 170 2.25E-04 YB-169 9.03E-04 O
G:/odem/ generic /AttCr2-0/ C-11
Revision 2.0 April 1999 Tchle C-8 Bloaccumulation Factors (B ) to be Used in the Absence of Site-SDecific Data B,for ~
Freshwater Fish Element foci /ko per DCi/L) Reference H 9.0E-01 6 Be 2.8E+01 Footnote 2 C 4.6E+03 6 F 2.2E+02 Footnote 16 Na 1.0E+02 6
{
Mg 2.8E+01 Footnote 2 i Al 2.2E+03 Footnote 13 P 1.0E+05 6 Cl 2.2E+02 Footnote 16 l Ar NA NA K 1.0E+03 Footnote 1 Ca 2.8E+01 Footnote 2 Sc 2.5E+01 Footnote 3
{
(
Ti 3.3E+00 Footnote 4 I V 3.0E+04 Footnote 5 Cr 2.0E+02 6 Mn 4.0E+02 6 Fe 1.0E+02 6 Co 5.0E+01 6 Ni 1.0E+02 6 Cu 5.0E+01 6 Zn 2.0E+03 6 g Ga 2.2E+03 Footnote 13 Ge 2.4E+03 Footnote 12 As- 3.3E+04 Footnote 14 Se 4.0E+02 Footnote 15 Br 4.2E+02 6 Kr NA NA Rb 2.0E+03 6 Sr 3.0E+01 6 l Y 2.5E+01 6 I Zr 3.3E+00 6 Nb 3.0E+04 6 Mo 1.0E+01 6 Tc 1.5E+01 6 Ru 1.0E+01 6 Rh 1.0E+01 6 Pd 1.0E+02 Footnote 9 Cd 2.0E+03 Footnote 11 in 2.2E+03 Footnote 13 Sn 2.4E+03 Footnote 12 Sb 1.0E+00 98 Ag 2.3E+00 56 Te 4.0E+02 6 1 1.5E+01 6 Xe NA NA Cs 2.0E+03 6 Ba 4.0E+00 6 Le 2.5E+01 6 O Ce 1.0E+00 6 l Pr 2.5E+01 6 Nd 2.5E+01 6 Pm 3.0E+01 98 Sm 3.0E+01 Footnote 3 G:/odem/ generic /AttCr2-0/ C-12
Revision 2.0 April 1999 l
' Table C 8 (Cont'd)
Bioaccumulation Factors (Bg) to be Used I
in the Absence of Site-Soecific Data B,for Freshwater Fish Element (oCi/ko per DCi/L) Reference Eu 1.0E+02 Footnote 3 Gd 2.6E+01 Footnote 3 Dy 2.2E+03 Footnote 3 Er 3.3E+04 Footnote 3 Tm 4.0E+02 Footnote 3 Yb 2.2E+02 Footnote 3 l Lu 2.5E+01 Footnote 3 l Hf 3.3E+00 Footnote 4 Ta 3.0E+04 Footnote 5 l W 1.2E+03 6 i
Re 2.1 E+02 Footnote 6 Os 5.5E+01 Footnote 7 Ir 3.0E+01 Footnote 8 l Pt 1.0E+02 Footnote 9 l Au 2.6E+01 Footnote 10 l Hg 2.0E+03 Footnote 11 l Tl 2.2E+03 Footnote 13 Pb 3.0E+02 98 Bi 2.0E+01 98 Ra 5.0E+01 98 i
q Th 3.0E+01 98 Q U Np 1.0E+01 1.0E+01 98 6
Am 3.0E+01 98 1
Footnotes:
NA = lt is assumed that noble gases are not accumulated in Reference 6, see Table A 1.
A number of broaccumulation factors could not be found in literature. In this case. the periodic table was used in conjunction with published element values. This method was used for penodic table columns except where there were no values for column 3A so the average of columns 2B and 4A was assigned 1 Value is the average of Reference 6 values in hierature for H. Na. Rb and Cs.
2 Value is the average of Ret 6 values in hterature for Sr. Ba and Ref 98 values for Ra 3 Value is the same as the Reference 6 value used for Y.
4 Value is the same as the Reference 6 value used for Zr.
i 5 Value is tne same as the Reference 6 value used for Nb l 6 Value is the average of Reference 6 values in literature for Mn and Tc.
l 7 Value is the average of Reference 6 values in hierature for Fe and Ru.
8 Value is the average of Reference 6 values in hterature for Co and Rh.
9 Value is the same as the Reference 6 value used for Ni 10 Value is the average of Reference 6 values in literature for Cu and Reference 56 value for Ag 11 Value used as the same as the Reference 6 value used for Zn.
12 Value is the average of Reference 6 value in hterature for C and Reference 98 value for Pb.
13 Value is the average of columns 2B and 4A. where column 2B is the " Reference 6 value for Zn" and column 4A is the average of " Reference 6 value for C and Reference 98 value for Pb".
14 Value is the average of Ref. 6 value found in hterature for P and the Ref 98 values for Bi and Sb.
- 15. Value is the same as the Reference 6 value used for Te.
16 Value is the averaqe of Reference 6 values found in hterature for Br and I.
D G:!odern/ generic /AttCr2-O' C-13 i
Revision 2.0 April 1999
+
Table C-9 Beta Air and Skin Dose Factors for Noble Gases Beta Air Beta Skin Dose Factor Dose Factor Li Li Nuclide (mrad /vr per uCi/m8) (mrem /vr per UCi/ m*)
Kr-83m 2.88E+02 -
Kr-85m 1.97E+03 1.46E+03 Kr-85 1.95E+03 1.34 E+03 Kr-87 1.03E+04 9.73E+03 Kr-88 2.93E+03 2.37E+03 Kr-89 1.06E+04 1.01 E+04 Kr-90 7.83E+03 7.29E+03 Xe-131m 1.11 E+03 4.76E+02 Xe-133m 1.48E+03 9.94E+02 Xe-133 1.05E+03 3.06E+02 Xe-135m 7.39E+02 7.11 E+02 Xe-135 2.46E+03 1.86E+03 Xe-137 1.27E+04 1.22E+04 Xe-138 4.75F 03 4.13E+03 O Ar-41 3.28E+03 2.69E+03 Source: Table B-1 of Reference 6.
O G:/odem/ generic /AttCr2-0/ C-14 i
e .
Revision 2.0 Tcble C-10 External Dose Factors for Standing on Contaminated Ground DFGn (mrom/hr per DCl/ m*)
~
Whole Body V Element H-3 Dose Factor Reference Element Dose Factor Reference 0.00E+00 6 Be-7 535E-10 99 C-14 0.00E+00 6 F-18 1.19E-08 99 Na-22 2.42E-08 99 Na-24 2.50E-08 6 Mgu7 1.14E-08 99 Mg-28 1.48E-08 99 AL26 2.95E-08 99 AL28 2.00E-08 99 P-32 0.00E+00 6 Cl-38 1.70E-08 99 Ar-41 1.39E-08 99 K-40 2.22E-09 99 K-42 4.64E-09 99 K-43 1.19E-08 99 Ca-47 1.14E-08 99 Sc-44 2.50E-08 99 Sc-46m 1.21E-09 99 Sc-46 2.24E-08 99 Sc-47 1.46E-09 99 Ti-44 1.95E-09 99 V-48 3.21E-08 99 Cr-51 2.20E-10 6 Mn-52m 2.79E-08 99 Mn-52 3.80E-08 99 Mn-54 5 80E-09 6 Mn-56 1.10E-08 6 Fe-52 9.12E-09 99 Fe-55 0.00E+00 6 Fe-59 8.00E-09 6 Co-57 1.65E-09 99 Co-58 7.00E-09 6 Co-60 1.70E-08 6 Ni-63 0.00E+00 6 Ni-65 3.70E-09 6 Cu-64 1.50E-09 6 Cu-67 1.52E-09 99 Cu-68 8.60E-09' -
Zn-65 4.00E-09 6 Zn-69m 5.06E-09 99 Zn-69 0.00E+00 6 Ga-66 2.70E-08 99 Ga-67 1.89E-09 99 Ga-68 1.24E-08 99 Ga-72 3.00E-08 99 Ge-77 1.34E-08 99 As-72 2.23E-08 99 As-73 1.16E-10 99 As-74 9 41E 09 99 As-76 6.46E-09 99 As-77 1.79E-10 99 Se-73 1.38E-08 99 Se-75 4.98E-09 99 Br-77 3.84E-09 99 Br-80 2.01 E-09 99 Br-82 3.00E-08 99 Br-83 6.40E-11 6 Br-84 1.20E-08 6 Br-85 0.00E+00 6 Kr-79 3.07E-09 99 Kr-81 1.59E-10 99 Kr-83m 1.42E-11 99 Kr-85m 2.24E-09 99 fO Kr-85 Kr-88 1.35E-10 2.07E-08 99 99 Kr-87 Kr-90 1.03E-08 1.56E-08 99 99 Rb-84 1.07E-08 99 Rb-86 6.30E 10 6 Rb-87 0.00E+00 99 Rb-88 3.50E-09 6 Rb-89 1.50E-08 6 Sr-85 6.16E-09 99 St-87m 3.92E-09 99 Sr-89 5.60E-13 6 Sr-90 1.84E-11 99 Sr-91 7.10E-09 6 Sr-92 9 00E-09 6 Y-86 4 00E-08 99 Y-87 5 53E-09 99 Y-88 2.88E-08 99 Y-90 2.20E-12 6 Y 91m 3 80E-09 6 Y-91 2 40E-11 6 Y-92 1.60E-09 6 Y 93 5.70E-10 6 Zr-95 5.00E-09 6 Zr-97 5.50E-09 6 Nb-94 1.84E-08 99 Nb-95 5.10E-09 6 Nb-97m 8.57E-09 99 ND-97 8 48E-09 99 Mo-99 1.90E-09 6 Tc-99m 9 60E-10 6 Tc-101 2.70E-09 6 Tc-104 1.83E-08' -
Ru-97 2.99E-09 99 Pu-103 3.60E-09 6 Ru-105 4.50E-09 6 8
Ru/Rh-106 5.76E-09 6.99 Pc-109 3.80E-10 99 Cc-109 1.12E 10 99 in-111 5.11E-09 99 In-115m 8 2.01 E-09 99 in-116 0.00E+00 -
Sn-113 1.15E-09 99 Sn-117m 1.96E-08 99 Sn 119m 8 7.05E-11 99 Sb-117 0.00E+00 -
Sb-122 2.71 E-09' -
Sb-124 1.16E-08' -
Sb-125 4.56E-09 99 Sb-126 7.13E-10 99 Ag-108m 1.92E-08 99 Ag-108 1.14E-09 99 Ag-110m 1.80E-08 6 Ag-111 6.75E 10 99 Te-121m 2.65E-09 99 Te-121 6.75E-09 99 Te-123m 1.88E-09 99 Te-125m 3.50E-11 6 Te-125 0.00E+00' -
Te-127m 1.10E-12 6 Te-127 1.00E-11 6 Te-129m 7.70E-10 6 Te-129 7.10E-10 6 Te-131m 8 40E-09 6 Te-131 2.20E-09 6 O
Te-1-132 3.40E-09' 6 Te-134 1.05E-08 99 l-123 2.12E-09 99 l-124- 1.23E-08 99 l-125 2.89E-10 99
- f. 1-130 1.40E-08 6 l-131 2.80E-09 6 l-133 3.70E-09 6 l-134 1.60E-08 6 6-135 1.20E-08 6 Xe-127 3.44E-09 99 G:/odem/ generic /AttCr2-0/ C-15 l
L
Fe Revision 2.0 Tcble C-10 (cont.)
External Dose Factofs for Standing on Contaminated Ground
, DFGg (mrom/hr per oCi/ m'n , {
t Whole Body (j Element Dose Factor Reference Element Dose Factor Reference Xe 129m 5.57E-10 99 Xe-131m 2.13E-10 99 l Xe-133m 4.81E 10 99 Xe-133 5.91E-10 99 Xe-135m 5.23E-09 99 Xe-135 3.36E-09 99 Xe-137 4.26E-09 99 Xe-138 1.30E-08 99 Cs-129 3.39E-09 99 Cs-132 8 40E-09 99 Cs-134 1.20E-08 6 Cs-136 1.50E-08 6 Cs-137/Ba-137m 1.14E-08' 6,99 Cs-138 2.10E-08 6 Cs-139 5.15E-09 99 Ba-131 5.74E-09 99 Ba-133m 8.10E-10 99 Ba-133 4.85E-09 99
, Ba-135m 7.26E-10 99 Ba-137m 7.17E-09 99 l
Ba-137 0.00E+00' -
Ba-139 2.40E-09 6 Ba-La-140 1.71 E-08' 6 Ba-141 4.30E-09 6 Ba-142 7.90E-09 6 La-142 1.50E-08 6 Ce-139 2.04E-09 99 Ce-141 5.50E-10 6 Ce-143 2.20E-09 6 Co-Pr-144 5.20E-10' 6 Pr-142 1.84E-09 99 Pr-143 0.00E+00 6 Nc-147 1.00E-09 6 Nc-149 5.32E-09 99
- Pm-145 3.38E-10 99 Pm-148m 2.35E-08 99 Pm-148 7.22E-09 99 Pm-149 5.32E-10 99 Sm-153 8.95E 10 99 Eu-152 1.30E-08 99 Eu-154 1.41 E-08 99 Eu-155 8.27E-10 99 Gc-153 1.46E-09 99 Dy-157 4.39E-09 99 Er-169 6.12E-14 99 Er-171 5.11E-09 99 Tm-170 3.41E 10 99 Yb-169 4.12E-09 99 Yb-175 4 94E-10 99 Lu-177 4.60E-10 99 Hf 181 6.67E-09 99 Ta-182 1.42E-08 99 Ta 183 2.93E-09' -
W-187 3.10E-09 6 Re-188 1.89E-09 99 Os-191 9.83E-10 99 Ir-194 2.31E-09 99 Pt-195m 9.79E-10 99 Pt-197 3.57E 10 99 Au 195m 2.54E-09 99 Au-195 1.14E-09 99 Au-198 5.19E-09 99 O Au-199 Mg-203 TI-206 Pb-203 1.18E-09 2 89E-09 0 00E+00' 3.88E-09 99 99 99 Hg-197 TI-201 Ti.208 Pb-210 9 33E-10 1.24E-09 3.58E-08 3.57E 11 99 99 99 99 Pb-212 1.91E-09 99 Pb-214 3.18E-09 99 B+-206 3.74E-08 99 Bi-207 1.77E-08 99 Di-214 1.71E-08 99 Ra-226 8.78E-11 99 Th-232 814E-12 99 U-238 7.98E-12 99 Np-239 9.50E-10 6 Am-241 3 48E 10 99 l
1 Valued denved by comparing the percentage and MeV of the nuclide's gammas and then comparing to Cesium-137, as a value was not available in the hterature.
2 0 0 due to low yield and short half hte. A value was not available in the hterature.
3 Value is the sum of Ru-106 (1,50E-9) and Rh-106 (4.26E-9). The Rh-106 value is from Reference 99 and the Ru-106 value is from Reference 6. ,
j i
d Value is the sum of Cs 137 (4.20E-9) and Ba-137m (7.17E-9). The values are from references 6 and 99. resrectively.
5 Value is the ma of Te-132 (1.70E-9) and I-132 (1.70E-9).
6 Value is the sum of Ba-140 (2.10E-9) and La-140 (1.50E-8) from reference 6. In Reference 6 see Table E-6. !
7 Value is the sum of Ce 144 (3 20E-10) and Pr-144 (2.00E 10) from reference 6.
Note- Dose assessments fo.10CFR20 and 40CFR190 compliance are made for an adult only using the dose commitment factors of Federal Guidance Report 11 (Reference 93). These are given in units of Sieverts per Becqueret. To convert these data to the conventional units of (mrem /pCi) the data must be multiphed by 3.7x10'. !
[
(- Dose assessments for 10CFR50 Appendix are made using dose factors of Regulatory Guide 1.109 (Reference 6) for all age groups.
G:/odem/ generic /AttCr2-0! C 16
)
Revision 2.0 April 1999 b
Table C-11 Sector Code Defmitions D
Angle ,,,
Sector Sector from North Cqdg Direction (Dearees)
A N 348.75 < 0 511.25 B NNE 11.25 < 0 5 33.75 C NE 33.75 < 0 $ 56.25 D ENE 56.25 < 0 $ 7S.75 E E 78.75 < 0 5101.25 F ESE 101.25 < 0 5123.75 l G SE 123.75 < 0 5146.25 H SSE f 146.25 < 0 5168.75 L J S 168.75 < 0 5191.25 K SSW ,
191.25 < 0 5 213.75 L SW 213.75 < 0 5 236.25 M WSW 236.25 < 0 5 258.75 l
N W 258.75 < 0 5 281.25 {
P WNW 281.25 < 0 5 303.75 l O NW 303.75 < 0 5 326.25 R NNW 326.25 < 0 5 348.75 l
1
)
D (v
G:/odem/ generic /AttCr2-0/ C-17 l
L: