ML18033B612

Rev 8 to Radiological Effluent Tech Spec Manual.

ML18033B612
Person / Time
Site:	Browns Ferry
Issue date:	06/22/1990
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18033B610	List: ML18033B609 ML18033B611 ML18033B612
References
PROC-900622, NUDOCS 9102040316
Download: ML18033B612 (752)

Text

Tennessee Valley A r{ty Drowns Ferry Nucle lant Site Director Standard Practice a c 1(.,7 03 1999 FORH SDSP 1 PROCEDURE REVIEM ANO APP{lOVAL COVER SHEET Fane Page 1 of 1 Fane SOSP<<1 SOS~11 t~(for SP e Procedure No.-Ys'N'n Tracking No.Tf tl~~~8;Ofugi Cst(t=&lu.~n+f<mnt cdz f Gct4t c.o rsctl (,AC TS)f~r<tq~c.l AS APPROPRIATE

()New Procedure (CJ Pet<<anent Change.Two Year Review per QQ2O~T Yes~No)Cancellation

.)Te<<parary change Anticipated duration (date ar condition):

s o af ect p dIss{ng.(For TCs list<<arked pages): AS Pages reissued for pagination only:/-ORIGINATOR:

n.(PRINT your na<<e)7+Na<<e of Respo sible Organization Octa i O Occaataatiaa

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~~~5-/-g Phone Date Plant Nanager ZT.Prefect Controls 4 Financial Svcs Site Hu<<an Resource Servf ces Site Licensing ZZ Site Progra<<s and Support ZZ Nuclear Engineering (NE)IZ Hodfffcations (HOOS)Hat al 4 Procure<<ant Site quality QZWo Organization:

ZZ Organi zati on: 3Z Organization:.

XI Organization:

ZI Organizatian:

ZZ Organ{zati on: Organization:

rg'ion.'.t Yj'{ts ced usa V/..P a'(Sign Qgg a red{u{red S{gnatureS eXCept PORC, Res'ble A)rgan{zatfon Supervisor Date Principal Nanager, and Site Director,{f applicable

)I Principal Nanager Ti t'1~: PORC Review requiredt)Ye.(;)No~.C PORC Chafrssan or PORC inutes No.'lant Hanager or PORC Hinutes No.Retention Period: L{fet{<<e Responsibilityl OCRH l428p 9102040316 900622.iver a,~PDR ADOCK 0 0o02 (Required s{cmature for standard practices O)(L), Date except if Pnncfpaf Nanager is the Plant Hanager, then<<ark"NA" here and check Plant Hanager at, botto<<left.EZ.Site Oi or (SOSPs only)Date Date released fro<<Adafnfstratfve Hold~(SO aw>tataa Ii aoottcaal~t Effective Date 7 S"9Q'o<<pletes)

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HISTORY OF REVISION/REVIEW BFN RETS MANUAL Page 1 of 3~W REV.NO.DATE 02/01/84 REVISED PAGES REASON FOR CURRENT REVISION 1,2,3,4,6,12-20, Revise ODCM to incorporate 24-34,36,48,51-70; revision approved by RARC-add 16A,20A,30A, 30B~30C~31A,31B~

36A 06/26/84 11/20/84 09/26/85 Section 3 (As TI-47)Add 70A,70B,70C, Reinsert pages accidenty deleted 70D,70E,70F in February 1, 1984 revision.Section 3(As TI-47)2,3,13,15,16,19,'In response.to OQAB audit.(841112-05) 20,20A,24; add 24A thxu 24T;30B,32,33 51-56,64-66,deleted 31B Section 3'able of Contents, 14-16, to meet 18>>20A,24M-25T,25 Technical Specification commitment 32,24,51-53,70D; 6'.G (Ref.L61 850710803)

(850716-06)

TOF,71~Add 20B~24U,69A,69B,69C, 70G,70H,70X;Delete

.26-30,30A,30B~30C,31, 31A,T4-77 05/05/87 All 10/20/87 All OT/12/88 ALL New manual to incorporate TI-47 (ODCM)into a new manual called the RETS Manual which contains three documents; the REM, the ODCM, and the PCP.Also to revise the ODCM to incorporate changes approved by RARC.Correct page numbering and identification per CAQR BFT870328.

First revision approval and issued under SDSP2.11.Updated to reflect the results of the Fall 1987 Land Use Census and current program.To correct typographical errors.10/28/88 35-37,40-79,85,86, To more accurately and completely 96-'98>121-145 describe calculation of gaseous release rate limits and doses and to clarify 40CFR190 total dose calculations.

1141v-3

HISTORY OF REVISION/REVIEW BFN RETS MANUAL Page 2 of 3~W REV.NO~4 DATE 12/22/8&REVISED PAGES 1&5-206 REASON FOR CURRENT REVISION Section IV>Process Control Program, is heing revised in order to provide a more accurate and usable program.This revision will alow for the use of vendor supplied systems in radwaste processing and incorporates, by xeference, the latest NRC correspondence regarding radwaste processing using vendor equipment.

This xevision also provides information regarding various radwaste processing concerns including standard definitions, waste charatex'istics, shipment manifests and adminis trative controls.REASON FOR URGENCY: This revision needs to be implemented-prier'to;december 31, 1,988 so that the use of.the Chem Nuclear System currently onsite can be reported in the Semi-Annual Effluent report being issued in January 1989.06/02/89 ALL A two-year review was performed and changes were made to the ODCM to reflect this review and to update the ODCM.The following changes were made to the ODCM in accordance with its two-year revie~.: corrected references, change table 1.4 to reflect gamma and beta air dose values in RG 1.104, changed fraction of river flow for diluti.on, added max turain heights, and revised methadology descriptions per BEMATA code.URGENCY: Changes need to be in place so the 1st quarter of 1.989 report can be completed.

09/19/89~1141v=4 38,58,59,67,69,71, In accordance with RARC meeting 72,84,85,86,95,97-, minutes from June 1, 1989 (RIMS 98,124-131>137-146~

L60 890606 801).The following changes 148,150>>l.53,174 were made on ODCM Table 3-1;change collection frequency for surface water'nd drinking water samples from 7 to 31 days, delete Sr analysis for surface water,.change analysis frequency for gross beta and gamma in drinking water from weekly ground water from monthly to quarterly, change analysis frequency for ga~in mild from monthly to every 2 weeks, delete fish sampling from the dwonstream reservoir, and delete specifc locations for clam samples.On Table 3.2.A and figure 3.3'delete mild and vegetation sampling from a dairy farm which is now out of buisness and add replacement farm.Delete vegetation sampling except food products and those samples taken in lieu of mild samples.Correct sevex'al typos.

HISTORX OF REVISION/REVIEW BFN RETS MANVAL Page 3 of 3 REV.NO.7 DATE 11/28/89 REVISED PAGES 152%153 REASON FOR CURRENT REVISION To add Farm Gl to Table 3.1 under vegetation.

To Delete Farm 0 which is now out of business from Table 3.1 and 3'A.06/22/90'0%45%46%80&2%

170%171 Add description of the methodology to be used in setpoint calculations for effluent monitors to sections 1.1 and 2.2.Generated forms of the equations are added.A reference to the appropriate Technical Instruction is made for more detail concerning the calculation." This was a response to audit report item,BFA890I05006 of audit number-MA89006; Re&se"figure

.2.2-location of radmonitor and flow rate monitor are switched to accurately show plant configuration.

Revise figure 2.3 label for RCW rad monitor (RM-90-132) added to figure.114lv-3 RETS Manual Revision 8 Page 1 Brogans Ferry Nuclear Plant Radiological Effluent Technical Specification (RETS)Manual~~0242p RETS Manual Revision 8 Page 2 Section I.Introduction II.Radiological Effluent Manual (REM)III.Offsite Dose Calculation Manual (ODCM)IV.Process Control Program (PCP)0242p RETS Manual Revision 8 Page 3~&~&RETS Manual Section I Introduction

~~02429 RETS Manual Revision 8 Page 4 RETS Manual Section I INTRODUCTION The Radiological Effluent Technical Specification (RETS)Manual contains three documents; the Radiological Effluent Manual (REM), the Offsite Dose Calculation Manual (ODCM), and the Process Control Program (PCP).All three documents are referenced by the Radiological Effluent Technical Specifications which were issued on February 5, 1987 as Technical Specification Amendments Nos.132, 128, and 103 to unit 1, 2, and 3, respectively.

The REM and the ODCM were approved by the NRC when they.issued the RETS.The REM is controlled by the NRC, so changes to-She.REM must be approved by-..the NRC before they are put in this manual.The ODCM and PCP are controlled by TVA, so changes to the ODCM and the PCP must be approved by PORC.Initial NRC approval of the PCP is required and has been requested.

0242p RETS Manual Revision 8 Page 5 RETS MANUAL Section EI RADIOLOGXCAL EFFLUENT MANUAL REM For the Brows Ferry Nuclear Plant Limestone County, Alabama r'ennessee Valley Authority 0242p

)RETS Manual Revision 8 Page 6 RADIOLOGICAL EFFLUENT MANUAL TABLE OF CONTENTS SECTION PAGE NO.REV NO A.B.C.INTRODUCTION RESPONSIBILITIES 1 LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM 2.LIQUID WASTE TREATMENT 1 GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM 2.GASEOUS WASTE TREATMENT RADIOLOGICAL ENVIRONMENTAL MONITORING 1 SAMPLING AND ANALYSIS 2 LAND USE CENSUS 3~INTERLAB ORATORY COMPARISON PROGRAM REPORT CONTENT 1'NNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2.SEMIANNUAL'ADIOACTIVE EFFLUENT RELEASE REPORT 3~SPECIAL REPORTS (RADIOLOGICAL ENVIRONMENTAL MONITORING)

A>>l B-1 C-l C-5 D-l~a~E-l E-3 E-5 F-1 F 2 F-3 0 0 0 0 0 0.0 0 0 0 0 0242p I~RETS Manual Revision 8 Page 7 A.INTRODUCTION The purpose of this manual is to provide the sampling and analysis programs vhich provide input to the ODCM for calculating liquid and gaseous effluent concentrations and offsite doses.Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonable-achievable (ALARA).The Radiological Environmental Monitoring Program outlined within this manual provides confirmation that the measurable concentrations of radioactive material released as a result of operations at the Browns Ferry Plant are not higher than expected.In addition, this manual outlines the information required to be submitted to the NRC in both the Annual Radiological.

Environmental Operating Report, and the Semiannual Radioactive Effluent Release Report.A-1 0242p RETS Manual Revision 8 Page 8 B.RESPONSIBILITIES All changes to this manual shall be reviewed by the Plant Operations Review Committee prior to implementation.

All changes to this manual shall be approved by the NRC prior to implementation.

It, shall be the responsibility of the Plant Manager to ensure that this manual is used in performance of the surveillance requirements and administrative controls of the Technical Specifications.

/>~r~~02429 RETS Manual Revision 8 Page 9 C LI UID EFFLUENT SAMPLING AND ANALYSIS PROGRAM C.l Radioactive liquid vaste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with Table C-l.The results of the analysis of samples collected from release points shall be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits of the Technical Specifications.

0242p TABLE C-1 RADIOACTIVE Li ID HASTE SAHPLING AND ANALYSIS PROGRAH RETS Hanual Revision&Page 10 LIQUID RELEASE TYPE Batch Naltl Releases 1 SAMPLING FRE fNCY Each Batch HINIHUH ANALYSIS FRE ENCY Each Batch Prior.to Release TYPE OF ACTIVITY ANALYSIS Principaf gamma Emitters<4>

SYSTEH DESIGN CAPABILITY LONER LIHIT OF DETECTION (LLD)(Ci/ml)SE-Z(>>One Batch per Month Monthly Dissolved and Entrained Gases(5)1 E-S(3)Honthly Proportional Composite (2)Monthly Tri tium Gross a 1 E-5 1 E-7 Quarterly ProportionaJ Composite (<>Quarterly Sr-&9, Sr-90 Fe-55'~~5 E-8 1 E-6.0242p C-2 RETS Manual Revision 8 Page 11 TABLE NOTATION-TABLE C-1 (1)A batch release is the discharge of liquid wastes of a discrete volume.The discharge shall be thoroughly mixed prior to sampling.(2)A proportional composite sample is one in+hi,ch the quantity of liquid sampled is proportional to the quantity of liquid waste discharged from the plant and is representative of the liquid discharged.

,(3)The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that vill be detected with 95K probability vith only 5X probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which-may'.include radiochemical separation):

4.66 sb LLD a E*V'*2.22 x 10 Y+exp (-X4t)Mhere: LLD is the"a priori" lover limit of detection as defined above (as microcuries per unit mass or volume), sb is the standard deviation of the background counting rate or of the'counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable), i is the radioactive decay constant for the particular radionuclide, and lt for plant effluents is the elapsed time between the midpoint of sample collection and time of counting~Typical values of E V;Y, and 4t should be used in the calculation.

It shcuid he recoanised that the LLD is defined as a priori'(hefore ths fact)limit representing the capability of a measurement system and n t as an a posseriort (after the fact)limit for a particular measuremeat.

t n no 0242p C-3 RETS Nanual Revision 8 Page 12 TABLE NOTATION-TABLE C-1 Continued (4)The principal gamna emitters for which the LLD specification will apply are exclusively the following radionuclides:

Zn65, Co60, Cs137, Nn54, Co58, Csl34, Ce141, Ce144, Mo99, and Fe59 for liquid releases.This list does not mean that only these nuclides are to be detected and reported.Other nuclides detected within a 95K confidence level, together with the above nuclides, shall also be identified and reported as being present.Nuclides which are below the LLD for the analysis may not be reported as being present at the LLD Level for that nuclide.I-131 shall have a LLD of<1 E-6.(5)Gamma Emitters Only.~~0242p C-4

RETS Manual Revision 8 Page 13 C 2 LI UID RADIOACTIVE WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified.

This provides assurance that the releases of radioactive materials in liquid effluents will be kept"as low as is reasonably achievable".

This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section II.D of Appendix I to 10 CFR Part, 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a suitable.fraction of the guide set forth in Section II A of Appendix I, 10 CFR Part 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and.unexpected failureS of, aon-,redundant.radwaste processing equipment halt waste treatment.

The liquid radwaste system shall be used to reduce the radioactive materials in liquid wastes prior to their, discharge from the site when the projected monthly dose would exceed 0.06 mrem to the total body or 0.21 mrem to any organ per unit (see Figure 4.8-1b, Technical Specification).

Doses due to liquid releases to unrestricted areas shall be projected at least once per 31 days, in accordance with the ODCM.With radioactive liquid waste being discharged for more than 31 days without treatment and when the projected dose is in excess of limits specified above prepare and submit the Special Report pursuant to Section 6.7.2 of the Technical Speci,fications.

0242p C-5

/RETS Manual Revision 8 Page l4 D.GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.l Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table D-1.Dose rates shall be determined to be within limits of the Technical Specifications using methods contained in the ODOM.Samples of offgas system effluents shall be analysed at least weekly to determine the identity and quantity of the principal radionuclides being released.,~0242p

TABLE D-l RADIOACTIVE GASEOUS HASTE SAHPLING AND ANALYSIS PROGRAM RETS Manual Revision 8 Page 15 GASEOUS RELEASE TYPE SAHPLING FRE ENCY MIN IHUH ANALYSIS FRE ENCY TYPE OF ACTIVITY ANALYSIS SYSTEH DESIGN CAPABILITY LONER LIHIT OF DETECTION (Ci/ml)A.Containment Prior to Each Prior to Each Purge Principa)gamma Purge Purge Grab Sample Emitters~3~

H-3 1 f 4(l)1 f-6 B.l.Stack Grab Sample 2.Building Grab Sample Ventilation Monthly(4)

Monthly(4)

Principal gamma Emitters<3>

1E 4(l)lE-6 a.b.C.Reactorl Turbine Turbine Exhaust Radwaste C.All Release Points Listed in B.Above Continuous Sampler Continuous Sampler Charcoa'}Sample Meekly(4)Particulate Sample Meekly(4>I-131 Principa)Gamma , Emitters<3) and.I-131 1E-12(>>lE-11 1E-12(2)~~0242p Continuous Sampler Continuous Sampler Composite Particulate Gross Alpha Sample Monthly)I Composite Parti cul ate Sr-89, Sr-90 Sample Quarterly D-2 1E-11 1E-1 1 RETS Nanual-Revision 8 Page 16 TABLE NOTATION-TABLE D>>l s (1)The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count.(above system background) that will be detected with 95K probability with only 5%probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

" Where: 4.66 sb E~V~2.22 x 10~Y>>exp (-Xht)e~~~~LLD is the"a priori" lower limit of detection as defined above (as microcuries per unit mass or volume),~~sb is the standard deviation of theibackground counting rate or of the counting rate of a blank sample as appropriate (as counts er minute), s per E is the counting efficiency (as counts per disintegration), V is the sample sire (in units of mass or volume), 2.22 r.10 is the number of disintegrations per minute per 6 microcurie, Y is the fractional radiochemical yield (when applicable),.is the radioactive decay constant for the particular radionuclide, and 4t for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.Typical values of E, V, Y, and ht should be used in the calculation.

Zt shoul.d be recognized that the Lib is defined as an a riori.(b E the fact))limit representing the.capability od a measuremeat system and not as an a posteriori (after the pact)limit for a particular measurement.

(2)When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly higher.0242p D-3 RETS Manual Revision 8 Page 17 TABLE NOTATION-TABLE D-I.Continued (3)The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides:

Kr87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Hn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144 for particulate emissions.

This list does not mean that only these nuclides are to be detected and reported.Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported.Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.(4)Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.0242p

De2 GASEOUS RADIOACTIVE WASTE TREATMENT RETS Manual Revision 8 Page 18 Doses due to gaseous releases to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days./~*~~0242p RETS Manual Revision 8 Page 19 RADIOLOGICAL ENVIRONNENTAL NONITORING E,l SANPLING AND ANALYSIS The radiological monitoring program required by this section provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to'he highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.'I The radiological environmental monitoring program shall be conducted as specified in Table E-l./The radiological environmental monitoring samples shall be collected pursuant to Table E-l from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirement of Table E-1 and the detection capabilities required by Table E-2.With the radiological environmental monitoring program not being conducted as specified in Table E-l, in lieu of a LER, prepare and submit to the Comaission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program.as required and the plans for preventing a recurrence.

Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment.

If the l.atter, every effort shall be made to complete.corrective action prior to the end of the next sampling period.All deviations form the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table E-3 when averaged over any calendar quarter, in lieu of a LER, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a report which identifies the cause(s)for exceeding the limit(s)and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is less than the calendar year limits of the Technical Specifications.

When more than one of the radionuclides in Table E-3 are detected in the sampling medium, this report shall be submitted if:~Cane 1+~Cane 2)+...>1.0 Limit(l)Limit(2)When radionuclides other than those in Table E-3 are detected and are result of plant effluents, this report shall he submitted if the'otential annual dose to a member of the public is equal to or greater than the calendar year limits of the Technical Specification.

0242p

RETS Manual Revision 8 Page 20 Such reports are not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.Mith milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1 identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days.The specific locations from which samples were unavailable may then be deleted from the monitoring program.Zn lieu of a LZR, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating-Jteport

-..and also include a revised figure(s)and table(s)for the ODCM reflecting the new locations.

The provisions of Technical Specification 1.0eC are not applicable.

The detection capabilities required by Table E-2 are state-of-the-art for routine environmental measurements in industrial laboratories.

lt should hs recognised that the Lip is deHnsd as an a priori (hefore the fact)limit representing the capabil'ity of the measurement system and not as an a~sterfari (after the fact)limit for particular measurement.

Analyses shall be performed in such a manner that the stat'ed LLDs will be achieved under routine conditions, Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

Zn such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.0242p

RETS Nanual.Revision 8 Page 21 E 2 LAND USE CENSUS A, land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden*of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use census shall also identify the locations of all milk animals and all gardens of greater Chan SOO square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of three miles).arith a land use census identifying a location(s) which yields a calculated dose or dose commitment greater than the maximum value currently being calculated in section D.2 of this manual, in lieu of a LER, identify the new locations in the next Annual Radiological Environmental Operating Report.arith a land use census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway)20 percent greater than at a location, from which samples are currently being obtained in accordance with sect.'ion E.l, add the new location(s) to the radiological environmental monitoring programs within 30 days if the owner consents.The sampling location(s), excluding the control station location, having the lowest calculated dose or dose commitment(s)(via the same exposure pathway)may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted.

In lieu of a LER,.identify the new location(s) in the next hnnual Radiological Environmental Operating Report and provide a revised figure(s)and table for the ODCM reflecting Che new location(s)..

• Broad leaf vegetation sampling may be performed at the site boundary in~e direction section with the highest D/g in lieu of the garden census.0242p E-3 0

RETS ManuaL Revision 8 Page 22 a.Within a 2 mile radius from the plant or within the 15 mrem per year isodose line, whichever is larger, enumeration by a door-to-door or equivalent counting technique.

b Within a 5 mile radius from the plan, enumeration by using appropriate techniques such as door-to-door survey, mail survey, telephone survey, aerial survey, or information from local agriculturaL authorities or other reliable sources.The land use census shall be conducted at least once per calendar year between the dates of April 1 and October 1 using the following techniques:

y4tc ,~I.}r('I'C~'L This specification is provided to ensure Chat changes in the use of unrestricted areas are idenCified and that modifications to the monitoring program are made if required by the'result@

o'f this::cen'sus~

The best survey information from the door>>to-door, mail, telephone,'erial or consulting with local agricultural authorities shall be used.~This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50.Restricting the census to gardens of greater than.500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this sise is the minimum required to produce the quantity (26 kg/year)of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child.To determine this minimum garden sise, the following assumptions were used: 1)that 20K of the'arden was used for growing broad leaf..vegetation (i.e., similar to lettuce and cabbage), and 2)a vegetation yield of 2 kg/square meter.~pq 0242p RETS Manua1..Revision 8 Page 23 Ei 3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent

'checks an the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid.Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program<<hich has been approved by the Coamission.

h sumaary of the results obtained as part of the above.'required Znterlaboratory Comparison Program and in"Waco'idance.

<<KtL the.QDCM (or'..participants in the EPA cross check program shall provide the EPA program code desi'gnation for the unit)shall be included in the Annual Radiological Environmental Operating Report.Hath analyses not being perfonadd as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report.0242p E-5

<<l TABLE E-1 RETS Hanual Revision&Page 24 RADIOLOGICAL ENYIRONHENTAL HONITORING PROGRAH l.Exposure Pathway~dl d 1.AIRBORNE Radioiodine and Particulates 2.DIRECT RADIATION Number of Samples and Sam le Locationsa Hinimum of 5 locations At least 40 locations with>2 dosimeters at each location.Sampling and Collection Fre uenc Continuous operation of sampler with sample collection as required by dust loading but at least once per 7 days.At least once per 92 days~.~~Type and Frequency of Anal sis.Radioiodine canister.Analyze at least once per 7 days for I-131.Particulate sampler.Analyze for gross beta radioactivity

>24 hours following filter change.Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples.Perform gamma isotopic analysis on composite (by location).sample at least once per 92 days.Gamma dose.At least once per 92 days.aSample locations are given in the ODCH.'2420

, TABLE E-1 (Continued)

RETS Hanual Revision 8 Page 25 RADIOLOGICAl ENVIRONHENTAL HONI TORING PROGRAH.Exposure Pathway and/or Sam le Number of Samples and L tk Sampling and Collection Fre uenc Type and Frequency of Anal sis 3.HATERBORNE a.Surface b.Drinking c.Sediment d.Groundd 2 locations Hinimum of 1 downstream location, or all water supplies within 10 miles downstream which are taken from the Tennessee River.Hinimum of 1 location Compositeb sample co'llected over a period of c 31 days.Compositeb sample collectedc over a period<31 days.At least once per 184 days.Gamma isotopic analysis of each composite sample.Tritium analysis of com-posite sample at least once per 92 days.Gross beta and gamma isotopic analysis of each composite sample.Tritium analysis of composite sample at least once per 92 days.Gamma isotopic analysis of each sample.aSample locations are shown in the ODCH."Composite samples shall be collected by collecting an cComposite samples shall be collected over a period of within 3 miles downstream of the plant.dGround water.movement in the area has been determined Since no drinking water wells exist between the plant"0242p aliquot at intervals not,exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.<14 days for 131I if drinking water is obtained (I to be from the plant site toward the Tennessee River.and the river, ground water will not be monitored.

E-7

kj TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM RETS Manual Revision 8 Page 26 Exposure Pathway and/or Sam le 4.INGESTION a.Hi lk b.Fish Number of Samples and~Sl L ti 3 locations 2 samples Sampling and Collection Fre uenc At least once per 1S days when animals are on pasture;at least once per 31 days at other times.One sample in season, or at least once per 184 days if not s'easonal.-bne sample of commercial and game species.Type and Frequency of Anal sis I-131 analysis of each sample.Gamma isotopic analysis at least once per 31 days.Gamma isotopic analysis on edible portions.c.Food Productse 2 locations At least once per year at time of harvest.Gamma isotopic analysis on edible portion.aSample locations are shown in the OOCH.~~eSince water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed.(I E-8."0242p

TABLE E-2~HAXIHUH VALUES FOR THE LONER LIHITS OF DETECTIOH (LLD)a~c RETS Hanual, Revision&Page 27 Analysis Airborne Particulate Hater or Gag Fish Hl1k (pCi/1)(pCi/m>)(pCi/kg, met)(pCi/1)Food Products (pCi/kg, wet)Sediment (pCi/kg, dry)gross beta H-3 Hn-54 Fe-59.Co-58, 60 Zn-65'I~Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 2000 15 30.15 30 30 lb 15 1&60 15 lx10 2 N.A.N.A.N.A.N.A.N.A.H.A.N.A.7 x 10-2 5 x 10-2 6 x 10-2 N.A.N.A.H.A.N.A.130 260 130 260 H.A.H.A.N.A.130 150 N.A.N.A.E-9 N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.15 18 60 H.A.H.A.H.A.N.A.N.A.H.A.H.A.H.'A tj0&g.N.A.N qA.H.A.N.A.fl.A.N.A.N.A.N.A.N.A.H.A.N.A.150 180 N.A.H.A.~.0242 p

/s RETS Manual Revision 8 Page 28 TABLE E-2 (Continued)

TABLE NOTATION a.The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95K probability with 5'i probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

4.66 sb E*V~2.22*Y+exp (-Xdt)Where:~~LLD is the"a priori" lower limit of detection as defined above (as picocurie per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample sise'in units of mass or volume), 2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), X is the radioactive decay constant for the particular radionuclide, and ht is the elapsed time between sample collection (or end of the sample collection period)and time of counting (for environmental samples, not plant effluent samples).It should be recognised that the 11D is defined as a priori (before the fact)limit representing the capability of a measurement system and not as an a posteriori (after the fact)limit for a particul'ar measurement.

0242p.E-10

~~RETS Manual Revision 8 Page 29 TABLE E-2 (Continued)

TABLE NOTATION b.The LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L.If levels greater than 15 pCi/L are identified in sux'face water samples downstream from the plant, or in the event of an unanticipated release of I-131, dxinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.c.Other peaks which are measurable and identifiable, togethex with the x'adionuclides in Table E-3, shall be identified and reported.0 g~~~0242p E-11

TABLE E-3 RETS Manual Revision 8 Page 30 REPORTING LEVELS FOR RAOIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES Reporting Levels Hater~Anal si s~(Ci/1)Airborne Particulate or Gases (Cilm>)Fish (CilK wet)Hi lk~(cill)Food Products (CilK wet)H-3 2 x 104<<)H.A.N.A.H.A.N.A.Hn-54 Fe-59 Co-5S Co-60 Zn-65 Zr-Nb-95 I-131 Cs-134 Cs-13?1 x103 4 x 102 1 x 163 3 x 102 3 x 102 4 x 102 30 50 Ba-La-140.2 x 102 N.A.N.A.N.A.N.A.H.A.N.A.0.9 10 20 H.A.3 x 104 1 x104 3 x104'1 x 104 2 x102 N.A.N.A.'1 x 103 2 x 103 N.A.N.A.N.A.N.A.N.A.N.A.~$.A.1.'3",60 7,0.~~'.3 x 102 N.A.N.A.N.A.N.A.N.A.N.A.1.x 102 1 x 103 2 x103 H.A.~(a)For.drinking water samples.This is 40 CFR Part 141 value.E-12-~,0242 p RETS Manual Revision 8 Page 31 F, REPORT CONTENT F,l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Reports covering operation of the plant during the previous calendar year shall be submitted prior to May 1 of each year.The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment.

The reports shall also'inc1ude-the't'esulfa af land..use censuses required by section E.2 of this manual.If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problems and a planned course of action to alleviate the problem.0 The annual radiological environmental operating reports shall include sumaarixed and tabulated results in the format of Regulatory Guide 4.8, December 1975 of all radiological environmental samples taken during the report period.In the event that some results are not available for inclusion with the report, the report shall be submitted noting and'explaining the reasons for the missing results.The missing data shall be submitted as soon as possible in a supplementary report.The reports shall also include the following:

a summary description of the radiological environmental monitoring program;a map of all sampling locations keyed to a table giving distances and directions from one reactor;and the results of licensee participation in the Interlaboratory Comparison Program, required by section E.3 of this manual.0242p F-1 RETS Manual Revision 8 Page 32 F,2 SEMIANNUAL RADIOACTIUE EFFLUENT RELEASE REPORT A report on the radioactive dischax'ges released from the site during the pxevious 6 months of operation shall be submitted to the Director of the Regional Office of Inspection, and Enforcement within 60 days after January 1 and July 1 of each year.The report shall include summary of the quantities of radioactive liquid and gaseous effluents released and solid waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1,"Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light>>Water-Cooled Nuclear Power Plants," with data sunmarixed on a quartex'ly basis following the format of Appendix B thereof The report shall include a summary of the,-meteorological.'.canditgons concuxrent with the release of gaseous effluents during each quarter as outlined in Regulatory Guide 1.21, Revision 1, with data summarixed on a quarterly basis foLlowing the format of Appendix B thereof.Calculated otfsite dose to members of the public resulting from the release of liquid and gaseous effluents an'd their subsequent dispersion in the river and atmosphere shall be reported as recommended in Regulatory Guide 1.21, Revision 1.The Radioactive Effluent Release Report shall include the following information for each type of solid-waste shipped offsite during the report period (a)container volume, (b)total curie quantity, (specify whether determined by measurement or estimate), (c)principal.

radionuclides'specify whether determined 5y measurement or estimate), (d)sources of waste and processing employed (e.g.dewatered'pent

'resins, compacted dry waste, etc.), (e)type of container (e.g., LSAi Type A, Type B, large quantity), and (f)solidification agent or absox'hant (e.g.concrete, urea formaldehyde, etc.).0242p F-2 RETS Manual Revision 8 Page'33 F.3 SPECIAL REPORTS Radiolo ical Environmental Monitorin If measured levels of radioactivity in an environmental sampling medium are determined to exceed the reporting level values of Table E-3 when averaged over any calendar quarter sampling period, a report shall be submitted to the Commission pursuant to Section E.l of this Manual.0242p F-3 RETS Manual Revision 8 Page 34 RETS MANUAL Section III OFFSITE DOSE CALCULATION 0242p RETS Manual.Revision 8 Page 35 1.0 Gaseous Effluents TABLE OF CONTENTS~Pa e 40 1.1 Alarm/Trip Setpoints 40 1.1.1 Release Limit Methodology

-pCi/s 40 Release.Rate Limit Methodology

-Dose Rates-Noble Gas-Iodine and Particulate Release Rate Limit Methodology

>>Setpoints 1.2 Monthly Dose Calculations 1.2.1 Monthly Noble Gas Dose (Conse&fative-Model)

"--.-Gaaiaa dose to air-Beta dose to air 40 40 42 43 47~-.47 48 48 1.2.2 Monthly dose from Zodines, Particulates, and Tritium (Conservative Model)49-Thyroid dose-Bone Dose-Gastrointestinal Tract (GIT)-Comparison to Limits 49 50 51 52 1.2.3 Monthly Noble Gas Dose (Realistic Model)52-Gamma dose to.air-Beta dose to air 53 53 1.2.4 Zodines, Particulates and Tritium (Realistic Model)53 1.2.5 Cumulative Quarterly and Annual Dose 54"-1.3 Quarterly Dose Calculations

-Population Dose 55 55 1.4 Gaseous Radwaste Treatment System Operation 1.4.1 System Description 57 57 1.4.2 Dose Projections

'7 1~5 Gaseous Releases-Dose Calculation Equations 1.5.l.Noble gas-Gamma ai.r dose 58 58 1.5.2 Noble gas-Beta air dose 1.5.3 Radioiodine, particulate>

and tritium-Maximum organ dose.59 0242'

p RETS Manual Revision 8 Page 36 TABLE OF CONTENTS 1.6 Gaseous Releases-Dose Factors 1.6.1 Pasture Grass-Co>/Goat-Milk Ingestion Dose Factors-RCPi 1.6.2 Stored Fead-Co+/Goat-Milk Ingestion Dose Factors~Pa e 61 61 1~6.3 Pasture Grass-Beef Ingestion Dose Factors-RMPi 63 1.6.4 Stored Feed-Beef Ingestion Dose Factors-RMSi 64 1.6.5 Fresh Ieafy Vegetable Ingestion Dose Factors-RVFi 65 P~4~~I'1.6.6 Stored Vegetable Ingestion Dose Factors-RVSi 66 1.6'Tritium-Pasture Grass-Co+/Goat

-Milk Dose Factors RCTP 1.6.8 Tritium-Stored Feed-Cov/Goat-Milk Dose Factors-RCTS 1.6.9 Tritium-Pasture Grass-Beef Dose Factors-RMT 1;6.10 Tritium-Stored Feed>>Beef Dose Factors-'RMTS 1.6.11 Tritium-Fresh Leafy Vegetables Dose Factors-RVTF 1.6.12 Tritium'-Stored Vegetables Dose Factors-RVTS 1.6.13 Inhalation Dose Factors'RZi 1.7 Dispersion Methodology-1.7.1 Air Concentration

-X 1.7.2 Relative Concentration

-X/Q 1.7.3 Relative Deposition

-D/Q 1.7.4 Effective Release Height 2.0 Liquid Ef f li~ents 67 68 69 70 71 72" 73 74 76 76 77 79 2.1 Release Rate Limit Methodology 2.1.1 RETS Requirement 2.1.2 Prerelease Analysis 2.1.3 Release Floe Rate Calculations 79 79 79 80 0242p 2.2 Instrument Setpoints TABLE OF CONTENTS RETS Manual Revision 8 Page 37~Pa e 80 2 2.1 Setpoint Determination 2.2.2 Post-Release Analysis 2o3 Dose 80 82 82 2.3.1 RETS Requirement 2.3.2 Monthly Analysis 2.3.2.1 Water Ingestion 2.3.2.2 Fish'Ingestion

'.3.2.3 Recreation 2.3.2.4 Monthly Suahary 2.3.3 Quarterly Dose Calculations

/~82 84 85 86 87 88 2.3.3 1 Water Ingestion 1 2.3~3.2 Pish Ingestion.

2.3.3-3 Recreation Shoreline 88 89 89 2.3 3.4 Total Maximum Individual Dose 2.3.3.5 Population Dose 2.4 Operability of Liquid Radvaste Equipment 2.5 Liquid Dose Factor Equations 2.5.1 Water Ingestion Dose Factors 2.5.2 Fish Ingestion Dose Factors 2 5.3 Shoreline Recreation Dose Factor 90 91 93 93 93 94 3.0 Radiological Environmental Monitoring 94 3.1 Monitoring Program 3.2 Detection Capabilities 3.3 Nonroutine Reports 4.0 Annual Maximum Individual Doses-Total 0242p 94 95 95~95 LIST OF TABLES RETS Manual, Revision 8 Page 38 Table Number 1~1 Title BFN-Offsite Receptor Location Data 1~2 Expected Annual Routine Atmospheric Gaseous Releases from One Unit at BPN 1 3 (Sheets 1-22)Joint Percentage Frequencies of Wind Speed by Mind Direction for Stability Class 1.4 Dose Factors for Submersion in Noble Gases 1.5 1.6 Sector Elements Considered for Population Doses BFN 50-Mile Population Within.Each Sector'..'.".'...

1'(Sheets 1-8)1.8 (Sheets 1&?)1 9 (Sheets 1&2)Ingestion Dose Factors>>DFL Radionuclide Decay and Stable Element Transfer Data Dose Calculation Factors 1.10 (Sheets 1-8)(1 11 (Sheets 1&2)Inhalation Dose Factors-DFA External Dose Factors for Standing on Contaminated

~Ground-DFG 2.1 2e 2 Receptors for(Liquid Dose Calculations Bioaccumulation Factors for Freshwater Pish-B 3'(Sheets 1-4)Radiological Environmental Monitoring 3.2 3.3 Atmospheric and Terrestrial Monitoring Station Locations Maximum Values for the Lover Limit of Detection (LLD)0242p

RETS Manual Revision 8 Page 39 LXST OF.FIGURES Fi e Number 1~2 1 3 1.4 (Sheets 1W)1.5 1.6 (Sheets 1-4)2 1 2.2 2 3 3.1 3.2 3.3 Titte BFN>>Land Site Boundary BFN Offgas System and SGTS Effluent Monitoring BFN Normal Building Ventilation Plume Depletion Effect (All Atmospheric Stability Classes)~~~~~~Vertical Standard Deviation of Material in a Plume (All Atmospheric Stability Classes)Relative Dep6sition (All Atmospheric Stability Classes)Assumed Liquid Effluent Restricted Area BFN Liquid Effluent Monitors Liquid Radwaste Treatment System Environmental Radiological Sampling Locations within 1 mile of plant Environmental Radiological Sampling Locations From 1 to 5 miles from the plant Environmental Radiological Sampling Locations Greater than 5 miles from the plant 0242p 1.0 Gaseous Rffluents 1.1 Alarm/Tri Set pints RETS Manual Revision 8 Page 40 Specification 3.8.B.1 requires that the dose rate at or beyond the site boundary (Figure 1.1)due to gaseous effluents from the site shall be limited at all times to the following values: 1.500 mrem/y Co the total body and 3,000 mrem/y to the skin from noble gases'.1,500 mrem/y to any organ from radioiodines and particulates.

S'pecification 3.2.K.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that the above dose rates are not exceeded.This section of the ODCM describes the methodology that will be used to determine allowable values which are used to calculate setpoints.

'i'gu'res 4.i2 anh-1 3"shew the Offgas System, the Standby Gas Treatment System and normal building ventilation with effluent monitor locations.

The methodology for determining alarm/trip allowable values is divided into two major parts.The first consists 6f backcalculating from a dose rate to a release rate limit, in pCi/s, for each nuclide and release point.The second consists of using the release rate limits to determine the allowable values which are used to calculate Che physical settings on the monitors.The monitor setpoints are calculated in the applicable Scaling and Setpoint Document.1,1.1 Release Rate Limit Methodolo-Ci s Release Rate Limit Methodolo-Dose Rates First, a dose rate is calculateii based on the design objective source term mix used in the licensing of the plant.Dose rates are determined for (1)noble gases and (2)iodines and particulates.

Release Rate Limit Methodolo>>Dose Rates-Noble Gas Dose rates are calculated for total body and skin, due to submersion within a cloud of noble gases, using a semi-infinite cloud model.The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN.The dose rates are evaluated at the offsite locations with the highest expected concentrations, i.e., the nearest land site.boundary points in each sector (from Table 1.1)and at other locations expected to be the maximum exposure points.The noble gas radionuclide mix use'd in this calculation is based on the design objective'ource term given in Table 1.2.Dispersion of the released radioactivity is handled as described in Section 1.7 using historical annual average meteorological daga given in Table 1.3.No credit is taken for shielding by residence.

0242p

~~~RETS Manual Revision 8 Page 41 To calculate the dose rate from radiological effluents discharged from a given release point for any one of the potential maxinm~xposure points, the following equations are used.Total Bod Dose Rate Xi DFBi vhere~total body dose rate, mrem/y.Xi DFBi~air concentration of radionuclide i, pCi/m3.Air, concentrations are calculated as deacgihed,by.Equation'1.l4.

~total body dose factor due to ganja radiation, mrem/y per pCi/m3 (Table 1.4).Skin Dose Rate Ds~E Xi (DFSi+1.11 DFY@here Ds~skin dose rate, mrem/y.~air concentration of radionuclide i, pCi/m3.Air concentrations are calculated as described by Equation 1.14.DFSi~skin dose facto>>due to beta radiation, mrem/y per.pCi/m3 (Table 1.4).~the average ratio of tissue to air energy absorption coefficients, mrem/mrad DFYi~gsama-to-air dos'e factor for radionuclide i, mrad/y per pCi/m>(Table 1.4).4 The total body and skin dose rate calculations are repeated for each release point.Dose rates for releases from all building vents are sunIm-'d.The maximum stack and building vent total body and skin dose rates vill be used to determine release rate limits.0242p

RETS Manual Revision 8 Page 42 Release Rate Limit Methodolo-Iodine and Particulate Dose Rates For setpoints, the iodine and particulate dose rates are calculated for the design objective source term given in Table 1.2.Dose rates are calculated for the critical organ, thyroid, of the critical age group, infant.Pathways considered are inhalation, ground contamination and milk ingestion.

The dose rates are evaluated at the offsite locations with the highest expected concentrations>

i.e., the nearest land site boundary points in each of the 16 sectors (from Table 1.1)and at, other locations expected to be the maximum exposure points.This calculation assumes that a (hypothetical) cow is at each of these locations.

These cows are assumed, conservatively, to obtain 100 perceat of their food from pasture grass.The iahalation, ground contamination, and milk ingestion dose rates (ia mrem/year) for the selected organ (thyroid)and-age.group.(fxtfant).

ate calculated usiag Equation 1.13 as described in section 1.5.3.For determining the total thyroid dose rate from iodines and particulates:

DTHr.+DTBG+DTHM (1.3)where:~total thyroid dose rate, mrem/yr.TBG~thyroid dose rate due to: inhalatioa, mrem/yr.~total body dose rate due to ground contamination, mrem/yr.The thyroid dose rate is assumed to be equal to the total body dose rate for this pathway.~thyroid dose rate due to pasture grass-.cow-milk ingestion, mrem/yr.The above dose rate calculation is repeated for each release point.Dose rates for releases from all building vents are suamed The maximum stack and building vent thyroid dose rates will be used to determine release rate limits.0242p RETS Manual Revision 8 Page 43 Release Rate Limit Methodolo-Set pints The dose rate limits of interest (Specification 3.8.B.1)are: Total Body~500 mrem/yr Skin~3000 mrem/yr Maximum Organ~1500 mrem/yr These limi,ts are divided by the corresponding calculated dose rates (from Equations 1.1, 1.2, and 1.3): Total Body Dose Rate Limit RTB(vent or stack)DTB (vent or shack)r~Skin Dose Rate Limit RS(vent or stack)DS (vent or stack)RTH(vent or stack)Maximum Organ'Dose Rate Limit DTH (vent or stack)These ratios represent how far above or below the guidelines the dose rate calculations were.h total release rate, g, for each nuclide type (noble gas o i odine/particulate) and release point (building vent or stack)is s or calculated, using the source term data in Table 1.2.Thus, four total release rates are calculated:

gzgv~Total noble gas release rate from building exhaust vents,.Ci/s.gngs~Total noble gas release rate from main stack, Ci/s.Qipv'Total iodine and particulate release rate f rom building exhaust vents, Ci/s.pips~Total iodine and particulate release rate f rom main t k Ci/s.nsac, To obtain a release rate limit, r, for each nuclide type and release point, the total release rate, g, for that nuclide type and release point is multiplied by the corresponding ratio>R: 0242p RETS Nanual Revision 8 Page 44 For noble gases released from building vents.'ngv

~RTBv~ngv~or a RSv Qngv whichever is more restrictive, i.e., smaller.where rngv~Calculated release rate limit for noble gases released from building vents.~Ratio of total body dose rate limit to total body dose rate for building vent releases, as calculated above.~Total Table 1.2 noble gas release rate from building vents.RSv~Ratio of skin dose rate Limit to skin dose rate for building vent releases, as calculated above.For noble gases released from the stack: rngs RTBs~ngs~~RSs~ngs or vhi<<hever is more restrictive, i.e., smaller.rngs'Calculated release rate limit for noble gases released from the stack.RTBs~Ratio of total body dose rate limit to total body dose rate for stack releases, as calculated above.~Total Table 1.2 noble gas release rate from stack.RSs~Ratio of skin dose rate limit to skin dose rate for stack releases, as calculated above.0242p

RETS Manual Revision 8 Page 45 For iodines and particulates with half-lives greater than 8 days released from building vents: ripv RTHv~ipv where ripv RTHv~Calculated release rate limit for iodines and particulates released from building vents.k~Ratio of maximum organ dose rate limit to maximum organ dose rate for building vent releases, as calculated above.Qipv~To tal Tab 1 e 1 2 iodine and par ticulate re lease rate f rom building vents.For iodines and particulates with half-lives greater than 8 days'-=-released from the stack: rips+THs~ips where rips~Calculated release rate 1 imi t f or iodines and particulates released from the stack.RTHs~Ratio of maximum organ dose rate limit to maximum organ dose rate for stack releases, as calculated above.pips~Total Table 1.2 iodine and particulate release rate from stack.The release rate limits, r, calculated for BFN using this methodology are: Nable Cas Iodine and Particulate Stack, rngs~1.44E+01 Ci/s'ips~3.57E&5 Ci/s Building Vents rngv~1.50E-Ol Ci/s ripv~2 19E&6 Ci/s e~The values listed are used as administrative guidelines for operation and for development of alarm/trip setpoints to ensure that instantaneous dose rates do not exceed release rate limits.Allowable Values To determine allowable values for gaseous efflvent monitors, shown in Figures 1.2 and 1.3, the noble'as release rate limits are used.The allowable values are calculated using the following equatiog 0242p Allowable Value c r f'A F E RETS Manual Revision 8 Page 46 vhe re release rate limit for stack or ground level, pCi/sec.The release rate 1 imi ts used for the a 1 lovab 1 e value calculation are 1.44E+07 pCi/sec for the s tack and 1.50E+05 pC i/sec for the building vents.f~fraction of the 1 imits r which is allowed for the release mode (e 1 evated or ground level)~NOTE: The sum of the f values for.elevated and ground levels must be less than or equal to 1.This lovers the Limits to ensure that the s i te dose rate Limit vi 1 1 not be exceeded i f both the stack and the ground leveL re 1 ease rate limits vere reached simultaneously.

A~allocation factor.This is the portion of the release rate Limit r which is assi gned to the re 1 ease point under consideration.

This ensures that the ground level re lease rate limit vi 1 1 not be exceeded i f al 1 building vents were..to reach their Limit simultaneously This is equal to'-f or the.s t'ack;=The bui 1 ding vent re 1 ease rate Limit is d ivided among the ten vents based on the f lov rates.F~f lov rate for the vent, cc/sec.Maximum f lov rates are used to ensure conservative se tpo inta.E~efficiency of the moni tor, pCifcc/cpm (or pCi/cc/cps for the'tack monitor)B~background of the monitor, cpm (cps f or the stack moni ter)The cal culat ion of these se tpo ints are documented f urther in Technica 1 Instruction 15 and the app 1 icab 1 e Seal ing and Setpoint Document, including the numerical values f or each of the parameters descr ibed above.Instantaneous Re 1 ease Rates Instantaneous release rates, q in C i/s, f or each nuc 1 ide type and release poi nt are limited'y the f o 1 loving equations:

For nob le gases,+c 1%agv'a'gs 0.15 14.4 For iodines and particulates, q i pv+qips 2.1 98-06 3~5 l E-05 c 1 vhere qngv~ins tantaneous noble gas release rate from bui 1 d ing~'ants, C i/s.~instantaneous noble gas release rate'qipv~ins tan taneous iodine and particulate vents, Ci/s.f rom the stack, Ci/s.release rate f rom building qips~ins tantaneous iodine and particulate re 1 ease rate f rom the 0242 stack, Ci/s.

RETS Manual Revision 8 Page 47 1 2 Monthl Dose Calculations Dose calculations will be performed once per 31 days to determine compliance with specifications 3.8.B 3 and 3 8 B.5~These specifications require that the dose at or beyond the site boundary due to gaseous effluents from each reactor at the site shall be limited to the following.'or noble gases, 1.During any calendar quarter, 5 mrad to air for gamma radiation and 10 mrad to air for beta radiation.

2.During any calendar year, 10 mrad to air for gamma radiation and 20 mrad to air for beta radiation.

r~+~~~For I-131, I-133, Tritium and particulates with half lives greater than&days, 1.During any calendar.quarter, 7.5 mrem to any organ.I 2.During any calendar year, 15 mrem to any organ.This section of the ODCM describes the methodology that will be used to perform these monthly calculations Doses will be calculated using the conservative model described in Sections 1.2.1 and 1.2.2.If the monthly fraction-of the annual one~it Technical Specification Limit is exceeded, a realistic model, described in Sections'1.2.-3 and 1.2.4, will be used.1.2.1 Monthl Noble Gas Dose (Conservative Model)Doses to be calculated are gamma and beta air doses due to exposure to a semi-infinite cloud of noble gases.The use of a finite cloud model would result in caLculated doses of 0 to 10 percent higher.than those calculations using the semi-infinite cloud model for BFN.Releases of hz-41, Kr-85m, Kr-85, Kr-87, Kr88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 are considered.

Because only these nuclides are considered, the dose is divided by ,0.9, to account for a possible 10 percent contribution=of dose from other nuclides.The dispersion factor used will be the highest annual-average X/Q based on 1977-L979 meteorological data (Table 1.3).Dispersion factors are calculated using the methodology described by Equation 1.15'tack releases are considered elevated releases.hLL other vent releases will be treated as ground level.No credit is.taken for radioactive decay.0242p Nonth1 Conservative Nodel-Gamaa dose to air RETS Manual Revision 8 Page 48 where: Dy-g Qi DFyg (X/Q)10 0 9 3.15xlO~(1.4)Dy X/Q~gamma dose to air, mrad.~highest land-site boundary annual-average relative concentration, s/m~(from Table 1.1).~1.84xlO 6 for ground level releases,~2.08xlO~for elevated releases (stack).0.9 loi~fraction of total gamma dose expected to be contributed by the assumed nucl ides./,~~pCi/Ci conversion factor.3.15x10~~s/yr conversion factor.Ri~monthly release of radionuclide i, Ci.DFgi~gamna-to-air dose factor for radionuclide i, mrad/yr per pCi/ms (Table 1.4).Nonthl Conservative Model-Beta dose to air (X/Q)10<0 9 3~15xlO 7 Qi DFSi (1.5)where:~beta dose to air, mrad.X/Q~highest land-site boundary annual-average relative concentration, s/m~(from Table 1.1).~L.84x10 6 for ground level releases,~2.08xlO 8 for elevated releases (stack).0.9~fraction of total beta dose expected to be contributed by the assumed nuc 1 ides.loi~pCi/Ci conversion factor.3.15xlO~~s/yr conversion factor.DFai~monthly release of radionuclide i, Ci.~beta-to-air dose factor for radionuclide i, mrad/yr per pC1/m~(Table 1.4).0242p RETS Manual Revision 8 Page 49 1.2.2 Monthl dose fxom Iodines Particulates and Triti,um (Conservative Model)Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen gastrointestinal tract (GIT)fxom vegetable ingestion.

Releases of H-3, I-131, and I-133 are considered for the milk pathway.8-3, Si-89'r-90, Cs-134, and Cs-137 releases are considered for the vegetable pathway to the child bone.8-3, Co-58, and Co-60 releases are considered for the vegetable pathway to the teen GIT.tract.The most, critical real cow location is considered for the milk pathway and the most critical location with a home-use garden is considered for the vegetable pathways (see Table 1.1).The cow is assumed to graze on pasture grass for the whole yeax.The highest annual-average X/Q and D/Q based on 1977-1979 meteorological data (Table 1.3)will be used for ingestion pathway locations.

Dispersion values are calculated aa-+scribed.by

-.......-'quations 1 15 and 1.16.Stack releases are considered elevated releases.All other vent releases will be treated as ground level.No credit is taken for xadioactive decay.Doses are divided by 0.9 to account for a passible 10 percent contribution from other nuclides.Monthl Conservative Model-Infant Th roid Dose from Milk In estion The monthly thyxoid dose f'rom milk ingestion is calculated using the following equation: where E(Qi RCPi)D/Q 10+(QT RCPT)X/Q 0.9 x 3.15x1.0~(1.6)Qi~monthly release of iodine nuclide i, Ci.~monthly release of 8-3>Ci.RCPi~I-131 ox'-133 pasture'rass-cow-milk ingestion dose factor fox'nfant thyroid, mrem/yr per pCi/mz-s.Dose factoxs are calculated as described in Section 1.6.1.~8-3 pasture grass-cow-milk ingestion dose factor for infant thyroid, mrem/yr per pCi/cc.The dose factor is calculated as described in Section 1.6.7.0242p D/Q\f w highest relative deposition rate for a location identified milk co+, m>(from Table 1.1).~3.16x10 10 for ground level releases,~2.30xl0 10 for elevated releases (stack).RETS Manual Revision 8 Page 50 with an X/Q~highest relative air concentration for a location with an identified milk co+, s/m~(from Table 1.1).~1.47x10"07 for ground level releases,.~1.69x10 08 for elevated releases (stack).0 9~fraction of dose expected to be contributed by I-131, I-133 and 8-3.3.15x10~~s/yr.10c pCi/Ci r'/Monthl Conservative Model-Child Bone Dose from Ve etable In estion The monthly bone dose from vegetable ingestion is calculated using the following equation: E (Qi DFi)D/Q 10~+QT DFT X/Q DBC~0.9 x 3~15xl0>@here Qi~monthly release of Sr or Cs nuclide i, Ci.~monthly release of E-3, Ci.DFi~Total vegetable ingestion dose factor to child bone for Sr-89, Sr-90, Cs-134 or Cs-137, mrem/yr per pCi/m~-s.~RVFi+RVSi,+here RVFi is the dose factor for fresh leafy vegetables (as calculated in Section 1.6.5)and RVSi is the dose factor for stored vegetables (as calculated in Section 1.6.6)-DFT~Total vegetable ingestion dose factor for chi.ld bone for 8-3, mrem/yr per pCi/cc.~RVFT+RVST, where RVFT is the tritium dose factor for fresh leafy vegetables (as calculated in Section 1.6.11)and RVSi is the tritium dose factor for stored vegetables (as calculated in Section 1.6.12).0243p RETS Manual Revision 8 Page 51~highest relative deposition rate for a location vith an identified home use garden, m~(from Table 1.1).~4.46xl0 09 for ground level releases,~1.13xl0~9 for elevated releases (stack).X/Q~highest relative air concentration for a location with an identified home use garden, s/m>(from Table L.l).~1.57x10"06 for ground level releases,~9.50x10 09 for elevated releases (stack).3.15x10>~s/yr.10'pCi/Cl 0.9~fraction of total child bone dose expected to be contributed by H-3, Sr-89, Sr-90, Cs-134, and Cs-137.Monthl Conservative Model Teen Gastrointestinal Tract GIT Dose from Ve etable In cation The monthly teen GIT dose from vegetable ingestion is calculated using the folloving equation: E (Qi DFi)D/Q 10'QT DFT X/Q DGT~0.9 x 3.15xl0~(1.8)~monthly release of cobalt nuclide i>Ci.a monthly release of H-3, Ci, DFi~Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem/yr per pCi/m~-s.~RVFi+RVSi,+here RVFi is the dose factor for fresh leafy vegetables (as calculated in Section 1.6.5)and RVSi is the dose factor for stored vegetables (as calculated in Section 1.6.6).DFT~Total vegetable ingestion dose factor to the teen GIT for H-3, mrem/yr per pCi/cc.~RVFT+RVST, where RVFT is the tritium dose factor for'resh leafy vegetables (as calculated in Section 1.6.11)and RVST is the tritium dose factor for stored vegetables (as calculated in S=ition 1.6.12).0243p D/Q'ETS Manual Revision 8 Page 52~highest relative deposition rate for a location with an identified home use garden, m~(from Table 1.1).~4.46x10"09 for ground level releases'1.13x10"09 for elevated releases (stack).X/0~highest relative air concentration for a location with an identified home use garden, s/m~(from Table 1.1).~1.57x10~6 for ground level releases,~9.50xl0 09 for elevated releases (stack).3.15x10>~s/yr.10'pCi/Ci.0 9~fraction of total teen CIT dose expected to be contributed by H-3, Co-58, and Co-60.Total Monthl Dose-Co arison to Limits The calculated.

gamaa-air and beta-air doses are compared to the mo'nthly fraction of the annual one>>unit limit'or these doses, i.e., 0.83 mrem for gsama-air and 1.67 mrem for beta-air.The maximum monthly organ dose is the highest of the three doses calculated; it is compared to the aenthly fraction of its annual limit, i.e., 1.25 mrem.If any of the doses calculated by the conservative monthly dose model exceed the monthly fraction of the one-unit annual Technical Specification limits, a more comprehensive.

dose assessment will be performed as described below.For doses calculated to be less than these limits, the results of the conservative monthly model will be used to determine cumulative quarterly and annual doses as described in Section 1.2.5.1.2.3 Monthl Noble Gas Dose (Realistic Model),...In the-realistic model, all measured radionuclides are used to calculate gamaa and beta air doses The dose is evaluated at the nearest land site boundary point in each sector and at other locations expected to be maximum exposure points using a semi-infinite cloud model.The use of a finite cloud model would result in calculated doses of 0 to 10 percent higher than those calculations using the semi-infinite cloud model for BFN Historical onsite meteorological data from the period 1977-1979 (Table 1.3)will be used to calculate dispersion factors as described in section 1.7.Stack releases will be considered elevated releases.Radwaste and reactor building releases will be considered split-level releases.Turbine building releases will be treated as ground level.Radioactive decay is considered in this calculation.

The monthly release is averaged over one year to obtain an average release rate.0 0243p

RETS Manual Revision 8 Page 53 Realistic Model-Gamma dose to air Dyn~tm E}(ni Dpi (l.e)where: Dgn Xni~gaama dose to air for sector n, mrad.~air concentration of radionuclide i in sector n, pCi/m>.Air concentrations are calculated as described by Equation 1.14.DF>i w gamma-to-air dose factor for radionuclide, i, mrad/yr per pCi/ms (Table 1.4).~time period over which the release is'aver'aged, yr.Realistic Model-Beta dose to air Dg, t E Xni Dpi i (l.10)where:~beta dose to air for sector n, mrad.Xni~air concentration of radionuclide i in sector n, pCi/ms.Air concentrations are calculated as described by Equation 1.14.Dpi~beta to air dose factor for radionuclide i, mrad/yr per pCi/m~(Table 1.4).~time period over which the release is averaged, yr.The highest gamma-air and beta-air doses calculated will be used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.8.B.3.1.2.4 Zodines Particulates and Tritium (Realistic Model.)Doses for releases of iodines, particulates, and tritium will.be calculated using Equation 1.13 given in Section 1.5.3.Thc calculation will consider all measured radionuclide releases.The dose will be'valuated for all organs and a11 age groups, and the maximum organ dose selected.Actual land use survey data and gracing information will be.used to determine the dose for real individuals and pathways.:.02439

RETS Manual Revisi.on 8 Page 54 Historical onsite meteorological data from the period 1977 1979 (Table 1.3)vill be used to calculate dispersion factors as described in section 1.7.Stack releases vill be considered elevated releases.Radvaste and reactor building releases vill be considered split-level releases.Turbine building releases vill be treated as ground level.The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathvays including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cov, and/or goat milk ingestion (if a cov or goat is identified for the location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors vill be considered the beef dose for all receptors).

The receptor having the highest organ dose is then used in the cumulative quarterly and annual dose determination to check compliance vith Specification 3.8.3.5.1.2,5 Cumulative rterl and Annual Doses Cumulative calendar quarter doses are estimated.

by summing the doses calculated for each month in that quarter.Cumulative calendar year doses are es imated by sunming the doses calculated for each month in that year.The cumulative calendar quarter and calendar year doses are compared to their respective one-unit Technical Specification limits to determine compliance If any limit is exceeded, a determination will be made to apportion the dose betveen the reactor units in accordance vith the releases that can be assigned to each.Q243p 1.3 rterl Dose Calculations

', RETS Nanual Revision 8 Page 55 A complete dose analysis utilising the total estimated gaseous releases for each calendar quarter vi11 be performed and reported as required in Specifications 6.7.5.Methodology for this analysis is that which is described in Section 1 5, using the quarterLy release values reported by the plant pcrsonneL.

For iodine releases, it vill be as'sumed that half the iodines released are organic iodines, vhich contribute only to the inhalation dose.All real pathvays aad receptor locations (as identified in the most recent land use survey)are considered.

In addi.tion, actual meteorological data representative of each corresponding calendar quarter vill be used to calculate dispersion factors as described in section 1.7.Stack releases vill be considered elevated releases.Radvaste and reactor building releases vill be considered split-level releases.Turbine building releases vill be treated as ground leveL.The highest gamaa-air and beta-air doses calculat'ed wili-be used to-oheck compliance vith the quarterly limits of Specificatioa 3.8.B.3.The highest orgaa dose for a real receptor is determined by sunning the dose contribution from all real pathvays including ground contamination, inhalation, vegetable ingestion (for identified garden loc;ations), cow and/or goat milk ingestion (if a cov or goat is identified for t'e location), beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors'ill be coasidered the beef dose for all receptors).

The receptor having the highest organ dose is then used to check compliance vi.th the quarterly limits of Specification 3.8.B.5.Po ulation Doses For determining population doses to the 50-mile population around the plant, each compass sector is broken dovn into elements.These elements are defined in Table 1.5.For each of these sector elements, an average dose is calculated, and then muLtiplied by the population in that sector element.Dispersioa factors are calculated for the midpoint of each sector element (see Table L.S).For population doses resulting from ingestion, i.t is conservatively assumed that all food eaten by the average i.ndividual is grown locally.The general equation used for calculating the population dose in a given sector element is: Dosepop~$RATIOp+POPN*AGE+0.001+DOSEp P where RAT IOp~ratio of average to maximum dose for patt say P.(Average ingestion rates are obtained from Regulatory Guide 1.109, Table E-4.)I~0.5 for submersion and ground exposure pathways, a shielding/occupancy factor.0243p RETS Nanual Revision 8 Page 56~1.0 for the inhalation pathway.~0.515, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult, respectively.(It is assumed that the ratio of average to maximum infant milk ingestion rates is the same as that for child.)~1.0, 0.90, 0.91, 0.86 for beef ingestion, for infant, child, teen and adult, respectively.

~L.O, 0.38, 0.38," 0.37 for vegetable ingestion, for infant, child, teen and adult, respectively.(It is assumed that the average individual eats no fresh vegetables, only stored vegetables.)

POPN AGE~the population of the sector element, persons (Table 1.6).~fraction of the population belonging to each age group.0 001~0.015, 0.168, 0 153, 0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).~conversion from mrem to rem.~the dose for pathway P to the maximum individual at the location under consideration, mrem.For ingestion pathways, this dose is multiplied by an average decay correction to~account for decay as the food is moved through the food distribution

>cycle.This average decay.correction, ADC, is defined as: ADC~exp(-'hit), for milk and vegetables, where~decay constant for nuclide i, seconds.~distribution time for food product under consideration (from Regulatory Guide 1.109, Table D-l).~1.21E+06 seconds (14 days)for vegetables.

~3.46E+05 seconds (4 days)for milk.exP(-Alt)'Xitcb 1-exp(-Xitcb)

, for meat, where'Ai~decay constant for nuclide i, seconds.0243p RETS Manual Revision 8 Page 57~additional distribution time fox meat, over and above the time for slaughter to consumption described in Section 1.6.3, 7 days (from Regulatory Guide 1.109, Table D-2).tcb~time to consume a whole beef, as described in Section 1.6.3.For beef ingestion, the additional factors in the calculation of ADC negate the integration of the dose term over the period during which a whole beef is consumed, for the calculation of population dose.This assumes that the maximum individual freezes and eats a whole beef, but the average individual buys smaller portions at a time.Population doses are summed over all sector elements to obtain a total population dose for the 50-mile population.'.4 Gaseous Radwaste Treatment S stem 0 eration The gaseous radwaste treatment system (GRTS)described below shall be maintained and operated to keep releases ALARA.1.4.1 S stem Descri tion A flow diagram for the GRTS is given in Figure 1.3.The system includes the subsystems that process and dispose of the gases from the main condenser air ejectors, the startup vacuum pumps, and the gland seal condensers.

Qne gaseous radwaste treatment system is provided for each unit.The processed gases fxom each unit are routed to the plant stack fox'ilution and elevated xelease to the atmosphere.

The air-ejector off-gas line of each unit and the stack are continuously monitored by radiation monitors.In accordance with Section D.2 of the REM, dose projections will be performed.

This will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.If the results of the dose projection indicate potential doses in excess of the monthly fraction of the annual Technical Specification dose limit, efforts vill be recomnended to minimize future releases.0243p

RETS Manual Revision 8 Page 58 1.5 GASEOUS RELEASES-Dose Calculation'Equations 1.5.1 Noble as-Gamma air dose Gamma air doses due to exposure to noble gases will be estimated with the fo'llowing equation: 'y~Xim Dpi (1~11)where: Dy DF~i~Gaama air dose, mrad~concentration of nuclide i at locate.m;-pCi/m3.-:.Air....-

concentrations are calculated as described by Equation 1.14.~dose conversion factor for external gamma fax nuclide i, mrad/year per microcurie/m3 (Table 1.4).1 5i2 Noble as-Beta air dose~.Beta air doses due to exposure to noble gases will be estimated with the following equation: Dg~Xim Dpi I (1~12)where:~Beta air dose, mead.~concentration of nuclide i at location m, pCl/m3.Air concentrations are calculated as described by Equation 1.14.Dpi~dose conversion factor for external beta for nuclide i, mrad/year per microcurie/m3 (Table 1.4).0243p

RETS Manual Revision 8 Page 59 1.5.3 Radioiodine articulate and tritium-Maximum or an dose.Organ doses due to radioiodine, particulate and tritium releases are calculated using the fallawing equatian: Dorg~3.17E)8 f E (X/Q Z Rpi+D/Q RO1+X/Q RIi)Qi+(X/Q RPT)QT)P (1.13)where: Darg~Organ dose, mrem.3.17E&8 i conversion factor, year/second.

X(Q~Relative concentration for Location under cansiderat'.ion,"sec/aP~-

Relative concentrations are calculated as described by Equation 1.15.~ingestion dose factor for pathway P for each identified nuclide i (except tritium), m~em/year pft.r microcurie/second.

Ingestion pathways available for consideration include: D/Q RIi pasture grass-cow-milk ingestion sCored feed-cow-milk ingestion pasture grass-goatmilk ingestian stared feed-goat-milk ingestion pasture grass-beef ingestion stored feed-beef ingestion fresh leafy vegetable ingestion stored vegetable ingestion II Equations for calculating these ingestion dose factors are given in sections 1.7.1 through 1.7.6.~Relative deposition for lacation under consideratian, m 2.Relative deposition is calculated as described in Equation 1.16.i Dose factor for standing on contaminated ground, m2~rem/year per microcurie/second.

The equation for calculating the ground plane dose factor is given in Section 1.6.14.~Inhalation dose factor, mrem/year per microcurie/m3.

The equation for calculating the inhalation dose factor is given in Section 1.6.13.1, 4 fi~tt4~

RETS Manual Revisxon 8 Page 60~adjusted release rake for nuclide i for location under consideration, pCi/sec.The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector.Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.9~gi0 E fj exp(-Xi x/uj)~here Qi0~initial average release rate for nuclide i over the period, pCi/sec./fj~joint relative frequency of occurrence.ef'-winds.in windspeed class j blowing toward this exposure point, expressed as a fraction.~radiological decay constant for nuclide i, sec l.x~downwind distance, meters.uj~midpoint value of wind speed class interval j, m/s.~ingestion dose factor for pathway P for tritium, m2-mrem/year per microcurie/second.

Tngestion pathways available for consideration are the.same as those listed above for Rpi.Equations for calculating ingestion dose factors for tritium are given in sections 1.7.7 through 1.7.12.~.adjusted release rate for tritium for location under consideration, pCi/sec Calculated in the same manner as Q above.

RETS Manual Revision 8 Page 61 1.6 GASEOUS RELEASES>>Dose Factors 1~6.1 PASTURE GRASS-COW/GOAT-MILK INGESTION DOSE FAOTORS (m2-mrem/year per microcuries/second) 6 r(lmxp(-%Etc

))Biv(l exp(-'Xitb)

)ROPi~10 DFLiaoUapFmiPfexP(-Xitfm)fp(Yp E+)P where: 106~conversion factor, picocurie/microcurie.

DFLiao Uap~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7).~milk ingestion rate for age group a~-iiters/year.

"-'transfer factor for nuclide i from animal's feed to milk, days/liter (Table 1.8).~animal's consumption rate,'g/day.

~decay constant for nuclide i, seconds 1 (Table 1.8).tfm fp~transport time from milking to receptor, seconds.N~fraction'f time animal spends'n pasture, dimensionless.

~fraction of activity retained on pasture grass, dimensionless.

~the effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi+'Xw.~weathering decay constant for leaf and plant surfaces, seconds 1.tep Yp>iv~time pasture is exposed to deposition, seconds.~agricultural productivity by unit area of pasture grass, kg/m2.~transfer factor for nuclide i from soil to vegetation, picocuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).tb~time period over which accumulation on the ground is eva'luated, seconds.NOTE:~effective surface density of soil>kg/m2.Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p

RETS Manual Revision 8 Page 62 1 6'STORED FE~QM/GOATWILK INGESTION DOSE FACTORS-ROSi~~(m2-mrem/year per microcuries/second) 6 exP(Xitcsf))ROSi~10 DFLiao Uap Fmi Qf fs cxP(Xitfm)tcsf i (r(1~(-'X t~q())~B~(l-exp(-X~t),))

)where: lo6 DFLiao'conversion factor, picocurie/microcurie.

~ingesti'on dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1 7).~milk ingestion rate for age group a, liters/year..

~transfer factor for nuclide i from aaimal's feed to milk, days/liter (Table 1.8).fs~animal's consumption rate, kg/day.~fraction of time animal spends on stored feed, dimensionless.

~decay constant for nuclide i, seconds 1 (Table 1.8).~transport time from milking to receptor, seconds.tcsf~time between harvest of stored feed and consumption by animal, seconds.~fraction of activity retained on pasture grass, dimensionless.

~the effective decay constant, due to radioactive decay and weathering, seconds 1, equal to'Ai+Xw.~weitheriag decay constant for leaf and plant surfaces, seconds 1.tesf Ysf~time stored feed is exposed to deposition, seconds.~agricultural productivity by unit area of stored feed, kg/m2.>iv~transfer factor for nuclide i from soil to vegetation, picocuries/kg (wet weight of vegetation) per picocuries/kg (dry sail.).tb~time period over which accumulation on the bround is evaluated, seconds'OTE; 0243p~effective surface density of soil, kg/m2.Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.

1+6.3 PASTURE GRASS-BEEF INGESTION DOSE FACTORS-RMPi (m2-mrem/year per microcuries/second)

RETS Manual Revision 8 Page 63 (lexP(-Xitcb))

lit<<<<Q~(-'k i tcb (rOm>(-'I t p))~B(1-ex (-X ty))P Yp E+P where: 106~conversion factor, picocurie/microcurie.

DFLiao~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7).U~~meat ingestion rate for age group a-Qg/year;

..Ffi tcb~transfer factor for nuclide i from cow's feed to meat, days/kg (Table 1.8).~cow's consumption rate, k'g/day.~decay constant for nuclide i, seconds 1 (Table 1.8).~time for receptor to consume a whole beef, seconds.ts fp XE'~transport.time.from sliughter to consumer,'seconds.~fraction of time cow spends on pasture, dimensionless.

~fraction of activity retained on pasture grass, dimensionless.

~the effective decay constant, due to radioactive decay and~eathering, seconds , equal to Xi+Xw.~weathering decay constant for leaf and plant surfaces, seconds 1.tep Yp Biv~time pasture is exposed to deposition, seconds.~agricultural productivity by unit area of pasture grass, kg/m2.~transfer factor for nuclide i from soil to vegetation, picocuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).tb~time over which accumulation on the ground is evaluated, seconds.~effective surface density of soil, kg/m2.NOTE-'actors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p RETS Manual Revt.sion&Page 64 1~6 4 STORED FEED-BEEF INGESTION DOSE FACTORS-RMSi (modem/year per microcuries/second) where: (1-exP(-'Xitcb))

(-1',)i tcb (1-e (-X t g))~r(l exp(-X~tg))

~B(1-ex (-X t~))i tcsf Ysf AE P 106~conversion factor, picocurie/microcurie.

DFl.iao~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/plcocurie (Table 1.7).Ffi~meat ingestion rate for age group a, kg/year./~~transfer factor for nuclide i from cow"s feed to meat, days/kg (Table 1.8).~cow's consumption rate>kg/day.~decay'constant for nudiide i, seconds 1 (Table 1.8).tcb~time for receptor to consume a~hole beef, seconds.ts fs I tcsf~transport time from slaughter to consumer, seconds.~fraction of time cow spends on stored feed, dimensioaless.

~time between harvest of stored feed and consumption by cow, seconds.'fraction of activity retained on pasture grass, dimensionless..

tesf~time stored feed is exposed to deposition, seconds.Ysf~agricultural productivity by unit area of stored feed, kg/m.~the effecti.ve decay constant, due to radioactive decay and weatheriag, seconds 1, equal to 3(i+Xw.~weathering decay constant for leaf and plant surfaces, seconds l.~transfer factor for nuclide i from soil to vegetation, picocuries/kg (wct weight of vegetation) per picocuries/kg (dry soil).tb~time over which accumulation on the ground is evaluated, seconds.~effective surface density of soil, kg/m2.NOTE0 Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p

(,x RETS Manual Revi.sion 8 Page 65 1.6,5 FRESH LEAFY UEGETABLE INGESTION DOSE FACTORS-RUFi (m2-mrem/year per microcuries/second) 6 r(l~(-%Etc)

)Biv(lm(-Xitb)

)(-i',)(~')Yf E P where: 106~conversion factor, picocurie/microcurie.

DFLiao~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7)~~decay constant for nuclide i, seconds 1 (Table 1.8).J'average time between harvest of vegefables arid thiir consumption" and/or storage, seconds.~consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.~fraction of fresh leafy vegetables grown locally, dimensionless.

~fraction of deposited activity retained on vegetables, dimensionless.

~the effective decay constant, due to radioactive decay and weathering, seconds l.+Xw~decay constant for removal of activity on leaf and plant surfaces'y weathering, seconds l.~exposure time in garden for fresh leafy and/or stored vegetables, seconds'" w vegetation areal densi.ty for fresh leafy vegetables, kg/m~.>iv~transfer factor for nucli.de i.from soil to vegetables, picocuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).tb~time period over which accumulation on the ground is evaluated, seconds.~effective surface density of soil, kg/m2.NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p

/" Q 1.6.6 STORED VEGETABLE INGESTION DOSE FACTORS-, RVSi~~~m>-mrcm/year per microcuries/second) 6 (1-e(-Xi tsv))~I i tsv RETS manual Revision 8 Page 66 where:+Ysv E P (r(1~(-'X tc))B (lm(-X t)))106~conversion factor, picocurie/microcurie.

DFLiao thc~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7).~decay constant for nuclide i, seconds 1 (Table 1.8)./~average time between harvest of vegetables and'heir con'sumpti'on and/or storage>seconds.USa fg tsv~consumption rate of stored vegetables by the receptor in age group a, kg/year.r'fraction of stored vegetables grown locally, dimensionless.

~time between storage of vegetables and their consumption, seconds.~fraction of deposited activity retained on vegetables, dimensionless.

~the effective decay constant, due to radioactive decay and weathering, seconds 1~Xi+lw~decay constant for removal of activity on leaf and plant surfaces by weathering, seconds l.tc~exposure time in garden for fresh leafy and/or stored vegetables,'econds.

~vegetation areal density for stored vegetables, kg/m.Biv~transfer factor for nuclide i from soil to vegetables, picocuries/kg (wet weight of vegetation) per picocuries/kg (dry soil).tb~time period over which accumulation on the ground is evaluated, seconds.~effective surface density of soil, kg/m>.NOTE: Factors defined abovh which do not reference a table for their numerical values, are listed in Table 1.9.0243p

'

1.6 7 TRITIUM<<PASTURE GRASSWO'M/GOATWILK DOSE FACTOR-RCPT (mrem/year per microcuries/m3)

RETS Manual Revision 8 Page 67 RCPT~10 10 DF+ao FmT Qf Uap[0'5(0.5/H)]

fp exp(-'ATtfm) where: 103 106~conversion factor, grams/kg.~conversion factor, pi.cocuries/microcurie es.DFLTao~ingestion dose conversion factor for tritium for age group a, organ o, mrem/picocurie (Table 1.7).~transfer factor for tritium from animal's feed to milk, days/liter (Table 1.8).0.75~animal's consumption rate, kg/day.a milk ingestion rate for age group a, liters/year.

~the fraction of total feed that is water.0.5~H~the ratio of the specific activity of the feed grass water to the atmospheric water.~absolute humidity of the atmosphere, g/m3.fp XT tfm~fraction of time animal spends on pasture, dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8).~transport time from milking to receptor, seconds.NOTE" Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p

RETS Manual Revision 8'Page 68 1 6.8 TRITIUM-STORED FEE~OR/GOATWILK DOSE FACTOR-RCTS (mrem/year per microcuries/m3) bn P 0" f>>(~I)I 4~(-'I)~13 6 (1-exP(ATtcsf))T tcsf T fm't where!103 106~conversion factor, gramslkg.~conversion factor, picocuries/microcuries.

DMao~ingestion dose conversion factor for tritium for age.group a,'rgan o, mrem/picocurie (Table 1.7)~transfer factor for tritiura from animal's feed to milk, days/li,ter (Table 1.8).Rf Cap'.75~animal's consumption rate, k'g/day.~milk ingestion rate for age group a, liters/year.

~the fraction of total feed that is water.0.5~the ratio of the specific activity of the feed grass water to the.atmospheric water.~absolute humidity of the atmosphere, g/m.fs~fraction of time animal spends on stored feed, dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8).tcsf~time between harvest of stored feed and consumption by animal, seconds'fm

~transport time from milking to receptor, seconds.NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p

RETS Manual Revision 8 Page 69 1 6~9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR-RMTP (mrem/year per microcuries/m3}

RMTP~10 10 D~ao FfT Qf Uam[0~75(0~5/H)l fp exp(its)(L~(-'A t))T tcb where: 103 106 DMao~conversion factor, grams/kg.~conversion factor, picocuries/microcuries.

i ingestion dose conversion factor for-tritium for agp group a, organ o, mrem/picocurie (Table 1.7).~transfer factor for tritium from cow's feed to meat, days/kg (Table 1.8).a cow's consumption rate, kg/day.0.75~meat ingestion rate for age group a, kg/year.~the fraction of total feed that is wat'er.0.5~'he ratio of the specific activity of the feed grass water to the atmospheric water.~absolute humidity of the atmosphere, g/m3.fp~fraction of time cow spends on pasture,'dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8).tep tcb~transport time from slaughter to consumer, seconds.~time pasture is exposed to deposition, seconds.~time for receptor to consume a whole beef, seconds.NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p RETS Manual Revision 8 Page,70 1 6.10 TRITIUM-STORED FEED BEEF DOSE FACTOR RMTS (mrem/year per microcuries/m3)

RMTS~10 10 DFLTao FfT gf Uam[0.75(0.5/H)~

s exp(-'its)(l~xp(-X~t)

)(1-ex (-X t~))Xg t~p T tcb vhere: 103 106 DMao~conversion factor, grsms/kg.~conversion factor, picocuries/microcuries.

~ingestion dose conversion factor for Arithfor age group.a, organ o, mrem/picocurie (Table 1.7).~transfer factor for tritium from co+'s feed to meat, days/kg (Table 1 8).~~~co+'s consumption rate, kg/day.~meat ingestion rate for age group a, kg/year.0.75 0.5~the fraction of total feed that is eater.'I~the ratio of the specifi.c activity of the feed grass eater to the atmospheric eater.~absolute humidity of the atmosphere, g/m3.~fraction of time cow spends on stored feed, dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8).tep tcb~transport time from slaughter to consumer, seconds.~time pasture is exposed to deposition, seconds.~time for receptor to consume a~hole beef, seconds.NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p RETS Manual Revision 8 Page 71~W~%1.6~11 TRITIUM-FRESH LEAFY UEGETABLES DOSE FACTOR-RgFT (mrem/year per microcuries/m3)

RUFT 10 10 DFLTao[0.75(0.5/H)]

UFLa fL exP(-XT hc)where: 103 106~conversion factor,, grams/kg.~conversion factor, picocuries/micxocuries.

DFLTao Q.75~ingestion dose conversion factor fox'ritium fox age group a, organ o, mrem/picocurie (Table 1.7).~the fraction of total vegetation that is water.0.5~the'ratio of the specific activity of the vegetables watex to the atmospheric water.~~~absolute humidity of the atmosphere, g/m3.~consumption rate of fresh leafy vegetables by the receptor in age group a, kg!year.fL'AT.~fraction of fresh leafy vegetables grown locally, dimensionless.

~decay constant fox tx'itium, seconds 1 (Table 1.8)..thc~time between harvest of vegetables and their consumption and/or storage, seconds.NOTE Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0243p~~

RETS Manual Revision 8 Page 72 1 6'2 TRITIUM-STORED VEGETABLES DOSE FACTOR>>RVST (mrem/year per microcuries/m3) 3 6 (lem(-XTtsv))

RVST~10 10 DFLTao~'7>(0 5/H)l USafg exp(-'ATthc)

T tsv where: 103 106~conversion fact'or, grams/kg.~conversion factor, picocuries/microcuries.

DFLTao~ingestion dose conversion factor for tritium for, age group a, organ o, mrem/picocurie (Table 1.7)..:.~.'., 0.75 a the fraction of.total vegetation that is water., 0.5~the ratio of the specific activity of the vegetation water to the ,atmospheric water~absolute humidity of the atmosphere, g/m.USa*fg~consumption rate of stored vegetables by the receptor in age group a, kg/year.k~fraction of'.stored vegetables grown locally, dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8).tsv.~time between harvest of stored vegetables and their consumption and/or storage, seconds.~time between harvest of vegetables and'their storage, seconds.NOTE: Factors defined above which do not reference a table for their numerical values>are listed in Table 1.9.0243p RETS Manual Revision 8 Page 73 1 6~13 IMQQATION DOSE FACTORS-'Zi (mrem/year per microcuries/m3)

RIi~DFAiao BRa 106+here!DFhiao BRa 106~inhalation dose conversion factor for nuclide i, age group a and organ o, mrem/picocurie (Table 1.10).~breathing rate for age group a, m3/year (Table 1.9).~conversion factor, picocurie/microcurie.

/~~e y~~1~6~14 GROUND PLANE DOSE FACTORS-RGi (m~-mrem/year per microcuries/second)

RGi~DFGio 1/Xi 10 8760[1-exp(-Xitb)]

@here: DFGio'Ai 106 8760~dose conversion factor for standing on contaminated ground for nuclide i and organ o (total body and skin), mrem/hr per picocurie/m>(Table 1.11).'~decay constant of nuclide i, seconds 1 (Table 1.8).~conversion factor, picocurie/microcurie.

~conversion factor, hours/year.

tb~time period over whee,ch the ground accumulation is evaluated, seconds (Table 1.9).0243p

RETS Manual Revision 8 Page 74 1.7 Dis ersion Methodolo Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected onsite.Meteorological data for ground level releases'onsist of windspeed and direction measurements at 10m and temperature measurements of 10m and 45 m.Hourly average meteorological data for the ground level portion of a split.level release consist of wind speeds and directions measured at the 10m level and temperature measurements at 10m and 45m.The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.Raw meteorological data for the elevated releases consist of:windspeed and directions measured at 93m.Stability class 4.,is-assumed"-to perekst during the entire period for elevated releases, except for the quarterly dose calculations described in Section 1.3 when all stability classes vill be used to evaluate the elevated releases.Meteorological data are expressed as')oint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated).

The)oint-frequency distributions which represent the historical meteorological data for the period January 1977 to December 1979 are given in Table 1.3.The wind spe'ed classes that are used are as follows: Number I I<0.3 0'3 0.3&.6 0.7-1.5 1'-2.4 2.5-3 3 3.4-5.5 5.6-8.2 0.45 1 10 1.99 2.88 4.45 6.91 8.3-10.9 9.59>10.9 10 95 The stabi1ity classes that wi11 be used are the standard A through G classifications.

The stability classes 1-7 will correspond to Wlj B~2, aery Q~7~0243p

"?RETS Manual Revision 8 Page 75~%~%A sector-average dispersion equation consistent with Regulatory Guide~1.111 is used.The dispersion model considers plume depletion (using information from Figure 1.4), and building wake effects.Terrain effects on dispersion are not considered except for reducing the effective height of an elevated release by the terrain height.1.7.1 Air Concentration

-(pCi/m3)Air concentrations of nuclides at downwind locations are calculated using the following equation: 9 xi-E)ml where f)k 7{2/c)1 2 x/z exp(-Xi x/ug)exp(h2/202k)(1 14 k~1 Ezk u)(2'/n)~)oint relative frequency of occurrence of.w$gds in.windspeed class j, stability class k, blowing toward this.exposure point, expressed as a fraction.~average annual release rate of radionuclide i, pCi/s.~fraction of radionuclide remaining in plume (Figure 1.4).or~vertical dispersion coefficient for stability class k which includes a building wake ad)ustment,~(oak+cA/~)>/>,~d3 crzk, whichever is smaller (for ground level releases).

where azk is the vertical dispersion coefficient for stability class.k (m)(Figure 1.5),.c is a building shape factor (c&.5), 2'/n h is the minimum building cross-sectional area (2400 m>).~midpoint value of wind speed class interval), m/s.~downwind distance, m.~number of sectors, 16.~radioactive decay coefficient of radionuclide i, s~sector width at point of interest, m.~effective release height, m.The effective release.>eight is calculated as described in Section 1.7.4.0243p 1,7,2 Relative Concentration

-/(sec/m3)RETS Manual Revision 8 Page 76 Relative concentrations of nuclides at downwind locations are calculated using the following equation: 7 f k X/1 7 7 (2/~)'/'xP

(-he2/2ez2k) j~l k~1 Zzk uj (2'/n)(1.15)where fjk~joint relative frequency of occurrence of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as a fraction.E or~vertical dispersion coefficient for stability class k which includes a building wake adjustment,?"??(ozk+~/~)1/2~~43 crzk, whichever is smaller (for ground level releases).

where ezk is the vertical disPersion coefficient for stability class k (m)(Figure 1.5), c is a building shape factor (c&.5),?A is the minimum building cross-sectional.

area (2400 m>).~midpoint value of wind speed class interval j, m/s.~downwind distance, m.~number of sectors,.16.

2~/n~sector width at point of interest, m.he~effective release height, m.The effective release height is calculated as described in Section 1.7.4.1.7.3 Relative De osition-D/(m"2)Relative deposition of nuclides at downwind locations is calculated using the following equation: 9 7 fjk QR j~l k4.(2'/n)(1.16)

,I RETS Manual, Revision 8 Page 77 where DR~joint relative frequency of occurrence of winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.~relative deposition rate, m 1 (from Figure 1.6).The choice of figures is governed by the effective release height calculation described in Section 1.7.4.A linear interpolation is used for effluent release heights that fall in between the given curves.~downwind distance, m.Zmc/n~number of sectors, 16.~sector width at point of interest;m F 7.4 Effective Release Hei ht-he For effluents exhausted from release points that are higher than twice the height'f adjacent structures (elevated releases)the effective release height is.determined by the following equation, consistent with Regulatory Guide 1.111 where he~hs+hpr-ht m~I~downwash correction factor for low'relative exit velocity,~3(1.S-Wo/u)d, where Wo~the vertical plume exit velocity, m/s.u~mean wind speed at the height of the release, m/s.d~inside diameter of the release point, m.hpr~plume rise above the release point, m.hs~physical height of release point, m.~maximum terrain height between release point and receptor location, m.0243p

/RETS Manual Revision 8 Page 78 For effluents released from points less than the height of adjacent structures, a ground level release is assumed (he~0).~&~%For effluents released from points at the level of or above adjacent structures, but lower than elevated release points, releases are treated as follows: Case 1-elevated if W/u>5.Csee 2-ground level 4e 0)if go/uc 1.Case 3-split level if 1<wo/u<5.Under Case 3 a split level dispersion approach is implemented using a model.that requires for each release point two JFDs, one for elevated releases and one for ground level releases.The summation of the elevated and ground level JFDs account for the total period;of record..Releases are considered to be elevated 100(I-Et)-pei,'Cent of the time-and ground level 100 Et percent of the time where the entrainment coefficient, Et, is defined by Et 2'58 1'58(Wo/u) for 1<Wo/u 1 5 Et~0e3-0.06(Wo/u) for 1.5<Wo/u<'0243p

2.0 Li uid Effluents RETS Manual Revision 8 Page 79 2 1 Release Rate Limit Methodolo 2.1.1 RETS Re uirement Specification 3.8.A.l of the Radiological Effluent Technical Specifications (RETS)requires that the concentration of radioactive material released at any time from the site to unrestricted areas (Figure 2.1}shall be limited to the Maximum Permissible Concentration (MPC)specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2xl0~pCi/ml total activity.To ensure compliance, the following approach will be used for each release.2.1~2 Prerelease Anal sis Prior to release, a,.grab sample will be analysed to determine the concentration (Ci)of each gamma emitting radionuclide i in the radwaste tank.The following equation is used to calculate MPC fractions (Mi).where: Mi C MPCi (2.1}~MPC fraction of radionuclide i.i concentration of radionuclide i in the radwaste tank, pCi/ml.MPCi~MPC of rad'ionuclide i as specified in Section 2.1.1, pCi/ml.

r/The sum of the ratios (R)vill be calculated by the folloving relationships R~g Mi RETS Manual Revision 8 Page 80 (2.2)vhere: R~the sum of the ratios.~MPC fraction from equation 2.1..2.1.3 Release Flow Rate Calculations There is one liquid release point into the discharge canal by one of three possible modes: Radvaste open-3 pumps 9 200,000 gpm/pump helper<<3 pumps 9 180,000 gpm/pump closed-50,000 gpm Discharge conduit The sum of the ratios at the diffuser pipes must be<1 due to the releases from the above source.The following relationship vill assure this criterion is met: where f (R-1)<F (2-3)~the effluent flov rate (gallons/minute) before dilution.~the sum of the ratios as determined by Equation 2.2.~minimum dilution flov rate for prerelease analysis.The allowable release rate is calculated before each release and the release rate is continuously monitored during the release so that the MPC limit is not exceeded.'I 2 2 Instrument Set pints 2.2.1 Set oint Determination Alarm/trip setpoints for each liquid monitor vill be established and set such that Equation 2.3 is satisfied.

Thc: locations and identification numbers for each liquid effluent radiation detector are shovn in figures 2.2 and 2.3.This section of the ODCM describes the methodology that will be used to determine allowable values.The allovable values are then used to determine the physical settings on the monitors.The physical settings are calculated in the applicable Scaling and Setpoint Document.0243p

RETS Manual Revision 8 Page 81 2.2 1 Set oint Determination (Continued)

The auudmum activity concentration>

of liquid radwaste that can be discharged into a CCW conduit can be calculated as: (MPCi WFi)F where f h~maximum batch activity concentration,.

yC1/ml.MPCi~Maximum Permissible Concentration, from 10CFR20 Appendix B for nuclide i, pCi/ml~weighting factor for nuclide i~CCW dilution water flow rate, gpm~mmchnum discharge flow rate, gpm WFi f The allowable value for the radwaste discharge monitor (RM-90-130), shown in Figures 2.2 and.2.3, will be established using the methodology below.The alarm/trip allowable value will be set such that Equation 2.3 is satisfied.

The trip allowable value for the monitor, which vill automatically isolate the release, is set at less than or equal to the Technical Specification Limit.The alarm allowable value is set at 50K of the trip allowable value.The monitor isolation allowable value, in cps, for releases to the CCW discharge conduit is calculated using the following equation: Monitor Isolation Allowable Value~A+B CF where A~mqcimum batch activity concentration as calculated above, pCi/ml CF~calibration factor for the monitor, pCi/ml/cps B~monitor background, cps The calculation of these allowable values are documented further in Technical Instruction 45, including the numerical values for each of the parameters described above.Releases can be simultaneously discharged to multiple CCW discharge conduits.If releases are routed to more than one CCW discharge conduit;the allowable activity concentration and hence the corresponding allowable value may be increased based on an increase in.dilution flow.The allowable value for the Raw Cooling Water (RCW)monitors and the Residual Heat Removal Service Water (RHRSW)monitors (RM-90-132 and RM-90-133,134 respectively), shown in Figure 2.2, vill be established using the methodology below.The alarm/trip allowable values will be set such that Equation 2.3 is satisfied.

The allowable values for these monitors, which will alarm in the control room, are based on the 10CFR20 Appendix B concentration limits.These allowable values are also based on a selected isotopic mixture.1 The maximum activity concentration is based on a selected isotopic mixture so that an allowable value can be calculated.

The selected isotopic mixture will be documented in TI-45.If the actual batch MPC is less restrictive than the MPC for the selected isotopic mixture, then the actual activity concentration may be higher than.the calculated maximum activity concentration.

0243p RETS Manual Revision 8 Page 82 The monitor alarm allowable values, in cpm, for the RCW and RHRSW effluent monitors are calculated using the following equation: MPCi*WFi Monitor Allowable Values<g{)+B i Ei where MPCi Ei B Maximum Permissible Concentration, from 10CFR20 Appendix B for nuclide i, pCi/ml.weighting factor for nuclide i, defined as the fraction of the total concentration which is attributed to nuclide i.efficiency of the monitor for nuclide i, pCi/ml/cpm.

monitor background, cpm The calculation of these allowable values are documented further in Technical Znstruction 45, including the numerical valises'for ehch'of" the parameters described above.2.2.2 Poet-Release Anal sis A post-release analysis will be done using actual release data to ensure that the limits specified in Section 2.1.1 were not exceeded.A composite list of concentrations

'(Ci)by isotope, will be used with actual liquid radwaste (f)and dilution (F)flow rates (or volumes)during the release.The data will be substi,tuted into Equations 2.1, 2.2 and 2.3 to demonstrate compliance with the limits in Section 2.1.1.Thi's data and setpoints will be recorded in auditable records by plant personnel.

2.3 Dose 2.3.1 RETS Re uirements Specification 3.8.A.3 of the Radiological Effluent Technical Specifications (RETS)requires that dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas (Figure 2.1)from each reactor shall be limited: a.During any calendar quarter to c 1.5 mrem to the total body and to c 5 mrem to any organ, and b.During any calendar year to c 3 mrem to the total body and to c 10 mrem to any organ.To ensure compliance, cumulative.

dose calculations will be performed at least once per month according to the following methodology.

0243p RETS Manual Revision 8 Page 83 2.3.2 Monthl Anal sis Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose.If the projected dose calculated by this monthly method exceeds the monthly fraction of the annual limits in section 2.3.1~then the methodology in Section 2.3.3 will be implemented.

The 20 nuclides (listed below), based on operational source terms, contribute more than 95 percent of the total estimated dose to the total body and the most critical organ for both the water and fish ingestion pathways.The organs considered for both water ingestion and fish ingestion are the gastrointestinal tract (GIT), bone, thyroid, and liver.H-3 Na-24 Cr>>51 Mn-54 Fe-55 Fe-59 Co-58 Co-60 Zn-65 Sr-89 Sr-90 I-131..r Zr/Nb-95=~.-I-133 No/Tc-99m Cs-134 Ag-1Mm Cs-136 Sb-124 Cs-137 h conservative calculation of the monthly dose will be done according to the following procedure.

First, the monthly operating report containing the release data will be obtained and the activities reported (if any)for each of the above 20 radionuclides will be noted.This information will then be used in the following calculations.

0243p

C RETS Manual Revision 8 Page 84 2.3.2.1 Water In estion The dose to an individual from ingestion of water is described by the following equation.20 10'D)k~~5-$(DFL)i)k Iik~mrem i.~l.where: Dgk~dose for the jth organ and the kth age group from the 20 radionuclides, mrem.the organ of interest (bone, GIT, thyroid, liver or total body).the age group being considered, child or adult.10>>~conversion factor, pCi/Ci.0 95~conservative correctiod factor, considering only 20 radionuclides.

DFLigk~ingestion dose coamitment factor for the ith radionuclide for the gth organ for the kth age group, mrem/pCi (Table 1.7)Iik~monthly activity ingested of the ith radionuclide by the kth age group, Ci.The activity ingested due to drinki.ng water, Iik, is described by: 10 Ai Uwa (1/12)F d (7 34 x 10xo)where: Ci~conversion factor, ml/L.Ai~activity released of ith radionuclide during the month, Ci.~maximum.individua1, water consumption rate corresponding to the kth age group (Table 1.9), L/yr.1/12~conversion factor,'r/month.

0243p

('3 RETS Manual Revision 8 Page 85~1 I'~%~average river flow rate for the month (cubic feet per second)~fraction of river flow available for dilution (0.30)7.34x10 x o~conversion from cubic feet per second to milliliters per month Inserting this for Zik in equation 2.4, the dose equation for water ingestion then becomes: Dgk 2.3.2.2 20 3~98 x 109 Uwa DFLi]k Ai , mrem F i~L Fish In estion (2.6)~~The dose to an individual from the consumption of fish is described by Equation 2.4'n this case the activity ingested of the ith radionuclide due to eating fish (Iik)is described by 103 Ai Bi Ufa (1/12)Iik~, Ci Fd (7.34 x LOio)where'2.7)103~conversion factor, g/kg.Ai~activity released of the ith radionuclide during the month, Ci Bi Ufa 1/12~bioaccumulation factor of ith radionuclide, pCi/g per pCi/mls (Table 2.2.)~amount of fish eaten'yearly by the kth age group (Tabl.e 1.9), kg/yr.~conversion factor, yr/month.~average river flow rate for the month, cubic, feet per second 7.34x10 a o fraction of river flow available for dilution, 0.30.~conversion from cubic feet per second t~milliliters per month.

0 y RETS Manual Revision 8 Page 86 Inserting this for Iig in equation 2.4, the dose equation for fish ingestion then becomes: 3.98 x 10~DgL 2.3.2.3 Recreation 20 Ai Bi Ufa DFLigg i~1 (2.8)Dr g[42'FGi Cil lOx a 0'5 i~1 whereo I~recreation dose from plant releases, mrem.For the recreation dose calculation, the total dose is estimated based on a calculation of the shoreline dose for Co-58, Co-60, Cs-134, and Cs-137.The shoreline dose due to these four nuclides is expected to contribute over 95 percent of the total recreation dose.The total body and maximum organ dose to an individual via the shoreline recreation pathway are assumed to be equal.The recreation dose is described by the following equation: (2-9)gpja 0.95~conversion factor, pCi/Ci.~conservative correction factor for considering only 4 radionuclides.

DFGi~dose coaaai.tment factor for standing on contaminated ground for the i.th radionuclide, mrem/hr per pCi/m~(Table 1.11).~concentration of ith radionuclide in shoreline'ediment, Ci/m~, as described by the following equation (based on equation A-5 in Regulatory Guide 1.109).(i i 10~~6.94E-04~100~RHLi~Ci~W[l~xp(>>hitb))

(2.10)where: Lp~~conversion factor, ml/L 100 Ci~transfer constant defined in Regulatory Guide 1.109 equation A-4, L per m~-day.~radioLogical half-life of the ith radioisotope, minutes (Table 1.8).~concentration of ith radionuclide in the Tennessee River, Ci/ml.~Ai/(F~d~7.34 x Lpio)0243p RETS Manual Revision 8 Page 87 where: Ai d?34 x 10>a tb~activity released of i,th radionuclide during the month, Ci.~average river flow for the month, cubic feet per second.~fraction of river flow available for dilution, 0.30.~conversion from cubic feet per second to milliliters per month.~shoreline width factor (Table 1.9).~decay constant of the ith radionuclide, sec"~(Table 1.8).~buildup time in sediment, seconds (Table 1.9)42~assumed monthly exposure time for maximum individual,~500 h/year+12 months/year The recreation dose equation then becomes: 1 Dr F (29.8 Al+1690 A2+539 Ag+812 A4)(2.11)where: Al, A2, A3, A4,~the activities of Co-58, Co-60, Cs-134, and Cs-137, respectively, Ci.2.3.2.4'onthl Sumna To obtain the total monthly dose to the total body, sum the total body dose re from water ingestion, the total body dose from fish ingestion a d th creation dose.This value will be compared to the Technical Specification limit for total body dose.To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from.fish ingestion, and the recreation dose.This value will be compared to the Technical Specification limit for maximum organ dose.Calendar doses are first estimated by summing the doses calculated for each month in that quarter.Calendar year doses are first estimated by summing the doses calculated for each month in that year.However, if the annual doses determined in this manner exceed or approach the specification limits, doses calculated for previous quarters with the methodology of Section 2.3.2 will be use instead of those quarterly doses estimated by summing mont'y results.An annual check will be made to ensure that the monthly dose esmates account for at least 95 percent of the dose calculated by the method described in Section 2.3.3.Zf less than 95 percent of the dose has been estimated ei.h s f principal isotopes will be prepared or a new correction factor will be used.'he latter option will not be used if less'han 90 percent of the total dose is predicted.

0243p 2.3 3 uarterl Dose Calculations RETS Nanual Revision 8 Page 88 h complete dose analysis utilising the total estimated liquid releases for each calendar quarter vill be performed and reported as required in Section F.2 of the REM.Methodology for this analysis is that which is described in this section using the quarterly release values reported by the plant personnel.

The releases are assumed, for this calculation, to be continuous over the 90 day period.The average dilution factor, D, used for the quarterly calculations is: II where+1 D~RF+0.30 D s (2.13a)(for receptors upstream of Wheeler Dam)/(for receptors downsfream

"'(2.13b')of Mheeler Dam)RF~the average actual riverfiow for the location at which the dose is being determined, cfs.0.30~the fraction of the riverflow available'for dilution in the near fiel'd, dimensionless.

2.3.F 1 Water In estion Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of BFN (Table 2.1).Mater ingestion doses are calculated.

for the total body and each internal organ as described below: Dorg~104 9.88-09 AMit Qi D exp(-8.64E+04

'Ai td)where..(2.14)10'conversion factor, pCi/Ci.9.8K&9~conversion factor, cfs per ml/hour.~Dose factor for water ingestion for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.1.~guantity of nuclide i released during the quarter, Curies.~dilution factor, as described above, cfs~radiological decay constant of nuclide i, seconds>(Table 1.8).0243p RETS Manual.Revision 8 Page 89~decay time for water ingestion, equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)to account for the time of processing at the water supply (per Regulatory Guide 1.109), days.8.64E+04~conversion factor, seconds per day.Fish ingestion doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 2.1).Individual fish ingestion doses are calculated for the total body and each internal organ as described below: Dorg 10 9 o SE&9 0 e 25 AFit Qi D exp (-8 o 64E+04 Xi td)where 10~conversion factor, pCi/Ci.9.8M)9~conversion factor, cfs per ml/hour.0.25~fraction of the yearly fish consumption eaten in one quarter, dimensionless.

~Dose factor for fish ingest'ion for nuclide i;, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.2.Qi~Quantity of nuclide i released during the quarter, Curies.~dilution factor, as described above, cfs>.~radiological decay constant of nuclide i, seconds'(Table 1.8).td~decay time for fish ingestion, equal to the travel time from the plant to the center of the reach plus one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109), days.8 64E+04~conversion factor, seconds per day.2.3.3.3 Recreation Shoreline Recreation doses are calculated for each identified reach within a 50 mile radius downstream of BFN (Table 2.1).It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year on the shoreline at a location immediately downstream from the diffusers.

individual 0243p RETS Manual Revision 8 Page 90 recreation shoreline doses are calculated for the total body and skin as described beloN: Dorg~10~9.8E&9 rf ARit Qi D exp(-8.64E+04 Xi td)where (2.16)10'conversion factor, pCi/Ci.9.8E-09~conversion factor, cfs per ml/hour.~recreation factor, used to account for the fact that the same amount of time will not be spent at a recreation site during each quarter Recreation factors used are: ARit 1st quarter-0.1 2nd quarter>>0.3 3rd quarter-0.4 4th quarter-0.2.4~Dose factor for shoreline recreation for nuclide i, age group t, mrem/hour per pCi/ml, as calculated in Section 2.5.3.D~Quantity of nuclide i released during the quarter, Curies.~dilution factor, as described above, cfs~.h~radiological decay constant of nuclide i, seconds (Table 1.8).td 8.64E+04~decay time for recreation, equal to the travel time from the plant to the center of the reach, days.~conversion factor, seconds per day.2.3~3.4 Total Maximum Indi.vidual Dose The total auocimum individual total body dose is obtained by summing the following for each age group: the highest total body water ingestion dose.from among all the public water supplies;the highest total body fish ingestion dose from among all the reaches;and the total body maximum shoreline recreation dose.The total maximum individual organ dose is obtained by summing the following for each organ and each age group: that organ's highest water ingestion dose from among all the public water supplies;that organ's highest fish ingestion dose from among all the reaches;and he total body maximum shoreline recreation dose.The total maximum individual skin dose is that skin dose calculated for the maximum shoreline dose.0243p RETS Manual Revision 8 Page 91 2.3.3.5 Po ulation Doses For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and each pathway and Chen multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR, in man-rem for a given PWS is: 5 4 POPWTRC~'0 3$POPm$POPa*ATÃWa+TWDOSamt m 1 a~1 (2.17)where: POPWTRC POPa~water ingestion population dose to organ t, man-rem./a fraction of population in each age'gr'oup'a"(from

"'NUREt'R-1004'able 3'9).Adult~0.665 Child~0.168 Infant z.0.015 Teen~0.153 POPm~population at PWS m.The 3 PWSs and their populations are listed in Table 2.1 ATMWa~ratio'of average to maximum water ingestion rates for each age group a Maximum water ingestion rates are given in Table 1.9.Average water ingestion rates, ia L/year, (from R.Q.1.109 Table E-4)are: Adult~370 Child~260'nfaat~260 Teen~260 TWDOSamt~total individual water ingestion dose to organ t at PWS m, to the age group a, as described in Section 2.3.3.1, mrem.10 3~conversion factor for rcm/mrem.For population doses resultiag from fish ingestion the calculation assumes that all fish caught within a 50-mile radius downstream of BFN are consumed by local population.

An additional 7-day decay term is added due to distribution time of sport fish.The general equation for calculating population doses,.POPF, in man-rem from fish ingestion of all fish caught within a 50mile radius downstream is: II 453~6*HVST APR TFDOSart+POPa 10*10 1 1 FISHa+POPa 0243p where!RETS Manual Revision 8 Page 92 POPFt HVST APR>>total fish ingestion population dose to organ t, man-rem.>>fish harvest for the Tennessee River, 8.32 lbs/acre/year.

>>sise of reach, acres (Table 2.1).TFDOSar t>>total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 2.3.3.2, mrem.POPa FISHa>>fraction of population in each age group a, as given above.>>amount of fish ingested by each age group a, kg/year.The average fish ingestion rates (R.G.1.109 Table E-4)are: Adult>>6'Child'2.2 Teen>>5.2 453.6 10'0'conversion factor, g/lb.>>conversion factor, mrem/rem.>>conversion factor, g/kg.For recreation shoreline, the general equation used for'calculating.

the population doses, POPR, in man-rem is REQFRA POPRt>>E TSHDOSrt SHVISr HRSVISr 10'8760 (2.19)where.'OPRt

>>total recreation population dose for all reaches to organ t, man-rem.>>fraction of yearly recreation which occurs in that quarter, as given in Section 2.3.3.3.TSHDOSr t>>total shoreline dose rate for organ t,'n reach r, mrem/h.SHVISr>>shoreline visits per year at each reach r, (Table 2.1).~HRSVISr>>length of shoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.>>conversion factor, mrem/rem.8760>>conversion factor, bours/year.

RETS Manual Revision 8 Page 93 2 4 0 erabilit of Li uid Radwaste E ui ment The Radiological Effluent Manual (REM)requires that the liquid radwaste system (Figure 2.3)shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases*to unrestricted areas (see Figure 2.1)when averaged over 31 days would exceed 0.06 mrem to the total body or 0.21 mrem to any organ.Doses will be projected monthly.Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.2 5 Li uid Dose Factor E uations 2.5.1 RlTER INGESTION DOSE FACTORS-Agit (mrem/hr per pCi/ml)where: DFL'iat Uwa 10 10 8760 DFLiat~ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table F 7).10'10'8760~water consumption rate for age group a, L/year, (Table 1.9).~conversion factor,.pCi./pCi

~conversion factor, ml/L.~conversion factor, hours per year.2 5 2 FISH INGESTION DOSE FACTORS AFit (mrem/hr per ptCi/ml)DFLiat Ufa Bi 10 10 AFit 8760 where'FLiat

~ingestion dose conversion factor for nuclide i, age group a, organ t, mrem/pCi, (Table 1.7).Ufa Bi~fish consumption rate for age group a, kg/year, (Table 1.9).~bioaccumulation factor'or nuclide i, pCi/kg per pCi/L, (Table 2.2).*Per operating reactor unit.0243p

10',Q l conversion factor, pCi/pCi.RETS Manual Revision 8 Page 94 10'760~conversion factor, ml/L.~conversion factor, hours per year.2.5.3 SHORELINE RECREATION DOSE FACTOR-ARit (mrem/hr per pCi/ml).ARit where: DFOit Kc M M 10'04 U[1-exp(-'Xi tb)1 8760*3600 Xi Dpi~dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin);,.mrem/hr per pCi/m>, (Table 1.11).~transfer coefficient from~ater to shoreline sediment, L/kg-hr, (Table 1 9)~~mass density of sediment,'g/m>, (Table 1.9).10'shoreline width factor, dimensionless, (Table 1.9).~conversion factor, ml/L 10'conversion factor, pCi/pCi.3600~conversion factor, seconds/hour.

~'ecay constant-for nuclide i, seconds~, (Table 1.8).tb~time shoreline is exposed to the concentration in the water, seconds, (Table 1~9).~usage factor, 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year.

8760~conversion factor, hours/year.

3.0 Radiolo ical Environmental Monitorin 3 1 Monitorin Pro ram An environmental radiological.

monitoring.

program as described in Tables 3.1 and 3.2 and in Figures 3.1, 3.2, 3.3, and 3.4 shall be.conducted.

Results ot this program shall be reported in accordance with Section F-1 of the REM;The atmospheric environmental radiological monitoring program shall consist of 10 monitoring stations from which samples of air particulates

'and radioiodine shall be collected.

0243p j'.W RETS Manual Revision 8 Page 95 The terrestrial monitoring program shall consist of the collection of milk, soil, drinking vater', and food crops.In addition, direct gamma radiation levels vill he measured at 40 or more locations in the vicinity of the plant.The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hasardous conditions, sample unavailability, or malfunction of sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.3.2 Detection Ca abilities"r Analytical techniques shall be such that the de'titian capabilities-'

listed in Table 3.3 are achieved.3.3 Nonroutine Re orts Nonroutine reports shall be submitted pursuant to Section F-3 of the REM.4.0 Annual Maximum Individual Doses-Total To determine compliance with 40 CFR 190, the annual dose contributions to'he duodenum individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources vill be considered.

The annual dose to the maximum individual vill be conservatively estimated by: first, sumaing the total body air submersion dose, and the critical organ dose (except thyroid)from gaseous effluents; the total body dose, and critical'organ dose (except thyroid)from liquid effluents for each quartic calculated in accordance with sections 1.3 and 2.3.3.Then to.~this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the plant as determined by the environmental monitoring program outlined in section 3.0.These quarterly sums are then conservatively summed for the four calendar quarters to estimate the maximum individual dose for the year.This dose is compared to the limit of Technical Specification 4.8.C, i.e., 25 mrem per year to the total body or any organ (except thyroid), to determine compliance.

The total annual thyroid dose to the maximum individual vill be conservatively estimated in the following manner.For each calendar quarter, a total dose will be obtained by summing the totrJ.body gaseous submersion dose, the gaseous thyroi'd dose, the liquid total body dose, and the liquid thyroid dose.To this sum for each quarter is added any identifiable increase in direct radiation dose levels attributable to the 0243p RETS Manual Revision 8 Page 96 plant as determined by the environmental monitoring program outlined in section 3.0.These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year.This dose is compared to the limit of Technical Specification 4.8.C, i.e., 75 mrem per year to determine compliance.

~~r'g~ra s~0243p

Table 1 1 BFN-OFFSITE RECEPTOR LOCATION DATA RETS Manual Revt,sion 8 Page 97 GROUND LEVEL ELEVATED DISTANCE Elev above X/Q D/Q x/Q D/Q POINT f rom plant plant grade (s/m3)(1./m~)(s/m3)(1/m2)m m Site Boundary Site Boundary'ite Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Si.te Boundary Site Boundary Site Boundary'ite Boundary Site Boundary Site Boundary Air Dose Point Garden Garden Milk Cov Milk Cov 1525 N 1300 NNE 1250 NE 1450 ENE 1375 E 1575 ESE 5600 SE 2875 S,SE 2550 S 2425 SSM 2300'M 2500 MSM 2550 W 3325 WNW 2275 NW 1650 NNM 6100 NM 4437 E 1830 NNW 8045 N 10975 NNW 7 4 7 0 0 0-6-6 19-6-6-6 1 60E&6 7.88E&7 4 52E&7 7~30E-07 8 24E-07 4 56K&7 7+61E&8 4.86E&7 8 27E-07 1.08E&6-..'87E-07 6~38E&7 6~70E&7 3 69E&7 1 69E&6'84E&6 N/A N/A 1.57E06 1.47E-07 N/A 5'4E-09 1 97E-09 1.56E-O9 2o 92E&9 4.04E-O9 3 28E-09 3'3E-10 1 77E&9 2 24E-09'2 92E-09.--1.75E-09 1.14E-09 1.25E-09 9.07E-10 4+92E-09 5~29E&9 N/A N/A 4i46E-09 3.16E-10 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A.-N/A N/A N/A N/A N/A N/A 2.08E&8 9'0E-09 N/A N/A 1~69E&8 N/A NIA NIA N/A N/A N/A N/A NIA N/A,~N/A'N/A N/A N/A N/A N/A N/A 4.75E-10 N/A 1.13E-09 N/A N/A'OTE: For quarterly dose calculations, doses vill also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

'0243p RETS Manual Revision 8 Page 98 Table 1.2 EXPECTED ANNUAL ROUTINE ATMOSPHERIC RELEASES FROM ONE UNIT AT BFN i/r/Unit Buildin Vents Ci/r/Unit.Reactor Radvaste Turbine Complex Building Building Stack Gland Seal and~Off ss 1~66E+4 6 3E+2 7,47E+2 1.35E+4 MVP O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OK+0 O.OE+0 3.0E+2 Vent 1 c 1<1 3.4E+1 6.0E+1 2.94E+2 6 67E+2 3.28E+2 1.13E+2 2E+0 5'E-3 5.0E-2 2.5E-2 1.25E-1 5.0E-2 2.9E-2 2.9E-l 1.45E-1 7.25E-1 2.90E-1 9EW 5E-3 4E-4 SE-4 6E-3 2EW 3E-l 4E=3 hE-4 1E-4 lE-4 3E-4 3E-4 5E-5 4E-4 5EW 2EW OE+0 OR+0 9.5E+0 Vent~2E+0~Isoto e Vent Kr-&5m 6E+0 Kr-&5 Kr-87 6E+0 Kr&8..9E+0 Kr-89~1E+0 Xe-131m Xe-133m OE+0 Xe-133 1 03E+2 Xe-135m 1 llE+2 Xe-135 1 73K+2 Xe-137 7e&E+1 Xe-138 1.2E+1 I-131 I 5'4E-2 I-132 I 5~94E-1 I-133 I 2.97E>>1 I-134 I 1.49E+0 I-135 I 5.94E<<1 I-131 0 3 16E-2 I-132 0 3'6K-1 I>>133 0 1~5&E-1 I-134 0 7.90E<<1 I-135 0 3.16E-1 Cr-51 3E-3 Mn-54 3E 3 Co-58 2E-3 Fe-59 lE-4 Co-60 3E-2 Zn-65 3E-3 Sr-89 1E-2 Sr-90 2E-3 Nb-95 3E-4 Zr-95 lE-4 Ru-103'E-5 hg-110m 7E-6 Sb-124 3E-5 Cs-134 5E-3 Cs-136 2E-3 Cs-137 7E-3 Ba<<140 4E-3 Ce-141 4E-4 C@-144 5E-6 hr-41 2.5E+1 C-14 OK+0 Hw3 OK+0*Not available.

9.5E+1 1 02E+2 4.10E+3 3.09E+2 8 51E+2 5.03E+2 OE+0 5 81E+2 4.64E+2 9.47E+4 9.17E+2.O.OE+0-.-LOE+2 O.OE+0..'E5.99E+2

'.72E+2 3.86E+2 1 ISE+3 1 56E-2 1 79E-1 1 23E-1 2 67E-2 1.23E-l 6.5E-3 7.44E-2 5'3E-2 1.11E-2 5'3E-2 1E-3 2E-3 9E-5 4E-4 3E-3~4E-4*9EM 8E-6 2E-4 6E-5 5EW lE-4 2E-3 2E-2 2E-3 OK+0 OE+0 OE+0 5.04E+3 3.15E+3 4.1E-3 4 69E<<2 3 23E-2 7.0E-3 3'3E-2 3.32E-2 3.80E-1 2.62E-1 5'8K-2 2.61E-l 1EW 4E-5 2E-5 2E-4 1E-5 9E-5&E-5 8E-5 1E-4&E-5 2E-5 9E<<8 7E-4 8E-3 2E-S 4E-6 OK+0 9.5E+0 OK+0 0 OE+0 8.5E-3 9.73E-2 6.71E-Z 1.45E-2 6.71E-2 2.74E-1 3.14E+0 2.16E+0'4.69E-1 2.16E+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O B OE+0 O.OE+0 O.OE+0 O.OE+0 0<<0K+0 O.OK+0 O.OE+0 O.OE+0 O.OE+0 O.OK+0 O.OE+0 I denotes nonorganic iodine (elemental, particulate, HIO), 0 denotes organic iodine.0243p

I-q TABLE 1.3 (Sheet 1 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND.SPEED BY HIND DIRECTION FOR STABILITY CLASS A (DELTA-T<-1.9'C 100 H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 RETS Hanual Revision 8 Page 99 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH , SH HSH H HNH NH NNH HIND S 3.5-5.4 5.5-7.4 PEED (HPH)7.5-12.4 0.12 0.19 0.06 0.0 0.01 0.02 0.02 0.02 0.04 0.01 0.0 0.04 0.05'.09 0.17 0.06 12.5-18.4 18.5-24.4 1.5-3.4 0.6-1.4 0.04 0.05 0.04 0.01 0.0 0.17 0.40 0.10 0.11 0.05 0.04 0.07 0.05 0.03 0.02 O.ol 0.05 0.10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.01 0.06 0.11 0.09 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.ii 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.11 1.11 0.52 0.38 0.04 0.O5 0.04 0.01 0.02 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.o 0.0 0.0 0.0 0.02 0.02 0.0 0.0 0.0'0.0 0.0 0.01 0.03 0.04 0.01 0.0 O.O 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.09 2.29 1.19 0.90 0.42 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 25935 TOTAL HOURS OF STABILITY CLASS A 1262 TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS A 1259 TOTAL HOURS CALH 0 ALL COLUHNS AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 0244p HETEOROLOGICAL FACILITY: LOCATEO ABOUT 1.3 KH SH OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASUREO BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASURED AT THE 10.42 HETER LEVEL HEAN HIND SPEED 6.&HPH.>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0'.0 0.0 0.0 O.o 0.0 0.0 0.0 0.0 O.O TOTAL 0.21 0.34 0.10 0.01 0.01 0.31 1.56 O'.68 0.54 0.10 0.09 0.15 0.12 0.20 0.30 0.19 4.91 TABLE 1.3 (Sheet 2 of 22)JOINT PERCENTAGE FRE ENCIES Of HIND SPEED BY HIND DIRECTION FQR RETS Manual Revlslon 8 Page 100 HIND DIRECTION NN NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH SUBTOTAL 0.6-1.4 0.04 0.05 0.01 O.'O 0.0 0.0 0.0 Q.Q.0.0 0.0 0.0 0.01 0.03 0.08 0.13 0.12 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 i 004 0.01 0.0 0.06 O.O 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 00 034 211 100 1.63 0.47'TABILITY CLASS B (-1.9<DELTA-T<-1.7'C/100 M)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 HIND SPEED (MPH)1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-15.4 15.5-24.4 0.0 0.05 0.09 0.30 0.0 0.05 0.07 0.27 O.O O.'O4 O.O2 O.O9 O.Ol O.Ol O.Ol 0.01 0.0 0.02 0.01 0.0 0.02 0.10 0.04 0.0 0.13 0.64 0.09 Q.Q2 0.09 0.31 0.02 Q,ol 0.05 0.42 0.07 0.02 0.02 0.07 0.01 0.0 0.0 0.17 0.02 0.0 O.D 0.11 0.13 0.05 0.02 0.04 0.17 0.17'0.0 0.07 0.11 0.23 0.0 0.01 0.07 0.27 0.0.0.0 0.07~0.19>24.5 0.0 0.0 0.0 0.0 0.0.O'.O O.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.49 0.44 0.16 0.04 0.03 0.16 0.88 0.43 0.56 0.10 Q.19 Q.30 0.43 0.53 0.49 0.38 5.61 TOTAL HOURS OF\'ALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS 8 TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS 8 TOTAL HOURS CALM 25935 1445 1440 0 ALL COLUMNS AND CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS l METEOROLOGICAL FACILITY;METEOROLOGICAL FACILITY LOCATED 1.3 KM ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 METERS HIND SPEED AND DIRECTION MEASURED AT THE 10.42 HETER LEVEL MEAN HIND SPEED.~7.2 MPH 0244p Og TABLE 1.3 (Sheet 3 of 22)JOINT PERCENTAGE FRE EN IES OF HIND SPEED BY HIND DIRECTION FOR RETS Hanual Revision 8 Page 101 1 C C)I er'I HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH SUBTOTAL 0.6-1.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.'e Q.O 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 3.5-3.4 Q.01 0.03 0.0 0.0 0.0 0.01 0.17 0.12 0.11 0.03 0.03 0.0 0.0 0.01 0.0 Q.Q HIND SP 3.5-5.4 5.5-7.4 EEO (HPH)7.5-12.4 0.23 0.17 0.05 0.0 0.0 0.0 0.01 0.01 Q.02-0.0 0.01 0.07 0.10 0.17 0.22 0.18 0.11 0.09 0.08 0.02 O.Q2 0.02 Q.09 0.04 0.04 0.01 0.03 0.07 0.12 0.13 0.09 0.08.0.08 0.07 0.03 0.02 0.03 0.05 0.29 0.37 0.25 0.06 0.12 Q.ll 0.05 0.12 0.05 0.02 0.5Q 1.52 1.04 1.22 12-5-18.4 18.5-24.4 0.02 0.20 0.0 0.0 0.0 0.0 0.0 P.O 0.0 0.0 0.0 0.0 0.02 0.07 0.10 0.30 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.04 0.01 0.0 0.06 0.33 STABILITY CLASS C.(-1.7 c DELTA-Tc-1.5'C 100 H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79>24.5 0.0 0.0 0.0'.0 0.0 Q.Q 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.43 0.36 0.16 0.04 0.05 0.08 0.56 0.34 0.42 0.10 0.19 0.25 0.30 0.54 0.47 O.'38), 4.67 TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOllRS ALL COLUMNS OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS C OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS C CALH AND CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 25935 1202 1197 0'ETEOROLOGICAL FACILITY:HETEOROLOGICAL FACIlITY LOCATED 3.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED X(LAPSE RATE HEASURED BETHEEN 30.Q3 ANO 45.30 HETERS HIND SPEED AND DIRECTION MEASURED AT THE 10.42 HETER lEVEL HEAN HIND SPEED.7.0 HPH 0244p

(-~e.TABLE 1.3 (Sheet 4 of 22)JOINT PERCENTAGE FRE ENCIES OF HINb SPEED BY HIND DIRECTION FOR STABILITY CLASS 0 (-1.5<DELTA-Tc-0.5'C/300 H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-.OEC 31, 79 RETS Hanual Revis1on 8 Page 102 HIND DIRECTION NNE NE ENE E ESE SE SSE S SSH SH HSH H NH NNH SUBTOTAL TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS HIND SPEED (HPH)5.5-7.4 7.5-12.4 0.53 3.00 0.58 1.18 0.43'.52 0.15.0.05 0.17 0.05 0.30 0.08 0.83 0.26 0.26 0.11 0.34 0.17 0.08 0.04 0.09 0.02 0.29 0.33 0.62 0.63 0.42 1.10 0.38'1.01 0.55'.54 12.5-18.4 18.5-24.4 1.5-3.4 3.5-5.4 0.43 0.'56 0.3$0;23 0.31 0.51 1.31 0.99 1.17 0.29 0.29 0.70 0.55 0.39 0.28 0.40 0.6-1.4 0.37 0.38 0.01 0.01 0.0 0.0 0.0 0.02 0.0 0.0 0.01 0.11 0.22 0.82 0.87 0.74 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.03 0.22 0.14 0.05 I~'.46 0.19 0.20 0.12 0.26 0.20 0.24 1.36 0.99 0.92 0.45 0.24 0.32 0.1&0.13 0.04 0.13 0.0 0.01 0.01 0.'0 0.0 0.0 0;02 0.03 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 3.36 25935 8438 8341 1 0.05 5.77 8.77 6.02 8.09 OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS 0 OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS D CALH>~24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.02 0.0 0.03 TOTAL 2.51 2.72 1.47 0.70 0.73 1.13 3.58 2.38 2.60 0.86 0.65 1.75 2.23 3.09 2.74 3.41 32.55 ALL COLUMNS AND CALH TOTAL 100 PERCENT Of JOINT VALID OBSERVATIONS HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASURED BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL HEAN HIND SPEED~7.1 HPH 0244p i

Og TABLE 1.3 (Sheet 5 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS E (-0.5<DELTA-T<1.5'C 100 H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 RETS Hanual Revision 8 Page 103 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH SUBTOTAL TOTAL HOURS TOTAL HOURS TOTAL HOU/S TOTAL HOURS ALL COLUMNS HIND SPEED (HPH)5.5-7.4 7;5-12.4 0.43 0.41 0.55 0.47 0.42 0.27 0.17 0.08 0'.16 0.07 0.53'.16 0.92 0.55 0.48 0.33 0.44 0.63 0.08 0.06 0.02 0.03 0.14 0;11 0.42-0.27 O.ll 0.22 0.14 0.25 0.54'.59 12.5-18.4 18.5-24.4 3.5-5.4 0.6-1.4 1.5-3.4 0.05 0.04 0.02 0.02 0.0 0.01 0.02 0.04 0.14 0.01 0.0 0.04 0.04 0.09 0.09 0.09 0.47 0.61 0.57 0.71 0.61 0.76 2.04 1.16 1.03 0.52 0.30 0.53 0.37 0.15 0.17 0.41 0.54 0.74 0.63 0.45 0.74 1.01 1.75 0.7&0.74 0.14 0.07 0.60 0.77.0.13 0.20 0.48 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.02 0.02 0.01 0.07 0.04 0.05 0.05 0.05 0.04 0.03 0.11 0.07 0.05 0.02 0.04 0.01 0.02 0.03 0.02 0.05'I0.41 0.68 OF VAl.ID STABILITY OBSERVATIONS Of STABILITY CLASS E OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS E CALH 9.77 5.55 4.50 0.70 25935 8264&098 3 AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS

>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.95 2.46 1.96 1.4&1.62 2.50 5.39 2.&6 3.04 0.&3 0.46 1.43 1.89 0.75 0.89 2.17 31.68 HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACIt.ITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASUREO BETHEEN 10.03 AND 45.30 HETERS HIND SPEED ANO DIRECTION MEASURED AT THE'l0.42 HETER LEVEL HEAN HIND SPEED 5.0 MPH 0244p 0, TABLE 1.3 (Sheet 6 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS F (1.5<DELTA-T<4.0'C 100 H)BRO(NS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Hanual Revision 8 Page 104 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH SUBTOTAL 0.6-1.4 0.05 0.05 0.07 0.03 0.01 0.0 0.09 0.05 0.03 0.03 0.0 0.0 0.02 0.01 0.01 0.05 0.50 1.5-3.4 0.36 O.51 0.34 0.53 0.59 0.52 0.97 0.54 0.29 0.13 0.09 0.09 0.09 0.08 Q.QB 0.27 5.48 HIND S 3.5-5.4 5.5-7.4 0.28 0.34 0.18 0.05 0.03 0.0 0.17 Q.17 0.20 0.0 0.0 0.0 0.0 0.0 0.01 0.16 Q.52 0.66 0.27 0.33 0.52 0.22 0.48 0.34 0.18 0.03 0.03 0.07 0.06 0.01 0.04 0.27 4.03 1.59 PEED (HPH)7.5-12.4 O.Q6 0.11 0.01 0.0 0.0 0.0 0.13 0.25 0.27 0.01 0.0 0.0 0.01 0.0 0.0~Q.05 0.90 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.02 6.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.04 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 Q.Q 0.0 0.0 0.0 0.0 0.0 0 0 0.0 0.01 12.5-18.4 18.5-24.4)24.5 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.27 1.67 0.87 0.94 1.15 0.74 1.&5 1.38 0.98 0.2Q 0.12 0.16 0.18 0.10 0.14 0.80 12.55 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS F TOTAL HOURS CALH ,ALL COLUHNS AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 25935 3268 3223 2 0 HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASURED BETWEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASURED AT THE 10.42 HETER LEVEL HEAN HIND SPEED 4.0 HPH 0244p TABLE 1.3 (Sheet 7 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY MIND DIRECTION FOR STABILITY CLASS G.(DELTA-T>

4.0'C/100 M)BRONNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Hanual Revision 8 Page 105 HINO DIRECTION NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH SUBTOTAL 0.6-1.4 0.07 O.v5 O.u4 0.04 0.02 0.01 0;08 0.03 0.05 0.05 0.0 0.02 0.01 0.01 0.04 0.05 1.5-3.4 0.76 0.83 0.34 0.48 0.52 0.18 0.43 Q.44 0.09 O'.05 0.01 0.02 0.01 0.02 0.04 0.23 3.5-5.4 0.32 0.51 0.12 0.18 0.34 0.01 Q.09 0.31 0.12 0.01 0.0 0.0 0.0 0.0 0.0 0.12 HIND S 5.5-7.4 0.02 0.18 0.02'.02 Q.O Q.O o.a4 0.16 0.10 0.0 0.0 0.0 0.0 0.0 0.0 0.03 PEED (MPH)7.5-12.4 0.0 0.02 0.0 O.Q 0.0.0.0 0.03 0.08 0.04 0.0 0.0 ,0.0 0.0 0.0 0.0 0.0 0.57 4.45 2.13 0.57 0.17 0.0 0.0 0.0 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.a Q.a I 0.0 12.5-'18.4 18.5-24.4>24.5 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.a Q.a 0.0 TOTAL 1.17 1.59 0.52 0.72 0.88 0.20 0.67 1.02 0.40 0.11 0.01 0.04 0.02 O.Q3 0.08 0.43 7.89 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 25935 TOTAL HOURS OF STABILITY CLASS G 2056 TOTAL H(ROARS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS G 2019 TOTAL HOURS CALM 4 ALL COLUMNS ANO CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS I METEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BRONNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL HEAN HIND SPEED~3.2 HPH 0244p

, TABLE 1.3 (Sheet 8 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION DISREGARDING STABILITY CLASS BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Hanual Revision 8 Page 106.HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSN SN NSN N HNN NN NNN 0.6-1.4 0.02 0.0 Q.O'0.02 0.0 0.01 0.02 0.01 Q.n2 0..>0.02 0.01 0.02 0.0]0.02 0.01 1.5-3.4 0.19 0.13 0.12 0.14 0.22 0.23 0.36 0.38 0.4Q 0.31 0.38 0.26 0.20 0.17 0.19 0.22 3.5-5.4 0.38 0.33 0.35 0.32 0.47 0.53 1.26 1.20 0.90 0.65 0.66 0.69 0.66 0.46 Q.49 0.28 HIND SPEED 5.5-7.4 7 0.64 0.60 0.64 0.36 0.45 0.66 1.36 1.22 1.05'.69 0.69 0.68 0.81 0.69 0.70 0.41 (HPH).5-12.4 2.Q7 2.46 2.16 1.15 0.99 1.79 3.25 2.97 2.53 1.73 1.55 1.15 1.76 2.03 1.80'1;66 2.47 2.69 1.85 0.95 0.43 1.63 3.20 5.59 2,40 1.77 1.62 1.05 1.04 1.54 2.01 2.13 0.61 0.50 0.5&0.34 0.08 0.42 1.54 1.16 1.03 0.73 0.50.0.36 Q.42-i 076 0.96 0.70 12;5-18.4 18.5-24.4>24.5 D.oi 0.04 0.02 0.04 0.01 Q.Q9 0.69 0.59 0.43 0.19 0.14 0.17 0.35 0.30 0.2&0.13 TOTAL 6.44 6.75 5.72 3.32 2.65 5.36 11.68 10.12 8.76 6.07 5.56 4.37 5.26 5.96 6.45 5.54 TOTAL HOURS OF VALID HIND OBSERVATIONS TOTAL HOURS OF OBSERVATIONS RECOVERABILITY PERCENTAGE TOTAL HOURS CALM ALL COLUMNS AND CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 25784 26280 98.1 2 SUBTOTAL 0.19 3.90 9.63 11.65 31.05 29.37: 10.69 ia I 3.53 1QQ.Ql METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT HIND SPEED AND DIRECTION HEASUREO AT THE 92.63 HETER LEVEL HEAN NINO SPEED~12.0 HPH 0244p

~V TABLE 1.3~(Sheet 9 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS A'DELTA-'T<

-1.9'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE HODE..DAN 1, 77-.OEC 31, 79 O~RETS Hanual Revision S Page 107 H!ND DIRECTION N NNE NE ENE E ESE SE SSE S SSH.SH:2.HSH H HNH NH NNH CALH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.6 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 6.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.6-1.4 1.5-3.4 HIND SPEED (HPH)3.5-5.4 5.5-7.4 7.5-12.4 0.0 0.0'0.02 0.0 0.0 0.03 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0;02 0.0 Q.Q5 0.04 0.01 0.03 0.02 0.01 0.02 0.02 0.01 0.0 0.01 0.0 0.0 0.0'.0 0.0 0.01 0.01 0.0 0.0 0.01 0.0 ,0.0 0.01 0.0 0.0'.02 0.0 0.0 0.01 0.01 0.02 0.0 0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.0 0.0 O.o 0.01 0.02 0.02 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 12.5-18.4 18.5-24.4>24.5 TOTAL 0.0.0.03 0.0 Q.05 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.10 0.0 0.06 0.0 0.05 0.0 0.01 0.0 0.0 0.0 0.02 0.0 0.01 O.O Q.O2 Q.Q Q.04 0.0 0.05 SUBTOTAL 0.0 0.0 0.0 0.10 0.12 0.15 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL MOURS OF STABILITY CLASS A TOTAL HOURS OF GROUND LEVEL STABILITY CLASS A HETEOROLOGICAL FACILITY: HETEOROLOGICAL FACILITY LOCATED 1.3 KH STABILITY BASED ON DELTA-T BETHEEN 10.03 ANO 45.30 HETERS HIND DIRECTION HEASUREO AT 10.42 HETER LEVEL HIND SPEED HEASURED AT 10.42 HETER LEVEL EFfLUENT VELOCITY 12.60 H/S 0244p O.QS.'.02 25482.0;'S32.4'33.1: 127.5.ESE OF BROHNS FERRY 0.0 0.47 NUCLEAR PLANT

.TABLE 1.3.(Sheet 10 of 22)~RETS Hanual Revision&Page 108 SPLIT DOINT PERCENTAGE FRE ENCIES OF WIND SPEED BY HIND DIRECTION FOR STABILITY CLASS B (-1.9 c Delta T c-1.7 C/100M)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE HODE JAN 1, 77-.OEC 31, 79 HIND DIRECTION NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALH 0.0-0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0~0.0 0.0 0.0 0.6-1.4 1.5-3.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0~0.0 0;0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ND SPEED (HPH)5.5-7.4 7.5-12.4 0.01.0.05 0.01 0.05 0.0 0.01 0.0 0.0 0.0'..0.0 0.01 0.0 0.02 0.01 O.O1 O.o 0.01'.01 O.O 0.0 0.0 Q.O 0.02 , 0.01 0.01'.02 0.01 0.03 0.01'.04 0.0 0.03 WI 3.5-5.4 0.0 0.0 0.0 0.0 0.0 0.0 O'.02 0.01 O.Q2 0.0 0.0 0.0 0.0 0.0 0.0 00 SUBTOTAL 0.0 0.0 0.0 0.05 0.12 0.26 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS B TOTAL NOURS OF GROUND LEVEL STABILITY CLASS B HETEOROLOGICAL FA"ILITY:HETEOROLOGICAL FACILITY LOCATEO 1.3 KH STABILITY BASED ON DELTA-T BETWEEN 10.03 AND 45.30 HETERS WINO DIRECTION HEASUREO AT 10.42 HETER LEVEL HIND SPEED HEASURED AT 10.42 HETER LEVEL EFFLUENT VELOCITY~12.60 H/S 0244p>24.5 TOTAL 0.0 0.08 0.0 0.07 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.05 0.0 0.02 0.0 0.04 Q.O O'.O O.O Q.O 0.0 0.03 O.O 0.06 0.0 0.09 0.0 0.08 0.0 0.07 0.0 0.61 EAR PLANT 12.5-18.4 18.5-24.4 0.01 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0.0.0 0.0 0.0 0.0 O.O O.O O.O O.O Q.O 0.0 0.0.O.Q 0.02>0.01 0.02;0.03-0.03', 0.0 0.04.'.0 0.13-0.05 25482.0', 2832.4'&5.1: 163.4: ESE Of BROHNS FERRY NUCL RETS Hanual Revels)on 8 Page 109 FQR TOTAL 0.04 0.03 0.02 0.0 Q.Q.0.0 0.02 0.03 0.03 0.0 0.0 O.Q2 0.04 0.08 0.07 0.06>24.5 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.44 LEAR PLANT TABLE 1.3 (Sheet 11 of.22}SPLIT DOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTIQN STABILITY CLASS C (-1.7<DELTA-T<-1.5 Cll00 N}.BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE HOOE JAN 1, 77-DEC 31, 79 HIND HIND SPEED (HPH}.DIRECTION CALH 0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 N 0.0 0.0 0.0 0.0'.01.0.03 Q.O 0.0 NNE Q.Q Q.O 0.0 0.0 0.01 0.02 0.0 0.0 NE 0.0 0.0 0.0 0.0 0.01 0.01 0.0 Q.Q ENE 0.0 0.0 0.0 Q.Q 0.0..0.0 0.0 0.0 E 0.0 0.0 0.0 0.0 0.0'.0.0.0 0.0 ESE 0.0 0.0 0.0 0.0'.0 0.0 0.0 0.0 SE 0.0 0.0 0.0 0.01 0.01.0.0 0.0 0.0 SSE 0.0 0.0 0.0 0.01 0.01 0.01 0.0 0.0 S O.O 0.0 Q.Q 0.01 0.01 0.01 0.0 0.0 SSH 0.0 0.0 0.0 0.0 0.0 0.0-0.0 0.0 SH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HSH 0.0 0.0 0.0 0.0 0.0'1 0.01 0.0 0.0 H.0.0 0.0 0.0 0.0 0.01 0.01 0.01 0.01 HNH 0.0 0.0 0.0 0.0 0.01 0.02 0.02 0.03 NH 0.0 0.0 0.0 0.0 0.01 0.03 0.02.0.01 NNH O'.0 0.0 0.0 0.0 0.01 0.02 0.03 , 0.0 SUBTOTAL 0.0 0.0 0.0 0.03 0.11 0;17 0.08 0.05 t TOTAL HOURS OF VALID OBSERVATIONS 25482.0'OTAL HOURS OF GROUND LEVEL RELEASE 2832.4 TOTAL HOURS OF STABILITY CLASS C 259.0 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS C 106.3:.HETEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KN ESE OF BROHNS FERRY NUC STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 HETERS HIND DIRECTION MEASURED AT 10.42 HETER LEVEL I EFFLUENT VELOCITY)2.60 HIS 0244p I O',.TN";-..,;:;-.".:.:..;:-;;,:;.;:<

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.'.:.:.'~;.,:, l!"::-"".": '.',':...',,.'.":"":.":."-';:-:,"':::;.:i" RETS Hanual Revision 8 Page 110 TABLE 1.3 (Sheet 12 of'2)SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS D (-1.5<DELTA-T<-0.5'C 100 H)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND lEVEL RELEASE NSE DAN 1, 77-DEC 3'1, 79 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALH Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 HIND SPEED~5.5-7.4 0.04 0.05 0.04 Q.Ql Q.Q2 0.04 0.13 0.06 0.06 0.01 0.01 0.03 0.06 0.03 0.03 0.05 0.6-1.4 1.5-3.4 3.5-5.4 0.01 0.01 O.Q1 Q.01 0.01 0.03 0.11 0.09 0.09 0.02 0.01 0.03 0.02 0.0 0.0 0.01 0.0 Q.Q O.Q O.Q 0.0 0.0 0.01 0.02 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0.Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0.0.0 0.0 0.0~0.0 0.0 0.0 0.0 (HPH)7.5-12.4 0.15 0.18 0.08 0.01 0.01 Q.01 0.06 0.05 0.06'.01 0.0 0.06 0.10 0.16 0.15 0.25 SUBTOTAL 0.0 0.0*0.6 0.46 0.67.1.34 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS.OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS D TOTAL HOURS OF GROUND LEVEL STABILITY CLASS D HETEOROLOGICAL FACII ITY:HETEOROLOGICAL FACILITY LOCATED 1.3 KH STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 HETERS HIND DIRECTION HEASURED AT 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0244p>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 Q.O O.Ql 0.02 0.0 TOTAL 0.31 0.30 0.13 0.03 0.04 0.08 0.31 0.24 0.23 0.05 0.03 Q.16 0.29 0.53 0.53 0.54 0.03 3.80 EAR PLANT 12.5-18.4 18.5-24.4 0.10 0.01 0.05 0.01 0.0.0.0 0.'0 0'.0 0'.0 0'.0 0.0 0.0.0'.0 0'.0 4.02 0.0 0.0 Q.O 0.0 O.Q 0.01 Q.O 0.04 0.0 0.09l'.02 0 lg'14 0.23;.0.10 0.19" 0.04 0.92.'.32 25482.0;2832.4'3904,1: 968.6: ESE OF BROHNS FERRY NUCL

TABLE 1.3 (Sheet 13 of 22)RETS Manual Revlslon&.Page ill SPLIT 30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY WINO DIRECTION FOR STABIL/TY CLASS E (-0.5<DELTA-T<

1.5'C 100 H)BROHNS FERRY NUCLEAR PLANT.PART I OF 2 GROUND l.EVEl.RELEASE HODE JAN 1, 77-OEC 31, 79 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H WNH NH NNH CALH 0.0 0.0 0.0 0.,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 O.o 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.02 0.02 0.02 0.08 0.05 0.06 0.02 0.01 0.01 0.01 Q.Q 0.0 0.0 0.6-1.4 1.5-3.4 HIND SPEED 5.5-5.4 5.5-7.4 0.04 0.06 0.06 0.07;0.06 0.06: 0.04 0.03'.07 0.02 r 0.08 0.07., 0.22 0.16'.12 0.12 0.10 0.09: 0.02 0.02~0.0 0.0 0.05'.02 0.06 0.05 0.01 0.01 0.01 O.Q2 0.03 0.07 0.07 0.08 0.05.0.01 0.01 0.03 0.18 0.19 0.27 0.02 0.01 0.03 O.O5 0.04 0.04 0.10 0.02 0.02 0.01 0.01 0.0 0.0.O.Q2~0.04 0.13 0.01 0.0 0.02 O.ol 0.02 0.03 Q.Q2 0.01 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0,01 0.0 0.0 0.0~0.0.4 0.01 0.01 Q.Ql (HPH)7.5-12.4 12.5-18.4 18.5-24.4)>24.5 0.0 0.0 0.0 0.0 0.0 O.o 0.0 Q.o 0.0 0.0 0.0 0.0 0.0 Q.O 0.'0 0.0 TOTAL 0.20 0.24 0.19 0.11 0.12 0.20 0.66 Q.52 0.66 0.09 0.02 0.13 0.18 0.09 0.11 0.23 SUBTOTAL 0.0 0.0 0.32 0.97 0.87 1.18 TOTAL HOURS OF VALID OBSERVATIONS TOTAI HOURS Of GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS E TOTAL HOURS OF GROUND LEVEL STABILITY CLASS E HETEOROLOGICAL FACILITY:HETEOROLOGICAL fACILITY LOCATED 1.3 KH E STABILITY BASED ON DELTA-T BETWEEN I0.03 AND 45.30 HETERS HIND DIRECTION HEASUREO AT THE 10.42 HETER.LEVEL HIND SPEED MEASURED AT 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0244p 0.36 0.05 25482.0:.'832.4'920.6-'57.9'E OF BROHNS FERRY NUCL 0.0 3.75 EAR PLANT

TABLE 1.3 (Sheet 14 of 22)RETS Manual Revision 8 Page 112 SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS F (1.5<.DELTA-T<

4.0'C 100 M)PART 1 OF 2.GROUND LEVEL RELEASE MODE BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 HIND DIRECTION N NNE NE ENE.E ESE.SE SSE S SSH SH HNH NH NNH CATCH 0.6-1.4 1.5-3.4 0.0 0.0 0.01 0.0 Q.Q 0.01 0.0 0.0 0.01 0.0 0.0 0.02 0.0 0.0 0.01 0.0 0.0 Q.Q2 0.0 0.0 0.05 0.0 0.0 0.04 0.0 0.0 0.02 0.0 0.0-0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 HIND SPEED 3.5-5.4 5.5-7.4 0.06 Q.Q4 0.08 0.05 0.03 0.03 0.03 0.01 0.04 0.0 0.02 0.0 0.06 0.03 0.06 0.05 0.03 0.04 0.0 Q.Q 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 Q.Q 0.0 0.03 0.02 (MPH)7.5-12.4 Q.ol 0.02 0.0 0.0 0.0 0.0 0.06 0.18 0.11 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0,0 0.0 0.0 0.0 Q.Q Q.Q~0.01 0.02 Q.Q1 0.0 0.0 0.0 0.0 0.0 0.'0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 Q.Q 0.0 0.0 0.0 0.0..: 00 0.0 0.0 0.0 0.12 0.0 0.16 0.0 0.07 O.O 0.06 0.0 0.05 0.0 0.04 0.0~0.21 0.0 0.36 0.0 0.21 0.0 0.01 0.0 0.0 0.0 0.0 Q.O 0.01 0.0 0.0 0.0 0.0 0.0 0.07 12.5-18.4 18.5-24.4)a24.5 TOTAL SUBTOTAL 0.0 0.0 0.21 0.45 0.27 0.39 T()TAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF'STABILITY CLASS F TOTAL HOURS OF GROUND LEVEL STABILITY CLASS F Q.Q4 ,.0.01 25482.0'2832.4'385.0 357.0 l 0.0 1.37 METEOROLOGICAL FACILITY:METEOROLOGICAL FACIl ITY LOCATED 1.3 KM ESE STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 METERS HIND SPEED MEASURED AT THE 10.42 METER LEVEL EFFLUENT VELOCITY~12.60 MIS 0244p OF BROHNS FERRY NUCLEAR PLANT TABLE 1.3 (Sheet 15 of 22)RETS Hanual Revision 8 Page 113 SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS G (DELTA-T>4.0'C 100 H)PART 1 OF 2 GROUND LEVEL RELEASE HODE BROHNS FERRY-NUCLEAR PLANT JAN 1, 77-OEC 31,.79 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALH 0.6-1.4 1.5-3.4 0.0 0.0 0.02 0.0 0.0 0.02 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.03 0.0 0.0 0.04 0.0 0.0 0.01 0.0 0.0.0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 H 3.5-5.4 0.04 0.06 0.01 0.01 0.01 Q.Q O.ol 0.05 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0,03 0.0 O;0 0.0 0.0 0.01 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.08 0.0 0.0 0.0 0.0 0.0 0.0 0.02 Q.06 Q.Ql Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.'O 0.0.0.0 0.0 0.0 Q.o Q.Q Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0;.O'.0 0.0 0.0 0.0 0.0 IND SPEED (HPH)5.5-7.4 7.5-12.4 12.5-18.4 1&.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 TOTAL 0.06 0.11 0.02 0.02 0.02 0.01 0.07 O'.18 0.06 0.0 0.0 0.0 Q.o Q.Q 0.0 0.02 SUBTOTAL 0.0 0.0 0.17 0.22 0.09 TOTAL HOURS OF VALID OBSERVATIONS TOTAI HOURS OF GROUND I.EVEL RELEASE TOTAl.HOURS OF STABILITY CLASS G TOTAL HOURS OF GROUND LEVEL STABILITY CLASS G 0.09 0.0, 0.0~~25482.0: 2832.4,.'94.7 151.7 I 0.0 0.57 METEOROLOGICAL FACII ITY:HETEOROLOGICAL FACILITY LOCATEO 1.3 AH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0244p~~~I RETS Hanual Revtslon 8 Page 114 TABLE 1.3 (Sheet 16 of 22)SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS A (DELTA-T<-1.9'C 100 H)PART 2 OF 2 ELEVATED RELEASE HOOE BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CAL~i 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.6-1.4 1.5-3.4 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0.0 a.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HIND SPEED (HPH)3.5-5.4 5.5-7.4 7.5-12;4 O.a 0.0-0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0-0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q Q.O'.Q a.o o.o o.a 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0'.0 0.0 0.0 0.0 Q.o 0.0 Q.a 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.01 0.0 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATEO RELEASES TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS Of ELEVATEO STABILITY CLASS A METEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATED 1.3 KH STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 HETERS HIND DIRECTION MEASURED AT 45.67 HETER LEVEL HIND SPEED HEASURED AT 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0244p 12.5-18.4 18.5-24.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.a 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 a,'o o.o~0.0 0.0'0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 a.o.o'.o 0.'0,.o'.o 0.0;0.0 I 25482.0;22649.6.133.1 5.6;>24.5 D.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0.0 TOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.01 ESE OF BROHNS FERRY NUCLEAR PLANT TABLE 1.3 (Sheet 17 of 22)-~RETS Hanual-Revision 8 Page 115 SPLIT 30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS B (-1.9<DELTA-T<<<1.7'C 100 H)BROHNS FERRY NUCLEAR PLANT PART 2 OF 2 ELFVATED RELEASE HODE JAN 1, 77-DEC 31, 79 HIND DI RECTION N NNE NE'NE E ESE SE SSE S SSH SH NSH H HNH NH NNH CALH 0.6-1.4 0.0{).0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.5-3.4 3.5-5.0.0 0.0 Q.Q 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0.0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q HIND SPEED 4 5.5-7.4 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.02 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 O.Q.0.0'0.0 0.0 0.0 0.0 O.Q 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.'0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 (HPH)7.5-12.4 12.5-1&.4'18.5-24.4

>24.5 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 Q.O 0'.0 0.0 0.0 TOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0.0.01 0.01 0.02 0.0 0.0 0.0 0.0 SUBTOTAL 0.0'.0 0.'01 0.01 0.01 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAL HOURS OF STABILITY CLASS 8 TOTAL HOURS OF ELEVATED STABILITY CLASS B 0.03 0.0.'.0 25482.0-22649.6 185.1', 21.8 0.0 0.06 HETEOROLOGICAL.

FACILITY: HETEOROLOGICAL FACILITY LOCATED 1.3 KH STABILITY BASED GN DELTA-T BETHEEN 45.30 AND&9.60 HETERS HIND DIRECTION HEASURED AT 45..67 HETER LEVEL HIND SPEED HEASURED AT 45.67 HETER LEVEL EFFLUENT VELOCITY l2.60 H/S 0244p ESE OF BROHNS;FERRY NUCLEAR PLANT STABILITY CLASS C (-1.7 c DELTA-Tc-1.5 C 100 M)BROHNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE MODE JAN 1, 77-DEC 31, 79 HIND SPEED 5.5-7.4.0,0 0.0).0.0 0.0 0.0 0.0)0.01 0.0 0.0 0.02 0.05 0.03 0.01 0.0 0.0 0.0 (MPH)7.5-12.4 12.5-18.4 18.5-24.4 HIND DIRECTION 3.5-5.4 CALM 0.6-1.4 1.5-3.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.'0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.02 0.0 0.0 0.0 0.0 0.0.0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.01 0.02 0.05 0.03 0.02 0.0 0.0 N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.0 0.0 0.0 0.0 0.0 0.0-0.0 0.0 0.0 0.0 0.01 0.01 0.02 0.'02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.02 0.0 0.0 0.0 0.0 0.0 0.01 0.05 0.04 0.01 0.02 0.05 0.0 0.0 0.0 0.0 0.0 0.0 0.03 0.18 0.14 0.)4 0.07 SUBTOTAL 0.0 TABLE 1,3 (Sheet 18 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR RETS Manua)Revision 8 Page l)6-)24.5 0.0 0.0 0.0'0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.0 0.01 0.0 0.0 0.0 0.03 0.08 0.04 0.02 0.05 0.13 0.09 0.08 0.04 0.01 0.0 0.0 0.58 TOTAL HOURS OF VALID OBSERVATIONS 25482.0 TOTAL HOURS Of ELEVATED RELEASES 22649.6 TOTAL HOURS OF STABILITY CLASS C~259.0 TOTAL HOURS OF ELEVATED STABILITY CLASS C 152.7 I METEOROLOGICAL FACILITY: METEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 45.30 AND-89.60 METERS HIND SPEED AND DIRECTION MEASURED AT THE 45.67 METER LEVEL EFFLUENT VELOCITY~)2.60 M/S 0244p TAB (Sheet.22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS D (-1.5<DELTA-T<-0.5'C 100 M)BROHNS FERRY NUCLEAR PLANT JAN 1,-77-DEC 31, 79 rage III HIND DI RECTION NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALM 0.0 0.0 a.o O.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.01 0.0 0.01 0.01 0.01 0.01 0.01 0.0 0.01 0.01 0.02 0.0 0.0 0.0 0.0 0.12 Q.13 a.a9 0.11 0.10 0.22 0.67 0.48 0.34 0.20 0.24 0.16 0.07 0.09 0.07 Q.09 0.40 Q.62 0.46 0.72 0.36 0.48 0.24 0.23 0.20 0.28 0.52 0.68 1.66 0.89 0.90 0.63-0.99 O.67 0.52 0.37 0.79 0.43 0.51 0.57 0.36 0.80 0.33 0.48 0.36 0.55 Q.29 0.53 1.49 1.88 1.04 0.23 0.25 1.07 1.75 1.49 0.99 0.69 0.49 0.57 1.34 1.25 1.40 1.36 0.87 0.91 0.14 0.04 0.05 0.16 0.84 1.08 0.93 0.34 0.32 0.27 0.55 0.94 1.44 1.15 HIND SPEED (MPH)0.6-1.4 1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-18.4 18.5-24.4 0.12 0.05 0.02 0.01 0.01 0.0 Q.16 0.26 0.33 0.11 0.05 0.08 0,16 0.32 0.37 0.19>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.01 o'.m 0.02 0.0 0.0 0,0 Q.Ql 0.01 0.01 0.0 TOTA 3.62 4.16 2.13 0.87 0.&0 2.66 5.99 4.87 4.27 2.24 2.33 2.18 3.29 3.42 4.20 3.61 2.24 0.08 50.74 SUBTOTAL Q.o o.la 3.18 8.89: 8.93 17.29 I (TOTAL HOURS OF VALID OBSERVATIONS 254&2.0 TOTAL HOURS OF ELEVATED RELEASES 22649.6 TOTAL HOURS OF STABILITY CLASS D 13904.1 TOTAL HOURS OF ELEVATED STABILITY CLASS D 12935.5 l METEOROLOGICAL FACILITY: METEOROLOGICAL FACILITY LOCATED 1.3 KM ESE STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 METERS HIND SPEED AND DIRECTION MEASURED AT THE 45.67 METER LEVEL EFFLUENT'VELOCITY~12.60 M/S 0244p 10.03 OF BROHNS.FERRY NUCLEAR PLANT TABl.E 1.3 (Sheet 20 of 22)30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS E (-0.5<DELTA-T<1.5 C 100 H)~BROHNS FERRY NUCLEAR PLANT PART 2 of 2 ELEVATED RELEASE HODE JAN 1, 77-.DEC 31, 79.RETS Hanual Revlslon&Page 118 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALH 0.6-1.4 1.5-3.4 0.0 0.0 0.13 0.0 0.0 0.15 0.0 0.01 0.11 0.0 0.0 0.20 0.0 0.0 0..09 0.0 0.01 0.29 0.0 0.02 0.41 0.0 0.01.0.23 0.0 0.01 0.14 0.0 0.0'.11 0.0 0.01 0.17 0.0 0.01 0.12 0.0 0.0 0.09 0.0 0.0 0.06 0.0 0.0'.09 0.0 0.0 0.12 HIND SPEED 3.5-5.4.5.5-7.4 0.22 0.31 0.24 0.39 0.25 0.39 0.21 0.33 0.24 0.30 0.58 0.86 1.04 1.02 0.60 0.54 0.49 0.32 0.28 0.30 0.27 0.28'0.25 0.24 0.19 0.26 0.13 0.11 0.14 0.13 0.21 0.16 0.80 1.04 0.88 0.39 0,55 1.10 1.37 0.87 0.70 0.48 0.29 0.28 0.34 0.20 0.31 0.52 Q.15 Q.28 0.18 0.1Q 0.06 0.09.0.55 0.59 0.34 0.19 0.09 0.06 0.05 0.04 0.08 0.16 0.0 0.0 Q.O Q.O O.Q 0.01 0.0&0.14 0.05 0.01 0.0 0.0 0.0 0.01 0.0 O.Q (HPH)7.5-12.4 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 Q.Q Q.Ql 0.01 O.Q Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.61 2.10 1.82 1.23 1.24 2.94 4'.50 2.99 2.05 1.37 1.11 0.96 0.93 0.55 0.75 1.17 SUBTOTAL 0.0 0.08 2.51 5.34 5.94 10.12 3.01 0.30 0.02 27.32 TOTAl.HOURS OF VALID OBSERVATIONS 25482.0 TOTAL HOURS OF ELEVATED RELEASES 22649.6 TOTAL HOURS OF STABILITY CLASS E~7920.9 TOTAL HOURS OF El.EVATED STABILITY CLASS E 6962.9 HETEOROl.OGICAL FACILITY: HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 HETERS HIND SPEED AND DIRECTION HEASURED AT THE 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0244p

TABLE 1.3 (Sheet 21 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS F (1.5<DELTA-T<4.0'C 100 H)BROHNS FERRY.NUCLEAR PLANT PART 2 of 2 ELEVATED RELEASE NODE DAN 1, 77-DEC 31, 79 RETS Hanual Revision 8 Page 119 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH HIND SPEED CALH 0.6-1.4 1.5-3,4 3.5-5.4 5.5-7.4 0.0 0.0 0.03 0.08 0.06 0.0 0.0 0.04 0.06 0.11 0.0 0.0 0.04 0.10 0.15 0.0 0.0 0.04 0.11 0.11 0.0 0.0 0.03 0.07 0.11 0.0 0.0 0.13 0.26 0.24 0.0 0.0 0.13 0.38 0.30-0.0 0.0 0.09 0.11 0.12 0.0 0.0'.08 Q.ll 0.13 0.0 0.0 0.04 0.12 0.14 0.0 0.0 0.04 0.09 0.10 O.Q 0.0 0.03 0.07 0.06 Q.Q 0.01 0.04 0.04 0.05 0.0 Q.Q 0.02 0.04 0.01 0 0 0 0 0 Q3 0 04 0 03 , 0.0 0.0 O.Q2 0.02 0.04 0.34 0.42 0.40 0.29 0.32 0.24 0.19 0.14 0.21 0.24 0;06 0.05 0.04 0.01 0.02 0.10 0.05 0.21 0.12 0.07 0.02 0.0 0.0.0.03 0.03 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0!0.0 0.0 0.0 (MPH)7.5-12.4'12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.56 0.54 0.81 0.62 0.55 0.&7 1.00 0.49 0.56 0.55 0.29 0.21 0.18 0.08 0.12 0.18 SUBTOTAL 0.0 0.01 0.83 1.70 l;76 3.07 0.54'.0 0.0 7.91 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF ELEVATED STABILITY CLASS F 254&2.0 22649.6 2385.0 202&.Q HETEOROLOGICAL FACILITY: HETEOROLOGICAL FACILITY LOCATEO 1.3'H ESE STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 METERS HIND SPEED AND DIRECTION HEASURED AT THE 45.67 HETER LEVEL EFFLUENT VELOCITY~12.60 H/S 0244p OF BROHNS FERRY NUCLEAR PLANT 4

TABI,E 1.3 (Sheet 22 of 22)30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS G'DELTA-T>

4.0'C 100 M)BROHNS FERRY NUCLEAR PLANT PART 2 of 2 EI.EVATEO RELEASE MODE JAN 1,.77-DEC 31, 79 RETS Hanual RevlsIon 8 Page 120 (MPH)7.5-12.4 12.5-18 4 HIND SPEED 3.5-5.4 5.5-7.4 0.0 0.02 0.02-0.04.0.02 0.03 0.02 0.02'.02 0.01 0.15.0.07 0.20 0.13 0.06 0.06 Q.07 Q.06 0.02 0.02 0.01 0.03 0.0 O.Q 0.0 0.01 0.0'.0 0.0 0.0 0.01 0.0 HIND DIRECTION lB.5-24.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.0 0.0 P 0.0 0.6-1.4 1.5-3.4 CALM 0.0 0.0 0.0 Q.O 0.0 0.9 0.0 0.0 O.O 0.(.0.0 0.0 0.0 0.0 0.0 0.0>~24.5 TOTAL 0.09 0.22 0.21 0.13 0.07 0,.29 0.49 0.17 0.16 0.10 0.07 0.01 0.02 0.02 0.0 0.03 0.01 O.O4 0.02 0.02 0.0 0.0 0.0 0.0 0.0-0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.06 0.11 0.12 0.07 0.04 0.01 0.04 0.02 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.01 N NNE.NE.:-ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0;0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.01 0.02 0.0 0.0 0.05 0.12 0.03 0.02 0.0 0.01 0.01 0.01 0.02 0.0 0.01 SUBTOTAL 0.0 0.01 0.31 0.60 0.50'0.57 0.09 TOTAL HOURS OF VALID OBSERVATIONS 25482.0 TOTAI.HOURS OF ELEVATED RELEASES 22649.6 TOTAL HOURS OF STABILITY CLASS G TOTAL HOURS OF ELEVATED STABILITY CLASS'G 543.1 METEOROL'OGICAL FACILITY: METEOROLOGICAL FACILITY LOCATEO 1.3 KM ESE OF BROHNS FER STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 METERS HNS FERRY NUCI.EAR PLANT HEND SPEED ANO DIRECTION MEASURED AT THE 45.67 METER LEVEL EFFLUENT VELOCITY 12.60 M/S 0244p

.RETS Manual Revision 8 age 121 P Table 1 4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASESSubmersion dose mrem/yr per pCi/m3 DFBi DFSi Air dose mrad/yr per pCi/m3 DFyi Dpi Kr-83m Kr-85m Kr-90 Xe-131m Xe-133m Xe-133 7 56E-02 1~17E+03 1~61E+01 5.92E+03 1 47E+04 1 66E+04 1 56E+04 9.15E+01 2.5IE+02 2.94E+02 Xe-135 Xe-137 Xe-138 1 81E+03 1.42K+03 8.83E+03 8.84E+03 Xe-135m, 3.12E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7,29E+03 4.76E&2 9.94E+02 3.06E+02 7'1K+02 1.86E+03 1~22E+04 4.13E+03 2.69E+03 1.93E+Ol 1.23E+03 1.72E+Ol 6 17E+03 1.52E+04 2.88E+02 1.97E+03 1 95E+03 1.03E+04 2 93K+03 1.63E+04 1 56E+02 3 27E+02 3.53E+02 3.36E+03 1,.92E+03 1.51E+03 9 21E+03 9'0E+03 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03.1,.73E+04.,".1.06E+04

Reference:

Regulatory Guide 1.109, Table B-l.0244p I'L,~~w\

'ETS Manual Revision 8 Page 122 Table 1.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Sector Element Site boundary-1 mile 1-2 miles 2-3 miles 3-4 miles 4-5 miles 5-10 miles 10-20 miles 20-30 miles 30-40 miles 40-50 milei Midpoint of Sector Element 0.8 mile 1.5 miles 2.5 miles 3.5 miles 4.5 miles~/4 i 5"eiles 15 miles 25 miles 35 miles.45 miles 0244p

RETS Manual'Revision 8 Page 123 Table 1.6 BFN 50WILE POPULATION WITHIN EACH SECTOR ELENENT Distance to Midpoint of Sector Element 0.8 1.5 2.5 3.5 4.5 7.5 15 25 35 45 N 0 10 55 35 85 670 1515 2615 10660 3690 0 5 15 65 55 915 2990 2230 3125 0 5 25 45 8&4180 14180 6625 5385 34 20 12625 0 15 50 40 70 1310 4990 9615.13860 5425 0 0 30 10 40 945 1910 73405 75125 4610 SSE 0 0 0 0 0 0 0 0 9575 13850 0 0 90 1630 6250 11630 20 35 90 1250 3805 1800 15175 18945 4475 3730 5 0 0 165.1880.2535 7465 0 0 20 10390 30945'660 6230 SSW 0 0 60 75 175 845 5895 1270'490'535 0 0 20 35 90 685 2970 2280 2725 10675 WSW 0'0 0 0, 35 15 135 295 3060'005 25 5 30 625 2960 6830 11545 I 35070 3755 4785 0 0 0 0 0 25 55 50 885 9300 39875.5545'0 5 345 4345 5215 5485 3260 0 5 35 25 20 625 2090 2440 12350 7360 0244p'lit\I P,~~Pt I~~tt~~'4't 5 I%,~~P~.~1 0~

i Table 1.7 (1 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingesthd)RETS Manual Revision 8 Page 124 H<<3 C-14 Na-24 P-32 Cr-51 Ma-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni&3 Ni&5 Cu-64 Zn-65 Zn&9 Zn-69m Br-82 Br-83 Br-'84 Br-85 Rb-86 Rb-88'Rb-89 Sr-89 Sr>>90 Sr;91 Sr-92 Y<<90 Y-91m Y-91 Y-92': Y-93'r-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 RLL-L03 RQ-105 RLL-L06 Ag-110m bone 1 05E-07 2.84E&6 1 70E&6 1 93E&4 O.OOE+00 O.OOEWO 0.00E+00 2.7SE-06 4.34E-06 0.00E+00 0 OOE+00 O.OOE+00 1~30E&4 5 28E&7 O.OOE+00 4 84E-06 1.03E&8 l.70E-07 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00'" 3.08E&4 7.58E-03 5~67E&6 2.LSE&6 9.62K&9 9.09E-L1 1.4LE&7'8 45E-LO 2 68E&9 3.04E-08 1 68E-09 6~22E&9 S.22E-LL O.OOE+00 2.47E-10 2.54E-LO L.85E&7 1.54E-O8 2.75E-06 1.60E-07 liver 1 OSE&7 5.68E-07 1 70E&6 1 20E&5 O.OOE+00 4.57E&6 1.15E-07 L i 90E-06 1 02E&5 l.75E-07 7.45E-07 2.14E-O6 9.0LE&6 6.&6E-08 8.33E-08 1.54E-05 1.97E-O8 4.08E-07 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 2.11E-OS 6.05E-08 4.01E-08 O.OOE+00 O.OOE+00 0.OOE+00.O.OOE+00 O.OOE+00 0 OOK+00 O.OOE+00 O.OOE+00 O.OOE+00 9.75E&9 3'9E-10 3.46E-09 l.32E-L 1 4.31E-06 6'98E-10 3.66E-LO O.OOE+00 O.OOE+00 O.OOE+OO 1.48E-07 t body 1.05E-07 5.68E-07 1.70E-O6 7.46E-06 2.66E-09 8.72EW7 2.04E-08 4 43E-07 3.91E-06 2 91E-07 1.67E-06 4.72E-06 4.36E-06 3'3E-08 3.9LE&8 6~96E-06 1.37E&9 3.73E-d8 2.26E&6 4.02E-08 5.21E-08 2 L4E&9 9.83K&6 3 2LE&8 2.82E-08 8.84E&6 1.86EW3 2.29'9.30EW8 2 58E-LO 3.52E-12 3.77E-09 2.47E-L1 7.40E-11 6 60E-09 1.55E-10 1.86E-09 4.82E<<12 8.20EM7 8.89E-09 3.59EW9 7.97K&8 6.08E-O9 3.48E-07 8.79E-08 ADULT thyroid kidney 1.05E&7 1.05E-07 5.68E&7 5.68E07 1 70E&6 1.70E-06 O.OOE+00 O.OOE+00 1 59E&9 5.86E-LO O.OOE+00 1..36E-06 0.00E+00 1.46E&7 O.OOEh40 0.00E+00 0.00E+00 0~OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O,OOE+00 O.OOE+00 0.'OOE+00 0 OOE+6%.O~OOE+00 O.OOE+00 O.OOE+00 0'OOE+00 2.10E-07 O.OOE+00 LE 03E&5 O.OOE+00 1~28E-08 O.OOE+00 2.47E-07 O.OOE+00 0 OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0'.OOE+00 O'OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O'OOE+00" O.OOE+00 O.OOE+00 O.OOK+00 Q.OOE+00 O.OOE+00 0.OOE+00 1.53E-O8 O.OOE+00 5.128-10 0.00E+00 3.42E&9 O.OOE+00 1.54E-LL O.OOE+00 9.76E-06 O.OOE+00 1.06E-08 O.OOE+00 6.59E-09 O.OOE+00 7.06E&7 O.OOE+00 1.99E-07 O.OOE+00 5.3LE&6 O.OOE+00 2.91E-O7 lung L.OSE-07 5.68E&7 1.70E&6 O.OOE+00 3.53E-09 0.00E+00 O.OOE+00 1.06E-06 2.85E>>06 0 OOE+00 0 OOE+00 ,O.OOE+00 0~OOE+00-O.OOE+00 O,OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0~OOE+00 0'OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0~OOE+00 0.00E+00 O.OOE+00 0~OOE+00 0~OOE+00 0 OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 3.42E-10 1.87E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 gi<<lli 1 OSE-07 5.68E-07 l.70E-06 2.17E-05 6.69EW7 1.40E-05 3.67E-06 1.09E-06 3.40E-OS 4.44E-06 1.SLEWS 4.02E-05 1.88E&6 1.74E-06 7.LOE-O6.9 70E-06 2.96E-09 2.49E-05 2.59E-06 5.79E-08 4.09E-13 0.00E+00 4.16E-06 8.36E-19 2.33E-21 4.94E-OS 2'9E-04 2.70E-05 4.'26E-05 1.02E-04 2.67E-10 7.76E-05 1.48E-05 8.50E-05 3.09E-05 1.05E-04 2.10E-05 4.87E-08 9.99E-O6 4.13E-07 1.10E-21 2.16E-05 9.42E-06 1.78E-04 6.04E<<05 0244p

Table 1.7 (2 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 8 Page 125 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La 140 La-142 Ce-L41 Ce-143 Ce-L44 Pr-143 Pr-144 Nd-147 M-LST Np-239 bone liver 2.SOTS 5.29EWS L.79E-06 2.00E-OS 2 68E&6 9.?LE&7 6 7?E&6 2 42'&1 LQE&7 3~95E&8 L~LSE&5'.29E&6 3'4E&8 1~LSE-QS 1'3E&6 8.46EQT l.9?E&8 8.23E&9 2 52E&6 1.63E&6 7.56E&7 2.23E-06 4.L6E&6 5~95E&6 2+03E&7 5.43E&7 1+42E-06 2.4?E06 1 06E-07 2.88E-07 4.43E&7 1.L6E&6 6 22E&5 1.48E-04 6 5LE&6 2 5?E&5 7.97E-05 LE 09EO4 5.52K&8 1~09E&7 9.?OK&8 6'1E-11 2.03E-05 2.55E&8 4.71E-OS 3+56E-LL.2+L3E&8 2.19E-LL 2+50K&9 l.26E&9 1 28E-LO 5.82E-ll 9'6E-09 6'3E-09 1~65E&9 LE 22E&6 4eSSE-07 2.04E-07 9.20K&9 3.69K&9 3.01E-ll 1.25E-ll 6.29E-.09 7.27E-09 1.03E-O?8.61E-08 L~L9E&9 1.17E<<LO t body l.1 LE&6 4'26E&7 3.59E&7 8 25EWT 2 38K&8 1.82E&6?o 65E&9 7.05E-07 6~22E&9 1.53E-06 S.SOE-07 3 41EW6 l.9OE&7 7.53E-QT 1 03EWT 4.28E-QT 1~2LEW4 1.85EW5 7 o 14E-05 5,40E-QS 2.84E-09 1.33E-06 1~59K&9 1.34E-09 3 33E-10 1.45E-11 ELSE-10 1 35E-LO 2.62E-08 4.56E-LO 1.53E-12 4.35E-LO 3 QLE-Qa 6.45E-11 ADULT thyroid 6.79E&9 1.82E&9 8.06EWT 1.73E-06 8.L5E&8 3 95'&2.41E-OS 1.34E-06 1.62E&8 I.SOE-06 1.89E-04 l.95E&3 le 90E&5 3~63E&4 4.99E-06 7,65E-05 Oi OOE+00 Q.QQE+00 Q.OOE+00 Q.OOE+00 O.QOE+00 O.OOE+00 0.00K+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.QQE+00 O.OOE+00 O.OOE+00 Q.QQE+Oo O.QOEWO kidney O.OOE-OO O.OOOO 1.09K&5 2 75E05 4.48E-07 4.80EM5 1 32E-07 8 57E-06 a.63E-oa 1 5?E&5 3.48E-06 1.02E-05 8.65E-.QT, 4~3LE&6 4.58E-07 1 86E&6 4e 79E-05 1.43E&5 3.TQE-05 S.QLE-QS 6.46E-LL 8.6?E&9 3 3IE-ll 1.85E-11 O.OQE+00 O.OOE+00 2.94E-09 5.3?E-10 l.21E-07 2.13E-09.7.05E-12 4, 25E-09 0.00E+00 3.65K-10 lung gi-lli 2.LSE&6 7.95E&5 L.38E&6 1.9?E&5 0 OOE+00 1.07E-05 O.OOE+00 2.27E-05 O.QOE+00 8.68E-06 O.QOE+00 5.79E&5 O.OOE+00 2.37E-08 O.QOE+00 8.40E-05 Q.QQE+00 2 79E&9 Q.OQE+00 7.?LE&5 0 QQE+00 1.92E-06 0 OOE+00 1 57E-06 O,QOE+Og.1.02E-Q?O.QOE+00 2.22E-06 0 OOE+00 2.51E-10 O.OQE+00 1 3LE&6 1 59E&5 2.59E&6 1.96E&6 2.92E&6 1.23E&5 2.LLE&6 7.91E-09 4.65E-13 3.92E-LL 1.72E-07 1.46E-08 4.18E-05 2.02E-11 2.22E-17 1.24E-11 ,3.00E-26 0~QOE+00 9.25E-05 0.00E+00 4.25E-OT O.OOE+00 2.42E-05 O.OOE+00 4.56E&5 O.OOE+00 1.65E-04 O.OOE+00 4.03E-05 O.OOE+00 4.33E-18 O.OOE+00 3.49E-05 O.OOE+00 2.82E-05 Q.OOE+00 2.40E-05

References:

Regulatory Guide 1.109, Table E-ll.Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 axe from NURE~L?2 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 4.I NOTE: The tritium dose factor for bone is assumed to be equal to the total body dose factor.qs~g~pyp~o~~qvw~av~ep't"yama rq~V'rW~.~~~

Table 1.7 (4 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 8 Page 127 Sb-124 Sb-125 Te-125m Te-127m Te 127 Te-129m Te-129 Te-131m Te-131 Te 132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bone.3.87EM6 2.48E&6 3.83E&6 9 67K&6 1.58'1~63E&5 4.48E&8 2.44E-06 2.79E-08 3 49E&6 1.03E&6 5.85E&6 2 79E&7 2.01E&6 1.46E-07 6 10E&7 8.37E&5 8 59K&6 1 12E-04 7.76E-OS 1~39K-07 2.84E&5 6'1E-OS 2m99E&8 3.48E-09 1.79E-10 1~33K-OS 2.35E-09 6 96E-07*1.31E-OS 4.30E-11 9'8E-09 1.46E-07 1.76E-09 liver 7.13E-OS 2.71E-08 1.38E&6 3.43E-06 5.60E-OS 6.05E&6 1.67E&8 1.17E&6 1 15'&2.21E&6 2.98E&6 8.19E&6 7 30E&7 3.41E&6 3.87E-07 1.57E-06 l.97E-04 3.38E05 1.49K&4 1.49E-07 9 78E-11 3.48E-08 5.01E-11 2.99E-ll 1 71E&9 7.95E-I1 8 88E-09 l.71E&6 2'SSE&7 5.23E&9 l.76E-11 1.02E-08 1.19E-07 1.66E-10 t body 1.51E&6 5.80E&7 5.12E-07 l.15E&6 3.40E-08 2 58K&6 1.09K&8 9~76E-07 S.72E&9 2.08E&6 1~19E-06 4+40E-06 2 62E-07 1.04E&6 1 39E&7 5.82E-07 9.14E-05 2.27E-'d5 5'9E-05 7.45E-OS 4.05E&9 1 83E-06 2,24E-09 1.84K&9 4.55E-1Q 1~98E-ll 1.02EW9 1 91E-10 3.74E-08 6 52E-10 2 1SE-12 6.11E-10 4 17E&8 9 22E-ll TEEN thyroid 8.78E-09 2.37E-09 1.07E-O6 2.30E-06'~09E-07 5.26E&6 3.20E&8 l.76E-06 2 15E-08 2.33E&6 2.43E-04 2.39E&3 2.46E~4.76E-04 6+45E-06 1.01E-04 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 kidney O.OOE-OO O.OOE+00 O.OOE+00 3'2K-05 6.40E-07 6.82E-05 1.88E-Q7 1 22E-05.1~22K-O7 2~12E-05 4,59E-Q6 1.41E-O5~1;-15E&6 5~98E-06 6.10E-07 2.48E-06 6.26E&5 1 84E-05 5.07E-05 1.10E-07 9'2E-ll 1~18E&8 4.65E-11 2.53E-11 O.OOE+00 0 OOE+00 4.18E-09 7'7E-10 1~72K-07 3.04E-09 1.01E-11 5.99E&9 0.00E+00 5.21E-10 lung 3.38E-06 2.18E-06 O.OOE+00'O.OOE+00 Q.OOE+00 0~OOE+00 0 OOE+00 O.OQE+00 0.00E+00 O.OQE+00 O.QQE+00 , O.OOE+00 Q~OOE+00-0 QOE+00 Q.OOE+00 O.OOE+00 2'9E-05 2.90E-O6 1.97E-05 1 28E-0&6.74E-11 2.34E-08 3.43E-ll 1.99E-ll O.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OQE+00 O.OOE+00 0.00E+00 O.OOE+00 gi-lli 7.80E-05 1.93E-05 1 13EW5 2.41E-05 1.22E-05 6 12E-05 2.45E&7 9.39EW5 2 29E-09 7.00E-05 2 29E&6 l.62E-06 3.18E-07 2.58E-06 5.10E-09 1 74E&6 2.45E-06 2.72E-06 2.12E-06 6.76E-ll 1.24E-06 4.38E-05 1.43E-13 9.18E-20 9.82E-05 2.42E-06 2 54E-05 5.14E-05 1.75E-04 4.31E-05 4.74E-14 3.68E-05 3.22E-05 2.67E-05

References:

Regulatory Guide 1.109, Table E-12.Dose Factors for Co-57, Zn-69m, Be-82, Nb-97, Sb-124 and Sb-125 are from NURE~172 h e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 3~NOTE: The tritium dose factor for bone is assumed total body dose factor.to be equal to the 02449

Table 1.7 (3 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi, ingested)RETS Manual Revision 8 Page 126 H-3 C-14 Na-24 P-32 Cr-51 Ma-54 Ha-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu&4 Zn-65 Zn-69 Zn&9m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88'b-89 Sr89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc>>lol Ru-103 R1L-105 Ru-106 Ag-liam bone 1.06E-07 4 068-06 2 308-06 2.768-04 0.00E+QQ 0.008+00 0.008+00 3.78E-06 5.878-06 O.OOE+00 0 OQE+00 0 OQE+00 1~778&4 7>>498-07 0.00E+00 5~768&6 1 i478-08'.408-07 0.008+00 0+OQE+00 0.008wo 0.008&0 0.008+00 0.008+00 0.008+00 4,408~4 8.30E-03 8.07E&6 3 05E-'06 1~378-08 1.298-10 2.018-07 1 218-09 3.83E-09 4il28-08 2.37E-09 8'28-09 7.378-11 O.OOE+00 3.32E-lo 3.60E-10 2.55E-07 2.18E-Q8 3.928&6 2.05E-07 liver 1 06E&7 8'28-07 2.30E-06 1.718&/a.aoE+ao 5~90E-06 1.588-07 2 688&6 1~37E-05 2.38E-Q7 9'2E-07 2.818&6 1~258-05 9.57E-QS 1.15E-07 2.008&5 2 808&8 5.668-Q7, O.QQE+00 0.008~0 0.008+00 0.008+00 2.988-05 8.52E-08 5 508-08 0.O.OE+00 0.008+00 0 QQE+00 O.QOE+00 O.QOE+00 0.008+00 O.QOE+aa Q.QQE+00 Q.QOE+00 1.30E&8 4.698-10 4.568-09 1~838-11 6.038-06 9.268-10 5.12E-10 O.QOE+00 O.QOE+00 0.008+00 1.94E-07 t body 1.068&7 8.128-07 2.308-06 1.07E-05 3~6089 1.17E-O6 2 818-08 6.258-07 5.298-06 3.998&7 2.248&6 6 o 338&6 6.008&6 4 368&8 5.418-08 9.338&6 l.96E-09 5.19E-08 3+048&6 5.748&8 7.228&8 3.058-09 1,408-05 4.54E-Q8 3.89E-08 1 268&5 2.058&3 3.218&7 1.30E-07 3.698-10 4.93E-1.2 5.39E-09 3.50E-11 1.05E-10 8.948-09.2.168-10 2.518-49 6.688>>12 1.158&6 l.208&8 5.038-09 1.098-07 8.468&9 4.948&7 1.188-Q7 TEEN thyroid 1~068&7 8.128&7 2 308-06 O.OOE+00 2.008-09 0.008+00 O.OOE+00 O.OOE+00 O.QOE+00 O.OOE+00 0.008+00 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 0.008+00 0.008+00'Q.OOE+00 O.OOE+00 0.008+00 O.OOE+00 O.OOE+00 O.OQE+00 O.QOE+00 Q.OOE+00 O.OOE+00 0.008+00 0.008+00 O.OOE+00 O.QQE+QQ O.OOE+00 Q.QOE+OQ Q.OQE+00 0.008+00 O.OOE+00 O.OOE+Oo O.QQE+00, O.QQE+00 Q.QOE+00 O.OOE+00 0.008+00 0.008+00 O.QOE+00 O.QOE+00 0.008wa kidney t.ung gi-lli 1.06E-07 1.068&7 1.068-07 8 128-07 8.128&7 8 12E-07 2 308&6 2 308&6 2.30E-06 O.OOE+00 O.OOE+00 2.328-05 7.898-10 5'48&9 6.05E-07 1~768-06 O.OOE+00 1.21E-05 2 008-07 O.OOE+00 1.048-05 0.008+00 1.70E06 1.16E-06 0.008+00 4.328&6 3.24E-05 O.OOE+00 O.OQE+00 4.44E-06 0.008+00 0 OOE+00 1 348&5 0.008+00 0.008+00 3.66E-05.O.eOE+OO:

O.OOEWO.t;998-06..0.00E+00 0 OOE+00 5.198&6 2,91E-07 0.008+00 8.92E-06 1 288&5 0 008+Qo 8 478&6 1 838&8 0 OOE+Oo 5.168&8 3.448-07 O.OOE+00 3.118-05 0.008+00 0 OOE+00 0.008+00 0.008+00 O.OOE+00 O.OOE+00 OoaoE+00 Q.OQE+00 O.OQE+00 O.OOE+Oa 0.00E+00 Q.OQE+00 0.008+00 0.00E+00 4.41E-06 0.00E+00 O.OQE+00 7;30E-15 0.008+00 0.008400 8.43E-17 0.00E+Oa O.OOE+00 5.24E-05 O.OOE+00 0.008+00 2.338&4 O.OQE+00 O.OQE+00 3.66E-Q5 O.OOE+Qa 0.008+00 7.77E-05 O.OQE+QQ 0.008+00 1.138-04 O.QQE+aa O.OQE+ao 6.09E-O9 O.QOE+00 O.OOE+00 8.24E-05 0.008+00 O.OOE+00 3.32E-05 O.OOE+Oa O.OOE+Oa 1.17E-04 1.918-08 O.QOE+00 3.00E-05 7.118-10 O.OQE+00 1.27E-04 4.428&9 0.00E+00 1.95E-05 2.148-11 O.OOE+00 4.378&7 1.38E-05 O.QQE+00 1.088-05 1.38E-08 5.14E-10 6.08E-07 9.26E-Q9 3'2E-10 8.758-17 8'99E-07 O.QQE+00 2 13E-05 2.75E-Q7 0.00E+00 1..76E-05 7.56E-06 O.OOE+00 1.88E>>04 3.70E-07 O.OOE+00 5.458-05 0244p

Table 1.7 (5 of 8)INGESTION DOSE FACTORS-DFL (mremlpCi ingested);RETS Manual Revision 8 Page 128 H-3 C-14 Na-24 P-32 Cr-51 Hn-54 Ha-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88'b&9 Sr-89 Sr-90 Sr-91.Sr-92 Y-90 Y-91m Y-91'Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo<<99 Tc-99m Tc-101 RLj-103 Ru-105 Ru-106 Ag-110m bone liver 2, 03E&7 2.03EWT 1 21E-05 2.42E-06 5.80E-06 5.80E06 8 25E&4 3.86E&5 O.OOE+00 0.00E+00 0.00E+00 1.07E&5 O.OOE+00 3.34E&7 1.15E-05 6.10E&6 1.65E-05 2.67E&5 0'OE+00 4.93E&7 Q.OQE+00 1.80E-06 O.OOE+00 5.29E&6 5'8E-Q4 2 SSE&5 2 22E&6 2 09E-OT 0 OOE+00 2.45E-07 1.37E-05 3.65E-05 4.38E-08 6.33E-OS 7.10E&7 1.21E-06 O.OOE+00 0.00E+00 O.OQE+00 O.QOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 6.70E-05 0 QOE+00 l.90E-07 O.OOE+00'.17E-07 1.32E&3 0~QOE+00 1 TOE&2 Q.OOE+00 2 40E-05 0'0E+00 9.03E&6 O.QOE+00 4.11E&8 O.OQE+00 3.82E-10 O.OOE+00 6.02E-07 O.OOE+00 3.60E-09 0'0E+00 1 14E&8 0.00K+00 1.16E-07 2.55E-QS 6.99E-09 1.01E-Q9 2.25E-QS S.76E-09 2.17E>>10 3.92E-11 O.OOE+00 1.33E-05 9-23E-10 1.81E-09 1.07E-09 1.12E-09 7.31E-07 O.OQE+00 6.45E-QS Q.QQE+00 1.17E-O5 O.OOE+00 5'9E-07 3.64E-O7 g I.-0244p ((y~'<<~~Oh Wag%g g<<f'<<8 CHILD t body thyroid kidney lung gi-lli 2.03E&7 2.03E&7 2.03E&7 2.03E-07 2.03E&7 2e42E06 2o42E-06 2o42E-06 2o42E06 2e42E&6 5.80E&6 5.SOE-06 5.80E-.06 5.80E-06 5.80E&6 3.18E&5 0.00E+00 O.OOE+00 O.OOE+00 2.28E&5 8.90E-09 4+94E-09 1.35E-09 9+02E-09 4.72E&7 2.85E&6 0 OOE+00 3 OOE-06 Q.OOE+00 8 98E-06 7 54E-08 Q.OOE+00 4.04E-07 O.OOE+00 4.84E>>05 1 89E&6 O.OOE+00 O.QOE+00 3.45E-06 1.13E-06 1.33E&5 0.00E+00 O.OOE+00 7 74E&6 2.78E-05 9~98E&7 O.OOE+00 0 OOE+00 0 OOE+00 4.04E-06 5.51E&6 O.OOE+00 O.OOE+00 O.OOE+00 1.05E&5 1 56K&5 0.00E+00 O.OQE+00 O.OOEp00 2.93E-05 1.83E-05 O.OQE+00 0'OQE+00'-

0'OOE+00948-06 1.22E&7 O.OOE+00 O.OOE+00 O.OOE+00 2.56E-05 li48E-07 O.OOE+00 5.92E-07 O.OOE+00 1.15E-05 2 27E-05 Q.OOE+00 2'0E-05 Q OOE+00 6.41E-06 5 85E-09 O.OOE+00 3 84EWS O.OOE+00 3'9K-06 1.43E-07 0;ALOE+00 7.03E&7 0.00E+00 3.94E-05 7.55E-Q6 O.OOE+00 0 OOE+00 O.OOE+00 Q.OQE+00 1 71E-07 O.QOE+00 0 OOE+00 O.OOE+00 O.OOE+00 1 98E&7 O.OOE+00 0 OOE+00 0.00E+00 0 00E+00 9.12E&9 O.QOE+00 0.00E+00 O.OOE+00 0.00E+QQ 4.12E-05 0 OQE+OQ O.OOE+00 O.OOE+00 4.31E-06 1~32K&7 O.OOE+00 O.OOE+00 0.00E+00 9'2E-09 1 04E&7 O.OOE+00 0.00E+60 O.QOE+00 1 02E-09 3.77E&5 0.00E+00 Q.OQE+00 Q.OOE+00 5.11E-05 4 31E&3 O.OOE+00 O.OOE+00 O.OOE+00 2.29E-04 9.06E&7 0.00E+00 O.OOE+00 O.OOE+00'.30E-05 3.62EOT O.OQE+00 O.QOE+00 O.OOE+00 1.T1E-04.1.10E&9 0.00E+00 O.OOE+00 ,0~OOE+00 1~17E-04 1.39E-11 O.OOE+00 O.OQE+00 O.OOE+00 7.48E-07 1.61E-Q8 O.QQE+00 O.QOE+00 Q.OQE+00 8.02E-05 1.03E-10 O.QQE+00 O.OOE+00 O.OOE+00 1.04E-04 3'3E-10 O.OOE+00 O.OOE+00 O.OOE+00 1.70E-04 2.27E-08 0 OOE+00 3'5E8 O.OQE+00 2.66E-Q5 5'6E-10 O.QQE+00 1,45E&9 O.OOE+00 1.53E-04 6.26E&9 0 OOE+00 8~23E&9 O.OOE+00 1.62E-05 1,.83E-11 O.QOE+00 4.35E-ll Q.OQE+00 1~21E-05 3.29E-Q6 O.OQE+00 2.84E5 O.OQE+00 1.10E-05 3.00E-OS O.OOE+00 2.63E-08 9.19E-10 1.03E-06 1.42E-QS 0 OOE+00 1.91E&8 5.92E-10 3.56E-09 2.81E-07 0.00E+00 1.84E-06 O.OOE+00 1.89E&5 2.34E-08 O.OOE+00 5.67E-07 O.OOE+00 4.21E-05 1.46E-06 0.00E+00 1.58E&5 0.00E+00 1.82E-04 2~91E&7 O.OOE+00 6;TSE&7 O.OOE+00 4.33E-05 R<~~~gg g~~<<~'f~7 I'g<<g, f'Y'~",'A f<<(I g)gji'-(~g<<f'<<I~<<'g~;,g g<<<<egg Table 1.7 (6 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 8 Page 129 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-lZ9m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Ce-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 M-187 Np-239 bone l.118&5 7.168&6 1~148&5 2.898&5 4.71E-07 4.878-05 1.348-07 7.20E-06 8.308-08 1 018&5 2 92E-06 1~728-05 8.008-07 5~928&6 4.19E-07 1~758-06 Z.348-04 Z 358&5 3 278-04 2 288-07 4.148-07 8.31E-05 2.008-07 8.74E-08 1 018-08 5'4E-10 3'7E-OS 6~998&9 2.088&6 3'3E-OS 1~29E-10 2 798-08 4.298-07 5'5E-09 liver 1.44E-07 5~52E&8 3.09E-06 7~788&6 1.27E-07 1.368&5 3~74E-08 2.49E-06 2.538&8 4.478&6 5~908&6 1 738-05 1<478-06 7 328&6 7.788&7 3 158&6 3'848-04 6 46E-05 3.138&4 3.17E-07 2 218-10 7.288-08 1 12E-10 6'98-11 3+538-09 1.678-IQ 1~988&8 3.798&6 6.528&7 l.188&8 3'9E-ll 2.268&8 2 54E-07 3.77E-IO t body 3.898-06 1 i 508-06 1.52E-06 3.438-06 1.01E-07 7.568-06 3'88-08 2.658&6 2 47E-OS 5.408&6 3 048-06 9 838&6 6.768&7 2.778-06 3.588-07 1 498&6 8.108-05 4 18E-05 4.628&5 2.018-07 1~20E-OS 4.85E-O&6.518&9 4'888&9 1.198-09 5'38-11 2.948&9 5.498-10 1.118-07 l.958&9 6.498-12 l.75E-09 1.148-07 2.65E-10 CHILD thyroid 2.458&8 6.638&9 3 208&6 6.918&6 3.268W7 1.578-05 9 56E-08 5'2E-06 6.358&8 6 51E-O6 6.508&4 5~72E-03 6 828-05 1~36E-03 1~79E-05 2 798&4 O.OOE+00 0.008+00 0.00E+00 0 OOE+00 O.OOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 0.00E+00 O.OOE+00 0~OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney lung 0.00E+00 6.168&6 O.OOE+00 3.99E-06 O.OOEWQ O.OOOO 8.24E-OS'OOE+00 1.348W6 0 OOE+00 1.43E-04 0.008+00 3'28&7 0 OOE+OO 2.418&5 O.OOE+00 2.518&7 0.008+00 4.15E-05 0 OOE+00 8.828&6 0.008+00 2.848&5.-O.OOE+00~2i258&6 OcOOE+00-1~228-05 O.OOE+00 1~198&6 O.OOE+00 4.83E-06 0 OOE+00 1~198&4 4 278&5 3 448-05 5 13E-06 1.02E-04 3.67E-05 2.23E-07 2.40E-08 1.93E-10 1 30E-10 2.37E-OS 4.34E-OS 9'9E-ll 6.58E-10 5.09E-11 3 708-11 0.008+00 O.OOE+OO O.OQE+OO O.OOE+00 8.68E&9 Q.OOE+00 1.598&9 O.OOE+00 3.61E-07 0 OOE+00 6.39E-Q9 Q OOE+00 2 11E-11 0 OOE+00 1.248-08 0.008+00 O.OOE+00 O.OOE+00 1.09E-09 0 OOE+00 gi-lli 6.948-05 1.71E-05 1 10E 05 2.34E-05 1 848&5 5.948-05 8~348&6 1 018&4 4.36E-07 4.50E-05 2.768&6 1.54E-06 1~738-06"" 2.95E-06 5.16E-Q7 2.408-06 2.07E-06 2.27E-06 1.968-06 1~46E-07 2 39E-05 4.21E-05 1 14E-07 1 14E-09 9'4E-05 3.31E-05 2.47E>>05 5 55E-05 1.70E-04 4.24E-05 8.59E-08 3.58E-05 3.57E-05 2'98-05

References:

Regulatory Guide 1.109, Table 8<<13.Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table 2.NOTE: The tritium dose factor total body dose faccor.for bone is assumed to be equal".o the 0244p

Table 1.7 (7 of 8)INGESTION DOSE FACTORS-DFL (mrem/pai ingested)RETS Manual Revision 8 Page 130~&~A H-3 C-14 Na-'24 P-32 Cr-51.Ma-54 Ma-56 Fe<<55 Fe-59 Co-57 Co-58 Co&0 Ni&3 Ni&5 Cu>>64 Zn-65 Za-69 Zn&9m Br&2 Br-83 Br-84 Br-85 Rb&6 Rb&8 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-lal Ru-103 Ru-105 RIL-106 Ag-liam bone 3.08E-07 2.37E-05 1 01E-05 1 70E-03 0.00E+00 O.O.OE+00 0.00E+00 1.39E-05 3 QSE&5 O.OOE+00 O.OOE+00 O.OOE+00 6'4E-04 4.70E-06 0~OOE+00 1~84E&5 9.33E-OS 1.50E-06 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 2 51E-03 1.85E-02 5.00E-05 1.92E-05-8~69K-QS 8'0E-10 1~13E-06 7'5E-09 2.43E-08 2.06E-07 1.48E&8 4.20E-08 4.59E-10 O.OOE+00 1.92E-09 2.27E-09 1.48E-06 1.36E-07 2.41E-05 9.96E&7 liver 3.08E-07~5.06E&6 1.01E&5 1.00E-04 0.00E+00 l.99E&5 8.18E-07 8.98E6 5.38E&5 1 15E&6 3.60E&6 1.08E-05 3'2E-05 5.32E-Q7 6 09E&7 6+31E-05 1~68E-07 3.06K&6 O.OOE+00 0.00E+00 0 QOE+00 O.OOE+00 l.70E&4 4.98E-07 2.86E&7 O.OOE+00 0.00E+00 0.00E+00 0 OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OQE+Qo Q.QOEMO 5.02E-08 2.548-09 1.73E-OS 9.79E-11 3.40E-05 3.96E-09 2.86E-Q9 0.00E+00 O.OOE+00 Q.QOE~O 7.27E-07 t body 3 OSE-07 5.06E-06 1 01E&5 6.59E&5 1.41E&8 4 51E-06 1.41EW7 2 40E&6 2 12E-O5 1 87E&6 8.98K-06 2.558-05 2 20E&5 2 42E-07 2 82E-.07 2.91E-'05 1 25E&8 2.79E-'07 1.27E-05 3.63E-07 3.82E-07 1.94E-QS 8.40E&5 2.73E-07 1~97E-07 7~20E&5 4.71EW3 1,81E&6 7 13E-07 2.33E-09 2.76E>>ll 3.01E-08 2.15E-1Q 6'2E-10 3.56E-08 1.16E&9 1.00E-OS 3.53E-11 6.63E&6 5.10E&8 2.83EMS 4.95E&7 4.58E-OS 3.01E&6 4.81E&7 INFANT.thyroid kidney 3.08E&7 3'8E-07 5.06E&6 5.06E-06 , 1.01E&5 1 OlE-05 O.OOE+00 O.OOE+00'20E&9 2.01E-09 O.OQE+00 4.41E-06 O.OOE+00 7 03E-07 0~OOE+00 0.00E+00 0 OOE+00 O.OOE+00~O.OOE+00 0 OOE+00 0 OOE+00 0 QOE+00 O.OOE+00 0.00E+00 0 OOE+00.Q OOE+00 0 OOE+00 0 OOE+00~O.OOE+00 1.03E-06~0 OOE+00 3 06E-05 0 QQE+00 6 98E-08 O.OOE+00 1.24E-06 O.OOE+00 0.00E+00 0 OOE+00 0 OOE+00 0 OOE+00, 0.00E+00'.OOE+00 O.OOE+00 O,OOE+00 0~OOE+00 0.00E+00 0.00E+00 0 QOE+00 O.QOE+00 O.OOE+00 0.00E+00 0 OOE+00 O.OQE+00 Q.OOE+00 o.ooE+00 0 OOE+00 O.OOE+00 0.00E+00 0.00E+00 0~OOE+00 O.OOE+00 0 OOE+00.O.OOE+00 O.QOE+Qo O.QOE+00 O.OOE+00 0~OQE+00 0 OOE+00'5.41E-08 0 OOE+00 2.56E-09 0 OOE+00 1.24E-08 0.00E+00 7.65E-ll O.OOE+00 5.08E-05.0.00E+00 4.26E-QS.0.00E+00 3.40E-08 0.00E+00 3.08E-06 O.OQE+00 1.00E-06 O.QQE+00 2.85E-05 O.OOE+00 1.04E-06 lung 3.08E-07 5.06E-06 1.01E-05 O.OOE+00 1.79E-OS O.OOE+00 O.OOE+00 4.39E-06 1 59K&5 O.OOE+00 O.OOE+00.O.OOE+00 Q OOE+OQ 0 OQE+00 O.OOE+00 0~OOE+00 O.OQE+00 O.OOE+00 0 OOE+00 Q.QQEwo O.OOE+00 O.OOE+00 O.QOE+00 0.'OOE+00 O.OQE+00 O.QOE+00 O.OOE+00 0.00E+00 O.QQE+00 O.OOE+00 Q.OOE+QO O.OOE+00 O.QOE+Oo 0.00E+00 O.OOE+00 O.OOE+00-O.OOE+00 O.OOE+00 O.OOE+00 2.07E&9 1.56E-09 O.QOE+00 Q.OOE+00 O.OOE+00 O.OOE+00 gi-lli 3.08E-07 5'6E-06 1..01EW5 2.30E-05 4.11EW7 7.31E-06 7.43E-05 1.14E-06 2.57EW5 3.92E-Q6 8.97E-06 2.57E&5 l.95E-.06 4.05E-05 1.25E-05 5.33E-05 l.37EW5 4.24EW5 O.OOE+00 Q.OQE+00 O.OOE+00 Q.QQE+ao35E-06 4.85E>>07'.74E-OS 5.16E-05 2.31E-04 5.92E-05 2 07E-04 1..20E-04 2 70E-06 8.10E-05 1.46E-04 1.92E-04 2.50K&5 1~62E&4 1.46E-05 3.09E-05 1.12E-05 1.158-06 4.86E-O7 l.SOE-05 5'1E-05 le83E-04 3.77E-05 0244p

Table 1.7 (8 of 8)INGESTION DOSE FACTORS>>DFL (mremlpCi ingested)RETS Manual Revision 8 Page 131 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 C@-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bane 2.14E-05 1 23E-05 2.33E&5 5.85E&5 1.00E-06 1,00EO4 2.84E-07 1 52E&5 1 76E&7 2.08E05 6.00E&6 3.59E-05 lo66E-06 1~25E-05 8.69E-07 3.64E&6 3.77E-04 4.59E-05 5.22E-04 4.81EOT 8.81E-07 1.T1E-04 4.25E-07 1.84K&7 2.11E-OS 1.10E-09 7.87E-08 1.48EAS 2.98E-06 8.13E-08 2 74E-10 5.53E-08 9.03E-07 1.11E-QS liver 3.15E-07 1.19E-07 7'9E-06 l.94E-05 3.35E&7 3.43E-05 9.79E-OS 6.12E-06 6 50E&8 1.03E-05 1.32E-05 4.23E-05 3.37E&6 1.82E-05 1.TSE&6 7+24E-06 7+03E&4 1.35E&4 6~11E-04 T.SZE&7 5.84E-10 1.71EOT 2'1E-10 1.53E-10 8 32E&9 4.04E-10 4.80E-OS 9.82E&6 l.22E&6 3.04E-08 1.06E-10 5.68E-OS 6.2SE-07 9.93E-10 t bady 6.63E-06 2.53E-06 3~15E&6 7.08E&6 2.15E-07 1~54E&5 6.63E-08 5.05E&6 4.94E-OS 9.61E-Q6 5.30E-06 1.86E-05 1 20E6 5.33E-06 6 33E&7 2 64E&6 7.1QE-Q5 5.04E-05 4 33E-05 3.79E-OT 2.55E-OS 8.81E-O6 1.34E-OS 9.06E-09 2 14E-09 9 67E-11 5.65E&9 1~12E-09 1~67E-07 4.03E-09 1 38E-ll 3.48E-09 2.17E-07 5.61E-10 INFANT thyroid 5.68E-08 1.54E-OS 7 84E-06 1.69E-05 8 14E-07 3.84E-05 2.38E-07 1 24E-05 1.57E-07 1.52E-05 1.48E-03 1+39E-02 1.58E-04, 3 31E-03 4.15E-05 6 49E&4 O.QOE+00'O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.QQE+00 O.OOE+00 Q.OOE+00 0+OOE+00 O.OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.OOE+00 kidney O.OOE+00 O.OOE+00 O.OOE+00 1.44E&4 2.44E-06 2.50E-04 7.07E-07 4.21E-05 4.50E-07 6.44E-05 l.45E-.05 4 94E&5.Q'76K&6 2 14E-05 1.99E-06 8 07E-06 l..81E-04'.38E-05 1.64E-04 3'0E-07 3 51E-10 4.06E-08 1 75E-10'8.81E-11 Q.OOE+00 O.OOE+00 1.48E-08 2.86E-09 4.93E-07 1.13E-08 3.84E-ll 2.19E-Q8 Q.OOE+00 1.98E-09 lung gi-lli 1 34E-05 6'0E-05 7.72E-06 1.64K&5 O.OOE+00 1.11E-05 O.OOE+00 2.36E-05 O.OOE+00 2.10E&5 O.OOE+00 5.97E-05 O.OOE+00 2.27E-05 O.OOE+00 1.03E-04 0 OOE+00 7.112&6 O.OOE+00 3.81E-05 0.00E+00 2.83E-06 Q.OQE+00 1 51E-06 0:OOg+00...2-73E-06...

0 OOE+00 3 OSE-06 O.OOE+00 1.84E-06 0 QQE+00 2.62E-06 T.42E-05 1 91E-06 1 10E-05 2 05E-06 6.64E-05 1.91E-06 6.09E-08 1.25E-06 3.54E-10 5.58E-05 1 05E&7 4.20E-05 liTTE-10.5.19E-06 9'6E<<ll 7".59E-OT O.OOE+00 9.77E-05 O.OOE+00 6.86E-05 O.OOE+00 2.48E-05 O.OOE+00 5.73E-05 O.OOE+00 1.71E-04 Q.OOE+OQ 4.29E-05 O.OOE+00 4.93E-O6 O.OOE+00 3.60E-05 O.OOE+00 3.69E-05 O.OOE+OO 2.87E&5

References:

Regulatory Guide 1.109, Table E-14.Dose Factors for"Co-57, Zn-69m, Be-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977, Table l.NOTE: The tritium dose factor far bone is assumed total body dose factor.to be equal to the 0-0244p RETS Nanual Revision 8 Page 132 Table 1.8 (1 of 3)RADIONUCLZDE DECAY AND STABLE ELENENT TRANSFER DATA 8-3 C-14 Na-24 P-3R Cr-51 m-54 Nn-56 Fe-55 Fe-59.Co-57 Co-58 C~O Ni&3 Ni-65 CG-64 Zn-65 Zn-69m Zn-69 Br&2 Br-83 Br-84 Br-85 Rb&6 Rb-88 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-9S Nb-97 Mo-99 Tc-99m Tc-101 RLL-103 RLL-105 Ru-106 Ag-110m Half-Life (minutes)6.46E+06 3.018+09 9.00E+02 R.06E+04 3;99E+04 4.50E+05 1.558+02 1.428+06 6.43E+04 3.90E+05 1.028+05 2.77E+06 5'7E+07 1 518+02 7 62E+02 3.528+05 8.268+02 5.56E+01 2.128+03 1.43E+02 3.18E+Ol 2 87E+00 2.69E+04 1 78E+01 1.54E+01 7.28E+04 1.50E+07 5.20E+02 1.638+02 3.858&3 4.978+01 8.43E+04 R.l.RE+02 6.068+02 9.228+04 1.01E+03 S.OSE+04 7.21E+Ol 3.968+03 3.61E+02 1.42E+01 5.67E+04 2.66E+02 5.308+05 3.608+05 (us)1~798&9 3.848-12 1.288-05 5 618&7 2.908&7 2.578-08 7.45E-05 8.138-09 1.808-07 2 968-08 1 138-07 4+178&9 2 198 10 7.658-05 1.528&5 3.288-08 1 408-05 2 08E-04 5.458&6 8;088-05 3 638-04 4 028-03 4.29E-07 6.498-04 7.508-04 1.59E-07 7'08-10 2.038-05 7.098-05 3 OOE-06 2.32E-04 1.378-07 5.45E-05 1.91E-OS 1.25E-07 1.148-05 2 29E-07 1 608-04 2.928-06 3'08-05 8.13E-04 2.04E-07 4.34E-05 2.18E-O8 3.21E-08 Biv 4.808+00 5 50E+00 5.208-02 1.108+00 2 508-04 2.90E-02 2 90E-02 6.60E-O4 6'0E-04 9.408&3 9.408-03 9.408&3 1 908&2 1~908&2 1~208-01 4.008-01 4i 008&1 4 OOE-Ol 7~608&1 7.608&1 7.608-01 7~608&1 1~308&1 1~30E-01 1~308&1 1 708-02 1 708-02 1~708-02 1.70E-02 2.60E&3 2 608-03 2 608&3 2 608-03 2.608&3 1~708&4 l.708-04 9.408&3 9.408-03 l.208-01 2.508-01 2.50E-01 5 008&2 5.00E-02 5.008-02 1.50E-01 Fmi (co+)1.008-02 1 20E-02 4.00E-02 2+508&2 2.ROE&3 2.508&4 2.508-04 I~208-03 l.208&3 1.008-03 1~OOE-03 1.008&3 6.708-03 6~70K&3 1 408-02'~908-02'o 908&2 3'08-02 5.008&2 5.00E-02 5 008&2 5.008-,02 3.008&2, 3.008-02 3.008-02 1.408-03 1.408&3 1.408-03 1.408&3 1~008&5 1.008&5 1.008-05~1.008&5 1.008-05 5.008-06 5.008-06 2.508&3 2.50E-O3 7.50E-03 2.50E-OR 2.508&2 1.00E-O6 l.008-06 1.00E-06.5.00E-02 Fmi (goat)1 708&1 1 OOE-01 4.008-02 2 50EWl 2 208&3 2.50E-04 2.508&4 1.30E-04 1.30E-04 1.00EW3 1 008&3 1 008&3 6 708&3 , 6~7.08&3 1.308&2 3.908&2 3.908-02 3~908&2 5.008&2 5~OOE-02 5~008&2 5.008&2 3.00E-02 3.00E-02 3.008-02.1~408&2 1.408&2 1.408&2 1.40E-02 1.008&5 1.008-05 1.00E-05 1.00E-05 1.008-05 5~OOE-06 5.00E-06 2.508-03 2.508-03 7.50E-03 2.50E-OR 2.508&2 1.00E-06 1.00E-06 1.00E-06 5.00E-02 Ffi (beef)1.20E-02 3.LOUR 3.00E-02 4.60E-02 2.408-03 8.00E-04 8.00EW4.1.20E-02 l.208-02 1.308&2 1.30E-02 1.30E-02 5.30E-02 5.30E-Q2 9.708-04 3.00E-02 3.00E-02 3.008-02 2.60E-02 2.60E-02 2,60E-02 2.60E-02 3.10E-02 3.10E-02 3.108-02 6 OOE-04 6~OOE-04 6.00E-04 6.00E-04 4.60E-03 4.60E-03 4.60E-03 4.60E-03 4.60E-03 3.40E-02 3.40E-02 2.80E-Ol.2.80E-01 1.10E-03 4.00E-01 4.OOE-01 4.00E-01 4.008-01 4.00E-01 1.70E-02 0244p I,7t~.Pv~~g l P~t'Vh, I~~J)~f),1'0 sr o th aV4.,~T<lf~l~~1~(T.NP ft h ilh~t e~Ptl1tl+llt+e%1

RETS Manual Revision 8 Page 133 Ta RADIONUCLIDE DECAY SFER DATA ble 1.8 (2 of 3)AND STABLE ELEMENT TRAN Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-1,31 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs>>134 Cs-136 Cs-137 Cs>>138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-l.44 Nd-147 M-18?Np-239 Ar-41 Kr&3m Kr&5m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Half-Life (minutes)8.678+04 1.468+06 8.35E+04 1.578+05 5.61E+02 4.84E+04 6.968+01 1.808+03 2 50E+01 4.698+03 7 428+02 1.16E+04 1.388+02 1.25E+03 5.268+01 3'7E+02 1.08E+06 1.908+04 1 59E+07 3.228+01 8.318+01 1.&48+04 1.83E+01 1.07E+Ol 2.41E+03 9+548+01 4.68E+04 1.98E+03 4 09E+05 1 95E+04 1.738+01 1~588+04 1.438+03 3.39E+03 1.108+02 1+108+02 2.69E+02 5.648+06 7.638+01 1.708+02 3 16E+00 5.398-01 1~708+04 3.15E+03 (1/s)1~338&7 7.918&9 1~38E-07 7.36E-08 2.06E-OS 2 39E-07 1 66E-04 6.428&6 4.628-04 2.468&6 1~568&5 9.968-07 8.37E-05 9~248&6 2 20E-04 2 918&5 1~068&8 6.088-07 7.26E-10 3.598-04 1.398-04 6.288M?6.318-04=1.088&3 4.798-06 1.218&4 2.4?EW?5~838&6 2 828&8 5.928&7 6'88-04 7'1E-07 8.088-06 3 418-06 1.058&4 1.058&4 4.298-05 2.058&9 1.51E-04 6.79E-05 3.66E-03 2.14E-02 6.79E-07 3.67E-06 Biv N/A N/A 1.308+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 1~308+00 1.308+00 2 008-02 2 008-02 2.008-02 2 008&2 2 008&2 2.008-02 1 OOE-02 1 OOE-02 1.008-02 1.008-02 5.00E-03 5 OOEW3 5 008-03 5 OQE-03 2.508&3 2.508-03 2.508-03 2 508-03 2+508&3 2 508&3 2 50E-03 2 40E-03 1 808&2 2.50E-03 N/A N/h NIA N/A N/A N/A NIA N/A N/A N/A Fmi (co@)L.SOE&3 1 508&3 1 OOE-03 1 oOOE-03 1.00E-03 1.008-03 1 OOE-03 1 OOE-03 1.008-03 1.008-03 1.208-02 1.208-02 1 20E-02 1 208-g2 1~208-02 1~20E-02 8 F 008-03 8 008-03 8.00E-03 8 OOE-O3 4.00E-04 4.008-04 4.00E-04 4 OOE-04 5.00E-06 5.00E-06'1.008-04 1 008&4 1 OOE-04 Fmi (goat)1.508-03 1 508&3 1 OOE-03 1 008&3 1 OOE-03 1.00E-03 1.008W3 1 OOE-03 1 OOE-03 1.008-03 4 30EW1 4.308-01 4.30E-01 4.30E-.01" 4.30E-01 4i 308-01 3.008-01 3 OOE-Ol 3 OOE-01 3.00E-01 4.008-04 4.00E-04 4;OOE-04 4.00E-04 Ffi (beef)N/A N/A l.?OEAZ 7.708&2 7.70E-02 7.70E-02 l.70E-02 7.70E-02 7.708-02 7.70E-02 2.908&3 2.90E-03 2.908&3?9QE-03 2 90E-03 2.90E-03 1.508-02 1.50E-02 1.SOE-02 1.50E-O2 3 208&3 3.208-03 3.ROE-03 3.20E-03 2.00E-O4 Ri OOE-04 1~208&3 1.20E-03 5.00E&6 5~OOE-06 1 F 008-04 1.008-04 1.00E-04 1.208&3 5 F 008-06 5.00E-06 5.00E-06 5.008-06 5'OE-06 5.008&6 4.70E-03 4.70E-03.3.30E-03 1.30E-03'.00E-06 N/A N/A NIA NIA NIA N/A N/A N/A N/A N/A S.OOE-06 N/A N/A N/A N/h N/A N/A N/A N/A N/A N/A 2.00E-04 N/A N/A N/A NIA N/A N/A N/A N/A N/A N/A 5.00E-04 S.O08-04 0244p~rpyg gq<ygvnype<t'4oet>g~.

ep"%wwwptepLw iv.,q~~<p~i~~qffqtw1

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RETS Manual.Revision 8 Page 134 Table 1-8 (3 of 3).RADIONUCLIDE DECAY AND STABLE ELEMENT.TRANSFER DATA Half-Life'A Biv Fmi'm (miautes)(1/s)(cow)(goat)Ffi (beef)Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 7.55E+03 1.54E+01 5.47E+02 3.83E+00 1.41E+01 1.53E-06 7.50E-04 2.11E-05 3.02E-03 8.19E-04 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

References:

Half lives for all auclides: DOE-TIC-11026, Radioactive Decay Data Tables-A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D.C.Kocher, 1981.~~Transfer factors for Sb-isotopes are from'ORNL 4992;"Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.Cow-milk transfer factors for Iodine, Strontium, aad Cesium nuclides are from NUREG/CR-1004, Table 3.17.Goatmilk transfer factors'for Iodine nuclides are from NUREG/CR-1004, Table 3.17.Beef transfer factors for Iron, Copper, Molybdenum, and Cesium nuclides are from NUREG/CR-1004, Table 3.18'll other auclides'ransfer factors are from, Regulatory Guide 1.109, Tables E-l and E-2: 0244p

Table 1.9{l.of 2)DOSE CALCULATION FACTORS RETS Manual Revision 8 Page 135 Factor BRa (infant)BR (child).BRa (teen)BRa (adult)fg fL fp fs H M P gf (co+)gf (goat)r tb tcb tcsf te tep tesf tfm thc tsv Uam (infant)Uam (child)U~(teen)Uam (adult)Uap (infant)Uap (child)Uap (teen)Uap (adult)Value Units m3/year m3/year me/year m3/year 1400 5500 8000 8100 1 1 1 0 9 g/m3 0.072 L/kg-hr 40 kg/m>240 kg/m>64kg/day 08 kg/day 0.47 4.73E+08 seconds (15 years)7'8E+06 seconds (90 day')1.56E+07 seconds (180 days)5.18E+06 seconds (60 days)2 59E+06 seconds (30 days)7.78E+06 seconds (90 days)8.64E+04 seconds (1 day)8'4E+04 seconds (1 day)1.12E+06 seconds (13 days)2.38E+07 seconds (275 days)0 kg/year 41 kg/year 65 kg/year 110 kg/year 330 Llyear 330 Llyear 400 L/year 310 L/year R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table R.G.1.109 (Table E-5)E-5)E-5)E-5)E-5)E-5)E-5)E-5)Reference ICRP, 23 ICRP 23 ICRP 23 ICRP.23 TVA Assumption R.G.1.109 (Table E-15)TVA Assumption TVA Assumption TVA Value R G.1 109 (Section 2.C.)R.G.1.109 (Section 2.C.)R.G.1.109 (Table E-15)NUREG/CR-1004 (Sect.3.4)NUREG/CR-1004 (Sect.3.4)-NUREG/CR-1004 (Sect.3.2)R.G.1.109 (Table E-15)SgN FSAR Section 11.3.9.1 SQN FSAR Section 11.3.9.1 R.G.1.109 (Table E-15)R.'.1.109 (Table E-15)4 R.G.1.109 (Table E-15)SQN FSAR Section 11.3.9.1 NUREG/CR-1004, Table 3.40 NUREG/CR-1004; Table 3.40 SQN FSAR Section 11.3.9.1 0244p

Table 1.9 (2 of 2)DOSE CALCULATION FACTORS RETS Nanual Revision 8 Fage 136~&~&Factor Ufa(infant

)Ufa(child)

Ufa(teen)Ufa(adult)

UFL (infant)UFLa (child)UFL (teen)UFL (adult)USa (infant)US (child)US (teen)USa (adult)~(infant)U,(child)

U~(teen)Qa(adult)Yf Y Y',f Ysv (iodines)Xz (particulates)

Value Units 0 6.9 16 21 0 26 42 64.0 520 630 520 330 510 510 730 0.3 1 85 1.18 0 64 0.57 kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year L/year L/year L/year L/year none kg/m>kg/m>kg/m>kg/m>7.71E-07 sec i (15.4 d half-life) 5.2IE-07 sec (10.4 d half-life)

Reference R.G.1~109 (Table E-5)R.C.1.109 (Table E-5)R.G.1.109 (Table E-S)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1~109 (Table E-5)R.C.1 M9 (Table E-S)R'" C'.109'(Tabke-E-S)

R.G.1.109 (Table E>>5)R.G.1.109 (Table E-5)R.C.1~109 (Table E-5)R.G.1.109 (Table A-2)NUREG/CR-1004 (Table 3.4)NUREG/CR-1004 (Table 3.3)NUREG/CR-1004 (Table 3.3)NUREG/CR>>1004 (Table 3.4)(value selected is for non-leafy vegetables)

NUREG/CR-1004 (Table 3.1.0)NUREG/CR-1004 (Table 3;10)0244p

Table 1.10 (1 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 137 8-3 C-14 Na-24 P-32 Cr-51 ra-54.Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn&9 Zn-69m Br-42 Br-83 Br&4 Br-85 Rb-86 Rb-88 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91'Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc 99m Tc-101 RLL-103 RL1-105 Ru<<106 Ag-110m bone 1.58E-07 2.27E-06 1 288&6 1.658&4 0.008+00 0 OOE+00 0.00E+00 3.078&6 1 47E-06 0.008+00 0.008+00 0.008+00 5+408&5 1~92E-10 0 OOE+00 4.058&6 4 238-12 1 02E-09 O.OOE+00 0 OOE+00 0 008+00 0.00E+00 0.008+00 0.008+00 0.008+00 3.80E-05 1.248-02 7.74E-09 8.438-10 2.61E-07 3 268-11 5.78E-05 1.29E-09 1.18E-OS 1.348-05 1.218-08 1~76E-06 2.788-11 O.OOE+00 1.~298-13 5.228-15 l.918-07 9.888-11 8.64E-06 1~35E-06 liver 1.58E-07 4.26E-07 1 28E-06 9~648&6 0.008+00 4.958-06 1.55E-10 2 128&6 3.478&6 8.65E-OS 1.988-07 1.44E-06 3.938&6 2 62E-11 1.83E 10 1~29E&5 8 148-12 2.458&9 0 008+00 0.008+00 0.008+00 0.008+00 1 698-05 4.84E-OS 3'0E-08 0~OOE+00 0.008+00 0.008+00'.00E+00 O.OOE+00 0.00E+00 0.00E+00 0 008+00 O.OOE+00 4.30E-06 Z.458-09 9~778&7 7.03E-12 1.51E-08 3.64E-13 7.52E-15 O.OOE+00 0.00E+00 0.008+00 1.258-06 t body 1~5&E-07 4.268-07 l.288&6 6.26E-06 l.258-08 7.878&7 2.298-11 4.938-07 l.328&6 8.398-08 Z 598&7 1.858-06 1.81E-06 1.148-11 7;698-11 5 828-06 5 658-13 2.248<10 1~69E-06 3.018&8 3.918-08 1 608&9 7~378&6 2 418&8 2.128-08 1.098&6 7.628&4 3.13E-1.0 3.64E-11 7.018&9 1.278-12 1~558&6 3'7E-11 3 26E-10 2.91E-06 l.138&9 5~268&7 2.568-12 2.878&9 4.63E-12 7.38E-14 8.238&8 3.89E-ll 1.09E-06 7.43E-07 Sidney 1.58E-07 4.26E-07 1 28E-06 O.OOE+00 2.858%9 1.238-06 1.63E-10 O.OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 OOE+00 ,0 008+00'OOE+00 5.78E-10 8 62E-06 5 27E-12'1.48E-09 0.00E+00 O.OOE+00'0.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 d.OOE+00 0.00E+00 0.008+00 Oi 008+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 6.77E-06 3'IE-09 9'78-07 8.18E-12 3.64E-QS 5.52E-12 1~35E-13 7.298-07 1.27E-IO 1.678-05 2.46E-06 ADULT thyroid 1.58E-07 4.26E-07 I.288&6 O.OOE+00 7'48-09 0 008+00 0.008+00 0~OOE+00 0~OOE+00 0+008+00 O.OOE+00 O.OOE+00 0.008+QQ.0 OOE+00 O.OOE+00 0.008+00 0,008+00 O.OOE+00 0.008+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOOO O.OOE+00 0,00E+00 0.008+00 0.008+00 0.008+00 O.OOE+00.0.00E+00 0 OOE+00 0.008+00 0.008+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 0.008+00 O.OOE+00 O.OOE+00 lung gi-lli 1.58E&7 1.58E-07 4.26E-07 4.26E-07 1.28E-06 1.288-06 O.OOE+00 1~08E-05 1.SOE-06 4.158-07 1.75E-04 9.678-06 1 188-06 2.538-06 9.018&6 7.548-07 1 278&4 2.358-05 4.628&5 3.93E-06 1.168-04 1.33E-05.7 468-04 3.56E-05 2 238&5 1 678&6 7.00E-07 1.548-06 8.48E-07 6.12E-06 1.08E-04 6.68E-06 1.15E&7 2 048&9 2 3&E-06 1 71E-05 0 OOE+00 1 30E-06 0.00E+00 2.908&8 0.00E+00 2.05E-13 O.OOE+00 O.OOE+00 O.OOE+00 2.088-06 O.OOE+00 4.18E-19 O.OOE+00 1.16E-21 1 758&4 4.378&5 I.208&3 9.028&5 4.568&6 2.398&5 2 068&6 5.38E&6 2.12E-05 6.328&5 2 40E-07 1.668-10 2 13E-04 4.81E-05 1 968-06 9.198&6 6.06E-06 5.27E-05 2.218&4 1.88E&5 9.848-06 6.548&5 6.31E-05 1.30E-05 3.00E-07 3.02E-OS 1.14E-05 3.10E-05 9.55E-08 5.20E-07 4.998-08 1..36E-21 6 31E-05 1.388&5 1.378-06 6.028 46 1.17E-03 1.148-u4 5.798&4 3.788-05 0244p Table 1.10 (2 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 138~&~W Sb>>124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139'Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144'r-143 Pr-144 Nd-147 W-187 Np-239 bone 3.90E&6 6.67E&6 4.27E-07 1.58E&6 1.75E-10 1~22E-06 6.22E-12 8'4E-09 1.39E-12 3'5E-08 5'2E-07 3.15E-O6 1 45E-OT 1.08E<<06 8.05E-OS 3'5E-OT 4 66E-05 4.88E-06 5 98E-05 4 14E-OS 1~17E-10 4.88E-O6 1+25E-ll 3'9E-12 4.30E-OS 8.54E-ll 2+49E-06 2.33E-OS 4.29E-04 1~17E-06 3.76E-12 6'9E-07 1~06E-09 2'87E-08 liver 7 36EWS 7.44E-08 1~98E-07 7.21E-O7 8.03E-11 5 84E&7 2 99E-12 5.45E-09 7'4E-13 2 69E-08 1.68E-O6 4.47E-06 4 07E-01 1 85E&6 2 16E&7 8.73E-07 1 06E&4 1 83E-05 7.T6E>>05 7.76E-OS 8.32E-14 6.13E-09 9.41E-15 3;38E-,15 2.17E-'08 3.88E-11 1~69E&6 1 72E&8 1~79E-04 4.69E&7 1 56E-12 7.62E-07 8.85E-IO 2 82E-09 t body 1 55E-06 1 58E-06 5'4E-08 1.96E-07 3.87E-11 1.98E-07 1 55E-12 3.63E-09 4.49E-13 2 02E-O&6.60E-O7 2 56E-06 1 45E-OT 5~65E-O7 7.69E&8 3 21E-07 9'0E-05 1 38E-05 5.35E-O5 4.05E-OS 3.42E-12 3~21E-OT 4.20E-13 2.07E-13 5'3E>>09 9'5E-12 1.91E&7 1~91E&9 2.30E-05 5'0E-OS 1.91E-13 4.56E-OS 3.10E-10 1.55E-09 ADULT thyroid kidney 9'4E-09 0 OOE+00 6'5E-09 O.OOE+00 1.31E&7 1 55E&6 4.11E&7 5.72E-06 1.32E-10 6.37E-10 4.30E-07 4.57E-06 4.81E-12 2.34E-11 6.88E-09 3.86E-08 1 17E-12 5.46E-12 2.37E-O8 1.82E-07 1.42E-04 2.61E-06 1 49E-03 7 66E-06 1 43E&5=6i48E&7-2.69E-04 3 23E-06 3.73E&6 3 44E-07 5 60E&5 1.39E&6 0.00E+00 3.59E&5 O.OOE+00 1 OTE&5 O.OOE+00 2.18E-05 O.OOE+00 6.00E-OS O.OOE+00 7.78E-14 O.OOE+00 2.09E-09 0 OOE+00 8.75E-15 0,00E+00 2.86E-15 O.OOE+00 O~OOE+00 0,00E+00 0.00E+00 O.OOE+00 7.83E&7 O.OOE+00 7.60E-09 O.OOE+00 1.06E-04 O.OOE+00 2.70E-01 O.OOE+00 8.8lg-13 0.00E+00 4.45E-'07 0.00E+00 0.00E+00 O.OOE+00 8.75E-09 lung 3.10E-04 2.ISE&4 3.92E-05 1.20E-04 8.14E-OT 1.45E-04 2.42E-OT 1.82E-05 1.74E-07 3 60E-05 0.00E+00 O.OOE+00 0 oOOE+00.O.OOE+00 O.OOE+00 O.OOE+OO 1.22E-05 1.50E-06 9.40E-06 6.07E-09 4.70E-07 1.59E&4 2.42E-07 1.49E&7 1.70E-05 7.91E-07 4.52E-05 9.97E-06 9.72E-04 3.51E-05 1.27E-07 2.76E-05 3-63E-06 4.70E-06 gi-l.li 5.08E-05 1.26E-05 8.83E-06 1.87E-05 7-17E-06 4.79E-05 1.96E-08 6.95E-05 2.30E-09 6.37E-05 9.61E-07 7 85E-07-5.08E-OS 1 llE-06 1.26E-10 6.56E-07 1.30E-06 1.46E&6 1.05E-06 2.33E-13 1.12E-07 2.73E-05 1.45E-17 1~96E-26 5.73E-05 2.64E-07 1.50E-05 2.83E<<05 1.02E-04 2.50E-05 2.69E-18 2.16E-Q5 1.94E-05 1.49E-05

Reference:

Regulatory Guide 1.109, Table E-7.~Dose Factors for Co-57,'n-69m, Br-82, Nb>>97, Sb-124 and Sb-l.25 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977,.Table 8..NOTE: The tritium dose factor total body dose factor.for bone is assumed to be equal to the 0244p Table 1.10 (3 of 8)INHALATION DOSE FACTORS-'FA (mrem/pCi inhaled)RETS Manual Revision 8 Page 139 H-3 C 14 Na-24 P-32 Cr-51 Hn-54 Ha-56 Fe-SS Fe-59 Co-57 Co-S8 Co-60 Ni&3 Ni-65.Cu&4 Zn-65 Zn-69 Zn-69m Br&2 Br-83 Br-84 Br-85 Rb-86 Rb&8 Rb-89 Sr&9 Sr-90 Sr-91 Sr-92 Y-9Q Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97~Nb-95'b-97 Mo>>99 Tc-99m Tc-l.01 Ru-103 Ru-105 Ru-106 Ag-110m bone 1 59E&7 3~25E-06 1 72E-06 2+36E04 O.OOE+00 O.OOE+00 O.OOE+OO 4.18E-06 l.99E&6 O.OOE+00 O.OOE+00 O.OOE+00 7.25E-05 2 73E-10 O.OOE+00 4.82E&6 6+04E-L2 1~44K-09 O.OOE+QO 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 0+00K+00 O.OOE+QQ 5.43E-05 1 35E-02 1.10E-OS 1 19E-09 3.73E-07 4.63E-11 8'6E-05 1.84E-09 1~69E-08 1,.82E-05 1.72E-08 2.32E-06 3'2E-LL O.OOE+00 1.73E-13 7.40E-L5 2.63E-07 1.40E-LO 1.23E-05 1.73E&6 liver 1.59E&7 6.09E-07 1 72E&6 1~37E-05 O.OOE+00 6~39E&6 2 12E-LO 2.98E&6 4,62E&6 1~18'?2.59'?1 89E&6 5.43E&6 3.66E-LL 2.54E-10 1 6?E&5 1~15E-ll 3.'39E-09 O.QOE+00 O.OOE+00 0 OOE+00 O.OOE+00 2.38E-05 6.82E-08 4.40E-O&O.OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 0.00E+00 O.OOE+00 5.73E-06 3.40E-09 1.29E-06 9'2E-12 2.11E-08 4.83E-13 L.05E<<14 0.00E+00 0.00E+00 O.OOE+00 1.64E&6 t body 1 59E&7 6 09E&7 1..72E-06 8 95E-06 1.69E&8 1 05E-06 3ilSE-11 6'3E-07 1~79E&6 1~LSD?3 4?E&7 2 48E&6 2.4?E&6 1 59E-11 1.06E-LO 7.80E-06 8 07E-13 3.11E-'10 2.28E&6 4.30E-QS 5 41E-08 2 29E-09 1.05E-05 3.40E&8 2'1E-08 1 56E&6 8 35E&4 4 39E-LO 5.08E-11 1.00E&8 L.77E-12 2~21E-06 5 36E-11 4.65E-LO 3 94E&6 1 5?E&9 7.08E-07 3.55E-12 4.03E-09 6'4E-12 1.03E-13 1..12E-07 5.42E-11 1.55E&6 9'9E-O?TEEN thyroid kidney 1.59E-07 1 59E-07 6.09E-07 6.09E-07 l.?2E-06 1 72E-06 0.00E+00 O.OOE+00 9 3?EA9 3.84E-09 O.OOE+00 1~59E-06 0 OOE+00 2.24E-10 Q.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.OOE+00 0 OOE+00 0 OOE+00 0 QOE+00 0 OOE+00 O.OOE+00 0 OOE+09-0'OOE+00 Q OOE+00 OoOOE+00 0 OQE+00 8 OLE-LO 0 OOE+00 1,08E-05 O.OOE+00 7.53E-12 0 OOE+00 2.06E-09 O.OQE+00 O.OOE+00 O.OOE+00 O.OQE+OQ 0.00E+00 O.OOE+00 0.00E+00 0 OOE+00 O.QOE+00 0 OOE+00 O.OQE+00 0.00E+00 0 OOE+00 0 QOE+00 0.00E+00'O.OOE+00 0 QQE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0-OOE+00 0.00E+00 O.OOE+00 0.00E+00 0 V OCE+00 0.00E+00 O.OOE+00 8.42E-06 O.OOE+00 5 15E-09 O.OOE+00 1.25E-06 0~OOE+00 1.14E-L 1 O.OOE+00 5'4E-08 O.OOE+00 7.20E-1.2 O.OOE+00 1'0K-13 O.OOE+00 9.29E-Q7 0.00E+00 1.76E-10 O.OOE+00 2.38E-05 O.OOE+00 3'3E&6 lung 1 59E-07 6.09E&7 1 72E&6 0 QOE+00 2.62E-06 2.48E-04 1.90E-06 1.55E-05 1 9LE&4 7.33K&5 1 68E-04~1.09E-03 3:84EWS 1 17E-06 1 39E-06 1~SSE&4 1 98E-07 3.92E&6 0 OOE+00 Q.OQE+00 O.OQE+00 0 OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 3.02E-04 2.06E-03 7.59E&6 3.43E-06 3.66E-05 4.00E-O?3.67E-04 3.35E-06 1.04E-05 3'6E-04 1'2E-05 9.39E-05 4.91E-07 1.92E-05 1.44E>>07 8.34E-08 9'9E-05 2.27E-O6 2.01E-03 8.44E-04 gi-lli L.59E-07 6.09E-07 1.72E-06 1 16E-QS 3.?SEW?8.35E-06 7.18E-06 7.99E-07 2.23E-05 3~93E&6 1~19EW5 3.24E-05-1 77E-06 4.59E-06 7.68EW6 5.83E-06 3.56E&8 2.14E-05 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 2 21E-06.3 65E-15 4.22E-17 4.64E-05 9.56E-05 3.24E&5 1.49E-OS 6.99E-05 3.?7E-09 5.11E-O5 2.06E-Q5 7.24E-OS 1.86E-05 7.88E-OS 1.21E-05 2.71E-07 3.36E-05 7.66E-07 1.09E-16 1.36E-05 l.13E-OS 1.20E-04 3.41E-05 0244p Table 1.10 (4 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 140 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te>>129m Te-129 Te-131m Te-131 Te-132 I-130 I 131 I 132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-L39 Ba-140 Ba-141 Ba-142'a-140 La-'142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-L&7 Np-239 bone 5'&E-06 9.23E-06 6'0E-07 2.25E&6 2 51E-IO 1~74E-06 8.87E-12 1 23E-08 1.97E-12 4 50E-O&7.80E-07 4 43E-06 1~99E-07 1+52E-06 1~11E-07 4 62E-07 6.28E-05 6.44E06 8 38E-05 5 82E-08 li67E-LO 6.84E-06 1~7&E-11 4'2E>>12 5.99E-OS 1~20E-10 3.55E-06 3'2E-O&6 11E-04 1.67E-06 5.37E-12 9.83E-07 1.50E-09 4.23E-OS liver 9~92E&8 1~OIE&7 2.80E-07 1.02E&6 1~14E-10 8.23E-07 4 22E-12 7.51E&9 1.04E-12 3 63E&8 2 24E&6 6~14E&6 5.47E&7 2 56E&6 2 90E-07 1 ISE&6 1.41E-04 2 42E-05 1.06E-04 1 07E&7 1.1&E-13 8 3&E-09 1 32E-14 4.63E-15 2.95E-OS 5'1E-ll 2 37E&6 2.42E-4&2.53E-04 6 64E-07 2.20E-12.1.07E-06 1~22E-09 3 99E&9 t body 2.10E-06 2.15E&6 8.34E-OS 2.73E-07 5.52E-LL 2.&LE-07 2.20E-12 5.03E-09 6'0K-13 2.74E-O&8.96E&7 3 30E-06 1.97E-07 7.78E-07 1.05E-07 4.36E-07 6.868-05 l.71E-05 3.89E-05 5.5&E-08 4.87E-12 4.40E-07 5.93E-L3 2.84E-13 7.82E-09 1'2E-ll 2.71E-07 2.70E-09 3.2&E&5 8.28E-08 2 72E-13 6.41E&8 4.29E-10 2.21E-09 TEEN thyroid kidney 1 22E&8 0.00E+00 8.80E-09 0 OOE+00 1 75E&7 0.00E+00 5.4&E-07 8 17E&6 1 77E-10 9 LOE-10 5'2E-07 6.49E-06 6.4&E-12 3.32E-11 9 06E-09 5.49E&8 1 55E-12 7'2E-12 3.07E-OS 2.44EW7 1 86E-04 3 44E-06 1.83E-03 1 05E-05 1 89E-'05 8'65E&7 3'5E-04 4.49E&6 4 94E-06 4.5&E&7 7.76E-05 LE 86E-06 O.OOE+00 4 69E&5 O.OOE+00 1.3&E-05 0 OOE+00 3 SOE-45 O.OOE+00 8 28E-08 0 OOE+00 1~11E-13 O.OOE+00 2.85E-09 0 OOE+00 1 23E-14 O.OOE+00 3.92E-15 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 1 11E-06 O.OOE+00 1.08E>>08 O.OOE+00 1.51E-04 0 OOE+00 3.&6E-07 0.00E+00 1 26E-12 0.00E+00 6.2&E-07'.OOE+00 O.OOE+00 O.OOE+00 1.25E-08 lung 4.81E-04 3.42E-04 6.70E&5 2.07E-04 1.40E-06 2.47E-04 4.12E-07 2.97E-05 2.92E-07 5.61E-05 Q.OOE+00.O.OOE+00 0:OOE+OO O.OOE+00 0.00E+00 O.OOE+00 1.83E-05 K 22E&6 1.51E-05 9.84E-09 8'8E-07 2.54E-04 4 BELLE-07 2.39E&7 2.6&E-05 1.27E-06 7.67E-05 1.63E&5 1.67E<<03 6.04E-05 2.19E-07 4.65E-05 5.92E-06 8'1E-06 gi-lli 4.98E-05 1.24E-05 9.38E-06 1.99E-05 1.01E-05 5.06E-05 2.02E-07 7.76E-05 1.89E-09 5.79E-05 1.14E-06 8.11E-07-1.59E-07 1.29E-06 2.55E&9 8.69E-07 1.22E-06 1.36E-06 1.06E-06 3.38E-ll 8.06E-07 2'6E-05 9.33E-14 5.99E-20 6.09E-05 1.50E<<06 l.5&E-05 3.19E-05 L.OSE-04 2.67E-05 2.94E-14 2.2&E-05 2.21E-05 1.65E-05

Reference:

Regulatory Guide 1.109, Table E-8.Dose Factors for Co-57, Zn-69m, Br-&2, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November L977, Table 7.NOTE: The tritium dose factor total body dose factor.for bone is assumed to be equal to the 0244p Table 1.10 (5 of 8)INHALATION DOSE FACTORS>>DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 141~<<H-3 C-14 Na-24 P 32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni&3 Ni&5 Cu-64 Zn-65 Zn-69 Zn&9m Br-82 Br-&3 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru>>106 Ag-110m bone 3~048&7 9~70E-06 4.358&6 7 04E-04 Q.QQE+00 0 QOE+00 O.QOE+00 1 28E-05 5.59E-06 O.OQE+00 O.QQE+00 0.008+00 2 22E-04 8.088-10 O.QOE+00 1 15E-05 L.818-11 4 26E-09 0.008+00 O.QOE+00 0.008~0 O.QOE+00 0.QOE+QQ O.QOE+00 0.008%0 1.628-04 2.73E-02 3.28E-08 3.548&9 1~LLE&6 1~37E>>10 2 478-04 5.508-09 5.04E-08 5~138&5 5.07E-08 6~358-06 1.16E-LO 0.008+00 4.818-L3 2.198-14 7.55E-07 4.13E-LO 3.688-05 4.568-06 liver 3.048&7 1 82E-06 4 358&6 3 09E-05 O.OOE+00 1 168-05 4.48E-10 6.808-06 9.04E-06 2.44E-07 4.798-07 3.558-06 1.2S8-05 7'98-11 5.398-10 3.06E-05 2.618-11 7'88-09 O.QOE+00 0.008+00 O.QOE+00 O.QQE+00 5 36E-Q5 1.52E-07 9.338-08 0.008+00 0-008+00 O.QOE+00 0 QOE+00 Q.QOE+00 O.QQE+00 Q.QOE+00 0.008+00 0.00E+00 1.138-05 7'48-09 2.488-06~2.08E-LL 4.668-08 9.41E-13 2.308-14 O.QOE+00 O.QQE+00 O.QOE+00 3.088-06 t body 3'48-07 1.82E-06 4.3SE-06 2.67E-QS 4.17E-QS 2.578-06 8.43E-11 2.108-06 4.51E-06 2.888-07 8 558-07 6.128&6 7.568-06 4.44E-ll 2'08-10, 1~908-05 2.418-12 8 598-l0 5.668&6 1.288-07 1.48E-07 6.848-09 3.09E-O5 9~90E-08 7.83E-Q8 4.66E-06 1.748-03 1 24E-Q9 1.42E-10 2 998&8 4 98E-12 6.59E-06 1.578-10 1.388-09 1.00E-05 4.328-09 l.778&6 9.74E-12 1.158-08 1.56E-11 2.918-13 2.908&7 1.508-10 4h578-06 2.478-06 CHILD thyroid 3.04E-07 1~828&6 4.3SE-06 O.OQE+00 2 31E-08 0.008+00 Q.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.QOE+00 O.OOE+00 0.00E+00 0.00E+00 0.008+00 0.00E+00 0.008+00 0.008+00 0.008+00 O.QOE+00 O.OOE+00 0.008+00 0 QOE+00 0.008+00 0.008+00 O.QOKWO 0.008+00 O.OOE+00 O.OOE+00 0.008+00 0.008+00 O.OOE+00 O.OOE+00 0'OE+00 0.008+00 Q.QOE+00 O.OOE+00 0.008+00 0.008+00 O.OOE+00 Q.QOE+00 0.008+00 O.QOE+00 0.008+00 0.008+00 kidney 3.Q4E-07 1.828-06 4+358-06 O,QQE+00 6.57E-09 2 7LEM6 4.52E-10.0.008+00 0.008+00 O.QOE+00 0.008+00 O.OQE+00.0.008+00.

0.008+00 1~63E-09 1.938-05 1.588-11 4.228-09 0.008+00 0.008+00 0.008+00'0.008+00 Q.OQE+00 O.OOE+00 0 QQE+00 Q.QOE+00 O.OQE+00 0.008+QQ 0.008+OQ 0.008+00 Q.QOE+00 O.OOE+00 0.008+00 0.008+00 1.618&5 1.05E-08 2.338&6 2.318-11 L.068&7 1.37E-11 3.92E-13 1.908&6 3.63E-10 4.978&5 5.748&6 lung 3.04E-07 1.828-06 4 35E-06 0.QOE+00 4.59E-.06 4.268-04 3.558-06 3.00E-05 3.43E-04 1.37E-04 2.998&4 1 91E-03/43E-OS.2'1E-06 2.59E-06 2 69E-04 3.848-07 7~368&6 0.008+00 O.OOE+00 O.OOE+00 O.QQE+00 0.008+00 O.OQE+00 O.OOE+00 5.838-04 3.998&3 1 44E-05 6 498&6 7.078-05 7.608&7 7 10E-04 6.46E-06 2.01E-05 6.03E-04 3.068-05 1.66E-04 9.23E-07 3.66E-OS 2.57E-07 1 58E-07 1.79E-04 4 30E-06 3.87E-03 1.48E-03 gi>>lli 3.04E-07 1.82E-Q6 4.358-06 l.14E-Q5 2.93E-07 6.19E-06 3.33E-05 7.75E-07 l.91E-05 3.58E-06 9.29E-06 2.60E-05 M.718-06 2.27E-05 9.92E-O6 4.41E-06 2.75E-06 2.71E-05 Q.QOE+00 0.00E+00 O,.OQE+00 0.008+00 2.16E-06'.66E-09 5.11E-LO 4.52EWS 9.288WS 4 708-,05 6.S5E-O5 , 7.24E-05 4.648-07 4.978&5 6.46E-05 1.05E-04 1.658-05 9.49E-05 1.008-05 7.52E-06 3.42E-05 1.30E-06 4.4LK-09 1.2LE-05 2.69E-05 1.168-04 2.71E-05 Q244p'<<h,~'l~r~<,tgf hrh;J'>>r, Vtg 0'>>+E'hr Wl<<,'I, h>>r<<<<', r,h Ve<<~hr(or<<~l'~~g o p.>>rr<<r.~

Table 1.10 (6 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 142 Sb>>124 Sb-125 Te-125m Te-127m Te-127.Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I 132 I-133 I 134 I-135 Cs-134 Cs-136, Cs-137 Cs-L38 ,Ba-139 Ba-140 Ba-14L Ba-142'a-140 La-142 Ce-141 C@-143 Ce-144~Pr-143 Pr-144 Nd-L47 M-L87 Np-239 bone 1~55E-05 2.66E-05 1 828-06 6.728-06 7.498-10 5.198-06 2 648-11 3 638-08 5.878-12 1 308-07 2 ZLE&6 LE 308-05 5.728&7 4 48E-06 3'7E-07 1'38-06 1~768-04 LE 76E-05 2.45E-04 1.718-07 4 988-10 2.008-05 5'98-11 1.35E-11 1~74E-07 3.50E-10 1~Q6E-05 9.898&8 1.83E-03 4.998&6 1~618-11 2.928-0&4.418-09 1'26E-07 liver 2.008&7 2.058&7 6.298&7 2.3LE&6 2.57E-10 1.858&6 9.45E-12 1.608&8 2.28E-12 7'68-08 4.43E-06 1~30E-05 l.108-06 5.498-06 5.848-07 2.36E-06 2.748-04 4.62E-05 2.238&4 2.27E-07 2 66E<<13 1.758-08 2.95E-14 9'3E-15 6.08E-OS 1.11E-10 5.28E-06 5.378&8 5.728-04 1.50E-06 4.99E-12 2.368-06 2'1E-09 9.048-09 t body 5.4LE&6 5.598&6 2.47E&7 8.168&7 1 65E-1Q 8.228&7 6.448-12 1.37E-OS 1.78E-12 7.128-08 2.288-06 7.378&6 5.07E-07 2 088&6 2.698-07 L+LZE&6 6 078WS 3~148-'45 3 47E-05 1 F 508-07 1 45E-11 1 178&6 L.728-12 7'4E-13 2.048-08 3.49E-LL 7.83E-07 7.778&9 9 778&5 2 47E-07 8.10E-13 1.84E-07 1.17E-09 6.35E-09 CHILD thyroid kidney 3.418&8 O.OOE+00 2.468&8 O.OOE+00 5 208&7 0.00E+00 1.648-06 1~728-05 5 308-10 1.918-09 1~718-06 1 36E-05 1.93E-LL 6.94E-LL 2.648-08 1.08E-07 4.598-12 1.59E-LL 8 588-08 4.79E-07 4 99E-04 6.61E-06 4.39E-03 2 13E-05 5.238&5~.L;698&6 1.048&3 9.138&6 1 378-05 8'28-07 2 148&4 3 62E-06 0.008+00 8'3E-05 0.008+00 2.58E-05 0.00E+00 7.63E-05 0.008+00 1.688-07 O.OOE+00 2.338>>13 0.008+00 5.718-09 0.008+00 2.568-14 0 F 008+00 7.87E-15 0.008+00 0.008+00 0.008+00 0.008+00 O.OOE+00 2.3LE&6 Q.OOE+00 2 268&8 0.008+00 3.17E-04 0.008+00 8.118-07 O.OOE+00 2.64E-LZ 0.008+00 1.308-06 0~OOE+00 O.OQE+00 0.00E+00 2.63E-08 lung 8.76E-04 6.27E-04 1 29E-04 4.00E-04 2.71E-O6 4.768-04 7.938-07 5 56E-05 5.55E-07 1 02E-04 O.QQE+00.0.OOE+00 Oe 008+00-0.OOE+00 O.OOE+00 O.OOE+00 3'78-05 3.93E-06 2.81E-05 1.848&8 1.56E-06 4 71E-04 7+898&7 4.44E-07 4.94E-05 2.35E-06 1.47E-Q4 3'2E-05 3.23E-03 1.17E-04 4.23E-07 8.87E-O5 1 118-05 1.57E-05 gi-Lli 4.43E-05 1 09E-05 9.13E-06 1.93E-05 1.52E-05 4.91E-05 6.898&6 8.32E-05 3.60E-07 3.72E-05 l.3&8&6 7.68E-07 8 65E-07 l.48E-06 2.58E-07 l.ZOEM6 1.04E-06 1.13E-06'.78E-07 7.29E-08 1.56E-05 2.75E-OS 7.44E-08 7.41E-10 6.10E-05 2.05E-05 1.53E-O5 3.44E-Q5 1.05E-04 2.63E-05 5.32E-OS 2.22E-05 2.468-05 1 73E-05 Reference!

Regulatory Guide 1.109, Table E-9.Dose Factors for Co.-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG&L72 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 6 NOTE: The tritium dose factor total body dose factor.for bone is assumed to be equal to the 0244p

Table 1.10 (7 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 143 8-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni&3 Ni&5 Cu-64 Za-65 Za-69 Zn-69m Br&2 Br&3 Br-84 Br-85 Rb&6 Rb-88 Rb&9 Sr&9 Sr-90 Sr-91 Sr-92" Y-90 Y-91m...Y-9L-Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 RLL-LOS Ru-106 Ag-110m bone 4.62E-07 1.89E-05 7.54E-06 1.45E-03 O.OOE+00 O.OOE+00 O.OOE+00 1.41E-05 9.69E&6 O.OOE+00 0 QQE+00 O.QOE+00 2 42K&4 1 71E-09 O.OOE+00 1~38E&5 3.85E-L1 8.98E&9 0 OOE+00 O.OOE+00 0 OQE+00 0+OOE+00 0 OOE+00 O.QOE+00 0;QOE+00 2.84E-04 2.92E&2 6.83E-08 7.50E&9 2.35E-06 2 9LE-LQ 4.20E-04 1 17E-08 1.07E-07 8.24E-OS 1.07E-07 1~L2E&S 2.44E-LQ O.OOE+00 9'8E-L3 4.65E-14 1.44E-06 8.74E-LQ 6.20E&5 7'3E&6 liver 4.62E&7 3~79E&6 7.54E&6 8.03E+05 0 OOE+00 1 81E-OS 1.10E-09 8.39E&6 1.68E&5 4 65E-07 8i 71E-07 5.73E-06 1+46E-05 2.03E-LO 1.34E-09 4.47E-OS 6.91E-LL 1.84E-08 0 OOE+00 0 QOE+00 O.OOE+00 O.OOE+00 1 36E-04 3~98E&7 2.29E-07 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+QQ 0.00E+00 O.OOE+00 1~99E-05 1.83E-08 4.59E-06 5.21E-LL 1.18E-07 2;06E-12 5.88E-Q4 O.OOE+00 O.OOE+00~.OOE+00 ST 16E-06.t body 4.62E-07 3.79E-06 7.54E-06 5.53E-OS 6.39E-08 3 56E&6 1.58E-10 2.38E-06 6.77E&6 4.58E-07 1.30E-06 8.41E-06 8.29E-06 8.79E-LL 5.53E-10 2.22E-QS 5 13E-12 l.67E&9 9.49E&6 2.72E&7 2.86E-07 1.46E&8 6~30K&5 2.05K&7 1.47E&7 8.15E-06 1.8SE-03 2.47E-09 2.79E-10 6.30E-Q8 9'0E>>L2 1 L2E&5 3.29E-10 2.9LE&9 1.45E-05 8.36E-09 2.70E&6 1.88E-11 2.3LE-08 2.66E-11 5.80E-.13 4.85E07 2.93E-LO 7.77E-06 3.57E&6 INFANT thyroid kidney 4 62E&7 4.62E-07 3.79E&6 3.79E-06 7.54E-06 7.54E-06 0 QOE+00 O.OOE+00 4.LLEW8 9.45E-09 0 OQE+00 3.56E-06 O.OOE+00 7.86E-1Q O.OQE+00 0.00E+00 0 OOE+00 0~QQE+00 O.OOE+00 0.00E+00 0 OOE+00 0 OOE+00 O.OOE+00 0 OOE+00 O.QOE+QQ...Q.OOE+00 O.OOE+00 O.OOE+00 O.QOE+00 2.84E-09 0 OOE+00 2 32E&5 0 OOE+00 2 87E-11 O.OQE+00'.45E-09 O,OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.QQE+00 O.OOE+00.O.OOE+00 0 OQE+00 Q.OQE+00 OiOOE+00 0'OE+00 O.OOE+00 O.OOE+00 0 OOE+00 O.QQE+00 Q.OOE+00 Q.QOE+00 O.OOE+00 O.OOE+00 O.QOE+00 0.00E+00 O.OOE+00 O.QQE+00 O,OOE+00 0.00E+00 O.OQE+00 Q.QOE+OQ O.OOE+00 Q.OQE+00 O.OOE+00 2.22E&5 O.QOE+00 1.85E-08 O.OOE+00 3'7E-06 O.OOE+00 4.07E-LL O.OOE+00 L.89E&7 O.OOE+00 2.22E-11 O.OOE+00 6.99E-13 O.QOE+OQ 3.Q3E-06 O.OOE+00 6.42E-LA 0.00E+00 7.6LE&5 O.OOE+00 7.80E-06 7.54E-06 O.OOE+00 9.17E-O6 7.14E-04 8.95E-06 6.21E-05 7.25E-04 2.71E-04 5~SSE&4.3~22E-03'A9E-.G4 5.80E-06 6.64E-06 4 62E-04 1.05E-06 l.91E-05 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00&40 O.OOE+00 Q.OOE+00 1.45E-03 8.03E-03 3'6E-05 1.70E&5 1.92E-04 1.99E&6 l.75E-03 1 75E-05 5.46E-O5 1.25E-03 7.88E-05 3.42E-04 2.37E-06 9.63E-05 5.79E-Q7 4.L7E-07 3'4E-04 1.12E-05 8.26E-03 2.62E-03 7.54EW6 1.LSEWS 2.55E-07 5.04E-06 5~12E-05 7.82E-07 1~77E-05 3.47E-06 7.95EW6 2.28E&5 1.73EW6 3.58E-05 1.07E-OS 3.67E-05 9.44E-06 2.92E-05 0,00E+00 0.00E+00 O.OOE+00 0.00E+00 2.L7E&6 2.42K-07 4.87E-08 4.57E-05 9.36E-05 5.24E&5 1.00E<<04 7.43E-05 1.68E-Q6 5'2E-05 9.04E&5 1.19E-O4 1.55E-05 L.QOE-04 9.05E&6 1.92E-05 3.48E&5 1.45E-06 6.03E&7 L.15E-05 3.46E-O5 1.17E-O4 2.36E-05 lung gi-lli 4.62E&7 4.62E-07 3.79E-06 3.79E06 0244p

Table 1.10 (8 of 8)ZNHALATZON DOSE FACTORS.-DFA (mrem/pCi inhaled)RETS Manual Revision 8 Page 144 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 CQ-134 C0-136 C0-137 C8-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 W-187 Np-239 bane 2.71E-05 3.698&5 3.40E-06 1.198-05 1.598-09 1.018-05 5.63E-11 7.628-08 1 248-11 2.668&7 4 548&6 2.718-05 l.218&6 9.46E-O6 6.588&7 2.768-06 2.838&4 3.458W5 3.92E-O4 3.618&7 1.068&9 4.008-05 1~128-10 2.84E-11'.61E-QT 7'68-10 1 98E-05 2.09E-07 2 288-03 1.008&5 3.428-11 5.678&6 9.268-09 2.658-0T liver 3.978-47 3.41E-07 1.428-06 4.93E-06 6.818-10 4.358-06 2 488-11 3.938-08 5.878-12 1~698-07 9e918-06 3'7E-05 2+538-06 1.37E-05 1~.348-06 5 438-06 5 028-04 9'1E-05 4.37E-04 5.588-07 7.Q38-13 4.008&8 7'0E-14 2.368-14 1.438-07 2.698-10 1.19E-05 1.388-07 8.65E-04 3.748-06 1-32E-11 5 818&6 6.448M9 2.378&8 t body.8 568&6 7.7SE-06 4 70E-07 1 48EW6 3.498-10 1.598-06 1.34E-ll 2.59E-OS 3 578-12 1 268&7 3 988&6 1 408W5 8 998-07 4.008-06 4.758-07 1 o 988-06 5 32E-05 3 788-05.3 258-05 2 848-07 3.078-11 2 07E-06 3 558-12 1.408-12 3 688-08 6.468-11 1 428&6 1.588-08 1 268-04 4.998-07 1~72E-12 3 578-07 2.23E-09 1~348-08 ZNFANT thyroid 7.188-08 4.45E-QS 1.168-06 3.48E-06 1~328-09 3.918-06 4.82E-11 6'88-0&1.13E-ll 1.99E-07 1.148-03 1.068-02 1.218&4'.548-03 3'88-05 4.978&4 O.OOE+00 0.008+00 0.008+00 0.008+00 0.008+00 0.008+00 Q.OOE+00 0.008+00 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 kidney 0.008+00 O.OOE+00 O.OQE+00 2 68E-05 3 478&9 2 27E-05 1.25E-10 1.898&T 2.85E-ll 7 39EWT 1.09E-05 3~TOE-05-0;828-06'60E-05 1.49E-06 6 058-06 1.368-04 4 03E-05 1.23E-04 2 938-OT 4 238-13 9~598&9 4.648-14 1 36E-14 O.OQE+00 0.008+00 3.75E-06 4.03E-08 3.848-04 1.418-06 4.808-12 2.258-06 0.008+00 4.738-08 lung gi-lli 1.89E-03 4.22E-05 1.178-03 1.05E-05 3.198-04 9.228-06 9.378-04 1.95E-05 7.398-06 1.74E-05 1.208&3 4.938&5 2.148-46 1.888-05 1.42E-O4 8.518-05 1.47E-06 5.878&6 2 43E-04 3.15E-05 0.008+00 1.42E-06 O.OOE+00 7.56E-07'.008+00" t'i 36E-06-0 OOE+00 1,54E-06 O.OOE+00 9.218&7 O.OQE+00 1 318-06 5.69E-05 9.53E-07 8.408&6 1.028-06 5.098&5 9.53E-Q7 4.678&8 6.26807 4.25E-06 3.64E-05 1.148-03 2.74E-05 2 128&6 3.398&6 l.1LE&6 4.958-07 1.208&4.6.06E-05 5.87E-06 4.25E-05 3.698&4 1.54E-05 8 30E-05 3.55E-O5 7.03E&3 1.06E-04 3.09E-04 2.668&5 1.15E-06 3.06E-06'.30E-04 2.23E-05 2.838-05 2.548>>05 4.258-05 1.78E-05

Reference:

Regulatory Guide 1..109, Table E-1Q.Dose Factors for Co-57, 2n-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5.NOTE: The tritium dose factor far bone is assumed to be equal to the total body dose factor.0244p

RETS Nanual Revision 8 Page 145 Table 1.11 (1 of'2)EXTERNAL DOSE FACTORS FOR STANDING ON CONTANINATED GROUND-DFG (mremfh per pCifm2)Nuclide H-3 C-14 Na-24 P-32 Cr<<51 Ha-54 Ha-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu&4 Zn-65 Zn-69 Zn-69m Br&2 Br-83 Br&4 Br-85 R~6 Rb&8 Rb&9 Sr&9 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m Sb-124 Total Body 0.0 0.0 2i SOE-08 0.0 2i208-10 5.808&9 1~108&8 0.0 S.OOE-09 1.77E-09 7.00E>>09 1.708-08 0.0 3.708-09 1 50E-09 4.008-09 0.0 5.508&9'.18E-OS 6 40E-ll 1.208-08 0.0 6'08-10 3~508&9 1.508-08 5.60E-13 7.108&9 9.008&9 2.208-12 3.808&9 2.408-11 1~608-09 5.70E-10 5.008&9 5.508&9 5.10E-09 8.1IE-09 l.908&9 9.608>>10 2.70E-09 3.608&9 4.508&9 1.508-09 1;SOE-08 2.178-08~m a~'i~'kin 0.0 0.0 2.908-08 0.0 2 608-10 6.808&9, 1.30E-OS 0.0 9.408-09 2.218-09 8.208-09 2~008-08<<0 Q~'.~~~4.308&9 1~708&9 4 60E-09 0.0 6 59E-09 3.90E-08 9.30E-11 1.408&8 0.0 T.208-10 4.008&9 1~808&8 6.50E-13 S.30E-09 1.008&8 2.60E-12 4.40E-09 2.70E-11 1.908-09 7.80E-lo 5~SOE-09 6.40E-09 6.008-09 1.00E-08 2.208-09 1 108-09 3.00E-09 4 20E-09 5.10E-09 1.80E-09 2.10E-08 2.57E-OS 0244p

• '\RETS Manual Revision 8 Page 146 Table 1.11 (2 of 2)EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND-DFG (mrem/h per pCi/m2)Nuclide S'b-125-Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-1,34 I-135 Cs-134 Cs>>136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147 M-187 Np-239 Total Body 5.48E-09 3.50E>>ll 1010E-12 1.00E-11 7'0E-10 7.10E-10 8 40E-09 2 20E-09 1~70E-09 1+40E-08 2m80E-09 1~70E-08 3~70E&9~...:-..-1 60E-08 1 20E-08 le 20E-08 1~50E-08'4.20E-09 2 10E-08 2.40E-09 2.10E-09 4.30E-09 7,90E-09 1.50E-08'.50E-08 5'0K-10 2 20E-09 3'0E-10 0.0...,.: 2.00E-10 1.00E-09 3.10E-09 9.50E-10 Skin I 6'0E-09 4.80E-ll 1.30E-12 1 1QE-11 9.00E-10 8.40E-10 9.90E-09 2.60E-06 2 OOE-09 1.70E-OS 3.40E-09 2.00E-08 4.50E-09..

1 90E-08 1 40E-08 1.40E-08 1.70E-08 4.90E-09 2 40E-08 2.70E&9 2.40E<<09 4.90E&9 9.00E-09 1;70E-08.1.80E-08 6'0E-1.0 2.50E-09 3'0E-10 0.0 2.30E>>10 1~20E-09 3.60E-09 1.10E-09

References:

Regulatory Guide 1.109, Table E-6.Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for External Ex osure to Photon and Electron Radiation from Radionuclides Occurrin in Routine Releases from Nuclear Fuel C cle Facilities D.C.Kocher, Health Physics Volume 38, April 1980.0244p

Table 2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS RETS Manual Revision 8 Page 147 Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Name Wheeler Lake below BFN Wilson Lake Pickwick Lake Beginning TRM 294.0 275.0 260.0 260+0 15930 3,816~800 230 0 15048 705,500 Ending Sise Recreation TRM (acres)visi.ts/year 275.0 26076 1,408,600 ,~/Public Water Supplies Within 50 Mile Radius Downstream of BFN Muscle Shoals, AL Sheffield, AL Cherokee, AL TRM 259~6 254.3 239.2 Population 10s740 13%065 3,400 0244p

Neelide RETS Manual Revision 8 Page 148 Table 2.2 BIOACCUMULATION FACTORS FOR FRESHWATER FISH-B (Page 1 of 1)Neelide 8-3 C-1.4 Na-24 P-32 Cr-51 Ma-54 Ma-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br85 Rb-86 Rb-88 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo>>99 9.0E-01 4.6E+03 1.0E+02 1 OE+05 2.0E+02 4.0E+02 4.0E+02 1.0E+02, 1 OE+02 5.0E+01 5.0E+Ol 5 OE+01 1,0E+02 leOE+02 5 OE+Ol 2.0E+03 2.0E+03 2 OE+03 4.2E+02 4.2E+02 4.2E+02 4.2E+02 2.0K+03 2.0E+03 2.0E+03 5.6E+01 5.6E+Ol 5.6E+01 5.6E+01 2.5E+Ol 2.5E+01 2.5E+01 2.5E+Ol 2.5E+Ol 3.3E+00 3.3E+00 3.0E+04 3.0E+04 1.0E+01 Tc-101 RQ-103 RQ-105 Ru-106 Ag-110m Sb-124 Sb-125 Te<<125m Te-127m Te-127'e-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132'-133 I-134 I-135 Cs-134 Cs-136's-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142 C@-141 Ce-143 C@-144 Pr-143'r-144 Nd-147 W-187 Np-239 1 5E+101 1 OE+01 1 OE+Ol 1.0E+Ol 0 OE+00 1 OE+00 1~OE+00 4.0E+02 4 OE+02 4 OE+02 4.0E+02 4.0E2'-4" OE+02,-~-~--4 OE+02 4.0E+02 4.0E+01 4.OR+01 4.0E+Ol 4 OE+01 4.0E+Ol 4,0E+01 1~9E+03 1.9E+03 1.9E+03 1.9E+03 4.0E+00 4.0K+00 4.0E+00 4.0E+00'.5E+01 2.5E+Ol 1.0E+00 1.0E+00 1.0E+00 2.5E+01 2.5E+Ol 2'E+Ol 1.2E+03 1.0E+01

References:

Bioaccumulation factors for Sb-nuclides are from ORNL-4992,"A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.'12A.Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.All.other nucl.ides'ioaccumulation factors are from Regulatory Guide 1.109, Table A>>l.0244p

TABLE 3.1 (Sheet 1 of 4)ENVIRONME NTAL RADIOLOGICAL MONITORING RETS Manual Revision 8 Page 149 Exposure Pathway~dl d AIRBORNE Particulates Number.of Samples and Locations 6 samples from locations (in different sectors)at or near the site boundary (LM-l, LM-2, LH-3, LH-4, LH-6, and LM-7)2 samples from control locations greater than 10 miles from the plant (RM-1 and RM-6)3 samples from locations in communities approximately 10 miles from the plant (PH-l, PH-2 and PM-3)Sampling and Collection Fre uenc Continuous sampler operation with sample collection as required by dust loading but at least once per 7 days.Type and Frequency of Anal sis Particulate sampler.Analyze for gross beta radioactivity

>24 hrs fallowing filter change.Perform gamma isotopic analysis on each sample when gross beta activity is>10 times the average of control samples.Perform gamma isotopic analysis on composite (by location)sample at least once per 31 days.Radioiodine SOIL DIRECT Same locations as air particulates Samples from same locations as air particulates 2 or more dosimeters placed at locations (in different sectors)at or.near the site boundary in each of the 16 sectors 2 or more dosimeters placed at stations located>5 miles from the plant in each of the 16 sectors Continuous sampler operation I-131 every 7 days with charcoal canister col-.lection at least once per 7 days Once every year;Gamma scan, Sr-89, Sr-90 ance per year At least once per 92 days',.Gamma dose once per 92 days i At least ance per 92 days.Gamma dose once per 92 days.0244p TABLE 3.1 (Sheet 2 of 4)ENVIRONMENTAL RADIOLOGICAL HONITORING RETS Hanual Revision 8 Page 150 g Exposure Pathway Number of Samples and~dl Locations 2 or more dosimeters in at least 8 additional locations of special interest Sampling and Collection Fre uenc Type and Frequency of Anal sis NTERBQRNE Surface Drinking 1 sample upstream (TRH 305.0)1 sample immediately down-stream of discharge (TRM 293.5)1 sample downstream from plant (TRH 285.2)1 sample at the first potable surface water supply downstream from the plant (TRH 282.6)2 additional samples of pot-able surface water downstream from the plant (TRH 274.9 and TRH 259.5)I 1 sample at a control location (TRH 306)Collected by automatic sequential-type sampler with composite sample taken at least once per 31 daysa.Collected by automatic sequential-type sampler with composite sample taken at least once per 31 daysa c 1 Grab sample taken at least once per 31 days Gamma scan at least once per 31 days.Composite for tritium at least once per 92 days Gross beta and'gamma scan at least once per 31 days.Composite for Sr-89, Sr-90, and tritium at least once per 92 days.Gross beta and gamma scan at least once per 31 days.Composite for Sr-89 and Sr-90 and tritium at least once per 92 days a Composite samples shall be collected by collecting an aliquot at intervals'not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.b The surface water control sample shall be considered a control for the drirlking water sample.c This assumes that the nearest drinking water intake is>3.0 mile downstream of the plant discharge.

If a drinking water intake is constructed within 3.0 mlles downstream of the plant dischar e sam li and analysis shall be every 2 weeks.0244p

, TABLE 3.1 (Sheet 3 of 4)ENVIRONMENTAL RADIOLOGICAL MONITORING Exposure Pathway Number of Samples and Sampling and~dl Locations.Collection Fre uenc 1 addit onal symple at a con-Collected by automat c trol location o (TRH 305)sequential-type sampler with composite sample taken at least once per 31 days a RETS Hanual Revision 8 Page 151 Type and Frequency of Anal sis GROUND 1 sample ad)acent to the plant (well 46).1 sample at a control location upgradient from the plant (Farm L)Collected by automatic se-quential type sampler with composite sample taken at least once per 31 days.Grab sample taken at least once per 31 days..Composite for gamma scan Sr-89, Sr-90, and tritium at lease once per 92 days.Composite for gamma scan Sr-89, Sr-90 and tritium at least once per 92 days.AQUATIC Sediment.2 samples upstream from discharge point (TRH 297.0 and TRH 307.52)i sample in immediate down-stream area of discharge point (TRH 293.7)2 additional samples down-stream from the plant (TRH 288.78 and 277.98)At least once per 184 days Gamma scan, Sr-89, and Sr-90 analyses.1 At least once per 184 days'amma scan, Sr-89 and Sr-90 analyses INGESTION Hilk 02440 At least 3 samples from dairy farms in the immediate vicinity of the plant (Farms B, L and Bn)At least 1 sample from control locations (Farm Gl or Be)At least once per 15 days'i Gamma scan and I-131 on each when animals are on pasture;sample.Sr-89 and Sr-90 at at least one per 31 days least once per 31 days at other times.

l.l Sampling and Collection Fre uenc At least once per 184 days 3 samples representing commercial and game species in Hheeler Reservoir near the plant TABLE 3.1 (Sheet 4 of 4)ENVIROHHENTAI RADIOLOGICAL MONITORING Exposure Pathway Number of Samples and~dl S Locations Fish 3 samples representing commercial and game species in Guntersvi lie Reservoir above the plant RETS Manual Revision 8 Page 152 Type and Frequency of Anal sis Gamma scan at least once per 184 days on edible portions, Clams Fruits 5 Vegetables 1 sample downstream from the discharge.

1 sample upstream from the plant.(No permanent stations established; depends on availability of clams.)Samples of food crops such as corn, green beans, tomatoes,.and potatoes grown at private gardens and/or farms in the immediate vicinity of the plant At least once per 184 days Gamma scan on flesh only At least once per year at Gamma scan on edible orti time of harvest e e por on 1 sample of each of the same foods grown at greater than 10 miles distance from the plant Vegetation Samples from farms producing (pasturage)

~ilk but not providing a milk sample (Farm T)Once per 31 days I-131, gamma scan once per 31 days.Sr-89 and Sr-90 analysis on the last monthly sample of each quarter.0244p Control samples from 1 remote air monitor (RM-1)and 1 control dairy farm (Farm G-1}

i RETS Manual Revision 8 Page 153 TABLE 3.2 A BROWNS FERRY NUCLEAR PLANT Environmental Radiological Monitoring Program Sampling Locations Approximate Indicator (I)Location Number a Station Sector 1 2 3 4 5 6 7 8 9 10 11 12 13 14 18 22 23 24 25 26 27 28 29 30 31 32 33 34 36 37 NM NE SSE M M E N NNE ENE NNW SSW NNW N ENE PM-1 PM-2 PM-3 LN-7 RM-1 RM-6 LN-1 LM-2 LM-3 LN-4 LN-6 Farm B Farm Bn Farm L Farm Gl MSW Mell 06 NW TRNc 282.6 TRN 303.0 Muscle Shoals, AL M TRM 274.9 TRN 285 2 TRN 293.5 TRM 305.0 TRM 307.52 TRM 293.7 TRN 288.78 TRM 277.98 Farm Be NW Farm T MNM TRM 297.0 Wheeler Reservoir (TRM 275-349)'untersville Reservoir (TRM 349-424)Distance or Samples 13.8 I AP,CF,S 10 9 I AP,CF,S 8.2 I AP, CF, S 2.1 I APs CF, S 31 3 C AP,CF,S 24.2 C AP,CF, S 0.97 I AP,CF,S 0.88 I APs CF, S 0 92 I APs CFs S 1~7 I APs CFs S 3.0 I~AP, CF, S 6.8~'--..'-'I=~*" M-.~5,0 I M 5.9 I MsW 35 C M, V 0.02 I W'1.4d I PW 12.0 C PW 31.3.I PW 19.1d I PW s.sd I SM 0.5d I SM 11 Od Ce'W 13.52<<C CL, SD 0.3d I CL, SD 5.22d I CLs SD 16 02d I GLs SD 28.8 C M 3.2 V C SD I/O Fs CL c d e S~Soil SM~Surface Mater V~Vegetation See figures 3.1, 3.2, and 3.3 Sample codes: AP~Air particulate filter CF~Charcoal Filter F~Fish W~Well Mater" TRM~Tennessee River Nile Miles from plant discharge (TRN 294)Also used as a control for public eater>>SD~Sediment CL~Clams PM~Public Water 0244p TABLE 3;2 B BROWNS FERRY NUCLEAR PLANT Thermoluminescent Dosimetry Locations RETS Nanual Revision 8 Page 154 Nap Location Number 1 2 3 5 6 7 8 9 10 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 68 69 Stetiau NW-3 NE-3 SSE-2 W-3 E-3 N-1 NNE-1 ENE>>I NNW-2 N-2 NNE-2 NNE-3 NE-I NE<<2 ENE-2 E-1 E-2 ESE-1 ESE-2 SE-1 SE-2 SSE-1 S-l S-2 SSM-2 SSM-2 SW-1 SW-2 SW-3 WSM-1 MSM-2 WSM-3 W-1 W-2 W4 WNM-1 WNW-2 NW-1 NW-2 NNM-1 NNW-3 teeter NW NE SSE W E N WNW ENE NNW N NNE NNE NE NE ENE E E ESE ESE SE SE SSE S S SSM SSM SM SW SM MSW WSM WSM W M M WNW WNW NM NM NNM NNW Approximate Distance 13.8 10.9 8.2 31.3 24.2 0 97 0.88 0 92 1.7~.-SeO-" 0.7 5.2 0.8 5.0 6'0.8 5 2 0 9 3.0 Oe5 5.4 5.i.3.1 4.8 3.0 4,4 1.9 4.7 6.0 2.7 5'10.5 1.9 4'32.1 3.3 4,4 2.2 5.3 1.0 5.2~~r/Onsite (On)*or Offsite Off Off Off Of f'ff Off On On On On Off Off Off Off Off Off Off Off Off Off OEE Off On OEE OEE Off Off Off On Off Off Off OEE Off Off OEE TLDs designated onsite are those located two miles or less from the plant.TLDs designated offsite are those located more than two miles Erom the plant plant.0244p TABLE 3'RETS Manual Revision 8 Page 155 maximum Values for the Lour Limit of Detection (LLD)a~c (Sheet 1 of 2)Airborne Particulate Fish Water or Gases (pCi/kg,\tM M I Food Products Sediment Milk (pCi/kg, (pCi/kg, LR I)gross beta 4 2QQO 0.01 N/A N/A N/A N/A N/A N/A N/A N/A N/A Ma-54 Fe-59 15 30 N/A N/A 130 260 N/A N/A'" N/A~r'~~~N/A N/A N/A Co-58s 60 15 NIA 130 N/A N/A N/A Zn-65 Zr-95 Nb-95 I-131 Cs-134 Cs-137 Ba-140 La-140 30 30 15 lb 15 18 60 15 N/A N/A AN/A 0.07 Q.Q5 0.06 NIA N/A 260 N/A N/A N/A 130 150 N/A , N/A N/A N/A 15 18 60 15 N/A N/A N/A 60 60 80 N/A N/A N/A N/A N/A N/A 150 180 N/A N/A 0244p T+%I~>'r rrrr~ryla'f, er%ra I rlr r s~.4 1~~~~~

TABLE 3'RETS Manual Revision 8 Page 156 Maximum Values for the Lower Limit of Detection (LLD)abc (Sheet 2 of 2)Table Notation The LLD i,s the smallest concentration of radioactive material in a sample that will be detected with 95 percent probabili,ty with 5 percent probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system, whi.ch may include radiochemical separation:

Where: LLD sb E V 2.22 Y 4t Typical E V 2.22 X exp(-X4t)//~e~is the"a priori." lower limit of detection as defined above, (as picocuries per uni,t mass or volume).is the standard deviation of the background counting rate or of the counting rate of a,blank sample as appropriate, (as counts per minute).is the counting efficiency, (as counts per disintegration).

is the sample size (in units of mass or volume).is the number of disintegrations per minute per picocurie.

is the fractional radiochemical yield, (when applicable).

is the radioactive decay constant for the particular radionuclide, and for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples).values of E, V, X, and 4t should be used in the calculation.

It should be recognised that the LlD ds defined as an~ardort (bedore the fact)limit representing the capability of a measurement system and not as<<o<<b LLD for analysis of drinking water and surface water samples shall be performed by gaama spectroscopy at approximately 15 pCi/L.If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant, or in the event of an unanticipated release of I-131, drinking water samples wi.l'1 be analyzed at an LLD of 1.0 pCi/L for I-131.Other peaks which are measurable and identi,fiable shall be identified and reported.0244p

Figure 1.1 Land Site Boundary RETS Manual Revision 8 Page 157~z I I, Ci i I jl i I'I'i.Ci*I'C~~~e Sr W~~~)~~Oy'e~~i~C'..~"",~.:.." C~i P;r e BFÃ/4 i I, V w i CC~" ,~g tg'A'245p~~

0

~m~I Iaaae~~IIaasey~

t I P"1 4 I<1'4 Figure 1.2-BFH Offgas System and SGTS Effluent Monitoring RETS Manual Revision 8 Page 158 g~-~y>Elevated Release (600)from common stack FI90-271 RH 90-147 h6B~~D$ytion (l of 3)~Condenser From SGTS (commIon)Recombiners Steam.Packing Fxhsuster tlech;-Vacuum Pump I ll2 hL l 8000 cuft Iloldup Volumo 0245p I~a I~~~~~

Figure 1.3-BFN Normal Building Ventllatton RETS Manual Revision 8 Page.159'eRoof Fena iui 90-249 Turbine Deck AH 90-251 lf RH 90-2S0 Refuel l'loor from Primary Containment Purge gystcm r From Raduastu X Bi lldbig Turbine Building.(Typical.for each unit)Control Bay Reactor Bui]ding (Typical;fur each<<nit)Lo SAi'8 (emergency vcut Ilnliu>>)I~Roof Fans used seasonally tu cunt'rol temperature 0245p

.~~" J-~cy F)gure 1.4 (Sheet l of 4)RETS Manual Rev)s)on 8 Page 160 1.0 0.9 0.8 0.7 E3 R g 0.8 0.6 R 0 0.4 lC 0.3 0.2 0.1~I~0245p 0.1 1.0 10.0 PLt JME TAAVEL DISTANCE (KILOMETEAS)

~~100.0 2M.O pfuma Daplatfon EIIact lor Ground Laval Balan<as (All Atmost4ar jc~~~.we I f'

Figure 1.4 (Sheet 2 of 4)RETS Manual Revts1on 8 Page 161 r~1.0 0.9 NEUTRAL t)STAS LE lEFO w 0.8 D 0.7 C5 R g 0.6 0.5 z 0 0.4 IL 0.3 UNSTABL f A,B,C)'-0.2 0.1 0245p 0.1 1.0)0.0 PLUME TAAVEL DISTANCE fKILOME'TEAS)

Plttttte Ocplctlott Elfcct (or 30ttl Aelealcs (Lcttcti denote Pe>qttill Rt~titt tris I'I~eel 100.0 200.0

Figure 1.4 (Sheet 3 of 4)RETS Manual Revision 8 Page 162 1.0 0.9 STABI.E-tE,F,O).0.8 D 0.7 C9 R g 0.6 LO ps R O+04 K 0.3 EUTftaL (D)UNSTABLE (A,B,C)~f 0.2 0.1 0245p 0.1 1.0 10.0 PL(JME TI1AVEL DISTANCE (KILOMETEflS)

Plurne Dcplction Elfcct Ior 60m Ilclcc<cs (Letters<<lcnoto~I~e~e~~~~~~~100.0 200.0

F1gur~t.4 (Sheet 4 Of 4)etio Hanual RevIston 8 Page 163 1.0 0.9 NEUTR L (O)o, 1 l a 0.8 D 0,7 C9.R 0.6 0.5 R 0 o 0.4 fL O.0.3 STABLE tE,F,G)NOOEIL TION (FRACTION REMAINING~'I 0 UN iA STABLE ,B,C)O,Z 0.1 Q245p 1.0 10.0~PLIIME TRAVEL DISTANCE (KII.OMETERS)

Plaane Doplcalon 0((aos lor 100aa Bolaosos 1leoars alone le Paaqaalll Ssablllsy Class)100.0 200.0+Qf ga'gpg~ratpr

~4j~p+5m'Q~Saaa/s r.co+g.~.~s"grs..jryn~J'ppi ay.acr'pear'If a a.'".err'r).I 1M P I'+r~'P"'*

Figure 1.5 RETS Manual Revision 8 Page 164 1000.~~I I I I I I I~I~~~~I I~I~100 I~I I I I I I I I I 10 0.1 1.0 10 PLUME TRAVEL OlSTANCE (KlLOMETERS)

Figure 1.Ver.ical Standard Deviation of Material in a Plume (Letters dinote Patouill Stabilitv C;assi 0245p

Figure 1.6 (Sheet 1 of 4)RETS Manual Revision 8 Page 165~~~~~~~~~~~~~I~~~I~~I I I h~I I~I I~~~I I I I I I I II I I I I I I I II I I I~I I I~I I I I I I ill I I I I I I III I I I i i I I Ii I I I IIIIII I I I I IIIII I.I I I IIIII I I I IIIII-I I I I IIIII I I I I h I I I~I~I I I~I I~I I~~I i I I i I I I I i I I II I.I I I I I~l I I i I I I II I I I I>4 III"-.~I".I..I 3 I<iI I I I I IIIII I-I I!I I II I I I I I I I:I l.h I C~~CO es~Q~~I I I I I I~i i~~1"ghi~~~~~~~~I I I I~~~~I I i I Ill'I i i I I I lhhl I I I~~I lil I I II~'.I" I~I I I II.I.I I Iil'I I~I I I l I I~I I I I I i I I I I II I I I I I I I I.I I II I~I I I I I i I I I I III I I I I I I II I I I I'I I I I I...CA~La:-:,............

boa~.Zaa<Pt.UM 8 TRAV H.DISTANCh (Ktl.gM~Rg

~~Relanve Oeyaetioa tor CrouacI~ggaaaae (AIt AImo~mc.z~0245p C\~~

o Figure 1.6 (Sheet 2 of 4)RETS Manual Revision 8 Page 166~&0 1W~~I I I~~~I I I III~I I~I~~~g~~I I I'.I I I I~fee el~0~I I lt I I I I I I I I lit I I I I ill!!I I!!Ii~"I 10 UNSTABLE (A I g,C)I NEU I~i 1 I~I I I I I I I l I I I III!1J I Ct'W Ul I Lg NK RAL (0)STABLE I I STABLE (E,F,a I" I 10 7 0.1.1.0 10.0.'00.0 200.0 PLUME TRAVEL OISTANCE (KILOMETERS]

Relative Oeposition for 30m Releases (Letters denote Pasqui!I Stab!!ivy Class)0245p

Figure 1.6 (Sheet 3 of 4)RETS Manual Revision 8 Page 167~r~I s s I UNSTABLE (A,B C)~~~~~I I 1 I I~I I I I I I I III I I I I I Iiii i I I I i'I Il\I I f rl 1 p I f I f ff 1 T~1M.Ct: I a 1M l Cl.NEUTRAL (O)~r~~N~~~~I I I I I I I II'I UNSTAB I~I i.I I~~I I I I)I}I 10 7 STABLE (E,l'.G)~~I I I~r II ,1 1 1 f rj ,0-8 0.1 1.0 10.0'00.0 200.0 PLUME TRAVEL DISTANCE (KlLOMETERSi

~Relative Geposition

'or 60m Releasee (Lettea denote Pasquill Stabilicy Claa)sf'.":;;'0245p r , f 1~~~~1Pr~Kf ff fA~

0

>~Figure 1.6 (Sheet 4 of 4)RETS Nanual Revision 8 Page 168~~~I~~I~I~I I~~I~~'I~e I~I I I I I I I I i I.I I I II I I I VNSTABLE (A,B,C)l)I I~~I~I I i I ll f'I I I Ilii I l I Ill NEUTRAL (D)I I I~~~I I II I I I~~~~I I I I I 10-7 SrABLE (E,e,a)I NO OEPLETlON I~~~I~~I I I I I I I I I'.1-I,-'0 0: "-r:~-PLUME TRAVEL DlSTANCE (KlLQMETERQ 100.0 Zp0.p Relative Deposition for tppm Releases (Letters denote PasquiII Stabilicy Class)'245p'

~~~0 I~'0 P~0~~$~i 00 0~'4"0 0~~~-0~00r 0~'00-00000~~0~00~$00~g Q Q g Revf s)on 8--Page 169 0 00~>~~\~0~~~~0~0 s~0~~~0~~5~~~~~1~'i 40~~~~~~~~~00~~~~0 0(~0 0 5~~V>>igS I lIIt I (IIII ,~C I 0 e 0>>I.I: CNl~o v~...~V r r r Q rr or rr'r 5 r r r~.QONLb'>>%04.r r r~')55~i til<<~~I 0.'0 l~(~iO lllllllT ggii~~<<5 lillO(l.0 5(fllAOl i Al V ll 0245p c~~0 ill(Q~~0'0=-h~@hrq

~~~.'ill ll~~~~~~0~~~,C"~,~" 0~~0 0~

'C 1 C.~::-.=':,.=.::;

-::-.Br owns Fer r j Liquid-(Typical Unit and Common RadMaste)Condenier Cooling Mater-..;='-.,=;,'-,.'.".-,.-"-'-RETS Hanua1---:-':-.=;,-.--=;-'-.-.-'..=:.:.

Revels)on S Page 170 Effluent Moni toi s RHR Service Mater intake Bay i.oop l$4 90"i33 (3)Loo 2 rgt 90-i3a-90>>i32 Turbine Buildin Reactor Building Aaduaate (coaaan)AH 90"i30 Cate Cate I Opening for Helper Mode~~0245p 1 Turbine Bulldlng Equipment 2 Reactor Bulldlng Equipment 3 Condenser To Cooling Towers Cate Slowdown From Cooling To were Dlffuaer

~'f~

RETS Hanual Revlslon S Page ill BFN Liquid Radwaste Tr eatment System Floor Drains Floor Grain Collsc tar Flasr Drsln Filter Floor Drain Sample Tsnks Fx-n~o~o-iso Eqiiyasnt s ns launch y N sin Tanks Msste Collector Tank.Qsste Filter Masts Dsilnsrslizs ifsste Ssiple Tanks Condsnsste Storsgs Tanks 0245p Figure 3.1 RETS Manual Revision 8 Page 172 Environmental Radiological Sampling Locations Within 0 Mile of Plant 34B.rS<N NN%.326 2'1 0.25 NNE 33.T5 343 75 C wc'+eoC e g Xl ENE 281 20 IB 75 i I I 25B.T5 238.25 BROWNS FMRY NUCLEAR PLANT rl.s4 s.25~5 i ESE 123.75 213,75 I SSW'S 1'25:0 148.25 SSE C Ba.rS Scale t~0245p.~IL.4P P~g.d~~

Figure 3.2 RETS Manual Revision 8 Page 173~<<O Environmental

'Radiological Samptrng Locations~From 1 to 6 Miles From The Plant~~Oi47$~~<<<<.~~.O RJS d%ls f~4~%J~sOt<<5 4, 555 11 5Q da.~55W~54"~I)ILlS~~~~O O~~~~liL25~~~~~555~~~0245p'<<<<~O'~.O.<<<<~.~,O(OO~~<<~'4~<<O~

~'

I I f II44~~Figure 3'RETS Manual Revision 8 Page 174 Environmental Radiological Sampling Locations".Greater Than 6 Miles From The Plant 4 It I" I~\I'I ,I 30L7 r~~33.75 PA~Cta~g'2514<<Uf 4 ,'5L75 I ,I.213.75 8 I a'I CW I I I I;,"" 0$45p'*'\~'I 4 101.25>>46 15L7d 14L25 123.75 SCALE Pa!

(i 1 t RETS Manual Revision 8 Page l75 RETS MANUAL Section IV PROCESS CONTROL PROGRAM PCP~~

RETS Manual Revisi.on 8 Page 176 l:

1.0 INTRODUCTION

'.l Sco e/lk This Process Control Program (PCP)is applicable to radioactive waste solidification and dewatering of wet solid radioactive wastes generated as a result of the operation and maintenance'f Browns Ferry Nuclear Plant.This PCP is not applicable to the treatment of mixed wastes.2e3~,l 1.2~Pur ese/'I,.'he PCP provides those controls necessary to ensure that disposal:..criteria are met by BFN processing techniques or by vendor'".supplied systems, if used for dewatering,qr,.gaol'i'difjcation.

,'2e0 DEFINITIONS k'2.1 Absorb-To take liquid in through pores, or as if through pores or interstices of a material.k 2.2 Absorbent>>Media or material used to absorb li.quid.k k k Batch-An isolated quantity of waste to be processed having constant physical and chemical characteristics.

2e4 Container-The primary receptacle in which processed wastes (dewatered, solidified or absorbed)are packaged for disposal.2.5 Dewatered-Wet solid wastes which have had excess water removed.k 2'6 Free Liquid-Uncombined liquid not bound by the solid matrix of the solid waste mass;capable of flowing..2 7-Homogeneous,-

Of.uniform composition; the waste is uniformly ,distributed throughout the container.

,/J I 2.8-Liquid waste-For the purposes of this PCP, any aqueous or non-aqueous radioactive liquid which requires solidification or absorption before disposal.This may include oils, chemicals, water or other liquids unsuitable for in-plant clean-up or , treatment.

s IV-2/'II l k ,',;;-,.

'I 0245p V'/,, i:/~h pk/\~ekrgvse/esvvTe 2k'eekkek I/k'Tl'///CN/'

/////I p/v bee e~Qeesss k ho'I/ekr/Iks e/e,/e//e//k ee/per/%cere/es'v

~, e/%ek e~

RETS Manual Revision 8 Page.177 2.9 Mixed waste-Low level radioactive wastes containing chemical constituents which are hazardous under Environmental Protection Agency regulations in 40 CFR Part 261.2.10 Solidification agent-Material, which when mixed in prescribed proportions with liquid or wet solid wastes, can form a free standing product with no free liquid.2.11 Solidify-To immobilize by use of a solidification agent o th d whi ch converts the liquid or wet.solid waste to a free standing monolithic solid.I 2.12 Stability-A property of the waste form such that it is able to maintain its structural integrity under the expected disposal ,conditions; stabilized waste should~intafn'ts gross-physical , prope'rties and identity over a 300 year period.v.~0 2,13 Wet solid wastes>>Spent powdered ion exchange resins, filter aid sludge, bead ion exchange resins, and other sludges or slurries consisting of liquids with a high insoluble solid content."

3.0 REFERENCES

3.1 Code of Federal Regulations (CFR)Title 10, Parts 20, 61, and 71[10 CFR 20, 10 CFR 61, and 10 CFR 71]-Energy 3.2 3 3 v 3 4 Code of Federal Regulations (CFR)Title-49[49 CFR]-Transportation Browns Ferry Nuclear Plant Final Safety Analysis Report, Volume 4, Chapter 9.3, Solid Radwaste system Browns Ferry Nuclear Plant Technical Specifications (BFN Tech Spec)4.8.F.1, 3.8.F.l 6 3.8.F.2, 6.10.l.f, and 6 11.1, 2&3 3.5 TVA Office of Nuclear Power Radioactive Material Shipment M 1 (RMSM)en anua 3.6 v')~Ii I I I v I V 1'I 3.7 Nuclear Regulatory Commission (NRC)Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983, Rev.0 Nuclear Regulatory Commission (NRC)Technical Position on Waste Form, May 1983, Rev.0 t IV-3 1)0245p,, F i)VV V~V V I'I'I.)C vv.vvtv'4v

RETS Manual Revision 8 Page 178 4 0 WASTE CHARACTERISTICS 4.1 Waste Streams Three general waste streams applicable to this PCP have been identified for Browns Ferry.These are the Condensate Waste Phase D Separator (CWPS), Reactor Mater Cleanup Phase Separator (RWCV)d ry Active waste (DAM)~Other waste streams may be established

, an based upon plant operational needs.I(p g CWPS is fed by several waste sub-streams, including the Equipment Drain, Chemical Waste, Floor Drain, Fuel Pool Cooling, and Condensate systems.">>RMCU is fed by Reactor Mater Cleanup only.h.,'DAM is used for wastes generated within tice'regulated arees of the'eactor buildings and turbine buildings which cannot be"appropriately attributed to either RWCV or CWPS.DAM normal.ly includes paper, plastic, wood, metal and other such material generated as a result of the operation and maintenance of the plant.Waste Form Met solid radioactive wastes consist of bead resins, filter aids (such as activated charcoals ox carbons), powdered resins, and slurries or sludges.f h N t I I'hn I I h h h h Wastes which may require solidification-may include, but are not limited to, l.iquids which cannot be processed using installed plant'systems, oils, chemicals, aqueous filter media, and decontamination wastes.Wastes are processed as appropriate to ensure that the minimum physical characteristics required by 10 CFR and disposal site criteria are met.All Class B and Class C waste is stabilized.

On occasion, Class A waste (such as aqueous filter media with a concentration

>1 uCi/cc of isotopes with half-lives

>5 years)may be solidified or stabilized by BFN.Class A liquid wastes may be either solidified or packaged in sufficient absorbent material to absorb twice the volume of the liquid, as appropriate to the specific disposal site criteria or license requirements.

Tests are performed on those wastes which are solidified to th'e o ensure t e adequacy of the solidification agent.and procedural technique.

These tests are made on a minimum of three samples from each waste batch to be solidified.

IV-4-"024Sp h hl, RETS Manual Revision 8 Page 179 4.3 Waste Classification Scaling factors which relate hard-to-measure isotopes to key isotopes commonly measured at BFN have been developed for each waste stream.These scaling factors are used in the classification of the waste for disposal.Scaling factors may be developed on an as needed basis depending on changing plant operationaL conditions.

Updates are performed at least every two years for waste normally considered to be Class A, on an annual basis for other wastes, or when the scaling factors are considered to be high or low by a factor of ten.'I't I y J'1 5.0 Batch samples, separator samples, or sludge samples are taken for radiochemical analysis prior to processing the waste for shipment.DAW samples or area smears are taken to establish the relative percent abundance of isotopes for the DAW waste stream.a Materials which do not fit within the scope of existing scaling factors and waste streams are sampled.The samples are sent offsite for analysis and development of scaling factors prior to disposal of the materials., SHIPMENT MANI FESTS 5~1 Manifest Pre aration Manifests are prepared for each shipment of radioactive waste for disposal.Programmatic guidance for manifest preparation is provided'through the TVA Office of Nuclear Power, Radwaste Branch to ensure that all 10 CFR and 49 CFR criteria are met.Procedures for manifest preparation implement the specific requirements of 10 CFR 20 311, Transfer for Disposal and Manifests.

5'Manifest Trackin t'-Acknowledgment.

of receipt for each shipment to a disposal site is sent to BFN Water&Waste Processing Group by the disposal site.Shipments for which acknowledgment is not received within the time 1imits allowed in 10 CFR 20.311 are traced by the TVA Office of Nuclear Power, Radwaste Branch.I'I)IV-5 y*

RETS Manual Revisxon 8 Page l80 6.0 ADMINISTRATIVE CONTROLS 6.1 Procedures and Surveillance Detailed procedures are written and maintained by BFN which cover plant process systems, waste packaging, and shipment requirements.

Surveillance Instructions are used to verify that plant Technical Specifications for waste processing are met'.Personnel involved in processing radioactive waste for shipment are trained in site procedures, regulatory requirements, and disposal site criteria.Training and retraining sessions are held when'eeded to support operations.

Retraining is required on an annual basis to maintain qualification.

Personnel found not complying with procedures may have thei.r qualifications revoked by the Water and Waste Processing Group Supervisor, if deemed necessary.

Qualifications may be reestablished through completion of retraining, and approval of the Water&Waste Processing Group Supervisor.

Programnatic guidance is provided through the TVA Office of Nuclear Power, Radwaste Branch The Radwaste Branch maintains the Radioactive Mater'ial Shipment Manual and the Package Quality Assurance Program (for packages.licensed under 10 CFR 71).'.'.2 lit Assurance/

lit Control Quality assurance audits are conduct'ed'by'he"BFN s'ice Q'unity ,',*,',;..',',.'ssurance organisation, and by the TVA Division of Nuclear Quality Assurance.(DNQA}.Audit findings are r'eviewed by BFN management,.ensuring prompt, corrective actions when needed.~~Quality control measures include quarterly tests of the resin dewatering system performed by BFN personnel upon actual dewatered High Integrity Containers (HICs)or liners, site review of all radwaste vendor procedures before use, and second party verification by BFN personnel of end points or acceptance criteria in vendor procedures.

Quality control of solidi.fication methods is performed through controlled testing of a minimum of three samples from each batch to be solidified.

Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria f 6.3~Traiafn ,I l<v IV-6 J I'".0245p*oQ hf pig~qt~lgjsV~f l(y p 8~1~h f.-~

6.4 Retention of Records RETS Manual Revision 8 Page 181 Records are maintained to furnish documentation of items or activities affecting quality.Quality assurance records are stored in accordance with plant instructions and the TVA Nuclear Quality Assurance Manual.Retention times for radwaste records are established in the Radioactive Material Shipment Manual.Il , 7.0 II,-: '..: '..";,,',.

I'J II I I I Pl I'l II I 1 f 1 APPENDICES 7.1 Solidification Descri tion Topical Report

Reference:

None System or method in uses None~~sr Plant/Equipment Interfaces:

None Dewaterin Descri tion 7'Topical Report References DW-11118-01-P-A, Chem Nuclear Systems, Inc., CNSI Dewatering Control Process Containers, and RDS-25506-01-P, Chem Nuclear Systems, Inc., RDS-1000 Radioactive Waste Dewatering System, Rev.0 NOTE: See appended letter of interim approval from NRC to TVA of May 6, 1988.I\I Plant/Equipment Interfacess See appended letters of February 11, 1987 and October 16, 1987 from TVA to NRC.'RIMS OL44 870211 808 and IPL44 871016 807).System or method in uses Vacuum dewatering using portable air'riven diaphragm pumps and 10 HP electric high vacuum pump;and/or, Vacuum dewatering/high speed drying using the CNSI RDS-1000 Radioactive Waste Dewatering System I II I,II 1 I'I I'I*I"...-;<,'4 0245p ll'-4 I, IV-7 RETS Manual Revision 8 Page 182 02;QvS F 4M T4fC LaokoaaC, ylace iph7 r>>Ooakat idea 50 X59>><<0>>CSC<<C~Z9C I*~F U.S Vcac" mac'eaumsoc, C~eLon ,, ht c ocaen Ccns<L 0eax-';CffLse of Mc'aar.Seas ot Kaq+Lat'on.F-,,:;,:...'"~"'F,',",~eatkonc

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RETS iMnual Revision 8 Page 184 ENCLOSURE Dewatering is conducted at BFN using plant equipment and plant personnel.

Chem-Nuclear Systems, Inc., (CNSI)high-integrity containers and the CNSI dewatering procedures are used.1~EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT DATED DECENBER 1983.BFN dewaters powdered resin, filter media, and mixtures of powdered resin with small quantities of bead resin (normally less than 10 percent bead resin)using Chem-Nuclear Procedure FO-OP-022,"Ecodex Precoat(PowdexlSolka-Floe/Diatomaceous Earth Dewatering Procedure for CNSX 14-195 or Small Liners." The dewatering system was fabricated by TVA to meet the equipment specifications in FO-OP-022.

The TVA dewatering system differs from the Chem-Nuclear system in that: (a)TVA's system has no off-gas collector~--The-high integri4y-containers are open to the waste packaging room air during filling and dewatering.

Air from this room is normally discharged through the Radwaste Building ventilation system.This air then flows through a HEPA filter and is released through a monitored release point on the Reactor Building roof.(b)(c)The valves on the pump suction manifold are manually operated.The system is not operated remotely.However, the high integrity containers are enclosed behind a shielded wall or inside a shielded cask during filling and dewatering to keep radiation levels in the vicinity of the system near background.

There are no vacuum gauges at each inlet connection.

A single vacuum gauge is provided at the flush inlet connection to the manifold.This vacuum gauge will indicate a break in vacuum in any active (not isolated)filter set.Loss of vacuum normally occurs in sequence from the top to the bottom set of filters.When vacuum breaks at a given filter level, that level is isolated.Therefore, vacuum is monitored continually for all active filter'ets.(d)There is no automatic level control or level indicating instrument in the TVA dewatering system.Level is determined by visual observations.

TVA has conducted tests which conclude that mixtures of bead and powdered resin, in proportions of up to 50-percent bead, can be adequately dewatered using a modified procedure for dewatering powdered resin.These tests were conducted using TVA-fabricated steel 1iners with dewatering internaLs similar to those found in the Chem-Nuclear high-integrity containers and a dewatering pump which is inferior to that IV-10 K 0245p 1.~~i%}',.~i<

4v'.~bw~..'~..~~~~~~-~

RETS Manual Revision 8 Page 185 has specified in FO-OP-022, in that it is limited to a vacuum of 13" H s a flov rate of six SCFM.In addition, the dewatering procedure used uum o g and for the tests called for only four hours of bulk dewatering, as opposed to three eight-hour pumping cycles specified in FO-OP-022.

The conditions of the test were clearly less conducive to proper dewatering

'han those specified in FO-OP-022, (this equipment and procedure is not used for normal operation).

However, results shov that adequate devatering is guaranteed either by extending the dewatering time in the procedure or by applying an additional dewatering cycle at the end of the bulk dewate'ring process using a high flov rate (approximately 200 SCFM at 28" Hg)vacuum pump.TVA has modified FO-OP-022 to include two hours of additional dewatering vith the 200 SCFM vacuum pump for all resin.2 INTERFACES BETMEEN PLANT AND CNSI EQUIPMENT w/(a)The high-integrity container is filled'with'spent'esih slurry through a one-inch flexible hose.Flov.through the hose is controlled by way of a diaphragm-operated valve..The hose is connected to the high-integrity container vith an Evertight quick disconnect fitting that has been modified for remote operation.(b)The devatering pump discharges through a one-inch flexible hose t t he plant vaste packaging drain header vhich leads to the waste e ose o package drain tank.The connection to the header is made by an OPM 633 D Kamlock quick disconnect fitting.(c)Radwaste compressed air is supplied through a flexible hose with Chicago connections to the air operated positive displacement pump.(d)Demineralized vater is provided by a flexible hose with Chicago connections to the flush-inlet valve on the devatering pump suction~nifold.(e)The dewatering system is located inside the radwaste.packaging room (see figure 1).Any leaks or spills vill be contained inside this room by exterior doors which are closed during filling, and collected in radwaste floor drains.Failure of any of these resin processing components vill not provide a path~ay for radioactive materials into the environment or potable water supply.'~LOCATION AND ARRANGEMENT OF DEMATERINQ SYSTEM IN PLANT See Figure l.IU-11 0245p 1 ,>>-~q y'n!'g.awg g z~Awk~'ACE~

S RETS Manual Revision 8 Page 186 4.WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations are determined by direct measurement.

Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis.An inferential measurement program is, then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured.Scaling factors.are developed on a waste stream specific basis.Scaling factors are periodically reconfirmed through sampling and analysis.A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.5~DESCRIPTION OF WASTE CONTAINER , High-integrity containers manufactured by CNSI are used, for packaging resin.The following containers are used:"~120;14-195 14-170-and are'iscussed in a topical report dated December 1983 entitled,"Chem-Nuclear

'Systems, Inc., Topical'eport Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP

~" 6~CAPABILITY TO MEET 10 CFR 50 APP'ENDIX I This dewatering process does not cause any direct releases to the environment (note l.a above).IU>>12 g r./'0245p ih f'w+M iisw<q;~~'~<om-llllC104f Syolon>~iMol44~'i I l4'I>>~~I1 1101~100011~OOOOOOO~001 1~001000~)~I p~~~gg<lClI~y~I~~~~ooooooyooooi 18 lt.i~~~I~~>iI)I Wls~~~~~~~y~+0~~~~\g~~~~~~~~~Haste Packaging Room l.ayout for Chem Nuclear system Plan Elevation 565'~" 0245pIV-13 RETS Manual Revision 8 Page 188 5H 1578 Lookout place QQ(7 6 1R&7 U.~nuclear Regulatory Connnission Document Control Desk Mashingtan, D C.20555 Centlemenc

~>>Za the Hatter of Tennessee Valley Authority BROWSES FER3 RUaxaa Pum.(RFR)-BESZ7f DEMATMXRC)Docket Sos 50 259)50 260'50 296 PROCESS CONTROL PROCKQt FOR DEHL7ERALZ~

Sy letter f~me to D R Huller.dated February L'1987, TVh described'ts process cental program for demineraliser resin devatering and requested Fzc to reviev end a~rrove it as described ia that Latter.This resin devater'-g process vas tim~onsucnin8.

C?cen~uclear Systems Znc.(MSZ)has since improved this process by developing the RDS-1000, Rapid Deva~~&$ystem, for accelerathtg the devateehag process The time savings.ia this.dewaterm8 process viLL alLov SN.to aeccnnmodstm.4,ts spent resin generated@wag povec.ymchxctiaa TVh katends to hnplement the RDS IOOct+racess.before Vinit 2~.costar.The@afore~~submittaL supersedes the February..LI.

L9&$'1.atter..

aconseqaenbgy, Tvh has elected not to ansver HRd's bluest for idditi.anal information from J.*.Xvolinski to S h QhLta dated ZuLy 2I.1987 eoncening 3FI s current devat~process ia a'.separate submittalo Havever~these items are addressed ia the eacLosures to this Letter for the RDS-1400 system.Demiaeraliser resin dewater~vilL be performed at BFS using~Z aquipman.The operatcc8 methodology outlined by CEZ ia tapicaL raper~DQ-LLLL&>>OL-?-h.

~Devatering Central process Containers Topical Raper" and RDS-25506-01;p,"RD$1000 Radioactive Qaate Devatarin8 System" vill be used.HRC accepted CLSZ Topical Raper" DQ-LIII&I&h for reference by License applicants ia a letter fram C 0 Thames (lRC)to L X Poppe (~)dated Juae II~1985 C5Z Topical Report RDS 2550MI p vas submitted to NC by CSSZ for approval by letter frcna Q S>>House (~)to R L~Each (RC)dated Sarah 26~1987 and a nonpeqcrietsry copy is enclosed to this Letter (encLosure 2)~These CNZ topical reports vtLL fora the basis of the Qpg demineral&

resin devater~c process sad system Enclosure 1 provides information recpcired by SEC to revkev applicabU3.ty of the report to specific Licensees as outlined, ia the safety evaluation tor~Topical Report QV 1III&%1-p A.Procedures for this nev process and system are scheduled to be eternally approved by October 1987~TVh requests that IRC reviev the enclosed information and provide approval, vitMa this sama:-,'".-.-

tWfrsmeq far'se af this report aa a process control program as 4 the RFM technical specification 6~9~."',~,'~.~'~'"wa'g~~l IV-14 S 0245p

Q.S.nuclear Regulatory Casssssission RETS Manual Revision 8 Page 189 00"6'-'ycnL have any questions concerning this tequest, please t elaphone j J Z Turner at.(N)729 2853~4sa Enclosect 9 a check for the SdO revief fee requi ed by 10 QR 170.~~Very t~ly yours, T HHESSc~VŽ~AlPiHOR"~~~0 0 00~~~~~R ey, D actor:,Ruclear.

Wcerraing and Regulatory hf ayers~~-Sssbs~e4 an+cn to-aa on~s~Ca of c,.r Notacy Puh,'Kccrrsksrtoa ecpirrr to me 1987'~rir'I$0~~~Cnclasuras'sL (Eackosuras):

~~~0~~~~~~~0~~0~0~~~~~~~~0~~00rf*0A~fP~~00~~0~~~~~I~~~~~~~rr~~~~~~0~~~~0 Hc'Ci C Xechf Assistant Directo Regional Znsp actions'C,vision of TVA Prospects.Office of Special Projects C.S Ruclezu.Regulatory Commission Region ZZ 10I~etta St~HQ, Suite 2900-""----.Atlanta f'eorgia 30323 Re 4 A.WlinskL, Assistant Director foe'rojects Division of TV'A Projects Office of Special Pro)ects 10Sr nuclear'egulatory Cos?osission 4X50 East&est Highsfay Ce4 322 Bethesda,~land 20814 Brains Ferry Resident Xnspector Bcoffns E'erry Nuclear Plant Route 2, P 0.hox 3Q Athens, hlahasssa 554?1 I f~~~IV-15~~0245p A~*"E"I I ,'dll-~

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~~~~~I~I I~~

0 ENCLOSURE 1 RETS Manual Revision 8 Page 191 I Dewatering will be conducted at BFN using the Chem-Nuclear Systems, Inc.(CNSI)Rapid Dewatering System (RDS-1000).

CNSI high-integrity containers and/or steel liners and plant specific versions of CNSI Procedure FO-Op-032,"Setup and Operating Procedure for the RDS-1000 Unit" and CNSI Procedure FO-OP-035,"Setup and Operating Procedure for Dewatering Pre-Coat Media in a 21-300 Liner Using the RDS-1.000" will be used.1.EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORTS DW<<llll8-Ol--

RDS-25506&1-P 1-P-A AND TVA's system has no off-gas system connection available for interface with the RDS-100Q.The rapid dewatering skid of the RDS>>1000 system has a HEPA filter installed downstream of the safety relief valve and manual bypass valve.Liners will be vented through this HEPA filter to the waste packaging room.Air from this room is normally discharged'hrough the radwaste building ventilation system.This ale thin flows throughwn nstalled HEPA filter before release through a monitored release point on the reactor building roof.Exterior doors from the waste packaging room are closed during liner filling and dewatering operations.

2 INTERFACES BETWEEN PLANT AND CNSI'EQUIPMENT II A A plant connection stand (PCS)is provided as part of the RDS-1000 system.Its components are: 1.A remotely operated valve to control influent to the liner;2.A diaphragm pump with connections to tire liner fillhead for initial gross dewatering; 3.Manifolds for air and service water supplies to control elements and flushing systems.B.Radwaste building compressed service air will be provided to the PCS at approximately 40 SCFM at 80 psig (+20,-lO psig)throu h a flexibl e hose.The connection to plant air and water is made via roug a quick-disconnect fittings.The PCS connection to CNSI equipment is also a quick-disconnect fitting.IV-1.7 Q245p r t I c',t I i)

RETS Manual Revision 8 Page 192 C.Radwaste building service water (demineralized) will be provided to the PCS at approximately 25 gpm at 80 psig (+20 psig)through a flexible hose.Both connection points (plant and PCS)are equipped with quick-disconnect fi.ttings.

D.The dewatering pump discharge is provided by a 1.5 inch flexible hose to the p:.ant waste packaging drain header which leads to the waste package drain tank.The connection to the drain header is made by a 1-inch Kamlock quick-disconnect fitting.The dewatering pump connection is a 1.5 inch Kamlock quick-disconnect fitting.A 1 to 1.5-inch Kamlock adaptor will be used at the drain header.E.The connection to the plant waste media line will be made either by a 1 5-inch 150 ANSI flat faced flange connection or by a flange connection to Kamlock quick-disconnect adaptor-utilizing..existing flexible hose.A waste isolation valve will be installed downstream of this connection, providing local control by the CNSI operator over the flow of waste to the liners being filled.The waste isolation is controlled remotely, and is interlocked to close on high'waste level, high-high level, decreasing

'air pressure, or loss of electrical power.I 3~LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT See Figure 1 The RDS-1000 system will be located inside the radwaste packaging room, elevation 565'.Any leaks or spills will be contained inside this room by exterior doors, which are closed during liner filling and dewatering operations.

Any spillage will be collected in the radwaste floor drains.Failure of any of these resin processing components will not provide a pat/way for radioactive materials into the environment or potable water supply.IV-18'0245p

'

RETS Manual Revision 8 Page 193~3~t 4>>WASTE CLASSIFICATION TO MEET 10 CFR 61'5 e y rect measurement.

Samples Radionuclide concentrations are determined by direct or smears, as appropriate, of standard waste streams reams are sent ofrsite for analysis.An inferential measurement program is then established whereby concentrations, of radioisotopes whi.ch cannot be dil e rea y measured are projected through ratioing to concentrations of similarly behaving ng actors are developed on isotopes which can be readily measured.Scaling fa t d a waste stream specific basis.Scaling factors are periodically reconfirmed through sampling and anaLysis.Computerized calculation of individual container isotopic contents is performed.

Ma t testin orme.xntenance, data mani ulation.ng, and independent verification of this program t i ogram ascerta n correct man pu a on.TVA QA audits of the vendor laboratory conducting the periodi,c sample analysis confirm quali.ty practices at that location.Procedural controls, corporate assessments of the-d" ,*-" riodic h-ra waste progdain,*-" per o c Q audits of the program, and management evaluation of audit findings ensure quality in the plant program.5.DESCRIPTION OF HASTE CONTAINER~~High-integrity containers manufactured by CNSI are used for packaging resin The foLlowing containers are used: 8-120,14-195, and 14-170.They are discussed in a topical report dated December 1983 entitled,"Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity w t~'ontainers CNSI-HIC-14571-01-NP." CNSI 21-300 t 1 li stee ners are compatible wi h the dewatering system and may also be used.6.CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewaterin g process does not cause any direct releases to the environmenQ.

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RETS Manual Revision 8 Page 196 fear.S A.Mhfte Nay 6, r98O~$~If vou have any oues fons concernfno thfs fssue, p1ease ccn-act your Pro.=: Hanaaer, G.Gears at 301%92-0767.

Sfncere)y, cc: See nex-paoe Robert A.Herarann, Ac fna Assfstant Dfr:"r TVA Progecw Qfvfsfon Offfce ot Soecfal Progeca IV-22 LAST PAGE 0245p

~i ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT RADIOLOGICAL IMPACT ASSESSMENT REPORT JULY THROUGH DECEMBER 1989 9QQ3P9P446

.

Page 1 of 53 ENCLOSURE 1 Radiological Impact Assessment Browns Ferry Nuclear Plant July-December 1989 INTRODUCTIO Potential doses to maximum individuals and the population around Browns Ferry are calculated for each quarter as required in Section F.2 of the Radiological Effluent Manual.Measured plant releases for the reporting period are used to estimate these doses.Dispersion of radioactive effluents in the environment is estimated in accordance with the guidance provided by Regulatory Guides 1.109, l.ill and 1.113 using meteorological data and riverflow data measured during the period.Using dose calculation methodologies which are described in detail in the Browns Ferry Offsite Dose Calculation Manual, the doses are calculated and used to determine compliance with the dose limits contained in Browns Ferry's Operating License.In this report, the doses resulting from releases are described and compared to quarterly and annual limits established for Browns Ferry.S RY OF LI UID A GASEOUS EFFLUENT RELEASES-SECOND HALF 1 8 Although nuclear plants are designed to contain the radioactive material created by the fission rocess small amounts of this P l material escape from the fuel rods.Also, very small amounts of the structures and components of the systems become activated through the bombardment of neutrons and are worn away.This radioactive material can be transported throughout plant systems and released to the environment.

Airborne Re eases The noble gas fission products do not mix with water and are given off in a gaseous form.A very small amount of solid radioactivity is given off along with these noble gases.The most significant releases are processed so that the radioactive material is filtered and/or decayed prior to release through the plant vents.Sampling and monitoring methods are used to determine the amount of radioactive material released.If these methods indicate that radioactivity in airborne effluents is above preset limits, then releases are terminated.

Airborne releases for each quarter in the period are given in Section 1 of this submittal.

Li uid Releases Some small amounts of radioactive material migrate into the primary coolant water.The primary coolant water is routed through a purification system to remove most of these particles; however, not all are removed.Some of the radioactive liquids may leak from pipes or valves in the system.These liquids are collected in floor ll P&r,ii Page,2 of 53 and equipment drains and sumps.The collected liquids are then processed through a clean-up system, composed of storage tanks, recycling systems, and demineralizers, to remove contaminants.

The purified water is then monitored to determine the amount of radioactive material remaining in the water prior to its release.Steps are taken to ensure that the amount of radioactivity released to the environment is as low as reasonably achievable (ALARA).If the levels of radioactivity are above preset limits, the releases are circulated through the clean-up system again for additional processing.

Radioactivity released from the plant into the Tennessee River is quantified prior to release.Liquid releases for each quarter in the period are given in enclosure 1 of this submittal.

Effluent Monitorin Plant paths through which radioactivity is released are monitored.

These monitors record the radiation levels for each release.Monitors which are used for liquid releases will automatically alarm and stop any release which is above regulatory limits.Gaseous release monitors also provide alarming mechanisms to allow for the termination of any release above limits.DOSE LIMITS The U.S.Nuclear Regulatory Commission (NRC)requires nuclear power plants to be designed, built, and operated in such a way that the levels of radioactive material released into unrestricted areas is as low as reasonably achievable (ALARA).To ensure that, this is done, the plant's operating license includes Technical Specifications which govern the release, of radioactivity.

These Technical Specifications specify limits for the release of radioactive effluents, as well as limits for doses to the general public from the release of these effluents.

These limits are set well below the NRC lOCFR20 limits which govern the concentrations of radioactivity and exposures permissible in unrestricted areas.This ensures that radioactive effluent releases are ALARA.The Technical Specification limits for doses at or beyond thesite boundary from airborne noble gases releases are: Less than or equal to 5 mrad per quarter and 10 mrad per year (per reactor unit)for gamma radiation,-and-Less than or equal to 10 mrad per quarter and 20 mrad per year (per reactor unit)for beta radiation.

I'1 l Page 3 of 53 The Technical Specification limit for the dose to a member of the general public at or beyond the site boundary from iodines and particulates released in airborne effluents is: Less than or equal to 7.5 mrem per quarter and 15 mrem per year (per reactor unit)to any organ.The Technical Specification limit for doses to a member of the general public from radioactive material in liquid effluents released to unrestricted areas, is: Less than or equal to 1.5 mrem per quarter and 3 mrem per year (per reactor unit)to the total body,-and-Less than or equal to 5 mrem per quarter and 10 mrem per year (per reactor unit)to any organ The EPA limits for total dose to the public in the vicinity of a nuclear power plant, established in the Environmental Dose Standard of 40 CFR 190, are: Less than or equal to 25 mrem per year to the total body, Less than or equal to 75 mrem per year to the thyroid,-and-Less than or equal to 25 mrem per year to any other organ.DOSE CALCULA 0 S Estimated doses to the public are determined using computer models (the Gaseous Effluent Licensing Code[GELC]and the Quarterly Water Dose Assessment Code[QWATA]).These models are based on guidance provided by the NRC (in Regulatory Guides 1.109, l.ill and 1.113)for determining the potential dose to individuals and populations living in the vicinity of the plant.The area around the plant is analyzed to determine the pathways through which the public may receive a dose.The doses calculated are a representation of the dose to a"maximum exposed individual." Some of the factors used in these calculations (such as ingestion rates)are maximum values.Many of these factors are obtained from NUREG/CR-1004.

The values chosen will tend to overestimate the dose to this"maximum" person.The expected dose to actual individuals is lower.The calculation methods and results of the calculations are presented in the following sections.

L" Page 4 of 53 DOSES FROM AIRBOR EFFLUE S For airborne effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direct'radiation from radioactivity deposited on the ground, inhalation of airborne radioactivity, ingestion of vegetation which contains radioactivity deposited from the atmosphere, and ingestion of milk and beef which contains radioactivity deposited from the atmosphere onto vegetation which is then eaten by milk and beef animals.The concentrations of radioactivity in the air and the soil are estimated by the computer model GELC which uses the actual meteorological conditions to determine the distribution of the effluents in the atmosphere.

Again, as many of the parameters as possible are based on actual site specific data.The model that is used to estimate dose, as well as the parameters input to the model, is described in detail in Section 1.0 of the Browns Ferry Nuclear Plant Offsite Dose Calculation Manual.Meteorological variables at Browns Ferry are measured continuously.

Measurements collected include wind speed, wind direction, and temperature at heights of 10, 46 and 91 meters above the ground.Quarterly joint frequency distributions (JFDs)are calculated for each release point using the appropriate levels of meteorological data.A joint frequency distribution gives the percentage of the time in a quarter that the wind is blowing out of a particular upwind compass sector in a particular range of wind speeds for a given stability class A through G.The wind speeds are divided into nine wind speed ranges.Calms are distributed by direction in proportion to the distribution of noncalm wind directions less than 0.7 m/s (1.5 mph).Stability classes are determined from the vertical temperature difference between two measurement levels.There are four routine release points from Browns Ferry Nuclear Plant: the turbine building, the radwaste building, the reactor building, and the stack.Releases from the turbine building are considered ground-level releases to determine the dispersion of the airborne effluents.

The ground-level JFD is derived from windspeeds and directions measured 10 meters above ground and from the vertical temperature difference between 10 and 46 meters.

ry Page 5 of 53 Releases from the radwaste and reactor buildings are considered split-level releases to determine the dispersion of the airborne effluents.

This means that portions of the release are treated as elevated while other portions are considered ground-level depending on the ratio of the vertical exit velocity to the horizontal wind speed.The split-.level dispersion approach is implemented using a model that requires two complete quarterly JFDs for each effluent vent, one for the elevated releases and one for the ground-level releases.The ground-level portion of the split-level JFD is based on wind speeds and directions measured 10 meters above ground-level and from the vertical temperature difference between 10 and 46 meters.The elevated portion of the split-level JFD is based on wind speeds and direction measurements at the 46-meter level and the vertical temperature difference between 46 and 91 meters.Releases from the stack are considered elevated-level releases to determine the dispersion of the airborne effluents.

The JFDs for elevated releases are based on wind directions and wind speeds measured at 91 meters and the vertical temperature difference between 46 and 91 meters.The generally open terrain around BFN is not believed to cause any significant effects on the transport and dispersion of gaseous effluents from the plant.Within 30 kilometers of BFN, the terrain is mostly gently rolling hills (30-60 meters).Between 30 and 80 kilometers the hills become larger to the north and south, and mountainous to the east and northeast.

The Tennessee River/Wheeler Lake may have a minor effect on transport and dispersion in the immediate vicinity of BFN during periods of winds with a southerly component, overcast skies, and relatively high wind speeds.Then, the lower layer (10-46 meters)stability class tends to be more stable than would be expected.However, during this infrequent condition, dose estimates will be conservative.

l'~.

Enclosure l Page 6 of 53 External Ex osure Dose-Airborne Effluents Dose estimates for maximum external air exposures (gamma-air and beta-air doses)are made for points at and beyond the site boundary.These doses are calculated for all'receptor points shown on Table 3.The reported dose is chosen for the offsite location with the highest calculated exposure during the quarter.The doses calculated for Browns Ferry Nuclear Plant for each quarter are shown below.Individual Doses from Airborne Effluents External Air Exposures (mrad)Dose Location Third uarter 1 q Air dose 3 Air dose O.OE-OO mrad O.OE-OO mrad All locations All locations Fourth uarter 1 q Air dose 8 Air dose O.OE-OO mrad O.OE-OO mrad All locations All locations

<<p~h I pl 0 Page 7 of 53 Submersion Dose-Airborne Effluents External doses to the skin and total body, due to submersion in a cloud of noble gases, are estimated for the nearest residence in each sector.These doses are calculated based on the reported releases for noble gases'or all receptor points shown on Table 3.The highest of these exposures is chosen and is assumed to be the maximum individual dose.The submersion doses calculated for Browns Ferry Nuclear Plant for each quarter are shown below.Individual Doses from Airborne Effluents Submersion Exposures (mrem)Third uarter 1 Dose Location Total Body Skin O.OE-OO mrem O.OE-OO mrem All locations All locations Fourth uarter 1 Total Body Skin O.OE-OO mrem O.OE-OO mrem All locations All locations 4 1 Page 8 of 53 Or an Dose-Airborne EffluentsInternal doses to organs due to releases of airborne effluents are estimated for the inhalation, ground contamination, and ingestion pathways.The ingestion pathway is further divided into four possible contributing pathways: ingestion of cow/goat'milk, ingestion of beef, and ingestion of vegetables.

Doses from applicable pathways are calculated for each real receptor location defined in Table 3.Doses are calculated based on the reported iodine and particulate releases.To determine the maximum organ'ose, the dose contribution from the three pathways are summed for each receptor.For the ingestion dose, however, only those pathways that exist for each receptor are considered in the sum, i.e., milk ingestion doses are included only for locations where milk is consumed without commercial preparation and vegetable ingestion is included only for those locations where a garden is identified.

To conservatively account for beef ingestion, a beef ingestion dose equal to that for the highest site boundary location is added to each identified receptor.For ground contamination, the dose added to the organ dose being calculated is the total body dose calculated for that location, i.e., it is assumed that the dose to an individual organ is equal to the total body dose.The organ doses calculated for Browns Ferry Nuclear Plant for each quarter are shown below.Individual Doses from Airborne Effluents Maximum Organ (mrem)rd uarter 1 Organ Bone Age Group Child Dose 2.2E-04 mrem Individual Pathway Contributions:

Vegetable Ingestion>

1.9E-04 Beef Ingestion 2 6.0E-06 Inhalationl 2.9E-06 Ground Contaminationl 1.9E-05 Milk Ingestion N/A Fourth uarter 1 Thyroid Child 1.6E-05 mrem Individual Pathway Contributions:

Vegetable Ingestion3 1.1E-05 Beef Ingestion4 5.9E-07 Inhalation>

4.0E-06 Ground Contamination3 O.OE-OO Milk Ingestion N/A Maximum real receptor is located 2 Calculated for the site boundary 3 Maximum real receptor is located 4 Calculated for the site boundary at 1829 meters in the NNW sector.at 2275 meters in the HW sector.at 1829 meters in the NNW sector.at 1650 meters in the NNW sector.

E a>w J Page 9 of 53 Dose Su a-irborne Effluents The table below gives a comparison of the calculated quarterly doses to their respective limits.Doses from Airborne Effluents-Second Half 1989 Browns Ferry Nuclear Plant Dose Pathway Airborne-Gamma Air Dose Quarter Dose 3 O.OE-OO mrad 4 O.OE-OO mrad Quarterly Limit*5 mrad Percent of Limit 0%0%Airborne-Beta Air Dose 3 O.OE-OO mrad 4 O.OE-OO mrad 10 mrad 0%0%Airborne-Max Organ Dose 3 2.2E-04 mrem 4 1.6E-05 mrem 7.5 mrem 1%1%*Since airborne releases are quantified on a per site basis, and the Technical Specification dose limits are given on a per unit basis, calculated airborne doses are initially compared to the per unit limit.If this limit is exceeded, the release data is reanalyzed to determine which portion of the releases were attributable to each reactor unit.Then these per,unit releases can be used to calculate per unit doses which are compared to the per unit dose limits.As is shown by the table, all calculated quarterly doses were well below the allowable limits established in Browns Ferry's Technical Specifications.

For a comparison to previous releases and doses, graphs are presented as Figures 1 and 2 which show corresponding airborne releases and doses for the period 1980 to the present.

• I~~~~~I,,~l, E i w g~r, QAe, d Ql Page 10 of 53 DOSES FROM LI UID EFFLU S For liquid effluents, the public can be exposed to radiation from three sources: the ingestion of water from the Tennessee River, the ingestion of fish caught in the Tennessee River, and direct exposure from radioactive material deposited in the river sediment (recreation).

The concentrations of radioactivity in the Tennessee River are estimated by a computer model which uses measured hydraulic data downstream of Browns Ferry.Parameters used to determine the doses are based on guidance given by the NRC (in Regulatory Guides 1.109)for maximum ingestion rates, exposure times, etc.Wherever possible, parameters used in the dose calculation are site specific use factors determined by TVA.The models that are used to estimate doses, as well as the parameters input to the models, are described in the Browns Ferry Nuclear Plant Offsite Dose Calculation Manual.Li uid Release Points and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous.

Routine t liquid releases from Browns Ferry, located at Tennessee River Mile.294, are made through diffusers which extend into the Tennessee River.It is assumed that releases to the river through these diffusers will initially be entrained in one-fifth of the water which flows past the plant.The QWATA code makes the assumption that this mixing condition holds true until the water is completely mixed at the first downstream dam, at Tennessee River Mile 283.0.The average river flows past the plant site were 55,185 ft3/s for the third quarter of 1989 and 74,047 ft3/s for the fourth quarter.Dose Estimates-Li uid Effluents Doses are calculated for recreation, consumption of fish, and drinking water for locations between the plant site and the mouth of the Tennessee River.The maximum potential recreation dose is calculated for a location immediately downstream from the plant outfall.The maximum individual dose from ingestion of fish is assumed to be that calculated for the consumption of fish caught anywhere between the plant and the.first downstream dam (Wheeler Dam).The maximum individual dose from drinking water is assumed to be that calculated at the nearest downstream public water supply

'I Page ll of 53 (Champion Paper Company).This could be interpreted as indicating that the maximum individual, as assumed for liquid releases from Browns Ferry, is an individual who obtains all of his drinking water at the Champion Paper Company, consumes 21 kg (6.9 kg for a child)per'ear of fish caught from the Tennessee River between BFN and Wheeler Dam, and spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year standing on the shoreline just below the outfall from Browns Ferry.Dose estimates for the maximum individual due to liquid effluents for each quarter in the.period are presented below.Individual Doses from Liquid Effluents (mrem)ird ua te 1 Organ Total Body Age Group Adult Dose 7.5E-03 mrem Individual Pathway Contributions:

Mater Ingestion 3.7E-05 Fish Ingestion 6.8E-03 Recreation 5.8E-04 Liver Adult 1.1E-02 mrem Individual Pathway Contributions:

Water Ingestion 5.3E-05 Fish Ingestion 1.0E-02 Recreation 5.8E-04 ou th uarter 1 Total Body Adult 4.3E-03 mrem Individual Pathway Contributions:

Mater Ingestion 2.0E-05 Fish Ingestion 4.0E-03 Recreation 3.1E-04 Liver Teen 6.3E-03 mrem Individual Pathway Contributions:

Water Ingestion 2.7E-05 Fish Ingestion 6.0E-03 Recreation 3.1E-04 J Page 12 of 53 Dose Summa-Li uid E fluents The table below gives a comparison of the calculated liquid doses for the period to their respective quarterly limits.Doses from Liquid Effluents-Second Half 1989 Browns Ferry Nuclear Plant Dose Pathway Quarter Dose Quarterly Limit*Percent of Quarterly Limit Liquid-Max Organ Dose 4 4.3E-03 mrem 3 1.1E-02 mrem 4 6.3E-03 mrem Liquid-Total Body Dose 3 7.5E-03 mrem 4.5 mrem 15 mrem 1%1%1%1%*The quarterly limit for liquid doses is the total site dose limit (the one-unit dose limit times 3).This is because all liquid radwaste systems are common to all 3 units and the releases cannot be attributed to one particular reactor unit.As is shown by the table, all calculated quarterly doses were well below the allowable limits established in Browns Ferry's Technical Specifications.

For a comparison to previous releases and doses, graphs are presented as Figure 3 which shows corresponding liquid releases and doses for the period 1980 to the present.

gl+~ Page 13 of 53 POPULAT 0 DOSES Population doses for highest exposed organ due to airborne effluents are calculated for an estimated 627,000 persons living within a 50-mile radius of the plant site.Ingestion population doses are calculated assuming that each individual consumes milk, vegetables, and meat produced with the sector annulus in which he resides.Doses from external pathways and inhalation are based on the 50-mile human population distribution.

Population doses for total body and the maximum exposed organ due to liquid effluents are calculated for the entire downstream Tennessee River Population.

Water ingestion population doses are calculated using actual population figures for downstream public water supplies.Fish ingestion population doses are calculated assuming that all sport fish caught in the Tennessee River are consumed by the Tennessee River population.

Recreation population doses are calculated using actual recreational data on the number of shoreline visits at downstream locations.

Population dose estimates for airborne and liquid effluents are presented below.Browns Fer uclear Plant Po ulation Doses-Second Half 1 Third Quarter 1989 Total Body Dose Maximum Organ Dose (organ)Liquid Airborne 6.4E-02 man-rem 2.1E-04 man-rem 9.8E-02 man-rem (liver)3.9E-04 man-rem (bone)Fourth Quarter 1989 Liquid Airborne 3.0E-02 man-rem 2.5E-05 man-rem 4.9E-02 man-rem (liver)2.5E-05 man-rem (thyroid)Population doses can be compared to the natural background dose for the entire 50-mile population of about 56,430 man-rem/yr (based on 90 mrem/year for natural background).

0" pe Page 14 of 53 DIRECT RADIATIO External gamma radiation levels were measured by thermolumines'cent dosimeters (TLDs)deployed around BFN.The quarterly gamma radiation levels determined from these TLDs during this reporting period averaged approximately 17.0 mR/quarter at onsite stations and approximately 15.2 mR/quarter at offsite stations, or approximately 1.8 mR/quarter higher onsite than at offsite stations.This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than the levels offsite.This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite.the mass of concrete employed in the construction of the plants, or other undetermined influences.

Fluctuations in natural background dose rates and in TLD readings tend to mask any small increments which may be due to plant operations.

Thus, there was no identifiable increase in dose-rate levels attributable to direct radiation from plant equipment and/or gaseous effluents.

DOSE TO MB S OF THE PUBLIC INSIDE T E SITE BOU R No routine activities within the site boundary by members of the public have been identified which would lead to their radiation exposure.TOTAL DOSE To determi ne compliance with 40 CFR 190, annual total dose contributions to the maximum-individual from BFN radioactive effluents and all other nearby uranium fuel cycle sources are considered.

The annual dose to any organ other than thyroid for the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each quarter, the critical organ dose (for any organ other than the thyroid)from airborne effluents for each quarter from ground contamination, inhalation and ingestion, the total body dose from liquid effluents for each quarter, the maximum organ dose (for any organ other than the thyroid)from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program.This dose is compared to the 40 CFR 190 limit for total body or any t organ dose (other than thyroid)to determine compliance.

j~c PtC 4 Page 15 of 53 The annual thyroid dose to the maximum individual is conservatively estimated by summing the following doses: the total body air submersion dose for each quarter, the thyroid dose from airborne effluents for each quarter, the total body dose from liquid effluents for each quarter, the thyroid dose from liquid effluents for each quarter, and any identifiable increase in direct radiation dose levels as measured by the environmental monitoring program.This dose is compared to the 40 CFR 190 limit for thyroid dose to determine compliance.

Cumulative annual total doses are presented in the following section of this report.Total Dose from Fuel Cycle-Calendar Year 1989 Browns Ferry Nuclear Plant Dose First Quarter Total Bod or an Or an Dose (mrem)(except thyroid)Total body air submersion dose O.OE-OO Critical organ dose,(airborne) 1.7E-06 Total body dose (liquid)6.9E-03 Maximum organ dose (liquid)1.0E-02 Direct radiation dose O.OE-OO O.OE-OO 9.1E-04 7.5E-03 1.1E-02 O.OE-OO O.OE-OO 2.2E-04 7.5E-03 1.1E-02 O.OE-OO Second Third Quarter Quarter Fourth Quarter O.OE-OO 1.6E-05 4.3E-03 6.3E-03'.OE-OO Total 1.7E-02 1.9E-02 1.9E-02 1.1E-02 Cumulative Total Dose (Total Body or other organ)mrem 6.6E-02 Total body air submersion dose Thyroid dose (airborne)

Total body dose (liquid)Thyroid dose (liquid)Direct radiation dose O.OE-,OO 1.7E-06 6.9E-03 6.6E-04 O.OE-OO O.OE-OO 4.7E-04 7.5E-03 7.1E-04 O.OE-OO O.OE-OO 3.1E-05 7.5E-03 5.9E-04 O.OE-OO O.OE-OO 1.6E-05 4.3E-03 3.1E-04 O.OE-OO Total (Thyroid)7.6E-03 8.7E-03 8.1E-03 4.6E-03 Cumulative Total Dose (Thyroid)mrem 2.9E-02 ri4'E i J Page 16 of 53 CO CLUSIO As a result of operation of Browns Ferry Nuclear Plant for the second half of 1989, radioactive effluents were released to the atmosphere and the Tennessee River.The released radioactivity resulted in estimated potential doses to the public which are well below the Technical Specification Limits and Regulatory Guidance.Cumulative doses for the calendar year are given below'along with a comparison to the respective annual limits for the doses.Cumulative Doses from Effluents-Calendar Year 1989 Browns Ferry Nuclear Plant Dose Pathway Airborne-Gamma Air Dose Airborne-Beta Air Dose Airborne-Max Organ Dose Liquid-Total Body Dose Liquid-Max Organ Dose Dose O.OE-OO mrad O.OE-OO mrad 1.1E-03 mrem 2.6E-02 mrem 3.8E-02 mrem 2.9E-02 mrem Annual Limit 10 mradl 20 mradl 15 mreml 9 mrem2 30 mrem2 75 mrem Percent of Annual Limit 0%0%1%<1%1%<1%Total Dose-Total Body or Organ other than Thyroid 6.6E-02 mrem 25 mrem 1%Since"airborne releases are quantified on a per site basis, and the Technical Specification dose limits are given on a per unit basis, calculated airborne doses are initially compared to the per unit limit.If this limit is exceeded, the release data is reanalyzed to determine which portion of the releases were attributable to each reactor unit.Then these per unit releases can be used to calculate per unit doses which are compared to the per unit dose limits.The quarterly Technical Specification limit for liquid doses is the total site dose limit (the one-unit dose limit times 3).This is because all liquid radwaste systems are common to all 3 units and the releases cannot be attributed to one particular reactor unit.

Oc g'l a~l BFN Rad Impact July-Dec 1989 Page 17 of 53 TABLE 1A (page 1 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JOINT PCRCCNTAOC FRC UCNCXC5 OF WIND 5ttCD ST WIND DXRCCTXON FOR STASILITT CLA$5 A (DCXTA TC>>1~9 C/100 ((l SRDNNS FtRRT NUCLEAR PLANT JVL 1~$9 5tt 30~$9 MIND DXRCCTZON N NNC Nt CNC E$5C SC$5C 5 SSN 5'N W5N N MNW CA(J(0,0 0.0 0,0 0.0 4.0 4.0 0,0 0.0 0'0 0 0.0 0.0 0,0 0't NN 0.0 NNW 4,0 5USTOTAL 0.0 0.6 1.4 0~0 0.0 0~0 0.0 0'0.0 0'0'0~0 0~0 0'0~0 0'0~0 0~0 0.0 0~0 1.$3.4 4.0 0,0 0.0 0.0 0,0 4.051 1.279 1$42 l.$9~1 177 0.409 0~0$1 0,051 0~0$1 0.0 0~0 I.IOT 0~102 0.051 0.0 0 0 0~051 0~461 1~3IZ 0'61 0~I TO 0.563 0 F 665 0'5I 0 4DP 0~102 0.35$0~051 0.154 0,256 0~154 0,0 0.0 0,3$I 0~0 0 0 0.0 0,0 0.0 0~1$4 0 1S(0~20$0.614 0 15~0,61~0.512 0 205 0 0 0,0 0 0 0,0$1 0,0 0 0 0,0 0,0 0,0 0 0 0'DAN 09 0~102 0~0 0~205-0.051 0.0 0'0'DE 0 0,0 0'0,0 0.0 0~0 0 0 0~0 0'DE 0 5~IIS 2.201 t~$94 0.256 MZND StttD(NPN3 3.5 5.4 5$7.~7.5 12 4 12.5 1$.4 XI.S I~.4 0~0 0~0 0,0 0 0 0,0 0.0 0,0 0,0 0~0 0,0 0.0 0~0 0,0 0~0 0~0 0~0 0.0)QX~5 0 0 0~0 0 0 0 0 0~0 0 0 0 I 0~0 0~0 0~0 0'0'0~0 0'0~0 0~0 TOTAL 0~$70 1 024 0~409 D~0 0~051 0 ITO I~712 2'03 F 764 1.740 1 07$0~563 0 614 0'sd 1~ZIZ 0~307 17 F 042 TOTAL NOVR5 OF.VALID STASILITT OSSERVATZON5 20'TOTAL NOVR5 OF STAIILZTT CLA5$A 334 TOTAL NOVR5 OF VALID MIND DIRCCTXON NIND 5tCCD STASILITT CLA55 TOTAL NOUR5 OF VALZD Nl'ND DIRECTION MIND SPCCD 5TASILXTT OSSCRVATION5 1954 TOTAL NOUNS CALM 0 JOINT PCRCCNTAOt

~RtOUCNCZC5 OF N(ND StttD IT NXNO DIRECTION fOR STASILITT CZJLIS 5 ('1~9(DELTA Tl>>I~7 C/100 Nl SRONNS FCRRT NUCLEAR PLANT JUL XL$9 SCP 30L$9'NI ND DIRECTION CALM 0.6 j.~1.5 3.4 NXND StttD(Ntt) 3.5-$.4 5.$7.~7 5 12.4 12 5 1I~4 1I.5 24.4)%RE~,5 TOTA(.N NNC Nt ENt$5$SC SSE I 55N SN M5N N NNN NW NNW 0~0 0,0 0.0 0,0 0~0 0~0 0~0 0~0 0,0 0~0 0 0 0~0 0,0 0~0 0~0 0~0 0.0 0.0 0.0'~0 0,0 0~0 0'0~051 0'0'51 0'0'0'0.0 0'0'0,0 0,0 0,0 0,0 0 F 051 0 F 102 0'21 0$19 0~$12 0'05 0,256 0~154 0.051 0~154 0~0 0~0 0~0 0 F 102 0~154 0'51 0~0$1 0~102 0~051 0~0$1 0'0 F 051 0'0'12 0~102 0~15~0 154 0~102 0~154 0 20$0.205 0 0 0,0 0~0 0~0 0'0~0 0'0 0 0 154 0,154 0~102 0 F 102 0~15'~102 0.154 0~051 0,0 0,0 0'0~0 0'0'0,0 0,0 0,0 0,0 0~051 0~0 0,0 0,0 0'0 0 0~0 0~0 0,0 0 0 0~0 0'0,0 0 0 0~0 0'0'0 0 0'0~0 0,0 0'0'0'I'D 0'0'0'0,0 0,0 0'0'0,0 0~0 0,0 0.0 0 0 0.0 0.0 0~0 0~I 0'0.0 0,0 0 0 0~0 0~0 0~0 0~0 0~0 0.0 0~256 0~461 0~~09 0.051 0 102 0~205 0~972 0 921 0~512 0 F 307 0,256 0$19 0 F 307 0 461 0~256 0~256 SUSTOTAZ 0~0 0~102 3 F 224 1~63$1,22$0,35I 0.0 0~0 0~0 6~$$1 TOTAL NOVR5 OF VALID STASZLITT OISCRVATZONS 2043'IOTA(, NOUR5 OF STASZLZTT CLAS5 5 t29 TOTAL'ROVR5 OF VAI.ZD MIND DIRSCTZON WXND 59CCD STASZLITT CLASS 12$TOTAL.COURS OF VALID WINO DIRSCTZON WIND 5tttD STASILXTT OSStRVATIONS 1954 TOTAL NOVRS CAIJl 0 I~4 f BFN Rad Impact July-Dec 1989 Page 18 of 53 TABLE lA (page 2 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JOINT~CRCCNTAOE fbt UCNCZEI Of WIND I~CCD SY WIND D'IRECTZON FOR STASILZTT CLA5$C I I~TC DELTA T<0 I AS C/100 Nj bbolrtlS fCRRT NUCLtAR PLANT JUI, 1,~9 Stt 30, 59 WIND DIRECTION CAIJI 0.6 L.i 1.5 3.~WIND StttDINtb) 1.5 S.~5 5 T.i 1.5 12.~12.5 lb.i I~.5 I~I l%2i~5 TOTAI N NNC NC CNC 5$55 55 5$5 5 5$W 5W WSW W WNW NW 0~0 0~0 0~0 0~0 0~0 0,0 0~0 0'0~0 0,0 0,0 0.0 0.0 0,0 0'0'0~0 0'0'0'0,0 0'0'0.0 0~0 0'0,0 0,0 0'0'0'0'0'0~0 0'0.051 0'51 0'51 0'0~1$~0~35~0.716 0,609 0~0$1 0~15i 0,205 0~102 0'0 0 0 0 2.303 0.051 I~LOI 0.20$0.051 O.Isi 0.20$0'0.05L 0'0'51 0,102 0~102 0.051 0.256 0.205 0'51 1.635 0.051 0 LSI 0~LOR 0~0 0~0 0~0$1 0~0 0~0 0~0 0,0 0~0 0~156 0.156 0'51 0'56 0~0$1 0~921 0~0 0~102 0~102 0.051 0,0 0,0 0,0 0~0 0,0 0 0 0,0 0 0 0,0 0.205 0.102 0,0$1 0~616 0 0 O.OSL 0~0 0'0~0 0,0 0'0~0 0'0'0,0 0'0,0 0,0 0'0'0~OSL 0'0~0 0'0~0 0'0~0 0 0 0~0 0~0 0 0 0.0 0.0 0 0 0~0 0~0 0~0 0~0 0~0 0~0 0.0 0'0'0'0'0'0'0'0'0'0.0 0'0 0 0~0 0.0 0 102 0~i 61 0~~61 0~Isi O.Isi 0~609 0 351 0.765 0.609 0~102 0.256 0,661 0.307 O.SLR 0'61 0 Isi 5.$27 TOTAL NOVR5 Ot VALID 5TASZLZTT 055CRVATION5 Roil TOTAL NOVR5 Of 5TASZLZTT CLA$5 C 113 TOTAL NOVR5 Of VALID WIND DZRCCTZON WIND ItCCD 5TASILITT CLA55 C 10~TOTAL NOVR5 Of VAIID WIND DIRCCTZON WIND$9CCD STASILZTT 0$5tRVATION5 Itsy TOTAL NOUR5 CALN 0 JOINT~CRCtNTAOC f'bt UCNCICC Of WIND IVCCD ST W'IND DibtCTION fOR 5TASZLZ'TT CLA$5 D I 1~SI DELTA TI0 I~5 C/100 Nl IROWNS tlRRT NUCLEAR tLANT i JVL I~59 5tt 30,$9 WIND N NNC Nt CNC CSE 55$5$I$5'W 5W W5'N W WNW NW NNW CALN 0.002 0 F 002 0.002 0,002 0.00i 0.006 0 006 0.005 0.00$0.006 0,006 0,006 0 003 0.001 0.001 0.001 0616 0 0$1 0~0 0'0'0,0 0~102 0~051 0'56 0~156 0 20$0~102 0;jsi 0.0$1 0.051 0'0.0 I~5 3~I 0,307 O,ICI 0,512 0 i09 O,I70 O.I19 L.ill 0.921 1,026 0,76I 0.76I 1,279 0,66$0'05 0~lsi 0 101 WIND Sttt l.5 5.6 0~3$I 0.563 0.2$6 0~TCI I~331 1,177 0.616 0~RSC 0.307 00051 0~0$1 0.512 I, iii 0~$12 0,307 0~35I D(Ntb)$.$1.I 0,563 0.$61 0.20$0,107 O.ICL 0 609 0.307 0~1$6 0~0 0,0 0'0~1$6 0,66$0~355 0.2$6 GLOR 0~609 0.307 0~ibt 0,20$0~0 0.0 0.0$1 0'0.0 0 0 0.0 0~0$1 0~102 0~102 0~0$1 GLOR 0 0 0.0 0.0$1 0,0 0.0 0.0 0,0 0,0 0 0 0.0 0.0 0.0 0.0 0.0 0.0$1 0.0$1 0~0 0~0 0'0 0 0,0 0~0 0~0 0~0 0'0'0,0 0~0 0~0 0,0 0,0 0,0 1.5 12.~12.5 I~.~1$~5 2~.I)02~as 0.0 0,0 0,0 0,0 0,0 0,0 0~0 0.0 0,0 0.0 0,0 0'0'0'0,0 0~0 TOTAL I F 690 I~I96 I 63$I 691 2.66$I~511 2~~Cl I$91 I L~ORI 0.92$2~25$R.t71 I~129 0.519 0'22 SUSTOTAL 0~051 1.177 LO~901 I~90$i.~06 1.791 0~156 0 0 0'2'56 To'TAL NODES Ot.VALID ITASZLZTT 0$5CRVATZON5 Roil TOTAL COURS Ot 5TASILZTT CLASS D 591 TOTAL NOUR5 Ot VALID WIND DZRECTZON WIND StttD STASZLZTT CLA55 D Slt TOTAL NOVNS Ot VALID WINO DIRECTION-WINO stttb-ITASZLZTT OSICRVATIONS ISSUE TOTAL NOUR5 CAIN 00181' I Ig e BFN Rad Impact July-Dec 1989 Page 19 of 53 TABLE 1A (page 3 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JOINT~CRCtNTAOC fst UtNCIts Of Wlho S~CCD 0'1 WIND DIRCCTIDN FOR STAR)LITT CLASS C I 0~5<DCLTA T(>>I 5 C/100 Xl SROWNS Ftsst NVCLCAR SLANT JVL le 49 5tf)or 69 WIND DZRCCTIDN N NNC Nt tNt t t5t St 5$C 5$$W SW W5W'W WNW NW NNW CALX 0'42 0.070 0 047 0'50 0.040 0~110 0.06D 0.0$0 0.042 0.027 0~042 0.077 0.0$2 0~010 0.022 0.0)7 0.6 1.4 0,102 oi)54 0,1$4 0~512 0~20$0~~19 0~$12 0 512 0'09 0 154 0,~09 0,2$4 0,0 Oeosl 0,2D$oe102 1.5).~I~177 I 075 0~619 I~12~1.433 1.433 0~716 0~512 0~441 0~)07 0~441 1.)ll 1~0'75 0~15~0.256 0.44$WIND SfttDIX)as$.4 0.54)0.512 0~414 0.409 1,43$0,4~1 0 154 0.0 0,0 0,0 0.0 0~102 0 461 0,10'I 0.1$~0,)07~NI 5~5 7.4 0~307 0'54 0'07 0.154 0'54 o s)07 0 102 0~0 0'0~0 0~0 0 051 0'0~101 0~051 0 0$1 0,1$~0.051 0.102 0 0$1 0.0 0.0$1 0.0$1 0,0 0,0 0,0 0.0 0 0 0,0 0,0 0,0 0,0 0'0.0 0,0 0,0 0'0 0 0,0 0~0 0~0 0~0 0,0 0'0'0~0 0 0 0,0 0 0 0~0 0 0 0~0 0.0 0.0 0~0 0~0 0 0 0~0 0~0 0.0 0'0.0 0 0 0.0 7.5 12~~12.$1$.~1$.5 24.4 I>>24.$0,0 D D 0,0 0 0 O.o 0 0 0~0 0~0 0~0 0 0 0~0 0,0 0~0 0,0 0,0 0'TOTAL 2~145 2 42~2.0~3 2.331)~411 I~1$0 1.$95 1.07)0 912 0.$90 0~912 I~$17 I~56\0~~19 0.464 I~16)SVSTOTAL 0.~70 4,442 12.999$.474 2.047 0.441 0~0 0~0 0.0 26.71~TotAL NOVNS Of VALID STASIIITZ OSSCRVATZONS 2043 TOTAL XOURS Of STASILITT CLASS C$44 TotAL HOURS Of VALID WIND DZRCCTZON WIND SFCCD 5TASIZZTT CLA55 I 512 TOTAL HOURS Of'VALID WIND DIRCCTION WIND SFCCD STASILZZt OSSCRVAZIONS 1954 TOTAI.HOURS CAIJI 17 JOINT ftRCCNTAOC FRtOUCNCICS Of WIND sfCCD ST WIND DIRtCTIDN FOR 5TASILZTZ CLASS f I I~SC DCLTA T(%4 0 C/100 XI SROWNS FCRRZ NUCLCAR SLANT JUL li$9 SCF)0~69 WIND DIRCCTION N NNC Nt tNC C tst St Sst 5$5W SW WSW W WNW NW NNW CALX 0~112 0.190 0.097 0~117 0.093 0.019 0~010 0,0 0~010 0,0 0~0 0~00$0.0 0.00$0.010 0~132 0~4 I~4 0.441 0.$19 0.~09 0,~09 0.1$4 0~154 0.101 0.0 0,101 0.0'0 0 0.0$1 0.0 0.0 0.0$1 0,512 I~5).~0.714 I~177 0.414 0$19 0~$19 0'56 0'0~0 0.0 0.0 0 0 0.0 0~0$1 0.051 0'70 0,307 I~124 0.205 0.1$4 0,154 0,0 0,0 0.0 o,o 0.0 0 0 0,0 0~051 o,o 0'0,1~4 0.0$1 0,445 0~1$4 0.0$1 0 0 0.0 0'0'0'o.o 0~0$1 0.0 0'O.o 0.0 0 0 WZND 5rttD(XFNI

)~5$.4 5.5 7.4 0.0 0,051 0~0 0.0 0'0,0 0,0 0~0 0,0 0'0'0 0 0~0 0.0 0~0 0,0 0~0 0~0 0~0 0~0 0'0'0'0 0 0,0 0~0 0~0 0 D 0~0 0~0 0~0 0~0 0~0 0.0 0.0 0,0 0,0 0~0 0~0 0'0~0 0,0 0,0 0,0 0'.0,0 0,0 0~0 7512~~12$1$41$~$2~.4 I>>24.5 0~0 0 0 OIO 0,0 0'Oao 0 0 0,0 0,0 0~0 0,0 0~0 0~0 0,0 0,0 0,0 TOTAL I~447 4,02$I 479 1.$$0 l.219 0'4~0~112 0~0 0~112 0~0 0~0$1 0~054 0.0$1 0~0$4 0~112 1,4~7 5VSTotAL 0~419),224 5)74 2.149 0.972 0.051 0,0 0~0 0~0 12.590 TOTAL HOURS Ot VALiD 5TASZLITT 055CR'VATZON5 20'TOTAL HOURS OF STASZLZTT CLA55 F 2$2 TOTAL NOUNS of VAIZD WIND DIRCCTIDN WIND 5FCCD STASILITZ CLA55 F I~4 totAL Roost or VALID WIND DIRCCTZDN-WIND srtto-STAN)LITT osstRVATIONR lssi TOTAL HOURS CALX 14 00181 1$

BFN Rad Impact July-Dec 1989 Page 20 of 53 TABLE 1A (page 4 of 4)BROMNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JOIN'T tCRCCNVACC FRCOUCNCZC5 OF WIND StCCD ST WIND DZRCCTION FOR STAbZLITT CLASS 0 IDCITA T 7 i~0 C/IOO Nl bROWNS tCRRT NUCLLAR tLANT 3UL I, 59 5Ct 30, l9 WIND D I R 5 CT Z 0 N N NNC NC CNC 5 CSC SC 555 5 55W SW WSW W WHW NW NNW CALN 0.067 0 F 067 0'29 0'21 0 F 005 0,0 0'0'0'0'0'0.0 0'0'0'0~013 0.6 1.~0 F 256 0~156 0~0 0~102 0.051 0'0'0.0 0'0,0 0'0'0'0 0 0~0 0~051 1~5 3~6 0.563 0'65 0~35l 0,154 0~051 0~0 0~0 0'0'0,0 0~0 0 0 0~0 0,0 0.0 0~102 0 F 205 0'21 0~0 0~102 0.0 0'0~0 0'0'0'0'0'0'0'0'0.0 0~0 0~051 0~0 0~0 0~0 0 0 0'0'0'0'0,0 0'0.0 0,0 0'0,0 WIND 5FCCDINtbl 3.5 5'5.5 7.6 0~0 ,0,0 0'0 0 0,0 0'0'0'0 0 0,0 0,0 0'0 0 0,0 0 0 0,0 0'0'0 0 0,0 0.0 0~0 0~0 0~0 0~0 0,0 0'0,0 0'0'0'0'0,0 0'0,0 0.0 0'0,0 0,0 0~0 0'0'0'0'0~0 0'0~0 0 0 7~$12 6 12 5 15 I I~5 2~.I)026.5 0~0 0.0 0'0'0'0'0'0.0 0,0 0,0 0.0 0'0,0 0,0 0,0 0.0 TOTAL I~090 1,551 0~357 0 379 0~111 0.0 0~0 0~0 0'0'0,0 0'0'0'0'0~166 SUSTOTAL 0~205 0, 616 1.59i I~22l 0'51 0'0,0 0 0 0,0 3.992 TOTAL HOURS OF VALID STASZLZTT 055CRVATZON5 TOTAL HOUR5 OF STASZLITT CLASS 0 TOTAL HOURS OF VALID WIND DIRCCTZON WIND StCCD STASZIITT CLASS 0'TOTAI HOURS OF VALZD WIND DIRCCTION WIND StCCD 5TASZLITT ObSCRVATZONS TOTAL HOUR5 CALH 2063 7l 7~1956 00181 4 eg t BFN Rad Impact, July-Dec 1989 Page 21 of 53 TABLE 1B (Page 1 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION StLIT JOINT FCRCEhTAOC FRE UENCIES OF N1ND SPEED ST ltZND DIRCCTZOh FOR STASILZTT CLA55 A (DELTA T(%I~9 C/100 Nl bRONN5 FCRRT NUCLEAR PLANT PART I OF 2 OROUND LEVEL RCLCA5E NODE JUL I, 59 51')0, 59 WIND DZRCCTZON N NNC NC tNC 5 ESC SC$55 5$5N SW W5W N Whlf NW NEW SUSTOTAI CAL((0.0 0.0 0~0 0.0 0.0 0.0 0.0 0.0 0 0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 0'0.6 I.i 0~0 0'0~0 0~0 0~0 0~0 0~0 0'0.0 0.0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 I~5).~0.0 0,0 0,0 0.0 0.0 0.0 0.020 0 F 027 0~0)I 0.032 0~002 0.0 0 0 0.0 0.0 0 0-0~11$I~002 0.0 0~0 0'0.0 0~0)6 0 Oi)I~006 0 F 095 0 017 0~III 0~Ooi 0.002 0'0 F 00)0~001 0~OOI 0 019 0~011 0~0 0~0 0~0~7 0'0'0'0.0 0'0~016 0~015 0~012 0~Oi)0~012 0 AD)19 O.II'IND StCCD(hthl

)~5 SAN S.S T.~0'96 0~OIS 0 F 032 0'0,0 0~0 0'09 0~0 0,0 0,0 0.0 0.0 0.0 0 0 0~06$0,012 0,2IO 0.0 0~0~I 0~010 0,0 0.0 0 0 0.0 0,0 0 0 0.0 0.0 0.0 0 0 0,0 0.0 0.0 0~0$2 0~0 0'0~0 0~0 0~0 0'0'0~0 0'0'0'0'0'0'0'0'0~0 7....~0~0 0~0 0~0 0~0 0~0 0~0 0 0 0~0 0,0 0'0~0 0~0 0~0 0 0 0~0 0~0 0,0 TO'FA(0~107 0~Ill 0~051 0'I~0 0~OI)0~072 0~03)0~13)0'(9 0~011 0 F 020 0~017 0 012 0~090 0'25 0~$51 TOTAL NOUR5 OF VAIID 055tRVATZON5 19)I,OOO TOTAL NOUR5 Ot OROUND LEVtL RtLEA5t 109~990 TOTAL SOU!$OF 5TASZIZTT CLASS A 16~Sio TOTAL NOUR5 OF OROUND Ltttl STASILITT CITS A 16,5lo 5P(IT JOIÃt ttRCENTAOC tRCOUENCZE5'OF WIND StttD ST lfZND DZRtCTION FOR STASZLITT CLASS 5 I~Sf DELTA TC5 I~7 C/100 h)SRolfh5 ttRRT NUCLEAR PLANT PART I OF I OROUND LEVEZ RCLEA5E NODC JUL I~It 5tt 30, 59 NIND DZRFCTION CALN 0.6 I.~I~5 3.6 WIND StCCD(hthl

)5 5.i 5.5 T.~7.5 12~12~5 II~I II~5 1%26.5 TOTAI N NNE NC tNC 5 555 SC$5t I$5N SW W5N W WNW Nlf*NNW 0.0 0~0 0~0 I 0 0~0 0~0 0.0 0.0 0'0'0'0'0'0 0 0,0 0 0 0.0 0~0 0'0.0 0'0'0.0 0'0'0'0'0'0'0 0 0~0 0~0 0~0 0.0 0 0 0 0 0'0.0 0 F 002 0~020 0 017 0,00$0'0'0'0'0 0 0~0 0.001 0 F 002 0 F 002 0.0 0 F 000'0'0.005 0~0 0.00l 0~0 0,002 0~001 0 F 002 0~011 0~016 0~017 0'0.0 0.0 0,0 0,0 0.0 0,0 0,0 0.012 0~01$0~002 0~010 0~013 0~017 0~021 0 F 007 0'0'0'0.0 0'0 0 0.0 0~0 0.0 0'0~009 0'0~0 0 0 0~0 0~0 0.0 0~0 0'0'0'0~0 0.0 0,0 0'0'0'0'0'0~0 0~0 0'0,0 0'0'0'0,0 0'0,0 0'0'0,0 0'0,0 0,0 0~0 0'0'0~0 0.0 0'0,0 0~0 0~0 0.0 0'0'0,0 0,0 0'0'0~019 0.0)I 0~01$0~002 0.0 0.00I 0~002 0 F 020 0~017 0.013 0~0 0'25 0~01$0~011 0~010 0~016 SUSTOTAL 0.0 0~0 0~062 0'25 0~107 0,053 0'0,0 0.0 0~210 TOTAL COURS ot VALZD 055ERVATIONS 19)I~000 TOTAL NOUR5 Ot OROUND LEVEI, RELEASE Iotas 990 TOTAL NOUR5 ot 5TASILITT CLA55 b I~iio'OTAL ROUR5 OF OROUND LCVtL 5TAS ILZTT CIA5$5 l.iio

, 4 BFN Rad Impact July-Dec 1989 Page 22 of 53 TABLE 1B (Page 2 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY D1STRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION SPLIT JOINT ttRCtNTAOC tRCOVCNCItl OF'MIND St!CD I'I MIND DIRECTION FOR STAbZLZTT CLASS C l I~7(DtLTA 7>1.$C/100 NI bRol(55 tERRT NVCLCAR ASLANT FART 1 OF 1 OROUND LtVCL RCLCASE NODC JVL le 49 SCt low 19 WIND CALN 0.6 1.4 1.5 3.4 WIND SFCCD(NtNI 3.5$.4 5 5 7~4 7 5>>12~4 12 5'lS~~15~5 24.~l>>24.5 TO'TAL N NNC Nt tbt C CSC Sc SSC I 55W SW W5W W WIW NW NIW 5UbtOTAL 0 F 000 0 F 000 0 F 000 0 F 000 0 F 000 0.001 0.000 0,000 0~000 0 F 000 0.000 0~000 0~000 0.0 0.0 0.000 0.001 0~002 0~001 0.0 0,0 0.001 0.013 0.007 0.016 0.00$0 F 004 0'0~001 0 0 0~0 0,0 0~0 0~OSC 0.0)t 0.036 0~014 0.027 0~030 0.0'0,040 I')9 0.044 0.011 0.003 0*017 0'09 0.0 0~0 0.006 I~39I 0.061 0~04I 0~063 0 030 0~III 0 0~I 0~024 0'0'0~0 0~0 0 F 007 0~019 0.006 0'09 0 F 024 0 521 0 F 046 0.0$$0 F 04)0 022 0~015 0.0$3 0.0)I 0'0'0~0 0'0 F 00)0'0~011 0 F 006 0'06 0.)CC 0.026 0.009 0~OII 0,009 0'0.010 0~010 0~0 0~0 0.0 0'0'0.0 0'0,0 0,0 0 OI2 0~0 0 0 0'0~0 0 0 0,0 0 0 0,0 0'0,0 0'0~0 0,0 0'0'0,0 0,0 0,0 0,0 0,0 0,0 0'0~0 0,0 0'0,0 0,0 0 0 0'0~0 0,0 0'0 0 0 0 0~0 0'0.0 0'0,0 0'0.0 0.0 I~0 0~I 0.0 0'I~0 0'0.0 0.0 0:0 0~1)3 0 151 0~139 0 OII 0 252 0 210.0.159 0'55 0.0~9 F 016 0 003 0~Ill 0 F 02'F 020 0.014 0~016 1.426 TOTAL NOVR5 Of VAIZD 055tRVATION5 1935.000 TOTAL NOURS Ot OROUND LtVCL RCLCA5C 109 990 TOTAL NOUR5 Ot STAR)LITT CLA55 t CS)F 020 TOTA!.COURS Of OROUND I,tVEL STASZLZTT CLA55 E 2)~C40 sttlt Jozbt tcbccNTAoc rbcqvcbclcs or wIND srtcb st wIND olbcctlob roR StASILITT CLASS F I I,SC DELTA TC>>~.0 C/100 NI~RolRIS ttRRT NVCLtAR FLANT~ART I Of 2 OROUND LCVCL RCLCASC NODE JVL I,~9 Stt)0, 19 WIND DIRCCTZON CAIN 0~6 1.~I~5 3~~WIND 5tttD(Ntb)

)~5 5'5.5$).4).5 12.4 12.5 1I.4 II.5 2~.4)02~.5 TOTAL N NNt NL tbc 5 55E 5t SSC 5 SSW SW WSW W WNW IW NNW SVSTOTAL 0 F 000 0.000 0,000 0.000 0.000 0,000 0~000 0.0 0.000 0,0 0.0 0~00~0 0~0 0,000 0~001 0~002 0~001 0~0 0~0 0,0 0'0 F 004 0'0~001 0.0 0,0 0'0'0'0.0 0 F 002 0~013 0 F 025 0.032 0~015 0 F 037 0.0)I 0~006 0'0.0 0'0.0 0'0.0 0'0'.0.0 0 F 021 0~II~0 F 040 0'55 0 026 0~015 0 011 0,0 0~0 0 0 0~0 0.0 0.0 0.0 0,002 0~0 0 0~0~016 0'65 0 001 0~111 0.025 0,00I 0'0,0 0.0 0'0,0 0,0 0~OOC 0'0'0,0 0'0.0 0.16$0.0 0'09 0'0~0 0 0 0.0 0~0 0,0 0'0'0,0 0'0'0~0 0'0'0'09 0.0 0 0 0.0 0~0 0~0 0.0 0~0 0 0 0'0'0'0'0~0 0'0'0'0,0 0.0 0'0'0'0~0 0.0 0 0 0 0 0,0 0.0 0,0 0'0'0'0'0~0 0'0'0~0 0'0'0'I~0 000 0'0.0 0'0'0.0 0'0.0 0.0 0'0,0 0,0)5 0.317 0.056 0.061 0 039 0~OOC 0 F 000~001 0~0 0~'006 0.0 0 F 002 0.0 0 0 0 019 0OTAL NOVRS Of VALID OSSCRVATION5 19)I.000 TOTAL COURS OF OROUND LCVEL RCLCASC 109'90 TOTAL NOUR5 Of 5TASZLITT CLASS 1$4~IIO TOTAL NOVRS Of OROVND LtVtL STAblLZTT CLA55 F 12~)CO i C U BFN Rad Impact July-Dec 1989 Page 24 of S3 TABLE 1B (Page 4 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RFLEASES GROUND-LEVEL PORTION SFLZT JOINT FCRCCNTAOC FREOUENCZCS OF'MIND SFCCD SY MfND DZ RECTION FOR STASZLiTT CLA$5 0 I DtLTA T>4 0 C/I 00 Nl SROMNS FCRRT NUCLtAR SLANT FART 1 OF 2 OROURD LEVEL RELEASt NODE JUZ Zy 49 5tF 30p 49 MiND DIRECTION N NNC Nt CNC C CSC 5C$51'SSM 5M MSM M MNM NM NUM CALN 0~0 0'0 0 0 0 0,0 0'0.0 0'0.0 0'0~0 0.0 0'0'0 0 0.0 0.$1.4 0~0 0.0 0,0 0~0 0.0 0~0 0~0 0,0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 1.5-3.~0 019 0 F 032 0 F 0'~00$0.0 0,0 0'0'0'0'0 0 0.0 0~0 0'0'0~002 0~024 0,13~0'0~014 0 0 0 0 0~0 0'0.0 0,0 0,0 0'0'0.0 0'0,0 0~0 0 F 009 0'0.0 0'0'0'0'0.0 0'0'0'0'0.0 0.0 0,0 MIND SFECD(NFNI 3.5 5.~5.5 5V.~0~0 0~0 0.0 0~0 0'0 0 0~0 0.0 0'0'0'0'0'0'0'0 0 0'0 0 0 0 0 0 0.0 0'0'0'0'0.0 0,0 0.0 0~0 0 0 0.0 0,0 0'0 0 0~0 0.0 0.0 0~0 0.0 0'0'0.0 0.0 0.0 0'0'0'0'7.5 12.~12.5 14.~14.5 2~.~>%2~.5 0'0'0'0'0'0~0 0'0,0 0'0'0.0 0~0 0'0.0 0,0 0'TOTAL 0'42 O.2 2 5 0~024 0 F 020 0'0'0'0 0 0,0 0~0 0~0 0.0 0,0 0~0 0.0 0.002 5USTOTAL 0'0'0.042 0~172 0,009 0'0,0 0.0 0'0~2$3 TOTAZ NOUNS OF VAZZD OSSCRVAT10$

$1934 F 000 TOTAL NOUR$OF OROUSD LtVtL RCLtASt 109'90 TOTA1, MOORS OF STASii,ZTT CLA5$4 31~000 TOTAL COURS OF OROUND LEVEL 5TA41LZTT CLASS 0 5 100 00181 AVJ e BFN Rad Impact July-Dec 1989 Page 25 of 53 TABLE 1C (Page 1 of 4)BROMNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION srLIT soxhT tthcthTAct thtoushcxts or wxhn spsso sv wxho oxstcsxoh roh STASXLZTT CLA$5 A (DCLTA 740 1,9 C/100 Nl SROWNS ttRR'I NUCLtAR ALAI(T tART 2 Ot I CLCVATED RCLEASE NODC)UL I, 49 SCP)0,$9 WIND DIRECTION N NNC Nt CNE C CSE 5$$5C 5 Ssw sw w5w w wNlt Nlt lf Nlt CALN 0 0 0.0 0~0 0~0 0~0 0~0 0~0 0.0 0~0 0~0 0~0 0~0 0~0 0~0 0.0 0.0 0.4 1.~0~0 0~0 0~0 0.0 0~0 0.0 0~0 0~0 0.0 0~0 0~0 0~0 0~0 0'0'0'I~5)~4 0~0 0.0 0~0 0~0 0~0 0'0 0 0~0 0~0 0.0 0~0 0 0 0~0 0.0 0'0'0.0 0~0 0~0 0 0 0~0 0.0 0~0 0.0 0'0.0 0~0 0.0 0'0.0 0'0.0 0~0 0~0 0.0 0~0 0~0 0.0 0~0 0.0 0~0 0.0 0~0 0,0 0'0.0 0'0~0 WxhD SPCCD(NPK) 3.5 5.~5.5 7.4 7.5 12.~12.5 14.4 II.5 0~0 0~0 0.0 0~0 0~0 0~0 0~0 0.0 0'0 0 0'0~0 0'0.0 0'0'0~0 0.0 0'0'0.0 0 0 0.0 0~0 0'0 0 0~0 0 0 0'0'0.0 0'0~0 0.0 0 0 0~0 0.0 0~0 0 0 0'0'0'0'0'0'0~0 0'0')02~5 0~0 0.0 0 0 0~0 0.0 0~0 0~0 0~0 0'0'0~0 0~0 0'0~0 0 0 0~0 TOTAL 0~0 0'0'0'0'0'0'0.0 0'0~0 0'0.0 0'0.0 0 0 0.0 5VSTOTAL 0~0 0,0 0~0 0~0 0~0 0~0 0.0 0'0'0'TOTAL NOUR5 Ot VALID OSSCRVATZON5 TOTAL NOVR5 OF CLEVATCD RCLtASCS TOTAl NOUNS Ot STASZLITT CLASS A'tOTAL KOUR5 Ot CLCVATCD 5TASZLZTT CLA55 A 19)I~000 IIII~009 ISA 540 0'SPLZT)OxlfT PERC'thTAOC FREOUCNCIC5 Of ltIND SPCCD ST lfxND DIRECTION tos STASILZTT CLA5$5 (1.94 DCLTA TC0 I 7 C/100 Nl SROlfhs ftRRT NVCLtAR PLANT , tART 2 Ot 2 ELtVATtD RCLEASC NODC SUL I,$9 5CP 30, 49 ItI ND DZRCCTION CAIN 0 I I~~I~S)~~wZND 5PCCD(hthl

)~5 5 4 5 5 I~~7.5 12.4 12~5 XI.~1$.5 24.4 f024.5 TOTAI 0~0 0.0 0~0 0~00'0'0'0.0 0.0 0,0 0'N NNC Nt CNC C CSC St SSL 5$5w Sw w5w w 0~0 0,0 t lAfW 0.0 NW 0~0 NNW 0,0 SUSTOT*1 0.0 0'0'0~0 0'0'0'0;0 0'0'0'0.0 0'0'0'0,0 0'0'0.0 0'0'0'0,0 0,0 0'0,0 0'0'0'0'0'0'0,0 0,0 0'0~0 0,0 0,0 0,0'0~0 0'0'0,0 0'0,0 0'0,0 0'0.0 0'0'0.0 0~0 0,0 0,0 0.0 0'0,0 , 0,0 0,0 0,0 0~0 0'0'0'0 0 0'0,0 0~0 0,0 0~0 0~0 0,0 0~0 0,0"0~0 0~0 0~0 0~0 0.0 0~0 0 0 0~0 0~0 0 0 0'0.0 0'0,0 0'0'0.0 0'0,0 0~0 0'0.0 0'0 0 0~0 0'0~0 0 0 0~0 0,0 0~0 0~0 0~0 0.0 0,0 0.0 0'0'0'0'0'0.0 0'0~0 0,0 0,0 0'0,0 0.0 0'0,0 0'0'0,0 0'0'0'0'0~0 0'0,0 0 0 0~0 0'0,0 0'0'0.0 0'0,0 0,0 0'0'0.0 0~0 0~0 0'0~0 0~0 TOTAL KOVR5 OF VALID OSSCRVATIONS TOTAL KODES OF ELEVATED RCLEA5CS'TOTAL NOVRS Ot 5TASILZTT CLASS 5 TOTAL NOVRS Ot ELEVATED STASILZTI CLA$5 I 19)I.OOO II2I.009 4.440 0 0

BFN Rad Impact July-Dec 1989 Page 26 of 53 TABLE 1C (Page 2 of 4)BROWNS FFRRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION SPLiT JOINT PCRCtNTA4E tRCOUENCZE5 Ot WIND 5PCID IF WIttD DIRECTION FOR 5TASZLZTI CLASS C (I~7C DELTA TIQ I~5 C/100 NI SROWHS FERNE NUCLtAR PLANT tART 2 Ot 2 EICVATCD RCLtA55 NODE JUL I, 49 SCP 30, l9 WIND DIRECTION N NNt Nt CIIE t C5C SC SSC 5$5W SW WSW'W WHW NW NNW CALN 0,0 0,0 0'0'0'0'0 0 0~0 0.0 0,0 0~0 0~0 0 0 0.0 0,0 0.0 0.6 0~0 0.0 0~0 0~0 0.0 0,0 0~0 0.0 0.0 0,0 0'0,0 0'0'0'0'1.5).I 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0.0 0.0 0~0 0~0 0~0 0~0 0.0 0~0 0~0 0.0 0 0 0~0 0~0 0~0 0'0'0~0 0,0 0'0'0'0'0'0'0.0 0~0 0~0 0'0,0 0'0'0,0 0,0 0,0 0'0,0 0'0~0 0~0 0'0 0 WIND SPEED(NPNI 3.$$.~5.$7.4 0~0 0~0 0 0 0~0 0~0 0~0 0 0 0.0 0'0'0.0 0 046 0'0'0'0 0 0.0 0.0 0 0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0~0 0.0 0~0 0~0 0,0 0~0 0~0 0~0 0.0 0'0.0 0,0 0'0'0'0'0'0~0 0'0'7~$12.4 12~$1~.I 14.5 2~.~)~2'5 0'0'0 0 0~0 0~0 0~0 0 0 0,0 0,0 0'0~0 0.0 0.0 0,0 0 0 0IOTAL 0.0 0'0.0 0'0'0'0.0 0'0'0'0'0.0~6 0'0'0 I 0'5USTOTAL 0~0 0~0 0'0'0,0 0.0'0'0,0 0'0.046 TOTAL COURS OF VALID OlltRVATIOH5 TOTAL HOURS Ot EItVATCD RCLtASCS TOTAL SOUR5 OF STASILZTT CLASS C TOTAL HOURS Ot tltVATED STASILITT CLASS C 19)I~000 I~ll~009 6~190 0'00 5PIIT JOIN'T PCRCCNTA4C FRl UERCZES OF WIND SPCCD RF WIND DIRECTION FOR STASILZTT CLASS D I I~5C DCLTA T(Q I 5 C/100 NI CROWNS FCRRT NUCLEAR PLANT tART I OF 2 CLtVATCD REItA5C NODt JUL Ir l9 SCt 305 49'WIND CALN 0.6 I.I 1.5).I WIND SPCCD{NPH)

).5$.~5.5 7~I 555.555.55

~5.'\.~TOTAL N NNC Nt 1'Nt 5 555 55 SSC 5 55W SW W5W W WNW NW NNW SUSTOTAL 0'0'0'0'0,0 0~0 0.0 0.0 0.0 0'0'0,0 0,0 0'0,0 0 0 0~0 0.0$2 0,0 0'0'0 0 0,0 0~0 0.0 0'0.0$2 0 0 0'0~0 0.0 0.052 0~0 0 155 0 103 0 155 0 161 0.103 0,361 0~361 I~703 I~703 0~9IO 0.722 0.722 0~619 0~$16 0.361 0~103 0 101 l,974 0.2$I 0~l64 0~619 0.516 0~161 0.619 2~167 1 544 1.190 1,214 1,141 I~600 I~ll~0.$6I 0~56I 0.155 14~IOS 0 F 74ll)0,394 0~249 0,~47 I~041 1.203 1,)l~0.$90 0~341 0, AD)9 0~455 0,902 0 999 I~049 0~40$0.992 1.346 0$19 0,5'0.326 2.012 5 1.362 1.427 360 0,592 0.231 I~009 0.$95 0 552 0'70 0,504 14.77$0.~1$0~~32 0.16I 0 0 0.0 0.043 O.SI7 0,170 0.379 0~041 0.042 0.041 O,OII 0.0~3 0.045 0 0 1.9~9 0~0 0~0 0~0 0,0 0 0 0,0 0 F 071 0,1~I 0,019 0~0 0.0 0,0 0'0,0 0'0,0 0~210 0,0 0~0 0.0 0'0~0 0 0 0 F 009 0.021 0 011 0~0 0.0 0,0 0,0 0~0 0.0 0 0 0 F 042 2'4)3~440 Oll I~413 1.49$I~OI7 7.102 6.654 4.629 2.944 2.776),72~)~593 2.522 I,I66 I~171 le)69 TOTAL HOURS Ot VALID OSSCRVATIONS TOTAL HOURS Ot ELEVATED RELEASES TOTAL KOtlRS Ot STASZLZTT CLASS D TOTAL NOUR5 Ot CLCVATCD STASILZTT CLA55 D 19)I~000 1IZI:009 1072.910 1034.310

BFN Rad Impact July-Dec 1989 Page 27 of 53 TABLE 1C (Page 3 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION Sf(17 JOINT PCRCthTAOC FRCOUENCZtS OF WIND SfttD ST WIND DIRECTION FOR STA4111TT CLASS C (0~SI DtLTA T(i 1.$C/)00 Nl SROWNI FERRT NUCLEAR PLANT PART 2 Of 2 CLCVATED RE(EASE NODt JUL 1, 49 SCP)0~49 WIND DZRCCTZON N NNC Nt ENt 5 ESC SC SSC I SSW SW W5W W WNW NW NEW CALN 0~0 0'0'0'0'0'0'0.0 0,0 0,0 0,0 0,0 0'0,0 0 0 0,0 0~0 0~0 0 0$2 0~0$2 0,052 0'0.103 0,0 0,0 0'0'52 0'52 0'0'0~0$2 0.0$2 0~155 0~361 0 F 56'.671 0~25I 0.206 0~619 0~IC~I~$16 0.310 I~)C1 0~46~0.25~0~155 0 1$5 0,310 0.6 1.4 1.5 0~4~4 O S)64 0'71 I~Il6 0,671 0,619 1.1IT 0'64 0~103 0~1$$0~310 0,56I 0 F 722 0~2)I 0.206 0~361 0~54I 0,743 0~393 0,6091 0'97 1~003 O S)55 O S)51 0.147 0 44I 0~394 0~$4I 0~1$2 0.$00 0'52 WZND SPttD(NPH)

).5 5.4$.5-7.4 1~222 1.21$0.732 0'03 1.24l 1~505 0.230 0.369 0'27 0 ZIT 0~049 0 ZIS 0~)I9 0~145 0.092 0.231 0~0~3 0'55 0~OI5 0~0~3 0~0 0,0 0'0'0'0~0 0'0'0'0'0 F 041 0'0~0 0~0 0'0'0,0 0,0 0'0'0'0'0'0,0 0'0,0 0 0 0 F 026 7.5 12.4 12.5 14.4 14.5 24.~>%24~5 0'0,0 0'0,0 0'0'0~0 0'0 0 0'0.0 0'0 0 0 0 0~0 0~0 TOTAL 2~432 141 lan 99 l~C94 3~255 2'27 3~1~2 2.156 1 397 0'94 1.260 1~~67 1~717 0'50 1~046 1~332 5USTOTAL 0~0 0~464$.431 4,2$6 4'32 0,~67 0 F 026 0.0)2,217 TOtAL HOVR5 OF VALZD 0$5CRVATZONS TOTAZ NOUR5 Of t(CVATCD RCLtASCS TOTAL HOUR5 Of 5TASZLZTT CLASS C TOTAL HOUR5 Of CZCVAttD STASILZTT CLASS C 19)I 000 142I 00')652 020 F 24.)IO SPL1't JOINT PCRCEhtAOC FRCOUCNCZES Of WIND SfttD St WIND DIRECT)ON FOR STA$111TT CLASS F (1~SI DELTA TIR~0 C/)00 Nl CROWNS TERRE NUCLEAR PLANT PART 2 Of 2 CLCVATCD Rt(tA5t NODt JVZ 1, 49 SCP 30y 49 WZND DIRECT)ON h NNC Nt CNC 4 C55 St SSC 5 55W SW W5W W WNW NW NNW 0 A'Lh 0,0 0'0,0 0'0.0 0'0~0 0 0 0.0 0~0 0~0 0,0 0~0 0~0 0.0 0,0 0.6 0'0.0 0.0$2 0'0.0 0'0'0 0 0.0 0.0 0~052 0.052 0.0 0.0 0'0,0 1.5-).~0~0 0~155 0~10)0~0 0~0 0'52 0~155 0~0 0,052 0.0 0'52 0'52 0,0$2 0.0$2 0,0$2 0'0~0$2 0,103 0.~13 0~1$5 0'52 0.103 0'52 0.0 0.0$2 0.0$2 0'55 0.052 0".052 0.0 0~0 0~103 0.100 0'99 0~4I 0.349 0.24$0.050 0.0 0'0.052 0.049 0.0'0'0 0$1 0~0 0~0 0~1$4 WZND SPCCD(NPN) 3.5 5'5.5 T.i 0~091 0.730 0~I')9 0.325 0.)li 0.093 0.0 0'0'0.0 0.0'0'0'0'0.0 0'0'I'D 67 0~213 0.0 0,0 0.0 0'0'0'0.0 0,0 0,0 0'0'0.0 0,0 7~5 12.~12.5 14.~14.5 2~~~0'0~0 0'0.0 0'0'0,0 0'0'0 0 0~0 0.0 0~0 0 0 0 0 0~0 I 14.5 0'0'0'0'0'0'0.0 0'0.0 0'0'0.0 0'0'0.0 0'TOTAL 0~2~3 1~754 2~124 0~429 0'20 0 F 206 0'0'55 0.100=0.35l 0~155 0~154 0~052 0~052 0~2$7 5USTOTAL 0~0 0~1$$0,774 1 393 2'07 0 641 0~0 0.0 7.)$4 TOTAL HOVR5 OF VALZD 0$5CRVATZONS TOTAL HOVR5 Of CLCVATED RCLCA5CS TOTAL HOVR5 OF 5TA$1LZTT CLASS F TOTAL HOURS OF 5'LCVATCD ITASZLZTT CLASS f 19)4 000 1~25 009 1$4~~40 lil y)20 i

t BFN Rad Impact July-Dec 1989 Page 28 of 53 TABLE 1C (Page 4 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION Stt,tt JOINT tCRCCNTAOC tRCOUCNCICS Or WINO 5~CCO IT WtNO OtRCCTION toc STASILITT CLAS5 0 IDCITA T l~~0 C/100 N>IROWNS tcRRT NUCtCAR tLANT IART I Ot 2 CLCVATCD RCICASC NODC JUL I, 49 Sct 10, 49 WIND N NNC NC CNC 5 555 SC SSC 5 SSW SW W5W W WNW NW 5NW CALN 0~0 0~0 0~0 0~0 0~0 0.0 0.0 0~0 0'0'0'0'0.0 0,0 0'0'0.6 0.0 0'0'0.0 0'0'0'0'0'0,0 0'0'0.0 0,0 0,0 0'I~5 1.4 0 101 0~0 0.0 0~0 0~0 0~0 0~0 0'0'0'0'0'0.0 0'0'0'WIND SICCDINtNI 1.$5'5~5 7~4 0~0 0 09I 0'52 0'52 0~0$2 0~100~0~0 0~0 0~0 0~0 0'0'0'0'0.0 0'0.0 0~0 0~0 0'0'0'0,0 0'0'0,0 0~0 0~0 0,0 0~0 0~0$2 0'50 0'0~$11 0~119 0'0 0~0 0,0 0~0 0.0 0.0 0,0 0~0 0,0 0~0 0~0 0,0 0~0 0,0 0 12 0~0 0,0 0 0 0~0 0 0 0,0 0~0 0~0 0~0 0~0 0'0,0 0'0.0 0~0~0~0 0'0~0 0'0'0.0 0'0.0~0 0 0 0 0~0 0~0 0~0 0'2.$12.~12.$II~15.5 2~.4)024.5 0'0.0 0'0.0 0 0 0,0 0,0 0~0 0,0 0~0 0~0 0'0.0 0,0 0,0 0~0 TOTAL 0~201 0~742 0~291 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0 0 0~102 5UITOTAL 0'0,0 0~10$0~1$5 0'00 0 F 450 0~12I 0~0 0,0 1.216 TOTAL NOUR5 Ot VALID OISCRVATZONS TOTAL NOUR5 Ot CLTVATCD RCLCA5CS TOTAt COURS Ot STAIZLZTT CLASS 0 TOTAI NOURS Ot CLCVATCD STARZIZTT CLASS 0 1915 000 1III.009 11 F 000 IS F 900 00181

e BFN Rad Impact July-Dec 1989 Page 29 of 53 TABLE 1D (Page 1 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RFLFASES JO(NT PCRCCNTAOC FRC UCNCICS OF MIND 5ttCD RT MIND DIRECT(ON FOR 5TASILZTT CLASS A (DCLTA TI>>I~9 C/100 Nl bROMNS FERRI ROC(CAR PLANT JUL 1~$9 SCP 30~~9 MIND DIRECTION N NNC Nt ENC C CSL'$SSC 5 5$M SM MSM M MNM i lW OALN 0~0 0~0 0~0 0~0 0~0 0~0 0'0'0 0 0~0 0'0'0'0'0'NNM t 0~0 SVbTOTAL 0,0 0.6 1.4 0~0 0~0 0~0 0,0 0.0 0~0 0~0 0~0 0~0 0~0 0.0 0,0 0~0 0.0 0.0 0'0.0 1.5 3.4 0~0 0~0 0'0'0,0 0 0 0~0 0,0 0,0 0.0 0'0'0,0 0 0 0 0 0~0 0~0 0.0 0~0 0,0 0.0 0 0 0~0 0,0 0,0 0,0 0'0,0 0 0 0~0 0~0 0 0 0,0 0,0 0'0'0.0 0'0'0~0 0.0 0 0 0.0 0 0 0'0.0 0,0 0.0 0,0 0'0.0 M'(HD SPEED(NtH) 3.5$.4 5.5 TED 0,0 0'0'0'0'0'0'0'0'0'0'0 0 0,0 0'0'0'0'0~0 0,0 0 0 0~0 0.0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0.0 0~0 0~0 0~0 0~0 0'0'0,0 0'0 0 0'0'0'0'0'0,0 0,0 0,0 0'0'0~0 0 0 7.$12.4 12.$14.4 1$.$2~.4 l>>24.5 0.0 0~0 0.0 0~0 0~0 0,0 0'0.0 0'0'0.0 0.0 0,0 0'0'0.0 0.0 TOTAL 0.0 0~0 0.0 0~0 0~0 0 0 0~0 0~0 0 0 0,0 0'0'0'0,0 0 0 0,0 0,0 TOTA(, HOUR5 Ot.VALID 5TASZLZTT OSSERVATZON5 20~I TOTAL NOVRS OF STASILZTT CLASS A 0 TOTAL'OURS OF VALID MIND DZRCCTION MIND StttD STA41LITT CLASS A 0 TOTAL HOVR5 OF VAI ID MIND DIRECTION MlhD StttD STASILZTT 0$5CRVATIONS 2011 TOTAL NOURS CAIN 0 JOINT~CRCCNTAOC FRCOVCNCIES Ot MIND SPCCD ST M'IND DIRECTION tOR 5TA41(ITT CLA5$4 (I~94 DCLTA TI~1~7 C/(00 Nl SROMNS FCRRT NUCLEAR tZANT JUL 1, 59 5Et 30'9 MIND DIRECTION N NNC HC ENC C E5C 5E$55 5$5M SM MS M M lAW NM NNM CALM 0 0 0,0 0'0.0 0,0 0~0 0,0 0,0 0'0,0 0'0~0 0,0 0'0,0 0,0 0.6 1.4 0'0,0 0.0 0'0,0 0'0,0 0'0~0 0,0 0.0 0~0 0'0~0 0,0 0'I~5 3.~0~0 0~0 0'0'0'0.0 0.0 0'0.0 0'0~0 0'0.0 0'0'0.0 0~0 0.0 0 0 0~0 0 0 0.0 0.0 0'0'0~0 0,0 0'0~0 0 0 0'0'0~0 0'0'0'0'0,0 0'0~0 0'0~0 0'0'0,0 0 0 0~0 0~0 MIND StttD(NFHI 3.5 5.4 5.$7~~0,0'0 0 0~0 0'0,0 0'0,0 0,0 0,0 0,0 0~0 0,0 0'0'0.0 0.0 0'0,0 0 0 0~0 0.0 0.0 0'0'0~0 0,0 0'0'0'0'0'0.0 0~0 0'0,0 0.0 0.0 0~0 0,0 0'0'0'0 0" 0,0 0.0 0,0 0.0 0.0 7.5 12.4 12.5 1$.4 1$.5 24.4)%24,5 0~0 0.0 0~0 0 0 0.0 0'0'0'0.0 0.0 0.0 0~0 0'0'0.0 0.0 TOTAL 0 0 0~0 0~0 0'0.0 0'0'0'0'0~0 0'0 0 0,0 0~0 0'0'SUSTOTAZ 0,0 0.0 0.0 0'0'0,0 0'0'0 0 0.0 TOTAL HOVR5 OF.VALID STASILITT 045tRVATIONS 2043 TOTAL HOUR5 OF 5TASILZTT CLA5$4 0 TOTAZ HOURS Ot VALID MIND DIRtCTIOH MIND 5tttD STASILZTT CLA5$4 0 TOTAL HOUR5 Ot VAIZD MIND DIRtCTZON MIND SPCED 5TASILITT 0$5CRVATION5

.2021 TOTAL HOURS CAIN 0 00181 r~t, t BFN Rad Impact July-Dec 1989 Page 30 of 53 TABLE 1D (Page 2 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA THIRD UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RELEASES JOINT tCRCtNTAOt tRKOVCNCIKS Ot NIIID StCCD$2 WIND DIRCCTZON tOR STARILITT CLA$5 C (I 7~DtITA 2e24.5 0~0 0 0 0~0 0 0 0,0 0,0~0.0 0 0 0~0 0,0 0 0 0,0 0,0 0'0,0 0,0 TOTAL 1.437 1.623 0.093 0,0 0'0 F 274 2.59C 1.947 1 437 0.403 DATE)0,601 4,464 0'25 0 917 1.113 0.0 0,0 3~477 4.265 2,040 3.060 1~344 0~0 0~0 14.146 TOTAL NOUR5 OF VALID STASILITT OSSCRVATION5 2159 TOTAL HOUR5 OF STASZLZTI CLASS A 306 TOTAI COURS Ot VALID MIND DIRECTION MIND StCED 5TASZLZTT CLASS A 306 TOTAL ROUR5 Ot VALID WIND DIRECTION WISD StCCD 5TASIIITT OSSCRVA'IZORS 21S7 TOTAL COURS CALX 0 JOINT FCRCCNTAOE FRCOUENO'ZC5 OF lflND StEED ST MIND DIRECTION FOR 5TASILZTT CLASS R (1 94 DCITA Tfi I 7 C/100 Xl SROlfb5 tCRRT NUCLEAR tLAÃT OCT Ir 49 DEC llr it WIND DIRCCTIOII N NNC SE CNE 5 C5C SC$$5 5 55W SW'N5'W W MIW NN NIW CAIX 0,0 0,0 0,0 0'0,0 0'0,0 O,D 0,0 D'or 0,0 0~0 0 0 0~0 0'0~0 O'.6 I~4 0,0 0'0 0 0.0 0'0.0 0,0~6 4,046 0'0,0 0'0,0 0.0 0'0~0 0.0 1.5 3.4 0.0 0~0 0~0 0~0 0.0 0,0'0 F 271 F 232 0.0 0 F 046 0~0~6 0~046 0~0 0 F 046 0~046 0,0~6 0,046 0.145 0~0 0~0 0.046 D.OCC 0 F 093 0,091 0,046 0.046 0,0~6 0~115 0.139'.155 0 0~6 0'0~119 0'93 0,0 0~0 0,0 0'0,0 0 F 046 0,0 0~0 0,0 0'0~093 0 1)9 0,371 0,0 WIND StECDIXtNI

).S ST 4 S S 7.4 0~139 0~119 0,139 0~0 0,0 0,0 0,0 0,0 0.0 0~0 0~0 0~0~6 4,155 0~132 0,091 0.212 F 274 0'0'0,0 0.0 0.0 0'0~0 0.0 0'0'0'0 0 0~0 0.232 0.046 0'0'0'0~0 0'0.0 0 0 0~0 0,0 0 0 0~0 0'0,0 0'0.046 0'7~5 12~4 12.5 14 4 15~5 I~.4>>24 5 0,0 0'0,0 0~0 0,0 0 0 0,0 0,0 0~0 0,0 0~0 0~0 0'0,0 0,0 0'TOTAL 0~603 0~417 0~13~0,0 0~046 0~139 0 417 0 417 0.046 0,093 0~091 0 F 271 0~417 0 F 603 0~434 0,32$5USTOTAL 0~0 0~09S 0~411 I~205 0~141 1.205 0~556 0'4C 0.0 4 F 46'OTAL NOUR5 TOTAL NOUR5 TOTAI NOUNS TOTAI NOUR5 ,TOTAL COURS OF VALID 5TASILITT OSSCRVATZORS 2159 Ot STASILZTZ CLASS b 105 Ot VALZD MIND DIRECTION MIND 5tEED STASILZTT CLASS b 105 Ot 9'ALID IfIND DIRECTION If)CD StCCD STASZLITT 055RRVATZON5 2157 CALX 0 00181

~I f Ag I t BFN Rad Impact July-Dec 1989 Page 34 of 53 TABLE 2A (Page 2 of 4)BROMNS FERRY NUCLEAR PLANT HETEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR GROUND-LEVEL RELEASES JOINT tttCEIFFAOt FRtOUXNCXES Ot NXND I'ttto bf WIND DXRECTXON FOR 5TASILITT CLA5$C (I 1(DE(TA T(r 1,5 C/100 N)IROWNS FERRI NUCI EAR FLANT OCT 1~It DEC ll~It WIND D(btCTZON CALI(WIND 5tttD(llttl 0'I~4 I.S 3.~3.5 5.4 5~5 1~7~5 12.4 12~5 II~~1I~5 24~)02~5'totAL N NNE NS ENE 5 tSE 5t 555 5 I 55'N 5W NSW W WNW NW NNW 0,0 0~0 0,0 0~0 0,0 0,0 0'0'0.0 0'0'0,0 0,0 0'0.0 0~0 0 0 0,0 0~0 0~0 0,0 0~0 0'0'0'0,046 0,0 0,0 0.0 0.0 0,0 0 F 046 0 F 046 0'0,0 0'0,0 0.091 0~464 0.046 0~139 0~0 0~139 0,0 0 F 046 0'0'0.0(C 0,0~6 0.046 0'0~0~C 0'0~0 0,0 0'93 0'0'0 0 0,0 0~046 0 1IS 0~IIS 0.0 0~139 0~1IS 0,0 0.046 0,0 0,0 0,0 0'0'0'0,0~6 0.1IS 0'0,0~6 0.Sing 0'93 0.093 0.046 I~139 0~0 0~0 0,0 0,0 0~0 0~0 0,0 0,0 I~lit 0~139 0,0~6 0,046 0,214'.371 0.046 0 0 0'0 0 0~0 0~0 0'0'0'0'0 0 0~0 0~1$5 0,0 0.093 0~0 0'0,0 0 0 0'0~0 0~0 0 0 0~0 0,0 0~0 0,0 0 0 0,046 0.0~6 0'0 0 0 0 0~0 0,0 0,0 0'0'0,0 0,0 0,0 0,0 0,0 0,0 0~0 0,0 0'0,695 0'25 0~139 0~Otl 0,0 0.093 0.464 0~139 0~119 0.046 0~1IS 0,325 0,232 0~510 0,325 0.556 t SUBTOTAL TOTAL NOUR5 tOTAL NOUR5 TOTAL NOUR5 TOTAL NOUR5 TOTAL IlOURS 0~0 0~093 1.020 I'D 49 0,1II Ot VALID STAb!LZTT 0551'RVATION5 OF STASZLZTT CLA55 C OF VALID WIND DIRECTION WIND 5tttD 5TASILZTT CLA5$C OF VALID WIND DZRECTION WIND SFEED ITASILITT OS5IRVATZONS CALII 0,921 21St 92 92 2151 0 0 F 695 0'93 0,0 4,265 JOIST FERCtNTAOE tbt UtNCZ!S OF WIND 5FEED ST WIND DXRECTXON FOR 5TASILITT CLASS D (1 5(D'ELTA T(>>0~S C/100 III IROWNE FERRT SUCLtAR tLANT OCT I, It DEC 31~It NI ND DIRECTION 5 NNE Nt ENE ESE SE 555.5 SSW 5W NSN N lAIW NW NNW CALII 0.002 0,001 0,002 0 F 001 0~001 0 001 0.005 0,001 O.OOI 0~005 0,004 0.005 0.002 0 001 0.001'0 001 0 6 1.4 0'0.046 0 0 0~0 0'46 0,0 0.046 0,046 I~093 0,046 0 046 0,093 0~0 0'0'0'1.5 3~~0'32 0,139 0~232 0~091 I~Otl 0~1IS 0~1II 1~020 1~0~6 0.1420.556 0, F 95 0~311 0,139 0.139 0 1$5 0.F 11 0~CSS 0 lit 0~1I5 0~21$0.325 0,139 0.464 0,510 0~464 0'25 0,411 0.556 0~325 0,311 0'11 0,~64 0,914 0,325 0,091 0~0 0~046 O.139 o,lit 0 1IS 0,046 0,0 0~21I 0.311 0,21$0.275 0,311 WIND 59EED(NFNl 3'5.~5.5 1~~I 7IZ 2,364 O.C03 0~0 0~0 0,0 0.0 0'0~21I 0.Sing 0,0 0.311 0 F 464 0,5$1 0.556 I,IO~I~205 0'64 0'0'0'0,0 0'0,0 0'0'0~0 0'0'0~165 0 0~311 0,0 0~0 0~0 0,0 0.0 0,0 0'0.0 0'0'0,0 0.0 0,0 0.091 0~17~0~0 1.5 12.~12~5 XI 4 1~.5 24.4 l>>2~.5 0 0 0,0 0~0 0,0 0'0'0,0 0,0 0.0 0'0,0 0,0 0,0 0'0,0 0'TOTAI 5~101 4,6II I~300 0'11 0 biles 0.55$1 lit 1.6'~140 1~150 O.tll 1.560 I~16~I~902 2~45~1, 101 IUSTOTAI 0.0~6 0,464 6,676 5~9~1 3.951 10~153 F 060 0~111 0~0 30.111 TOTAL NODES TOTAX NODES t TOTAL NOURS TOTAL NOUNS TOTAl NODES Ot VALID 5TASILZTT OSSERVATION5 215$OF STASILZTT CLASS D Ccl Ot VALID W(ND DIRECTZON WIND 5)EED 5TASXZITT CLA55 D 663 Ot VALID WIND DIRECTION WIND SFEED STASILITT OSSERVATXONS IIS1 CALI(00181

BFN Rad Impact July-Dec 1989 Page 35 of 53 TABLE 2A (Page 3 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRTBUTTON jN PERCENT FOR GROUND-LEVEL RELEASES JoxNT rcbccN?Aoc rcc occczcs or wxND srcco I?NIND oxccc?xos Foc STAIILZtT CLA5$b'-0~Sl DELTA Tfi I,S C/100 KI IROWN5 FCRRt NVCICAR tLANT OCT I~I'I DCC 31, It'WZND DIRECTION N NNC NC CNE 5 CSE 55 55$5 Sslf 5N N5W N WNW NN NNN CALK I~016 0.006 0~04I 0~OOI 0~010 0~013 0~035 0~0~I 0~036 0,022 0.0'~011 O.OLL 0.006 0.0'~017 0'I~I 0.0(6 O.L39 0.093 0.093 0 0~6 O.L$9 0.371 0.32$O.LIS 0,2$2 0.139 0,OUI 0'93 Oio~6 0'0 139 L.S I.l 0.556 0'93 0~2$1 0~1$2 0 325 0,37L 0,9'.SIO 1.20$0~603 0'II 0'7L O.lit 0 LIS 0~139 0~$10 0.69$0.$10 O.LIS I~LIS O.LIS 0,27I 0~371 1.252 O,Clt o,olc 0.139 0,601 0~27$0.1~5 0~139 O,C(9 0 IL7 0~LIS 0,0 0.0~6 0 0 0,09$O,olc 0~27I 0~2$2 0,0 0'0~0~6 O,oic 0.09$4,0~6 0.$10 NzND IFEED(IIFNI 3.5 5~I$.5 7.i 0,325 0,0 0,0 0'0,0 0'0'0'0 IIS 0~Oic 0.0 o,oli 0'0~Oli 0 Oic 0 ll7 0.0 O.OIC 0'0'0~0 0,0 0,0 0,0 0,0 0.0 0.0 0 0 0.0 0,0 O.oic 0,1$9 0.0 0.0 0.0 0,0 0.0 0.0 0 0 0,0 0,0 0,0 0,0 0 0 0,0 0.0 0,0 o.o 7'12.~12 5 II'I~.5 2~.~)$2~.5 0,0 0'0'0 0 0~0 0~0 0 0 0~0 0 0 0~0 0,0=0 0 0~0 0 0 0.0 0~0 tOTAL 2,0$6 0'IO 0~sli 0.$6$0.$66 0~I9~I~797 3~l1 3 2,l93 0~9(9 I~090 1,12~O.III 0.562 0'21 I~lil 5VETOTAI 4.27I Lll l,530 6,3$1 2,0~0 I~113 0,232 oeo 0~0 10.677 TOTAI NOUR5 Ot VALID$?AIIXITT OISCRVATZON5 2159 TOTAL NOUR5 Ot 5?ASZLITZ CIA$5 5~i6 TOTAL NOQR5 Ot VALID NIND DIRECTION WIND I~CCD 5'tASILZTT CLA5$I~6 TOTAL NOVNS Ot VALID WIND DIRECTION lf(ND I~CED 5TAIIZ,IT?

OSICRVATIONS ZLS7 TOTAL NOUNS CALK JOINT FERCENTA4E tc'I UENCZE5 OF lfIND StccD RT WIND DIRECTION FOR 5?AIZLIT?CLA5$F (I S(DELTA T(i l 0 C/100 KI bROWNS tERR'I NUCLEAR tIANT OCT I~I'9 DEC 31, IS lflND DxbccrxoN N NNE NC ENC 5$55 5$5$$5 SSW SW NIN N WNW NN NEW O,oil 0 F 019 0.002 0,016 0,029 0.0$2 0,067 0~OII 0,035 0,00$0'09 0,002 0~001 0,007 0 F 005 o,oot CALK INC I~~0,091 0.0~I 0.0 0.139 0.2$2 O,lcl o,iCi 0.~Il 4.371 0.093 0.1$9 O,olc 0.093 0.0 4.093 4.093 I~5 3~I 0,$$6 0~~Ci Oeolc 0.27I 0.$56 0,927 l,ill 1.$$0 0 F 556 O,oic 0.091 0,0 0,0 0 1$$0.0~I 0.139 0~510 O,Cit 0~1$5 0~0 0'25 0 09$0.1$9 0,09$0 F 603 0,0 0'O.o 0 0 0 Of 0,0 0~232 I~139 0,0 0'(6 0 0 OIO 0.0 0 0 0~0 0~$25 0,0 I~4 0,0 0~Olc 0,0 o,oic O.oic NZND STEED(KFNI 3.5 S.l 5.$?.l 0.0 4.0 0.0 0,0 0.0 0.0 I 0 0,0 0.0 0~0 0 0 0~0 0'0,0 0,0 0.0 0~0 0'0'0'O.O 0'0~0 0,0 0,0 0'0~0 0~0 0'0,0 0'0'I 0 0,0 0,0 0.0 0+0 0,0 0,0 0,0 0,0 4.0 0,0 0,0 0.0 0,0 0'0.0 7~5 12~12 5 lb.l 1$~5 I~~I)02~5 0~0 4 0 0,0 0'0~0 0~0 0~0 0~0 0,0 4'0,0 0~0 0,0 0,0 0,0 0,0 TOTAI I~322 L 17I 0~1IO 0~ill L.Ill I~5$5 2~01~I~SIS I~Iit 0 Lli I~llo 0 0~I 0~lll 0,191 0~191 0~519 5UITOTAL 0.371 C.769 Ili Oecct 0~0 0,0 0 0 0,0 Ll Ils TOTAL NOURS OF VALZD STASZ'LITT OSSCRVATZONS 1159 TOTAL NOVR5 Ot STASILZT?CLA55 ltt TotAI.NOUNS OF VALID WIND DZRCCtlON WIND SFCED 5TARILITT CLA5$ltb'?OTAL NOQR5 Ot VALZD WIND DIRECTION lfxND StCCD$?ASILZTI OSSCRVATXONS 2157 tOTAL NOVNS CALI(I 00181

~'~'

BFN Rad Impact July-Dec 1989 Page 36 of 53 TABLE 2A (Page 4 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR'GROUND-LEVEL RELFASFS zoxNT rcaccNTAoc racoocacxcs or Nxab srcco ST wxan Dxacccxoa roa STASZLZTT CLA55 0 (DSLTA T I~0 C/xoo X)baoWN5 ttaRT NUCLSAR tLANT OCT 1, II DSC 11, 49 NZND DxaccTzoN N NNC Nt tat 5 555 55 555 I 55W SN W5W N NNW NW NNW CALX 0'75 0 07I 0'90 0.121 0 F 037 0.049 0.119 0.011 0~004 0,0 0~004 0'0 0 0 OOI 0,049 0~6 0.510 0~171 I~C95 O.IIS 0.27I 0.212 0'39 0~119 0~046 0~0~6 0 0 0~0 0,0 0,0 0,046 0 371 1~5 3~4 0,171 I~510 0 125 I~205 0~~14 0~145 0~417 1~l37 0~125 0.0 0~0 0.046 0'0~0 0,046 0.1IS 0.093 0,695 0~0 0 F 046 0~046 0~0 0~046 0~125 0~IIS 0'0,0 0 0 0'0,0 0,046 0,046 0,0 0,046 0~0~I 0,0~6 0'0,0 0.0 0 F 046 0'0,0 0.0 0'0 0 0~0 0~0 0~0 NIND Stttb(XINI 35545574 0.0 0'0,0 0.0 0.0 0 0 0'0'0,0 0 0 0,0 0.0 0 0 0~0 0,0 0 0 0,0 0,0 0,0 I 0 0'0,0 0'0,0 0'0~0 0'0'0,0 0,0 0,0 0 0 0 0 0~0 0,0 0'0'0'0,0 0'0'0'0'0 0 I~0 0~0 0.0 0~0 7.5 12.4 12.5 1I.4 1I.5 2~.4 402~.5 0 0 0'0.0 0,0 0.0 0'0,0 0'0'0 0 0~0 0'0,0 0 0 0'0'TOTAL 051 1.700 1~156 1~606 1~257 0'54 0,652 2~OIC 0,5I9 0.050 0,0 I F 050 0,0 0~0 0~1~7 0 F 652 SUbTOTAL 0.744 3 F 060 5~I~I 1.530 0,155 0~0 0.0 0'0.0 11~51 TOTAL NOURS TOTAL NOUR5 TOTAI NOUR5 TOTAL NOUR5 TOTAL NOUR5 Ot VALID STASZLZTT 055SRVATZONS 2159 Ot STASXLZTT CLA55 0 24~Ot VALID NXND DZRCCTZON WIND 5tttD STASZLITT CLA55 0 2l7 Ot VALZD WIND DZRSCTZON WIND 5rttD STASZLITT 055taVATION5 21ST CALX 17 00181 i Ig' BFN Rad Impact July-Dec 1989 Page 37 of 53 TABLE 2B (Page 1 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION stx,xT Joxbt tsaeENTAOE tas vsbexcs Or wxbo staso st wxho DIRECTION roa STAIILITI CLA5$A (DELTA TC%I~9 C/100 Nl IIOWN5 FCRRI NUCLEAR tLANT tART I ot I OROUND LEVEL 1CLCASC NODC OCT I g Is DCC 31, WIND D I R C CT I 0 N N NNC NC INC 5 551 51 55C I 55W CALN 0.0 0,0 0,0 0 0 0,0 0,0 0'0,0 0,0 0,0 0.0 0,0 0'0'0'0'0~0 0~0 0~0 0 0 0 0 0 0 0,0 0~0 0,0 0 0 0~0 0 0 0~0 0.0 0 0 0.0 0~0 0.0 0'0.0 0'0'0,007 0'05 0,019 o,ooi 0'0'0.0 0'0'0'0~I I.i).S).i 0,0 0~002 0~0 0'0'0~009 0.0))0~oil 0 120 0.017 0 oli 0 019 0,0 0 000 0~0 0.0 0,010 0~01)0,0 0,0 0~0 0 0 0 0 0~ois 0 042 0,0 0 oi7 0,03$0,005 0.005 0,017 0,00$WIND SFEED(hth)

).5 S.i 5-5-7'0 F 092 0~1)$0~01$0~0'0,0 0'I 0 0.0 0,0 0~019 0,0 0~0 0~0$)0~0li 0'5)0'95 0~li7 I~073 0 0 0'0 0 0'0'0 0 0,0 0'0,0 0'0,009 0~019 0~019 O,OSR 0,0 0,0 0,0 0~0 0,0 0~0 0'0,0 0,0 0'0,0 0,0 0'0'0'0'7~5 12.~12~5 ls.~14~5 2i.i)%2~.5 0 0 0 0 0 0 0~0 0.0 0,0 0 0 0.0 0~0 0~0 0~0 0'0~0 0 0 0 0 I~0 TOTAL 0.250 0,2'0~015 0~0 0,0 0'09 0 oiO 0~111 0,1I)0.0 i)0~oio 0~0$7 0~0$7 0~0)9 0~04~0 Iii SU4TOTAL 0~0 0~0 0,0)7 0 F 275 0.252 0, AD)7 0~)29 0~0 0,0 l,)71 TOTAL hooks Ot VALID 04$CRVATIONS Rli).000 TOTAL hov15 Ot OROUND LEVEL RCLCA5C 21$,200 TOTAL NOUR5 OF STASZLZTT CLA55 A 11,110 TOTAL hooks Ot OROUND LEVEL STASILZTT CLASS A 29,)io 5~LIT JOISt tERCENTAOC tas UENCZE5 ot WIND stCED ST WIND DIRECTION toR 5TASILZTT CLA55~(I~9(DELTA TC%1 7 C/loo Nl$10WNS FERRT NVCI CAR tLANT FAar I ot I Oaovho I.cvcx.RELEASE boos OCT I,$9 DCC)le Is WIND DxaccTzob b NNC NE ENE 5 CSC SC 555 5 SSW I'W W5W W WNW t NEW SUITOTAL CALN 0,0 0.0 0'0,0 0~0 0,0 0,0 0,0 0~0 0'0,0 0'0,0 0,0 0,0 0'0'O.S l.~0,0 0,0 0'0'0'0'0'0'0'0'0,0 0 0 0~0 0 0 0~0 0'0,0 1.5).~0'0,0 0.0 0'0,0 0,0 0'0,0 0'0,0 0.00i 0'0,0 0,0 0,0 0'I~osi WIND SFCCD(NFN)

)5 5~~$.5 7.i 0,0 0,007 0.0 0 F 007 0'0,0 0~0 0,0 0 F 001 0.0 0'0,0 0 0 0,0 0.00$0.009 0 F 001 0.0 0.005 0.0 0.0 0'0 010 0,0 0.0 0.015 0.0 0~010 0.0 0,022 0.0 0~0 0.019 0~0$9 0,012 I F 021 0,020 0'0'0'==0~0 0~0 0,0 0~0 0~0 0 00~'0 030 0')7 0.011 I~oil 0.05i 0,0 0~0 0~0 0~0 0~0 0,0 0,0 0,0 0~0 0'0 0 i 0'0~0 O,II'~015 0,0 0 0 0'0,0 0'0 0 0~0 0,0 0,0 0,0 0~0 0~0 0,0 0,0 I~033 0,0 I 195 0~155 0,0))7~5 12~I 12 5 II~I II.S Ri.~0.0 0,0 0 0 0~0 0,0 0'0~0 0,0 0'0,0 0'0 0 0~0 0,0 0'0,0 0,0 TOTAL 0~091 O,ORI 0 F 020 0,0 0 F 001 0,0 0'O,0li 0.00 I 0.00$0~00~0.019 0~oi)00 151%0'57 0~~9$TOTAI, COURS Ot VALZD 04511VATZONS Rlil~000 TOTAL hova5 OF OROUND LEVEL RCLEASC-225 F 200 TOTAL hooks OF STASZLZTT CLASS is,i)0 TOTAL books ot OROUND LCVCL STASILZTT CLASS 4 10,500

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BFN Rad Impact July-Dec 1989 Page 38 of 53 TABLE 2B (Page 2 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION IFLzT$0(NT rcactNTAOE rac Utaczt5 0F IIZND srtto ST NZND DxatcTzoa FOR ITASZI 1TT czASC c (1 7c DELTA Tci 1.5 c/300 III bkolAII FCtax NUCLEAR FLANT FART 1 Ot 1 OROUND LEVEL REZ,CASE NODE OCT le 49 DCC lie 49 N1ND DIRECTXON N NNE Nc tat C C5E 5C SSC 5 5$N SW CALN 0'0~0 0~0 0 0 0,0 0 0 0~0 0~0 0'0~0 0'0'0~0 0'0~0 0'0~6 I.~0 0 0.0 0 0 0~0 0.0 0~I 0 0 0~0 0'0,0 0'0 0 O.O 0,0 0,0 0,0 1.5 3.4 0~0 0.0 0 0 0'0,0 0,0 0 F 00'0 0~001 0,0 0~0 0.0 0,0 0,0 0,0 0'NZND SFEED(Era I 3'S.~5'7.4 0,001 0~019 0.0 0.030 0.0 0.0 0~I 0,004 0,0 0~0 0~0 0~0 0,0 0.0 0,00',0 0'0 0 0.0 0,0 0,0 0 F 009 0.0 0~017 0.0 0,0 0~0 0~00$0 F 001 0.005 0'0 F 007 0~017 0.007 0,013 0,0 0~0 0'0~0 0 0 0 0 0~0 0~0 0~01$0.011 0 F 005 0~00$0'44 I 047 0~010 0~0 0~0 0 0 0'0,0 I~0 0.0 0,0 0'0.0 0,0 00.0 0~019 0.0 0.0 0'0 0 0'0'0'0.0 0~0 0'0'0'0,0 0 Oli 0.041 0,0 7 3 11 4 11~3 I~4 1~3 14.4>%ZAN.5 0'0~0 0'0'0,0 0,0 0,0 0'0,0 0'0'0~0 0'0,0 0'0~0 TOTAL 0~133 0~0~7 0~011 0~004 0~0 0~0 0 F 00'006 0 F 001 0 0 0 F 009 0'31 0~011 0~111 0 F 056 0'73 5UITOTAL 0'0'0~007 0~OOI 0'93 0~1$4 0 191 0,077 0,0 0'33 T0TAL NQUR5 ot vALID 0$5cavATzoa5 3141~000 TOTAL NOVR5 OF OROQND LEVCL RELEASE 11$,100 T0TAL Novas ot STAazLzTT cLA$$c 35~030 TOTAL HOQR5 ot OROUND LCVC1 STASZLZTT CLASS C ll,ilo sroxT SOZNT rtaocNTAOE rac Utacxt$ot wxao Srcco ST Nxan oxatotxoa roa 5TASZLZTT CZAII D (l,SC DELTA TC~0$O/300 II)SkolAII FCRRT NUCLEAR FLARE FART 1 or 1 Oaooao Z.avcz, RELEASE Hoot OCT lr 49-DCC ll~$9 NZHD oxaccTZDN N aat Nt CSC C CSE 5E SSE 5 5 I'SN NIN N WSW NN SNN USTOTAL CALI(0,0 0,0 0~0 0,0 0,0 0~0 0,0 0~0 0'0'0.0 0.0 0.0 0'0,0 0'0,0 0~0 0~0 0,0 0,0 0.0 0,0 0 006 0,0 0.0 0~0 0'0'0'0.0 0.0 0'0~006 0 F 000'0 F 000 0.003 0 F 000 0 F 060 0.066 0 059 0~016 0~016 0~010 0~0 0'0'0,0 0.115 0.6 1.4 1$3.4 NZND 5FCCD(NFN) 3.5$.4 5.$7'0,019 0~03$I~014 0 F 097 0.001 0.014 O,ool 0,00'.013 0'0,034 0,007 0,011 0.01$0.071 0~OZI I~071 0~055 0~0$$O.OOI 0 F 030 0.0 0.01$0~041 0.036 0 F 045 0,013 0~015 0~004 0~010 I~011 0~035 I A ($6 0.474 0 494 0,409 0~100 0,0 0'0,0 0~0 0'0'94 0'09 0 0 0,06~0.076 0~1$3 0~09$0~ill 1~Ilo 0~ill 0~101 0~0 0'0'0~0 0'0'0'0'0'0,0 0,0 0~037 0~196 0'93 0~Iil 0,0 0,0 0 0 0.0 0,0 0~0 0.0 0'0'0.0 0 0 0'0'0~I~0 0.1$1 0.0 0~331 7.5 11.4 11~5 14~4 14 5 1~.4)0'0'0'0.0 0'0'0,0 0,0 0,0 0'0'0,0 0'0'0.0 0.0 0.0 0 0 TOTAX 0 I63 0,633 0 11$0,013 0.016 0,041 0.113 0,16$O.ZIO 0,04$0,047 0.1$$0.157 0.304 0 6~0 0,~43 171 TOTAL NOVR5 OI'ALID OSStRVAT10a5 1141 000 TOTA1 NOUR5 Ot OROUND LEVEL RCLCA5C 11$.100 TOTAL NOUR5 Ot STAOZLZTT CLA5$D 1113~1 30 TOTAl HOVR5 OF OROUND LCVEL STA51LZTT CLA$5 D 49,340

BFN Rad Impact July-Dec 1989 Page 39 of 53 TABLE 2B (Page 3 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION stLzt)OINT tcbccbTAOC Fccovcbcxcs or NZND stcco sv NZRD DIRCCTxob Fob STARZLZTZ CLA5$C I F 54 DCLTA Tc>>1$C/100 N}SRONN5 FCRRI NUCLCAR tLANT FART 1 Of I OROVND LCVCX, RCLIASC NOD!OCT I, I'I DCC 31, It'Nl!ID DXRICTXON N NNC NC CNC C CSC~SC SSC~I-CALM 0 0 4,0 0,0 0.0 0.0 0,0 0.0 0.0 0,0 0.0 0.0 4 0 0 0 0 0 0,0 0.0 0~0 0'0'0 0 o.o 0.0 0~011 0~413 O,OOI 0.004 0~0 0~4 0.0 0.0 0~0 0~0 0~012 0,0 0~009 0,007 0,00)0.011 0,079 0~171 0,100 0 041 0.031 0.007 0~011 0~009 I~001 0 007 O.C I~I~3)~4 MIND 5tCC).9 5~4 0'C)0,04$I~015 0.020 0~OL~0~01L 0.0$$0.2$7 O.LIS 0.007 0~021 0.049 0.017 0~Oll 0.010 0.040 D(NFNL$.$7.4 0~044 I~02$0 0 0~005 0,0 0~01$0,005 0~07$0~111 0.0 0,0 4.047 0,007 0~012 0~007 0,070 as 12.4 0.05$0'0'0'0~0 0.0 0,0 0'70 0.041 0.0 0.009 0,0 0 F 007 0,009 0.073 0'Oaoxx 0,0 0~0 0 0 0,0 0'0.0 0,0 0~0 0,0 Oeo 0'0'OeoL4 0,037 0.0 0~0 0~0 0 0 0.0 0~0 0~0 0 0 0,0 0 0 0~0 4.0 0.0 0.0 0.0 0.0 LIONS 10.4 1I.S 14.~>>>2~.5 0~0 0.0 0'0'0.0 0.0 0'0.0 0'0'0 0 0~0 0.0 0~0 0'0'TOTAX 0~193 0~0~4 0 F 025 0'34 0~021 0 F 057 0 1$$0~$19 0~41'~095 0 F 052 0 092 0~0~4 0~0~7 0 F 041 0 F 247 SUSTO'TAL 0,0 0~0)~0.$00 O.I as I~412 0 245 0,042 0 0 0'TOTAl.NOUR5 OF'VALID OSSCRVATION5 2142 000 TOTAL NOUR5 OF OROUND LCVCL RCICA5C 215.200 TOTAL COURS Of 5TARZLITI CLA55 C 400,0$0 TOTAL, MOORS Or OROVNO LCVCI, STARXLZTT CLASS 5 4S.ISO stx.xT JOINT tccccNTAOC rbcqvcbczcs or Nxbo stcco ST NIND Dxbcctxob rob STASZLZTT CLAS5 F I 1 5<DCXTA Tx>>4'C/100 NL SRONNS FCRRT NUCZCAR tLANT FART 1 Of I OROVND LCVCL RCLCA5$xxoDC OCT I~l9 DCC)I~I'9 NILID DXRCCTXON CALM 0 I I 4 5 3.4 NZND St!co(btbx 3.5$.4$.$'7.~'.5 L2.4 12.$-1I.~Ll.s 24.4>>>2~.5 TOTAL N NNC NC CNC CSC SC SSC 5 55N SN N5N 5USTOTAL 0 F 000 0~000 0.0 0,000 0 000 0.040 0~040 0~001 0,000 I F 000 0~040 0'0.0 0.000 0 F 000 0~000 0 F 002 0.0 0.0 0.0 0,0 0,000 0 022 0.014 0.0)~0.043 0.004 0,007 0 0 0 0 0,0 I 00~0'0,130 0 019 0.015 0~0 0~OLC 0~004 O.O)S 0~099 0~140 0 OI)0~OOI 0 F 012 0'0'0 OOC 0 F 000 0,011 0 lit 0 F 059 0~075-0 F 024 0'0.01$0~OOC 0~021 0~019 0 121 0'0 0 0~0 0'0'0,0 0 014 0.172 0.021 0.0 0.007 0~4 0.0 0 0 0,0 0.0 I 104 0.0 0,0 0.0 0,009 0 0 0,007 O.OOI 0,15$0.0 0.0 0~0 0 0 0.0 0~0 0.0 0~0 0 0 0~0 0,0 0~0 0~0 0'0'0~0 0 0 0,0 0.0 0.0 0 0 0,0 0,0 0.0 0 0 0.0 0'0,0 0 0 0~0 0,0 0'0~0 0~0 0~0 o.o 0,0 0.0 0.0 0.0 0.0 0.0 0 0 0,0 0.0 0.0 0.0 0,0 0,0 0,0 0.0 0.0 0.0 0'0.0 0.0 0.0 0,0 0,0 0 0 0~0 0 0 0~4 0.0 0~0 0 0 0~0 0,0 0~100 0,092 0,4)L 0~014 O.OL9 0~044 0~1)5 0~2)4 0'$0 0~012 O,OLI 0~0 0,009 0~004 0~011 0~OSO TOTAL MOVR5 Of VAXZD 0$5'CRVATION5 1142,000 TOTAL NOVR5 Of OROUND LCVCL RCLCA55 223 F 200 TOTAL MOVR5 OF STASZLITT CLASS f 2)0 A S)0 TOTAL MOVC5 Of O'ROUND LCVCL STASILITI CLA55 f 24,COO

'

BFN Rad Impact, July-Dec 1989 Page 40 of 53 TABLE 2B (Page 4 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES GROUND-LEVEL PORTION I'FZZT JOINT FZRCtbTAOC Ftt UCNCZC5 OF NZND 5'FttD SV WIND DIR!CTZON FOR ITASZLIT'I CLASS 0 (DCLTA T I~~0 C/joo Nl SRONN5 FCRRT NUCLCAR FIANT~ART I OF I OROUND LtVCL RtLCASC NODC OCT 1~IS DtC 31~I'NlND DZRCCTZON CAlJI 0.6 1.~1.5 3'WIND SFCCDINFNI 3.5 5.l 5'7.~7~5 12~~12~5 1I.~1$.5 I~.l)02I.5 TOTAL N NNC Nt CNC I CSC St 555 5 5USTOTAL 0 F 000 0,000 0,000 0,000 0 001 0~000 0~001 0 F 003 0.001 0 0 0,0 0~0 0'0,0 0'0 F 000 0~007 0~0 0~0 0 007 0.006 0 F 006 0 007 0~001 0~015 0'0 0 0~0 0.0 0'0'0'0,0 0~0~2 0~002 0~010 0~010 0~017 0~013 0 F 00'F 033 0.16I 0'55 0~0 0.0 0.0 0,0 0.0 0,0 0~010 0'5l 0~007 0,07$0'0 0 0.0 0,0 0'05 0~075 0,0~I 0'0 0 0,0 0'0,0 0~006 o,ool 0.223 0~0 0.005 0~OOI 0 00$0.0 0~0 0~0 0.021 0~0 0~0 0 0 0,0 0.0 0.0 0 0 0~0 0~0~6 0,0 0'0'0,0 0,0 0.0 0'0'0 0 0,0 0'0,0 0'0'0,0 0,0 0'0,0 0'0,0 0'0'0.0 0,0 0,0 0'0.0 0'0~0 0.0 0.0 0~0 0'0'0'0.0 o.o 0'0'0'0'0'0.0 0'0 0 0.0 0.0 0.0 0.0 0.0 0 0 0~0 0~0 0 0 0,0 0'0,0 0,0 0 0 0~0 0~0 0~0 0.0 0~0 0~0 0,0 0,0 0,0 0 00$0~107 0.026 0,033 0,060 0.015 o,ol3 0.251 0.0$$0'0 0 0,0 0.0 0'0'06 0~01l 0 672 TOTAL NOUR5 OF VALID 0551'RVATION5 2162~000 TOTAI NOUR5 OF OROUND LCVCL RCICASC 225.100 TOTAL COURS OF 5TASIZ ITT CIA55 0 102.620 TOTAL COURS OF OROUND LCVCL STASILITT CLASS 0 jl,loo 00181

BFN Rad Impact July-Dec 1989 Page 4l of 53 TABLE 2C (Page l of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT LEVEL RELEASES ELEVATED PORTION SPLIT JOINT tclCCNTAOC tRC UCHCZC5 Ot WIND SFCCD ST WIND DIRCCTZON fOR STASILZTT CLASS A (DCZTA'I(R 1 9 C/100 NI SROWNS ttRRT NUCLEAR FLINT tART 1 Ot 1 ELEVATED RCLtA55 NODE OCT lg 59 DCC 31, 19<<IND D I R C CT I 0 h N NNC HE CNC 5 CSE 5t 555 CALN 0'0~0 0'0'0'0,0 0~0 o.a 0~0 0,0 o.a 0~0 0'0'0'0 0 4.6 l.~0.0 a.o 0~0 0'0,0 0'0~0 0~0 4~0 0.0 0 0 0.0 0.0 0'0 0 0.0 1.5 3.~0,0 0,0 0'0,0 0 0 0 0 0,0 0.0 0.0 0,0 0.0 0'0,0 0,0 0,0 0.0 0~0 0 0 0'0,0 0~0 0'0~0 0'0'0'0'aio 0,0 0'0'oaa 0~0 0~0 0~0 0~0 0'0'00.0 I I 4~0 0'0'0'0'0 0 0~0 0~0 WIND StctD(NFN(3.5 S.~S,S T.i 0.0 0~0 0,0 0,0 0'~0'0 0 0 0 0~0 0'0 0 0~0 0,0 0'4.0 0.0 4,0 0'0,0 0,0 0'0,0 0.0 4.0 0,0 0~0 0,0 0.037 0,0 0,0 0,0 T.S 11.~11.3 1I~~la S 11 0~0 0.4 0~0 0,4 0.0 0,0 0.0 0.0 0 0 0.0 0.0 0.0 0.0 0 0 0 0 0 D)r16.5 0~0 0'0,0 0~0 0'0'0'0'0'0,4 0'0.0 0'0'0'TOTAL 0~0 0~0 0,0 0,0 0,0 0,0 0'0~OII 0.0 0'0'0'0~037 0'0'0'5URTOTAL 0'0.0 0.4 0'0 0~I 0.0 0.037 0.0 0~0 0~DI1 TOTAL HOUR5 OF VALID OSStRVATZON5 III I~000 TOTAL HOU'55 Of'CLCVAZED REL'CASts 1916 500 TOTAL HOURS OF 5TASILITI CLA5S A 31~110 ToTAL Hoots or CI,CVATED sTASZI.ZTT CLAss A 1 F 750 st(.IT 101NT tcxcchTAOE rlc uchclcs or<<Iho srcco sr<<Iho ozhccfloh rol STASILZTT CLA55 I (1,9(Dt(TA I(1.7 C/300 N(RROWN5 ttRRT NUCLEAR FLARE tART I Ot 1 ELCVA'IED RCLEASC NODC OCT 1~19 DCC 31~19 WIND N NNC Hc CNC E 55E 51'SC 5 55<<SW<<5<<W WNW CALN 0.0 0.0 o.o 0.0 0.0 o.o 0 0 4.0 4.0 4.0 0.0 0.0 0 0 0 0 NW 0.0 NNW 0.0 SUSTOTAL 4.0 4.6 0.0 0,0 0,0 0,0 0.0 0,0 0,0 0,0 0 0 0,0 O.D 0,0 0.0 0.4 0.0 0.0 0.0 1.3 3~(0 0 0'0'0~0 0,0 4.0 0.067 0.0 0,0 0,0 0~0 0.0 0.0 4,0 0.0 D.D 4~067 WIND 5ttc 3.5 S.~DINFH(5.5 T,i 0,0 4.0 0'0,0 0.0 0~0 0'0~0 4,0 0 0(6 0,0 0'0'0.0 0'0,0 0.0 0,0 0'0'0,4 0,0 0'0.0 0.0 0~0 0~0 0~0 0.0 0'0'0'0.0 0 066 0.0 0.0 0,0 0,0 0,0 0.0 0.0 O,DI~0,0 0,0 D,DIZ O.DIO 0,0 0,0 0,0 0.0 0,0 0 0 0~0 0 0 0~0 0~0 0.0 0'0'0 0 0'0'0,073 0,0 0,0 0.0 0 0 0'o.o 0'0,0 0,0 0'0 0 0'0'0'0,0 0 0 0'0'0~0 0 1(6 0.073 0~0 7.5 11~I 11~5 ls~~15 3 1~.I)%II'0,0 0.0 0.0 0.0 0.0 0.0 0,0 0,0 0,0 0.0 0.0 0.0 4 0 0.0 0.0 0.0 0~0 TOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0,0(7 D.DII 0.0 0.0(6 0.0II o.oao 4.073 4.0 0.0 0.0 4~(13 TOTAL Novas or VALID OSSCRVATIONS TOTA(HOURS Ot tttVATtD'RELCA5'C5 TOTAL HOURS Ot STASILITT CLA55 5 TOTAL HOURS Ot CLtVATtD 5TARILITI CIA55 5 11~1~000 1916,IOO 19~(SD I~ISO j

BFN Rad Impact July-Dec 1989 Page 42 of 53 TABLE 2C (Page 2 of 4)BROMNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLTT-LEVEL RELEASES ELEVATED PORTION SFLXt JOIST FCCCXSTAOC FbtovtSCXtc Of WXSD CFCCD UT WXSD DXRCCTXOS FOR 5TADZLZTT CLA$5 C (I 7(DCITA T(i I S C/100 Kl IROWNI FCRRX NVCLtAR FIANT PART I Or 1 CLZVATCD RtLCASt (toot OCT I~49 DCC 3)t IS WIND DXRCCTZOS SNC sc CSC t C55 St 0 0 0 0 0'0'0.0 0.0 0 0 0,0 0,0 0.4 0~0 0,0 0~0 0.0 0,0 0.0 0~0 0~0 0'O.o 0'0'0~0 0.0 0'0'Oro 0'0'0'0~0 0'0.0 0.0 0,0 0.0 0,0 0.0 0,1~0 0,047 0.047 AD 0.0 0.0 0,0 0,0 0.0 0 6 1.4 15 3~4 D(K1N(5~5-7.4 0.4 0~0 0'0 0 0~0 0.047 0.0 0.0 0,445 0 F 043 0,492 0.047 0'0~0 0~0 0'WIND SFCC).5 S.~0'4.0 0.0 0 0 4.0 4'47 0 093 0,0 0,0 0 F 047 4.49)4.0 0'0~0 0'7'12 4 12 5 14~14.5 0~0 0,0 0'0,0 0,0 0 0 0,0 0'0'0'0~OIX 0.124 0~0 0~0 0~0 0~0 0~0 0,0 0'DE 0 0,0 0.0 0.0 0 0 0,0 0.0 0,0 0'0.075 0 017 0 0 0,0 0 0 0~4 0~0 0,0 0,4 0~0 0 0 o.o 0'0.4 0.0 0.4 0.0 0 0 0~0 AD 0'0'0~0 0 0 0~0 0~0 0'0 0 0~0 0~0 0 0 0~0 0'0~0 0~0 TOTAL 0,0 0.0 0,4 0,0 0,0 0.093 O,J))0.047 0.092 0 F 041 0.11S O S)64 0.07$0.0)7 0,0 0.0 5VSTOTAL 0.4 0~0 0.231 0.244 0~273 0~205 0~112 0'0,0 l,)04 totA(Roots or TAI.ID 05$CRUAtzocs toTAL NOVNS Of CLC'l(AttD CCLtA5$5 TOtAL ROVRS 01 5TA4ZLZTT CLL$5 C TDTAL RovRs or cLcvAttD 5TASILITT cLAss c ZXI)oooo)916 IDO)5,050 23.640 51Lxt)OINT 1CRCtbtAOC 1cc VZSCX'C5 Of WXND SFCCD Rt WIND DxbtCTZON FOR STADILZTT CLASt D (I~5(DCLTA T(0 0~5 C/100 K)CROWNS FCRRT NUCLtAR FIANT FART 1 OF I CL'CVLTCD RRLCA5$KODC OCT lg 49 DCC)ly IS WXND D(ctCTIOS N ssc sz CNC C C5C 5C Sct 5$$'W$W'WSW CALK 0,0 0,0 0,0 0'0,0 0,0 0 D 0,0 0,0 0.0 0,0 0.0 0,0 0.0 0,0 0,0 0.6 X.l 0,0 0.0 0.0 0.0 4.0 0.0 0 0 0.0 0.0 4.0 0 0 ohio 0.0 0.0 0.0 0'I~5 l.~0'93 0,091 0~4 0.0 0~140 0~79'~314 0~2~0 0~D91 0~4'10 0.)27 0~XIO 0'91 0 1$7 0~047 0~)IO 0~)7)0~147 0.047 0~091 DAN 40 0 F 560 0~514 0~420 0*)71 0'67 0'73 0~S60 Oa560 0 F 560 Oe133 0 Io)O.ISO 0.)56 0.134 0,019 0.)12 0,6I)0.)13 0.62~0.227 0.535 0,265 O.S59 0.~92 0.6)0 0.3'99 WXSD 51CCD(KFN) 3~5-5~4 5~9 7'I~66~2.$94 0,566 0~125 0~D 0~170 0,406 0.99I I 019 0~$16 0~915 0.410 0 410 0.413 I~463 I~101 3 156 2.136 0 353 0~0 0~0 AD 0~II9 I~246 I~141 0 417 0~307 0'71 0~414 0 79I 0~67I I~39)0 56'.323 0'0,0 0,0 0,0 0~019 0~319 0,5')9 0 190 0.0 0,0 0.0 0,07$0 492 0.26I 7.5 12.4 12 I XI.I 1$5 14.~30]L,5 0.0 0,0 0~0 0.0 0.0 D.o 0'0.0 0,006 0,0 0~0 0'DE 0 O,D14 0~020 0~0 TO'TAX 6 F 576 6,669 I~SIS 0~305 O.II J 1,402 2.$61).903~~116 1.117 2~64~2~1$0 1.419 2 44$1.610 4~~41 SUSTOTAL 0.0 0 0)F 501 4.441 7,0'4.074 14.240 2.$4$0~019 (I~240 TOTAL NOUR5 or VALID DRSCRVATION5 TOTAL NOUNS or tLCVATtD RCLtASCS TOTAL NOURS OF STAIZLZTT CLLSS D TOTAL ROUR5 or I'LCVATCD STAIZLZTT CLL55 4 11~2~400 1916.IOO 1121~I)0 1033~730 BFN Rad Impact July-Dec 1989 Page 43 of 53 TABLE 2C (Page 3 of 4)BROtIlNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION 5FLZT)DZNT ttRCCNTAOC Fdt UCRCZC5 Ot NZND SFCCD bT NZND D1RCCTZON FOR 5TAbZLZTT CLA5$C{0~5I DELTA TI~1~5 C/100 hl IRONS FCRRZ RUCltAR FLANT FART 1 OF 1 CLCVATCD RCLCA5t hobt OCT 1~It DCC)1~'II 1ND DZRCCTZON h hht ht tht 1 155 55 55C 5 CALN 0.002 D,ooi O,ooi 0.002 0,0 0~013 0 006 0.004 0~ooi D 00$D,OOI 0.002 0.004 0.01)0,00$0.006 0.6 l.i 0,0 0.0 0'0,0 0,0 0 F 047 0,047 0,0 0.0 0.0 0 0 0 0 0.0 D,O 0.0 0'1.5).I 0.047 0.0$1 4~09)0.047 0 0 0~llo 0 0$)0~LIF 0.091 0.1~7 0.091 0~447 0.0$)0~1IO 0.1I7 0~LIO 4,1~0 0~2)1 0~514 0.0 0 AD)3)0~)IO le)20 0.700 0.560 0~2)1 0.5CO 4~2$0 0.I)0 0.23)0~LI7 0~147 0~)55 4~iol O.OII D,ot)0~179 D.LIL 0'90 0.9~5 0~I92 0~141 0.62~0~26t 0'67 0 F 225 0.092 0 F 227 NIRD IFCCDIRFR)

).5 S.I 5.5 7.4 1 F 027 027 0~535 0 05)0 F 167 0.496 0'4L 1.I)0 1~144 0~77I 0~707 0~574 0~25L 0'56 0~16I 0~656 0~0 0'0~0 0'0~0 0~0 0~154 0$91 O.I 56 0')7 0 F 076 0 037 0'0 0)I 0 0 0~15S 0~0 4'0~0 0,0 0 0 0~0 0~0 0.061 0~1I1 0~0 0~0 0~0 0,0 0.0 0'AD 7;5 12.~12.5 1$.4)I.S 2~.I)el i~5 0,0 o.o Oeo 0,0 0'0~0 0,0 0~0 0,0 0,0 0~0 Oeo 0,0 0,0 0,0 0 0'TOTAL 1 711'~TC1 1 190 0~124 D.SIO 1.299 1 792 I.)~5 1~$74 L.I)5 2,06t 1,209 1.035 1~245 0, 642 1,171 IVbTOTAL 0,09)O.DS)L.SCL 6.022 5~211 10~12)0~245 0,0 25.491 TOTAL 5004$Dt VAL1D 0$$'CRVATZONS TOTAL RDUR5 OF ELEVATED RELEASES TOTAL ROUR5 Ot 5TAbZL1TT CLASS 5 TOTAL RDUR5 Ot CLCVATCD STARZLZTZ CLA$5 5 llil~000 ltlC~400 600~050)34.600 5tLZT IOZNT FZRCENTAOt fdC UCNCZC5 Ot NZND IFCCD RT'NZND DXRCCTZON tOR ITASZLZTT CLASS f I L,SI DELTA TI a I~0 C/)DD h)~ROWNI t ERR'1 RV CLEAR SLANT FART 1 OF 1 tLCVATCD RCLCASC RODE OCT 1, It DtC lip It NZRD DZRCCTZON CALN 0~6 1~I 1~5 3~I NZRD SFECDlhthl 3.5 S.i 5.5 7.4 7'12.4 12~5 1'I 14~5 2l~I)~14~5 TOTAL 5 RRC ht tht 5 555 St$5!I 55N 5N NIN 0~0 0 0 0,0 0~0 0~0 0~0 0,0 0~0 0'0'0 D 0~0 0,0 t lAW 0 I 4 NW 0~0 NRW',0 5VITOTAL 0,0 0~0 0~0 0~0 0,0 o.o 0~0 0'0'oao 0,0 0'0,0 0.0 0,0 0,0 0,0 0,0 0~0 0'9)0.0 0.047 D,otl D.1 i 0 0.0 0 F 140 0, li0 0 047 D.LIO 0.09)0.447 0.047 0.0~7 0,0 1.074 0 047 0.091 0.0$3 0.0$)0.2))0.467 O.I10 0.700 0.2)l 0,)7)0~LIO D,lio 0,047 0 0 O.Lio 0'0,04)0~1IC 0,091 0.179 0.F 07 0~~LO 0.110 0.)61 0.270 0.0$1 O.oil 0.091 0 0 0'0 0'0.0)~221 2 516 0'65 0~252 0 207 0 166 D.))i O,OII 0,295 0'07 0.257 0,127 0.211 0~0 0,0 0~0 0.0 0.0 2.56'.0 0 F 077 0.0 0~115 0,0 0~0 0'0~0 0~0)9 0~0 0'0'0~0 AD 0~0 0 0 0'31 o.o 0.0 o o 0~0 o.o 0~0 0~0 0~0 0.0 0~0 0~0 0~0 0,0 0~0 0'0~0 0'0 0 0~0 0~0 0 0 0~0 0'0'0~0 0'0'0'0'0~0 0'0~0 0'0'0~ISS 0~7)2 0~391 0~Coo 1~067 1~101 1.026 1 IDI 0~SCS 0~61I 0')5 0'2'09)F 047 0~211 0~0 I~617 OTAI RDUR5 Of VALLD 045CRVATZORS TOTAL hOURS Of CLCVATtD RtLCAItt TOTAL NOVAS Ot STAbllZTT CLA55 TOTAL COURS Of CLCVATtD 5TASZLZTT CLA5$f 1142.000 191C,IDO 1)0.590 105,tto

,

BFN Rad Impact July-Dec 1989 Page 44 of 53 TABLE 2C (Page 4 of 4)BROWS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR SPLIT-LEVEL RELEASES ELEVATED PORTION SFI,IT JOIST FCRCCSTAOC FRC UCCCZCS Of WZCD 5~CCD ST dldb DZRCCTZOC fO'STASZLZTT CLASS 0 (DELTA T I 4~0 0/100 dl SROUSS ftRRT SUCICAR FIACT fART 2 Of 1 ELEVATED RCLCA55 CODE OCT 1,~I DCC)I, I9 WICD DZRCCTIOS d ddt CC CCC C CSC 55 55C I Std CALd 0~0 0~0 0,0 0,0 0,0 0 0 0,0 0'0'0,0 0 0 0'0.0 0'0'0,0 0.4 1.4 0~0 I 047 0.0 0'0'0'0,0 0~091 0~0 0 0 0.0 0.091 0,0 0~0 0.0 0,0 I~5 3.~0,0'0,0 0,0 0~140 0,0 0~140 0~110 0 117 0.0'0,0 0'0'0'0'0'0~093 UISD SFCCD(NFC)

)~5 5'5 5 7 4 0,0 0,0 0~0'Il 0~OI9 0'47 0~0 0'47 0'0 II7 I~OII I 5~0 0~409 0~157 0~093 0~420 0~091 0,0 0'35 0'0,0 0'0'0'0,0 0,0 0,0 0'0'0 0 0~0 0~0 0~0 7~5 12.4 0~0 0,0 0~0 0,0 0~042 0,0'I~I~3 0.117 0~125 0~OI3 0,0 0'0'0,0 0,0 0,0 12.5 15.4 0'0~0 0,0 0,0 0'0 0 0,0 0,0 0~0 0'0~0 0'0.0 0.0 0.0 0'1I~5 0,0 0~0 0,0 0,0 0~0 0,0 0 0 0,0 0,0 0,0 0,0 0'0,0 0,0 0'0')r24.5 0'0'0'0,0 0'0'0 0 0~0 0'0'0'0'0~0 0 0 0.0 0.0'ZOTAI 0~047 0.229 00~147 0~117 I 194 0~~03 0~919 0~loi 0,0I3 0~0 0'93 0,0 0.0 0.0 0'93 SUbTOTAL 0'0.131 0'34 I~5~I 0'07 0 50'.0 0 0 0'4 119 TOTAI EOUR5 Of VALZD OSSCRVATIOCS TOTAL COURS Of tLCVATtD RCLCAStt TOTAL COUR5 OF STAbILITZ CLASS 0 TOTAL COUR5 Of CLCVATtD 5TAIII ZTT CLASS 0 2142.000 1914.IOO 102.410 II~210 00181 i

BFN Rad Impact July-Dec 1989 Page 45 of 53 TABLE 2D (Page 1 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RELEASES JOINT tCRCCNTAOC tbt UtlfCZC5 Of fftllO St!CD bt NZND DIRECTION tOR STASILITT CLASS A (DCLTA Tf>>I 9 C/IOO f(l~ROWNS ftRR1 NUCLEAR f LANT OCT Iy 59 OCC 31~49 WIND DZRCCTION N NNE RC Cdt C Cbt St SSC 5 5$W SW W5W W WNW dlf NNW CALI(0~0 0~0 4.0 0~0 0'0'0.0 0'0'0'0 0 0~0 0 0 0~0 0~0 0'0,0 0~0 0,0 0,0 0'0,0 0~0 0,0 0,0 0'0.0 0'0'0'0,0 0 0 0.0 0,0 0.0 o.o 4,0 0,0 0,0 4'0.0 4.0 0,0 0~0 0.0 0'0.0 0 0 0 6 1.(1~5 I 6 0~0 0~0 0'0'0.0 0'0~0 0'0'0'0.0 0 0 0'0'0.0 0'0~0 0,0 0,0 0,0 0,0 0,0 0,0 0'0,0 0~0 0,0 0,0 0'0,0 0'0'WIND SttCD(dtdl I~5 5.(5.5 T.I 0,0 0.0 0 0 0.0 0.0 0.0 0~0 0.0(6 0 0 0 0 0,0 0 0 0,0 0,0 0 0 0.0 0'0~0 0'0~0 0'0'0~0 0'0'0'0'0~0 0'0'0~0 0'0 0 0 0 0.0 0~0 0.0 0.0 0,0 0~0 0 0 0,0 0~0 0,0 0~0(6 0,0 4'0'7~5 12'12.5 14.6 14'l>>2~~5 0.0 0~0 0.0 0.0 0.0 0 0 0.0 0 0 0,0 0,0 0 0 0,0 0.0 0,0 0.0 4,0 TOTAL 0~4 0~0 0~0 0~4 o.o 0.0 0~0 0'(6 0'0.0 0'0'o.o(c 0'0~4 0 0 0~0 0 0 0,0 0'0,0 0 066 0'0~0(6 0 0 0'93 TOTAI NOUR5 Ot VAt.lD 5TASZLZTT OSSCRVATZON5 2159 TOTAL ROVR5 Ot 5TASZLZTT CLASS A I TOTAL ROVR5 Ot VALID WIND DIRECTION WIND 5tCCD STAblt ITT CLASS A I TOTAL ROUR5 Ot VALID lftdD DIRECTION WIRD SSCCD 5TASZLITT OSSCRVATION5 21S9 TOTAL 50455 CAIN 0 JOZNT ttbotRTAOC fRC UCNCZC5 Ot'WIND SVCCD ST WIND DIRECTION tOR 5TA4ILITZ CLA55 4 (1~9(DELTA Tf>>1~7 C/100 Nl SROWNS ftRRT NUCLEAR tLANT WZND DIRECTION N ddt NC CNC 5 C5C SC 555 5 55'N SW WSW NNN SW NNW CAtJI 0.0 0.0 0.0 0~0 0.0 0.0 0.0 0,4 0.0 0.0 0.0 0 0 0~0 0.0 0 0 4.0 4~6 1~6 0,0 0.0 0'0'0,0 0.0 0,0 0,0 0,0 0,0 0,0 0'0'0 0 0,0 0.0 1.5 3.(0.0 0.0 0'0'0,0 0.0(6 0'0'0.0 0'0,0 0~0 0 0 0~0 0,0 O.O 0'0'0 0 0'0 0 0~0 0.0 0~0 0~0 0 0 0.0 0~0 0~0 0'0*0 0.0 0.0 0,0 0~0 0,0 0 0 0~0 0.0 0'0'0.0~6 Oso 0,0 0,0 0'0,0 0,0 0.4 0.0 0.0 o.o 0,0 0.0 4.0 0 093 0,0 0.0 4.066 0 0 0.0 4.0 0~0 0.0 OCT I, 59 OEC 31~$9 WIND 59CCDINtd) 3.5 5.6 5.5 2.(2.5 12.6 0~0 0.0 0'0'0~0 0'0.0 0 0 0~0 0'0'0.139 0'0,0 0~0 0~0 0~0 0,0 0~0 0,0 0.0 0,0 0,0 0,0 0 0 0~0 0~0 0,0 0~093 0'0 0 0 0 12~5 14.~1$.5 21.6>$24~5 4.4 0 0 4.0 0.0 0.0 0.0 0.0 0 0 0 0 0.0 0.0 0 0 0.0 0.0 0.0 0,0 TOTAL 0~0 0.0 0~0 Oeo 0'0 F 066 0'0 093 0'0~0(6 0~0(C 0 139 0~093 0'0,0 0'5USTOTAL 0 0 0 0 0~0~6 0,0 0 0(6 0 139 0~139 0~093 4,0 0~61 TOTAL SOVR5 Of VALID 5TASILZTT 045CRVATION5 2159 TOTAL NOVR5 Ot 5TASILZTT CLASS b 10 IOTA(, ROUR5 Ot VAt,lD WIND DtbtCTION'WIND Sttto STASILZTI CLA5$4 10 TOTAL NOVR5 Of VALID WIND DIRECTION WIND StCtD 5TACZ(ZTT OSSCRVATZON$

2159 TOTAL COURS CALI(0 00181

BFN Rad Impact July-Dec 1989 Page 46 of 53 TABLE 2D (Page 2 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RELEASES JOINT FCRCtlfTAOC FRIOUtlfCIC$

OF NISD ItICD RT if)MD DIRCCTZON 10%STAOI LITT CLASS C (I 7(DtLTA T4%I~5 C/100 Nl Stolf55 FCRRT SVCZ CAR tLAST OCT I~49 DtC 31~49 MIND CALff O.C 1.4 1.5).4 WIND 5FCCDINtltl i.$.$.$7.5 11.4 12'1$.4 II'I~~~>%2L~5 TOTAL ll NSC Nt tSC 5 tlt 55$55 5 5SW 5W WIM W WÃlf NW RNW 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0,0 0.0 0,0 0,0 0,0 0 0 0 0 0,0 0,0 0,0 0,0 0~0 0.0 0'0,0 0,0 0~0 0,0 0~0'0~0 0,0 0 0 0'0'0,0 0.0 0,0 0,0 0,0 0~0 0,0 0'93 0,046 0'0,0 0~046 0,0 0,0 0 0 0,0 0,0 0~1IS 0,0 0,0 0,0 0,0 0,0 0,046 0,046 0,0 0,0 0.0 0.093 0,0 0.0 0,0 0.0 0.0 0.1~5 0~0 0~0 0'0'0'0~0 0'0 0 0~0 0~0 0~046 0 F 046 0 0 0'0~0 0'0~091 0~0 0,0 0~0 0~0 0'0'93 0~044 0'0'0'93 0'93 0 139 0'0,0 0,0 0 0 0'61 0.0 0,0 0 0 0,0 0.0 0.0 0,0 0~0 0'0'0,046 0~046 0.0 0~0 0 0 0~0 0,093 0,0 0,0 0,0 0,0 0.0 0.0 0,0 0,0 0~0 0.0 0,0 0.0 0.13$0,0 0.0 0.0 0 139 0~0 0~0 0,0 0~0 0 0 0.0 0~0 0~0 0,0 0'0 0 0,0 0'0.0 0'0~0 0~0 0'0~0 0,0 0.0 0.0 0~139 0 1$5 0.046 0.0 0~093 0'24 0'32 0'39 0.0 0,0 0,0 1 15$TOTAL SOVR5 OF VALID STAOILITT 055CRVATIOSS 1159 TOTAL COURS Ot 5TARILZTT CIA5$C 25 TOTAL COURS OF VALZD WIND DIRCCTZOS WIND StttD 5TARILITT CLA5$C 25 TOTAL COURS OF VALID MIND DIRCCTZOS lftSD 5tCCD 5TAR'ILZTT 055CRVATION$

215~TOTAL SOU15 CALM 0 JOIST ttRCCNTAOC FRt VCSCIt$Ot NISD StCCD RT lftbD DIRtCTZOS FOR 5TASILITT CLASS D 4 I,S(DCLTA T4%0 5 C/100 ill SROlft5 FCRRT SUCLCAR tLAST WIND DIRCCTZOS N Stt Nt tNt 1 CSC St 55t 5 55M SM W5W W WNW Slf NNM CALM 0,002 0,0 0.0 0,0 0,001 0,002 0.004 0 F 00',0'.001 0~004 0~004 O,OOI 0 F 001 0,004 0'0.4 I~4 0,046 0,0 0,0 0.0 0,0 0'0 0 0,0~I 0~046 0,0 0'0,0 0'0,0 0,0 0'1.5)~4 0~091 0~0 0,0 0'0~046 0~13$0,)TI 0,463 0.463 0~046 0'7I 0.232 0'09 0.046 0.232 0,0 0~IIS 0.)TI 0,0~I 0~1)9 0~0 0,443 0~443 0,324 0~13~0 1)9 0.27I 0~145 I~1$5 0.417 0,27~0 093 0,232 0, F 02 0,0$3 0.0 0,139 0.371 0,509 0,371 0~212 0.417 0.324 0.232 0.371 0.556 0.64I 0,171 OCT 1$~9 DCC 31$WISD StttDtllttl 3.5 5~5~5 7.~I~621 2.640 0~556 0'32 0.0~I O,cil 0~741 1 436 0 F 926 1,111 1.390 0,602 0'56 0.$34 0~IIO I~ISI 4,539 2,131 0 741 0,0 0'0~0 0.324 1.251 1 760 0'09 0,556 0.757 1 019 I~204 0 F 550 1.779 2.270 0'24 0'93 0,0 0,0 0 0 0.124 O.I)4 0.926 0~695 0'93 0.171 0.417 0,463 0.$16 1.111 7.5 12 4 12~5 15.4 tl~5 I~.4 f%1~~5 0'0.046 0'0'0.0 0.0 0'0 0 0.0~6 0~13$0'0'0'0.171 0.602 0'TOTAL 4,94$6.021 1,52$0.371 0.23'I I 623 I~Cii T)2 4'47 3.05I 2 922 I~412 3.0~5 3.191 i.450 5~512 5VITOTAL 0.046 0~139),I)5 1~413 5 465 15.377 ll 4$1 I~$47 1~204 55~994 TOTAt SOVR5 OF VALZD STARILZTT 055CRVATZONS 2159 TOTAt$SOUR5 OF 5TARILZTT CLL55 D 1209 TOTAL NOVR5 OF VALID NIND DIRCCTZOS MIND 5FCCD 5TARILZTT CLL55 D 1209 TOTAL SOV15 OF VALID WIND DIRCCTIOS MIND 5FCCD 5TARILITT 05551VATZOS$

1159 TOTAt$SOVR5 CALX$I 00181' 4 tfV j'<

BFN Rad Impact July-Dec 1989 Page 47 of 53 TABLE 2D (Page 3 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RELEASES)ozst rcacxsTAUE rac Ucsc1E5 ot lfzsD srccD bt wzsn OIRECTzos F0%5TASZLZTT CLASS 5 I 4~SI DELTA t(i 1,$C/200 NI baosss I'ERRT RVCLEAR SLANT OCT 1>I'I DCC 31, It UZSD DXRCCTZOS s ssc sc CSE I 555 SC SSC 5 SSU 4 fr SSN W USN sw SSN CALN 0~004 0,001 0,0 0~004 0.002 0.006 0.004 4.002 0,002 0~0 0.0 0.002 0,0',009 O,OOC 0 F 002 0.0 0.0 0~0 I~0 ic 0,0 0,046 0,0 0~0 0~0 0~0 0~0 0,0 0 0 0~0 0 0~I 0~0 0,093 0.046 0.0 0~0~I 0.044 0~091 I~091 0~046 0~0~I 0,0 0'0~046 0'93 0'32 0.09)0 F 046 0'2.4 2.5)~~NIRD srcc)~5 5~I 0.093 0~093 0~0 0~093 0 232 0 1)t I~232 0'9)0.232 0 139 0'93 0,0~6 0~2)2 0 1)t 0~1I5 I~2)t DZNrsr 5.5 7.4 0~139 0>xlt 0>093 0 239 0.046 0~212 0 27I 0.27I 0,741 0 ZIS 0,1'0,091 0,091 0,139 0.145 0,09)0.602 0.601 0.271 I~)71 0.093 0.~17 0 371 1.343 2~667 0'09 4.434 0$)C 0.)24 0,371 0.2)2 0'IS 2 F 065 00'41 0.0$1 0.0 4 6 0, 172 I 5$6 2.3$0 1,724 0 971 0,~40 0~973 0~212 0.)71 0~046 0,601 0~0 0,0 0~0 0~0 0,0 0 4 0 139 0~463 0~~II 0'46 0~093 0~OIC 0'0.4'0'0.491 7~3 12.4 12~5 14~4 14~5 2~~I 0 0 0,0 0 0 0~0 0,0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0~0 0'0'TOTAL 1 99$2.6CS 1,112 I~791 0.46$2,302 1.471 3.62$5.0$4 1 IS)2~0 II 2,132 I~$7C 2,304 0'9)1,160 0.0~I 019 2~177 1~057$,125 20,4)I 1.575 0~0 27,97C tOTAL COURS Ot VALZD 5TARZLZTT OISCRVAT1055 2259 TOTAL COURS Ot 5TAbxLZTT CLAS5 I C04 totlr.Rooas or vaoxn wxso nxalctxos-wxsn srcln-ITAbxLztt cLAII 5 40I toTAZ, ROUR5 ot vALZD NIRD ozacctzos Uzsn 5rscD ITAIIL)TT 055cRvATZos5 2139 toTAL COURS CALN 2 zoxst rzaccsTAOE tss Usscxcs or Uzso srcEn bt wxso ozasctxos roa STASXLZTT CLASS t I 2 3(DELTA Tfi I~0 C/100 NI IROUSS FCRRT SVCLCAR tLAST OCT 1>It DEC)1>It lfISD DIRECT)OS CAXN 4.6 I.I 2.3 3.~lf1RD 5rcED(Ntsl

).5 5.4 5.5 7'7.$12.~12~5 II~I 25.5 1~~I>%2~~5 TOTAL s SSE SE ESE C 555 IE 555 5 SSW 5W Uss W USU Nf 5 Elf 0 0 0.0 0 0 0.0 0.0 0'0 0 0~0 0,0 0'0'0,0 0,0 0.0 0.0 0,0 0.0 0~0 0'0,0 0'0,0 0~0~4 0,0 0 0 0,0 0.0 0'0,0 0.0 0,0 0 0 0~Otl 0~OIC 0~0 0~0 0~046 0~1)9 o.o 0'0'0,0~I 0.0 0'0~044 0.046 0~Oic 0.0 0,046 0~0 0~0 0~OiC 0,0 0~Oic 0,0 0~093 0~046 0~OIC 0,093 0.046 0~091 0~139 0~046 0.046 0,0 0.0 0,0 0,091 0.239 0.$$6 0 119 0,091 0,091 0,0 0~0 0'39 0,)IS 0.139 0,0 0,0 0,0 0~046 0.0~I 0,046 0.)71 0.642 0~1)1 0.)71 1,04$0~212 0~274 0,)IS I 11$0'0.046 0 0 0~139 0 417 0,371 0,27I 0~046 0 139 0,145 0,27~0~402 0~232 0.)71 0~Oic 0'0,0 0~I 0,0 ZOIC 0.139 0~0~6 0~0~I 0'0 0 0~0 0~0 0.04~0~046 0~0 0'0 0 0'0'0~0 0~0 0>0 0~0 0~0 0'0,0 0~0 0,0 0,0 0,0 0,0 o.o 0 0 0,0 0,0 0,0 0.324 0.644 0,463 0'09 0,602 2.~Il I 602 0~I34 1.IS)0~602 0,741 0.417 0.$09 0 324 0.139 4.0~I 5UITOTAL 0.0 0~046 0 309 0.747 2.$75).70$1~101 0~)72 0.0 10~097 TOTAL SOVR5 Ot VALZD STASILITT 045CRVATZOES 2159 to'TAL COURS OF 5TASZLZTT CLASS F 21)TOTAL COURS Ot VALZD NZED DIRECT105 lfIED 5FECD 5TASZLZTT CZAI5 t 21I totar.sovas or vALzo wxsn oxacctxos-wzsn srcco-STARILztt obscavatzoss Zxlt TOTAL ROVRS CAXN 0 00181 4

BFN Rad Impact July-Dec 1989 Page 48 of 53 TABLE 2D (Page 4 of 4)BROWNS FERRY NUCLEAR PLANT METEOROLOGICAL DATA FOURTH UARTER 1989 JOINT FRE UENCY DISTRIBUTION IN PERCENT FOR STACK RELEASES JOIST FSRCSSTAOS FREOUESCIES OF VISD I~EED ST VIRD DIRSCTIOV FOR STAR!LITT CLASS 4 (DELTA T>I 0 C/100 bl SROVSS FIRST EUCLEAR tLART OCT I, IS DEC Il~IS VIED DZ RECT Z OS CAIJl O.C I.I I.S 3~I VIED I~EED(NFE)3.5 S.l 5 5 I~~7.5 12.~32.5 II.l 34.5 I~.~>sII.5 TOTAI 5 RRE RE ERE 5 ESE SE 555 I 5SV 5V VSV V VRV RV l b EV SUSTOTAL 0~0 0,0 0.0 0~0 0,0 0'0'0,0 0'0~0 0'0'0,0 0,0 0.0 0.0 0 0 0~0 0'0,0 0,0 0.0 0'0,0 0'0'0.0 O,olc 0'0,0 0,0 0'0'0,0~I 0~0 0.0 0 0 0~0 0.093 0~Olc 0,0 0'0'0'0'0'0~0~~0~Ol~0,0 0~0 0.212 0.0 0~0 0~0 0~0~I 0~139 0~091 0,0 0~Ol~0,0 0~212 0,0 0~Olc 0.0 0'0.0 0.093 0~C95 0~Olc 0 0 0~0l I 0.0 F 093 0 F 232 0 139 0~0~I 0~Olc 0'0'0'0'0'0 0 0~0 0~CII 0~0 0.0 0'93 I~0l C 0 093 0'09 0 ll7 0.119 0.32l 0 0~I 0~139 0.0 0~0 0.0 0~0 0'I.IOC 0,0 0,0 0,0 0~0 0 0 0~195 0~0 0~093 0.32l 0,091 0,0 0,0 0 0 0,0 0,0 0'O,C95 0 0 0~0 0~0 0~0 0~0 0~0 0~0 0 0 0 0 0,0 0'93 0,0 0,0 0,0 0.0 0,0 F 093 0.0 0,0 0.0 0.0 0,0 0.0 0,0 0.0 0 0 0 0 0 0 0 0 0.0 0,0 0 0 0 0 0.0 O.olc 0.0 O.l39 0~0'93 I I 37 I.OC5 0~55C 0~32~O.CSS 0~371 0~23I 0.0~I 0~0~I 0~Olc 0~0 0~093 I~215 TOTAI, ROURS OF VALZD 5TASZLZTT OSSERVATIOS5 2159 TOTAI ROUR5 OF STASZLITT CLASS 4 Sl TOTAL DOORS OF VALZD VIED DIRECTZOS VIED SFEED I'TASILITT CLA55 0 91 TOTAL ROUR5 OF VALID VIED DIRECTIOE VIED StEED STASILZTT 045ERVA'TZOSS Il59 TOTAL ROUR5 CAIJI 0 00181 i~l+II pk Page 49 of 53 TABLE 3 BRO S FERRY NUCLEAR PLA-RECEPTOR LOCATIO S A D POINTS OF INTEREST POI DISTANCE SEC OR m PO T DISTANCE SECTOR m Site Boundary locations Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary N 1525 NE 1250 E 1375 SE 5600 S 2550 SW 2300 W 2550., NW 2275 Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary Site Boundary NNE 1300 ENE 1450 ESE 1575 SSE 2875 SSW'425 WSW 2500 WNW 3325 NNW 1650 Real Receptors used for airborne doses (based on Fall 1989 Land Use Survey)Resident Resident Resident, Garden Resident Resident, Garden Resident, Garden Resident Resident Garden Garden Garden Garden Milk Cow Teen Milk Cow Child N NE E SE S SW W NW N NE W NW N WHW 1676 3772 3810 8100 4534 5066 2629 3048 1672 4420 3048 3543 7924 5181 Resident Resident Resident Resident, Garden Resident, Garden Resident, Garden Resident Resident Garden Garden Garden Garden Milk Cow Teen Milk Cow Teen NNE ENE ESE SSE SSW WSW WNW NNW NNE ENE WNW NNW ENE NNW 2705 1715 4343 7087 , 4191 4343 4534 1524 2895 2705 5410 1829 9448 10972 R, S++g y~~J Page 50 of 53 TABLE 4 F-'YEAR SUMMA Y OF UARTERLY DOSES*Air Submersion Real Pathway Air-Ai-B Skin TB Max Or an Year QTR mrad mrad mrem mrem mrem Liquid Effluents TB Max Or an mrem mrem 1985 1.07.12.10 2<.001<.001<.001 3<.001<.001 0.0 4<.001<.001 0.0.06<.001 0.0 0.0.03 Thyroid.017 Bone.Ol Bone.01 Bone.09.18.05.10.12 Liver.24 Liver.07 Liver.14 Liver 1986 1<.001 2<.001 3<.001 4<.001<.001 0.0<.001<.001<.001 0.0<.001 0.0 0.0.01 Bone<.001<.001 Liver 0.0<.001 Liver 0.0<.001 Liver.08.23.15.03.11 Liver.31 Liver.19 Liver.04 Liver 1987 1<.001 2<.001 3<.001 4<.001<.001<.001<.001<.001<.001 0.0<.001<.001<.001<.001 0.0<.001.0015 GI Tract.0024 GI Tract.0037 GI Tract.0071 Liver.02.05.06.09.02 Liver.07, Liver.07 Liver.12 Liver 1988 1 2 3 4 1989 1<.001<.001<.001<.001 0.0 0.0 0.0 0.0<.001 0.0<.001 0.0<.001 0.0<.001 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0.0001 GI Tract.0051 GI Tract.0022 GI Tract.0026 Bone<.001 Thyroid<.001 GI Tract<.001 Bone<.001 Thyroid.02.13.09.03.007.008.008.004.03 Liver.17 Liver.12 Liver.03 Liver.01 Liver.01 Liver.Ol Liver.006 Liver*Note: All calculated doses are below limits specified in Appendix I to 10 CFR 50.

BFN Rad Impact July-Dec 1989 Page 51 of 53 FIGURE 1 BFN Airborne Effluents Fission Gases Released and Resulting Doses 700000 Legend BFN releases 600000>500000 0400000 0 300000 K C o 200000 100000~l I I 1 I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 4.0 3.5 3.0 D 0 2.5~E 0 O 2.0 1.5 1.0.5 Gamma dose Beta dose 80 81 82 83 84 85 86 87 88 Bg bfnf

BFN Rad Impact July-Dec 1989 Page 52 of 53 FIGURE 2 ,50 SFN Airborne Effluents lodines and Particulates Released and Resulting Doses Legend.45 BFN releases.40 1.6 Maximum organ dose C.35 L 8 Q 0 g).30 0 8 9 a'8"'<.25 Cl aO 3 0 o.20 EL 0 C 0 m~15 0)C U 0 ,10 1.4 12 E L E 1.0 Pn 0 0 C 0 Ql.8 ,4~05.2 80 81 82 83 84 85 86 87 88 89 E bfn2 l

BFN Rad Impact July-Dec 1989 Pase 53 of 53 FIGURE 3 BFN Liquid Effluents Fission and Activation Products Released and Resulting Doses Legend BFN releases 4 8 C 1 I 8 0 I 8'C 3 ID ao 0)w 8 o'I I I I I I I 1 I I I I I I I I I I I I I I I I I I I h II I I I I I 1 I I I I I I I I I I I I I I I 1 I I 1 I 1 I I I I 1 1 I I I I I I 1 r I 1 1 1 1 I 1 1 1 I 1 1 lr 1.6 1.2 E 1.0~E 0 Q.8 Total body dose Maximum organ dose.2 80 81 82 83 84 85 86 87 88 89 bfn3

ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1989 Page 1 of ll EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT

SUMMARY

SECOND HALF 1989 The radioactive effluents for the second half of 1989 were normal for a three unit boiling water reactor plant in its fourth year of an extended outage.Because of the extended outage, only radionuclides with a long half-life (longer than a few months)have not decayed away and are being released to the environment.

The radioactive decay is particularly significant for gaseous effluents because no fission gases or radioactive iodines are being released.The only radioactive gaseous releases are very small quantities of particulate matter.The radioactivity being released now in liquid effluents is primarily long half-life radionuclides that have been deposited on the surfaces of piping and components.

During normal outage work this radioactivity is removed by process water that is purified and released to the river.The water purification process is unable to remove all the radioactivity before it is released to the river.The release of radioactive material to the environment from Browns Ferry Nuclear Plant has been a small fraction of the lOCFR20 Appendix B and 1OCFR50 Appendix I limits during the second half of 1989.

4' Page 2 of ll EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1989 Re ulato Limits A.Fission and Activation Gases in Gaseous Effluent: 1.The release of fission and activation gases is regulated by the dose limits of 10CFR50 Appendix I.The air dose to areas at and beyond the site boundary due to noble gases released in gaseous effluents per unit shall be limited during any calendar quarter to g 5 mrad for gamma radiation and g 10 mrad for beta radiation; and during any calendar year to g 10 mrad for gamma radiation and g 20 mrad for beta radiation.

B and C Iodines and Particulates with half lives greater than eight days in gaseous effluents.

1.The release of iodines and particulates in gaseous effluent is regulated by the dose limits of 10CFR50 Appendix I.The dose to a member of the public from radioiodines, radioactive materials in particulate form, and radionuclides other than noble gases with half live greater than 8 days in gaseous effluent released per unit to area at and beyond the site boundary shall be limited to any organ during any calendar quarter to g 7.5 mrem, and during any calendar year to g 15 mrem.D.Liquid Effluents 1.The release of radioactive liquid effluents is regulated by the dose limits of 10CFR50 Appendix I.The doses or dose commitment

'to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas shall be limited during any calendar quarter to g 1.5 mrem to the total body and<5 mrem to any organ and, during any calendar year to<3 mrem to the total body and<10 mrem to any organ.

t& Page 3 of 11 EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1989 Maximum Permissible Concentrations A.Fission and Activation Gases in Gaseous Effluent 1.The instantaneous release rate of fission and activation gases is regulated by the dose rate limit of 10CFR20 Appendix B.The dose rate at any time to areas at and beyond the site boundary due to noble gases released in gaseous effluents from the site shall be limited to<500 mrem/year to the total body and<3000 mrem/year to the skin.2.The BFN Offsite Dose Calculation Manual (ODCM)determines the maximum noble gas release rate based upon the dose rate limits in II.A.1.The instantaneous noble gas release rates are limited by the following equation: gl+g2<1 0.15 14.4 Ql=The release rate from the building exhaust vents in Ci/sec.Q2=The release rate from the main stack in Ci/sec.B and C.Iodines and Particulates with Half Lives Greater than 8 Days in Gaseous Effluents.

1.The instantaneous release rate of particulates and iodines is"regulated by the dose rate limit of 10CFR20 Appendix B.The dose rate at any time to areas at and beyond the site boundary due to I-131, I-133, H-3 and particulates with greater than eight days half-lives released in gaseous effluents from the site shall be limited to<1500 mrem/yr to any organ.2.The BFN ODCM determines the maximum particulate and iodine release rate based upon the dose rate limit of II.B and C.l.The instantaneous iodine and particulate release rates are limited by the following equation: Q3+g4<1 2.19 35.7 Q3=The release rate from the building exhaust vents in mCi/sec Q4=The release rate from the main stack in mCi/sec.

A i(l%~~~i1'bt Page 4 of llEFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1989 D.Liquid Effluents l.The concentration of radionuclides in liquid effluents released at any time from the site to unrestricted areas shall be limited to the concentrations specified in lOCFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.2.For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 mCi/ml total activity.III.Average Energy-Not applicable IV.Measurements and A roximations o Total Radioactivit A.Fission and Activation Gases: 1.Noble gases in the gaseous effluent from the building vent and stack are continuously monitored.

The flow rate of the stack is continuously monitored and the building vent effluent flow rates are calculated once a shift based on the configuration of operating exhaust fans.The flow rate data is consolidated weekly to determine the volume of airborne effluent released from the plant.The noble gas monitor data is consolidated monthly to determine the total curies of noble gases released during the month.2.Gas grab samples are taken and analyzed monthly to determine the relative noble gas activity concentrations.

This information is used to apportion the total curies of noble gases released between different noble gas radionuclides.

3.The tritium concentration is determined by the analysis of a monthly grab sample for each release point.B and C.Iodines and Particulates l.Iodines and particulates are continuously sampled on impregnated charcoal filters and particulate filters, respectively.

The charcoal and particulate samples are replaced at least weekly and analyzed to determine specific activity concentrations.

The specific activity concentrations and vent flow rate data are used weekly to verify that release rate limits were not exceeded.The specific activity concentrations and total volume of gaseous effluent are used on a monthly basis to determine the total curies of each particulate and iodine release'd during the month.

Page 5 of llEFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1989 IV.Measurements and A roximations of Total Radioactivit (Continued) 2.The gross alpha concentration is determined by analysis of a monthly particulate filter composite sample and strontium-89 and-90 are determined by analysis of a quarterly particulate filter composite sample for each release point.D.Liquid Effluents 1.The gamma ray emitting radionuclide concentrations are determined for each batch by gamma ray spectroscopy analysis of-a grab sample.The allowable release rate is calculated for each batch based upon the known dilution flow.The flow rate of the liquid effluent is continuously monitored and the total volume rel'eased in each batch is determined.

The total gamma activity released in each batch is determined by multiplying the radionuclide concentrations by the total volume discharged.

The total gamma activity released during the month is then determined by summing the gamma activity content of each batch discharged during the month..2.The gross alpha and tritium concentrations are measured on a monthly composite sample.The strontium-89 and-90 and iron-55 are measured on a quarterly composite sample.V.Batch Value THIRD FOURTH Units A.Liquid 1.Number of batches released 2.Total time period for batch releases 3.Maximum time period for a batch release 4.Average time period for batch releases 5.Minimum time period for a batch release 125 58 34>907 14,866 360 375 Each Minutes Minutes 30 145 Minutes 278.3 256.31 Minutes 6.Average stream flow during period of release of effluent into a flowing stream 55,185 74,047 CPS B.Gaseous None Cs' Page 6 of 11 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1989 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Fission and Activation Products 1.Total Releases Unit Curies" Third Fourth Quarter~uarte~r~or 3.97E-02 2.85E-02 9 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit (1.00E-7 mCi/ml)Tritium 1.Total Releases mCi/ml 7.39E-10 1.22E-09 7.39E-Ol 1.22E+00 Curies 1.71E-Ol 8.35E-02 6 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit (3E-03 mCi/ml)mCi/ml 3.18E-09 3.58E-09 1.06E-04 1.19E-04 1.Total Releases Curies ND 2.Average Diluted Concentration During Period 3.Percent of Applicable Limit (2E-04 mCi/ml)Gross Alpha Radioactivity 1.Total Releases 2.Average Diluted Concentration During Period mCi/ml Curies mCi/ml ND ND ND ND.0 ND ND 48 Volume of Waste Release (Before dilution)Volume of Dilution Water for Period Total CCW flow for Six Months Liters Liters 129.26 gigagallons 1.37E+07 6.09E+06 3 5.37E+10 2.33E+10 10 eludes Xe-133, Xe-135, and others.

n , it~ Page 7 of ll EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1989-BATCH MODE~Xsoto e (Required by REG Guide 1.21)Third Quarter Unit Curies Fourth Quarter Unit Curies 2~3~4~5.Cr-51 Mn-54 Co-58 Fe-59 Co-60 6.Zn-65 7.Nb-95 8.Zr-95 9.Mo-Tc-99m 10.I-131 ND 5.40E-06 ND ND 3.79E-03 1.87E-05 ND ND ND ND ND ND ND ND 2.49E-03 ND ND ND ND ND 12.Cs-134 13.Xe-135 14.Cs-137 15.Ba-140 16.La-140 17.Ce-141 18.Sr-89 19.Sr-90 4.65E-03 ND 3.10E-02 ND ND ND ND 3.69E-03 2.22E-02 ND ND ND ND ND~Isoto e Others (Not Required by REG Guide 1.21)1.Sb-125 2.70E-04 9.65E-05 2.Fe-55 ND section was prepared principally by P.S.Kirby.ND I' Page 8 of 11 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 19891 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Summation of All Releases Unit Third guarter Fourth Quarter I Error A.Fission and Activation Gases 1.Total Releases ND ND 2.Average Release Rate for Period mCi/sec ND B.3.Percent of T.S.limit>Iodines 1.Total Iodine-131 Ci ND ND 36 2.Average Release Rate for Period mCi/sec I 3.Percent of T.S.Limit2 ND ND 0 C.Particulates t 1.Particulates with half-lives

>8 days Ci 3.23E-05 ND 35 D.2.Avg.release rate for period 3.Percent of T.S.limit>4.Gross alpha radioactivity Tritium mCi/sec Ci 4.11E-06 ND 4.75E-Ol 0 3.24E-06 9.59E-07 2~3~4~Total release Ci Percent of T.S.limit>Ground level release Ci Average release rate for period mCi/sec 7.87E-02 4.19E-02 1.00E-02 5.33E-03 4.57E-01 2.43E-01 7.87E-02 4.19E-02 21 5.Elevated release 1 Reporting period-189 days.Ci ND ND 2 The dose rate limit for noble gases shall be<500 mrem/year to the total body and<3000 mrem/year to the skin and the dose rate limit for I-131, I-133, H-3, and rticulates with g eight day half lives shall be<1500 mrem/year to any organ.

Page 9 of ll EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1989 GASEOUS EFFLUENTS-ELEVATED RELEASE 1.Fission Gases Third Unit l}uarter Fourth guarter Krypton-85m Krypton-85 Krypton-87 Krypton-88 Xenon-133 Xenon-135m Xenon-135 Xenon-138 Ci Ci Ci Ci Ci ND ND ND ND ND ND ND ND ND ND ND ND ND ND Total for Period Ci ND ND 2.Iodines Iodine-131 Iodine-133 Iodine-135 Ci Ci ND ND ND ND ND otal for Period Ci ND V Page 10 of 11 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1989 GASEOUS EFFLUENTS-ELEVATED RELEASE (Continued) 3~Particulates Sr-891 Sr-901 Cs-134 Cs-137 Ba-140 La-140 Unit Ci Ci Ci Ci Ci Third Quarter ND ND ND 3.23E-05 ND ND Fourth Quarter ND ND ND ND ND Total for Period Ci 3.23E-05 ND 4.Tritium Ci ND ND redicted estimation of releases. Page 11 of ll EFFLUENT AND WASTE DISPOSAL SENIANNUAL REPORT SECOND HALF 1989 GASEOUS EFFLUENTS-GROUND LEVEL RELEASE Fission Gases Krypton-85m Krypton-85 Krypton-87 Krypton-88 Xenon-133 Xenon-135m Xenon-135 Xenon-138 U~it Ci Ci Ci Ci Ci Ci Ci Ci Third Quuar er ND ND ND ND ND ND ND ND Fourth~ua ter ND ND ND ND ND ND ND ND Total for Period Ci ND ND 2.Iodines Ci ND ND Iodine-133 Iodine-135 Ci ND ND ND ND Total for Period Ci ND ND 3~Particulates Sr-891 Sr-901 Cs-134 Cs-137 Ba-140 La-140 Ci Ci Ci Ci Ci ND ND ND ND ND ND ND ND ND ND ND Tritium Total for Period ND 7.87E-02 ND 4.19E-02 redicted estimation of releases.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 1989 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS SoLid Waste Shipped Off-site for BuriaL or DisposaL (Not Irradiated FueL)Type of waste units Amount Error%Spent resins, fiLter sLudges, evaporator bottoms, etc.m3 Ci 8.16E+0'1 1.02E+02 1.50E+01 c d.Dry compressibLe waste contaminated equip., etc Irradiated components, controL rods, etc.Absorbed oily materiaL m3 Ci m3 Ci m3 Ci 1.81E+02 2.81E+01 O.OOE+00 O.OOE+00 3.58E+01 8.85E-01 1.SOE+01 1-SOE+01 2.Estimate of major nucLide composition (by waste type)a~Spent r Psins, fiLter sLudge, evapordlor bottoms, etc.Nuclide Unit Unit Manganese-54(1) 2.Iron-55(2) 3.Cobalt-60(1)

Zinc-65(1) 1.39E-01 Ci 1.42E-01'A 2.61E+01 Ci 2.66E+01 2.86E+01 Ci 2.91E+01 1.78E+00 Ci 1.82E+00 S.Cesium-134 (1)Vo 5.53E+00 Ci S.64E+00 6.Cesium-137 (1)3.55E+01 7.Other NucLides(Z)

%2.35E+00 Ci 3.62E+01 Ci 2.40E+00 (1)Measured (2)Estimated through the use of scaLing factors 12

EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT 2nd HALF 196S SOLIO WASTE ANO IRRAOIATEO FUEL SHIPMENTS (Continued)

Estimate of major nuclide composition (by waste type)(Con't)b.Or y compressible waste, contaminated equipment, etc.Nucl ide 1.Chr omium-51(2)

Unit Unit 7.87E+00 Ci 2.20E+00 2.Manganese-54(2)

%2.S3E+00 Ci 6.26E-01 3.Iron-55(2)

Iron-59(2) 5.Cobalt-60(2) 6~Zinc-65(2) 7.Niobium-95 (2)Vo'1.33E+01 Ci 3.73E+00 1.42E+00 Ci 4.0'lE-01 3.15E+01 Ci 6.65E+00 8.2<E-01 Ci 2.32E-01'L 2.01E+01 Ci 7.SZE+00 6.Silver-110m(2) 0 6.63E-01 Ci 2.43E-01 9.Cesium-13<

(2)10.Ces ium-137 (2)5.03E+00 Ci 1.42E+00 6.72E+00 Ci 1.0SE+00'1'l.Other Nuclides(2)

%1.58E+00 Ci 4.ACE-01 ('1)Measured (2)Estimated through the use of percent abundance c.Irradiated components, control rods, etc.NONE d.Absorbed oily material Nuclide'1.Chr omium-5'1 (1)Unit Unit 1.21E+0'1 Ci 1.07E 01 2.Manganese-54(1)

V.4.43E+00 Ci 3.92E-02 3.Iron-55(2) 2.57E+01 Ci 2.20E-01 13 "p4 EFFLUENT ANO WA5TE OI5POSAL 5EMIANNUAL REPORT 2nd HALF 1S89.SOLID WASTE ANO IRRADIATED FUEL SHIPMENTS (Continued)

Estimate of major nucLide composition (by waste type)(Con't)I d.Absorbed oiLy materiaL (Cont'd)NucLide Unit Unit Ci'I.18E-02 Iron-5S(1) 5.CobaLt-60(1) 6.Zinc-65(1) 7.Niobium-95

('I)'L-1.34E+00 1.88E+01 Ci 1.66E-01=1.94E+01 Ci 1.72E-O'I Ci 2.05E-02 Ci 1.17E-02 2.3'IE+00 8.SiL ver-110m(1)

%1.33E+00 9.Cesium-134(1)

'lo 7.20E+00 Ci 6.36E-02'IO.Cesium-137 (1)'L 7.20E+00 Ci 6.36E-02 11.Other NucL ides(2)%2.21E-01 Cil.94E-03 (1)Measured (2)Estimated through the use of scaLing factors 14

ENCLOSURE 3 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT EFFLUENT AND WASTE DISPOSAL REPORT JULY THROUGH DECEMBER 1989 I'J'ol Page 1 of 2no crab e Radioact ve Effluent Instrumentation Re ort Browns Ferry Nuclear Plant (BFN)Technical Specifications (TSs)3.2.D.2 and 3.2.K.2 requires the semi-annual Radioactive Effluent Release Report to include an explanation of why the required radioactive effluent monitoring instrumentation that were inoperable for more than 30 days were not corrected in a timely manner.This report covers the period from July 1 through December 31, 1989.The Radiological Effluent Technical Specification (RETS)became effective at BFN on May 6, 1987 during the current administrative outage.Due to changes in the operability requirements of radioactive effluent monitoring instruments resulting from RETS, a number of radioactive effluent monitoring instruments were declared technically inoperable on May 6, 1987, that were previously considered operable.Resources have been allocated to resolve these problems and others in order to establish compliance with the RETS.The instruments that were inoperable for more than 30 days are: Residual Heat Removal (RHR)service water monitor (2-RM-90-133)

.,RHR service.water monitor (2-RM-90-134)

Liquid radwaste effluent flow loop (0-FR-77-60)

Stack effluent flow meter (0-FE-90-271)

Off Gas Post Treatment noble gas activity monitor (3-RM-90-265)

Off Gas Post Treatment noble gas activity monitor (3-RM-90-266)

During the entire reporting period, fuel was offloaded from units 1 and 3 and all compensatory sampling requirements were met.The following is a discussion of those instruments that were inoperable for more than 30 days.Li uid Process Radiation Monitors BFN TSs Table 3.2.D requires RHR service water monitors (2-RM-90-133 and 2-RM-90-134) to be operable when the associated RHR service water system is in service.These monitors were inoperable for greater than 30 days during this reporting period.2-RM-90-133 was declared inoperable on September 24, 1989 due to sample pump problems associated with auto start circuitry.

After investigation, it was determined the auto pump start time delay logic does not allow for charging the RHR service water headers.A DCN has been written to correct the problem.2-RM-90-134 was removed from service on November 5, 1989 due to sample pump breaker trips and returned to service on December 6, 1989.Problems with the sample pump were corrected by a Maintenance Request (MR).

)4C'4 f+l Page 2 of 2 Li uid Process Radiation Monitors (continued) 2-RM-90-132 had been removed from service be cause the system was not designed to operate at very low Raw Cooling Mater (RCW)discharge flow rates.DCN.H4377 was written to redesign the suction tap for 2-RM-90-132 to allow obtaining a sample from RCW regardless of RCW flow rate.DCN H4377 was closed out and 2-RM-90-'32 was declared operable on July 23, 1989.i uid Radwaste Effluent Instrumentation BFN TS Table 3.2.D requires the liquid radwaste effluent flow loop (0-FR-77-60) to be operable during liquid radwaste releases.Contrary to this requirement, the flow loop was inoperable during this entire reporting period.The flow loop (0-FR-77-60) was declared technically inoperable on June 21, 1989 due to inaccuracies.

DCN H4536A was written to replace the flow loop.Stack Radioactive Effluent Instrumentation The stack effluent flow meter (0-FE-90-271) was inoperable for more than 30 days, extending into this reporting period.The stack effluent flow meter (0-FE-90-271) was declared inoperable on May 27, 1989 due to a loss of flow indication in the control room.The meter was not returned to service within 30 days because spare parts had to be ordered and were not received in a timely manner.The flow meter was repaired and returned to service on July 27, 1989.Off Gas Post Treatment BFN Technical Specification Table 3.2.K requires the Off Gas Post Treatment noble gas activity monitors (1-RM-90-265, 1-RM-90-266, 2-RM-90-265, 2-RM-90-266, 3-RM-90-265, 3-RM-90-266) to be operable at all times.Contrary to this requirement, two of these monitors (3-RM-90-265 and 3-RM-90-266), were inoperable for more than 30 days, extending into this reporting period.The Unit 3 monitors, 3-RM-90-265 and 266, were taken out of service on January 19, 1989 due to the lack of performance of the Quarterly Functional Test Surveillance Instructions (SIs).The SIs could not be performed due to a hold order on the Unit 3 offgas isolation valve.The SIs were added to the hold order to ensure no releases were made through this pathway.This is in compliance with Technical Specification Table 3.2.K, action (F).These monitors were returned to service on July 12, 1989 to support Unit 3 off gas layup.The Unit 3 off gas system was not in service during this period.

~)e.v)4 Page 2 o'f 2 Li uid Process Radiation Monitors (continued) 2-RM-90-133 was declared inoperable on September 24, 1989 due to sample pump problems associated with auto start circuitry.

After investigation, it was determined the auto pump start time delay logic does not allow for charging the RHR service water headers.A DCN has been written to correct the problem.2-RM-90-134 was removed from service on November 5, 1989 due to sample pump breaker trips and returned to service on December 6, 1989.Problems with the sample pump were corrected by a Maintenance Request (MR).2-RM-90-132 had been removed from service because the system was not designed to operate at very low Raw Cooling Water (RCW)discharge flow rates.DCN H4377 was written to redesign the suction tap for 2-RM-90-132 to allow obtaining a sample from RCW regardless of RCW flow rate.DCN H4377 was closed out and 2-RM-90-132 was declared operable on July 23, 1989.i uid Radwaste Effluent Instrumentation BFN TS Table 3.2.D requires the liquid radwaste effluent flow loop (0-FR-77-60) to be operable during liquid radwaste releases.Contrary to this requirement, the flow loop was inoperable during this entire reporting period.The flow loop (0-FR-77-60) was declared technically inoperable on June 21, 1989 due to inaccuracies.

DCN H4536A was written to replace the flow loop.Stack Radioactive Effluent Instrumentation The stack effluent flow meter (0-FE-90-271) was inoperable for more than 30 days, extending into this reporting period.The stack effluent flow meter (0-FE-90-271) was declared inoperable on May 27, 1989 due to a loss of flow indication in the control room.The meter was not returned to service within 30 days because spare parts had to be ordered and were not received in a timely manner.The flow meter was repaired and returned to service on July 27, 1989.Off Gas Post Treatment BFN Technical Specification Table 3.2.K requires the Off Gas Post Treatment noble gas activity monitors (1-RM-90-265, 1-RM-90-266, 2-RM-90-265, 2-RM-,90-266, 3-RM-90-265, 3-RM-90-266) to be operable at all times.Contrary to this requirement, two of these monitors (3-RM-90-265 and 3-RM-90-266), were inoperable for more than 30 days, extending into this reporting period.The Unit 3 monitors, 3-RM-90-265 and 266, were taken out of service on January 19, 1989 due to the lack of performance of the Quarterly Functional Test Surveillance Instructions (SIs).The SIs could not be performed due to a hold order on the Unit 3 offgas isolation valve.The SIs were added to the hold order to ensure no releases were made through this pathway.This is in compliance with Technical Specification Table 3.2.K, action (F).These monitors were returned to service on July 12, 1989 to support Unit 3 off gas layupo The Unit 3 off gas system was not, in service during this period.0409k/8

%k ENCLOSURE 4 TENNESSEE VALLEY AUTHORITY SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT BROWNS FERRY NUCLEAR PLANT CHANGES TO THE BFN OFFSITE DOSE CALCULATION MANUAL JULY THROUGH DECEMBER 1989

BFN Technical Specification 6.12.2 requires that changes to the Offsite Dose Calculation Manual (ODCM)be submitted to the Commission with the semiannual-Radioactive Effluent Release Report for the period in which the changes were made.This report covers the period between July 1 through December 31, 1989.During this period, two changes to the ODCM were made.The description, justification and analysis of each change are discussed by the following BFN ODCM Change Description Forms.The changes were implemented by Revisions 6 and 7 to the Radiological Effluent Technical Specification (RETS)Manual, of which the ODCM is a part.Revision 7 of the RETS Manual is also provided for review.04091'/10 Ci P4l F, ,ag fca!~r

,:.'4;ji".'.>>'-."k.;."'~~~lg:

Handling of C~es to the BFN Of fsite Dose Calculation M~al ,"',l-","'VA hlU CLEAR RARC OP 9 Revision 1 Page 4 of 4 Appendix 1 BFN ODCM Change Description Form s.~yP~ce M~r Description of change.'r-/s

'h w'>er>/~s@au 2+3/d omP}/S]S Qr 0 MW~d~~z'~~P'SM l<Pu or cy~w r I cLri~k,'~uv~r 4tem wee/"/~d)Ve/~e So r prus'~o 48'~~~~d w er s'dw m~~y gum/++~)s~~@c~ys r'rc~~s h m)//s ru~ma~A(6 ever>-e'eeA>'Qe/@e m)(v'eye i'o~s~(s(,'~p u~d d~.'ry r~~h'c~s nc'w o~<<<~: ness c J4 (~e~r~'DcA~i S,l yc~&Lv deere ye5c rvd, gdh(e 3~P~~4~5 vo4~5 c se~p N~p oS'~>/g+,p 5 Pages affected: I l l>I')I~('6 (>('Cb'~"'(22 6)~>2p I>(2 p)(>3, I 2 t'~(j)r l 3 sip;()r 3, 2+~J JuStifiCatiOn far Change.'0 de..e A 4/'s Ac 4 ec o H(.','l,lv GT~5~/<coHrfAr~l~&G 4'g'~'Hs Al thL 570 K~Iv'l por~,'/~~j~-5~(z np'>Q)5r m ys,>no'6 re.~'ro 4 sv~cd'v'4 e e>a((4~d N~o~(~A d 8 er r~J bee dc (d.'mpler g~i'~~~cp s(p s ore,w,<~.wvct: c~<v~z~'sdes.~,'r'dmy%ly

~u uu au~ay g/'eg~'go)Arl/c c(<v~q'~czc,c.vied~

~GSer-C a qZ-oh O'V'R I r 4a.r/q mi do@IS 5 er v,'c's 0'97 o~)~co~~~d S o Mp'(,)p'f hw'r'nes ra (~ac(7 5~(lg vw~ro vi'ydd~~(+'c&l<'~5

.~"vi'K~raJ~7 g'd~~sodg'rck}auwsfro~~gcyvdr'yg(~s be<,c~r~p lc554b~d~>hu

~M'f'ed Ccc~fv 5')Z-~ro~d c Anscdcl 4"A>md+o5 ho-s d 4 r V~PŽ5 (Sir~/)(N')~(s/~~i<va Pf f4'Fc CW~s oD~i'(/7 Cs~(8.'h c<~~ox+b(8.>~+~~P'pnme 3.E.Analysis of effect of change on dose calculations, projections, or setpoint calculations:

(3')DQ+e SPssCs<'c OC+<Os S for c~5~7S us)g)D++O~e~sSuH S~(1Apd d Cgc M J~~Ssg A 8r i<.eu u7~,~/k 5/e5'd So M~e s"//4~<c c.-4.y'da5~r-c(c&~'c~C I CW5 O 7 5 a,m CATCH S~r dsS.Q (/Attach marked-up pages from the the, change.curre revision of the SgN ODCM which show RARC Review: RARC Chairman 0357p/DNS01 0 4(~JQ~r,alt" w<ia

~~~~I I~~~~I~~~~~II~~~~I.~~~~~~~I e~4 I~0 la).)~po~'i)i~~~~L'SL a I~~I I~I I i~4~ls aL o4~'~~I~~~~~~g/'0~I~I~~~~I~f~~I r I o I~

lFlit@A<<~'~A P l&tl~P WIP W,I~I f8 5 4O~

Tennessee Valley Authority Irouns Ferry Huclear Plant Si te.Director Standard Practi ce g%2'6 1%Fore Page 1 of 1 Fore SDSP 1 SDSP Rill FORN SDSPnel PRDCEDURK AHO IHSTltVCTIOH RKVIQI AHO APPROVAL COVER SHEET Tracking Hoi T(tie 840 OlgppCCL t~l nd carr i~n'ttn>0~'r,to+a~~g g~T S)'l ACL M~W h CHGX As AppRQpRIATEl

(]Has Procedure Wl Permanent Chan~.Tm Year Revien r d'L()2r-7 aT Y pe~~es Tenporary change Anticipated duration (date or condition):

Sp LIST s an fo ffected: age chord processing.(For TCs list earked pages?., (for Sp'~n1xL Reve Hoi Ho Pages reissued for pagination only: ORISIHATOR (PRINT your naee)pate cc c~+Optant teen lp Haec of Res nsible Qrgaaiaat'K Signature..r~bW/a g7" Phone Q o t C4>c~Plant Hanager IZ Project Coatrols 4 Financial Svcs Ngr Si te Support Nanager Si te Licensing Site Prog~.Nanager Prefect Engineering (PE)Nodi ficatioa (NODS)Nate'als Procurenent Nanager~r I ZZ Qrgaaiaatsont ZX: Orgaaizatson:

ZI Orgaai sation: ZI OrgaeizatL ZZ Organiaac r.n: ZT Organo sate on: IZ'rgani sation: '..IZ Orgaa'on: A Si te 1 i ty ance te Sl t P cedures---IZ)(Sign A~all required signatures except PORC, Res sibl~Organisation Supervisor principal Nanager, and Site Director if applicable.)

Princi pal tlanager T'I tie: (Required signature for standard practices~, Date except if Principal Hanager is the Plant Nanager, then nark"HAap here and check plant Nanager at bottoe left.)Ho.Hoi PORC: Re (~1 (.Xi (.<<dP POR C~h~or PORC Ninutes~plan Nanager or poRc tlinutes"~'etention Period: Li fetiae Responsibil i ty: OCRN 0705R~w~Date.iL'E9$Site Director (SDSPs only)Date released free ACaonistrative Hold tdp cenpletescc apple,caaiet Effective Date~~+~(SP coepletes)

Vaitdattcn Oats~~(tp ccnplecesl BFN RETS MANUAL Page 1 of 3 REV.NO DATE 02/01/84 HISTORY OF'EVISION/REVIEW REVISED PACES REASON FOR CtJRR1WZ'EVISION 1,2;3,'4,6,12-20, Revise ODCM.'o incorporate 24-34,36,48,51-70;.

revision approved.by RARC..add 16A+20ho30ho.

30Bg30Cy3LA,31B., 36A 06/26/84 Section 3 (As TIW7)Add.70A,70B,70C, Reinsert pages accideaty deleted 70D,70E,70F in February 1, 1984 revision.'1/20/84 09/26/85 05/05/87 Section.3(As.

TIW7)2,3,13,15,16,19,, In response to OQAB audit.(841112-05) 20,20A,24; add 24A thrL 24T;30B,32,33 51-56,64-66,deleted 31B'ection 3.Table of Contents, 14-16, to meet 18-20A,24M-25T,25 Technical.

Specification.

commitment 32,24~5l'-53~70D~

, 6~3~G-(Ref..

L61.850710803)

(850716-06) 70F,'7l't; Add 20B';241,69A,69B~69C'~

70Q',70H',70I;Delete 26-30~30A,30B,30C,31, 3IA~74-77'm manual to incorporate TI-47 (ODCM)into'new manual called the RETS Manual which contains three documents; the.REM;the ODCM, and the PCP.Also to.revise the~ODCM to incorporate changes approved'y RARC.10/20/87 All Correct.page aumberiag and identification per CAQR'FT870328.

1141v--1

BFN RETS MANUAL Page 2 of 3 HISTORY OF REVISION/REVIEW REV.NO.DATE REVISED PAGES REASON FOR CURRENT REVISION 2.07/12/88 ALL First revision approval aad issued under SDSP2.11.Updated to reflect the results of the Fall 1987 Land Use Census and.curxeat program.To correct typographical errors.'0/28/88 35-37>>40-79>>85>>86>>

9&98>>121-145 To more accurately and completely describe calculation of gaseous release rate limits ind doses aad to clarify 40CPR190 total dose calculations.

4 12/22/88 185-206 Section IV, Pxocess Control Program, is being revised in order to provide a more accurate and usable program.This revision wi11 alow for the use of vendor supplied systems in xadwaste processing and iacorporates, by reference, the latest NRC correspondence regarding radwaste processing using vendor equipment.

This revision also provides information regarding various radwaete proce'ssiag concerns.including standard.definitions, waste charateristics, shipment manifeets and adminietxative controls.REASON FOR URGENCY: This revision needs to be implemented prior to-December 31,1988 so that the use of the.Chem Nuclear System currently oneite-can be reported in the Semi-Annual Efflueat, report being issued in January 1989.06/02/89 ALL A, two-year.review was performed and changes, were made to the ODCM to reflect.this review and to update-the QDCri., lae xoiiowing cnanges were made to the ODCM in accordance.

with its two-year review.:.corrected references,.

change table 1.4" to reflect gamma and beta air dose values in RG 1.104, changed fraction of river flow for dilution, added.max turain heights, and revised methadology descripticns per gWATA code.URGENCY: Changes need to be in place so the 1st quarter of 1989 report can-be-completed; 1141v-2~~

BFN RETS MANUAL Page 3 of 3 HISTORY OF REVISION/REVIEW REV.NO.DATE 09/19/89 REVISED PAGES 38,58,59,67,69, 71, 72,84,85~86, 95, 97, 98,124-131,137-146 14&,150-153,174 REASON FOR VHGKNT REVISION In accordance with RARC meeting minutes from June 1, 1989 (RIMS , L60 890606&01).The following changes were made on ODCM Table 3-1;change collection frequency for surface water and drinking water samples from 7 to 31 days, delete Sr analysis for surface water, change analysis frequency for gross beta and gamma in drinking water from weekly ground water from monthly to quarterly, change'analysis frequency for gamma in mild from monthly to every 2 weeks, delete fish sampling from the dwonstream reservoir, and delete specifc locations for clam samples.On Table 3.2.A and figure 3.3 delete mild and vegetation sampling from a dairy farm which is now out of buisness and add replacement farm.Delete vegetation sampling except food'roducts and those samples taken in lieu of mild samples.Correct several typoso ll/28/89 152~153 To add Farm Gl to Table 3.1 under vegetation.

To Delete Farm 0 which is now out of business from Table 3.1 and 3 ZA 114lv-3 RETS Manual Revision 7 Page l Brogans Ferry Nuclear Plant Radiological Effluent Technical Specification (RETS)~~038 2p.'Vw'

, RETS Manual Revision 7 Page 2 Section.I.Introduction II..Radiological Effluent Manual (REM)III Offsite Dose Calculation Manual (ODCM)IV.Process Control Program (PCP)~~0382p

RETS Manual Revision 7 Page 3 RETS Manual Section I Introduction

~W~C~~~~~~r~0382p RETS Manual Revision 7 Page 4 RETS Manual Section I INTRODUCTION The Radiological Effluent Technical Specification (RETS)Manual contains three documents; the Radiological Effluent Manual (REM), the Offsite Dose Calculation Manual (ODCM), and the Process Control Program (PCP).All three documents.

are referenced by the Radiological Effluent Technical Specifications which vere issued on February 5,.l.987 as Technical Specification Amendments Nos..132,, 128, and 103 to unit 1, 2, and 3, respectively.

The-REM and the ODCM vere approved by the NRC+hen they issued the RETS.The REM is:controlled by the, NRC, so changes to the REM must be approved by the NRC before they are put in: this manual..The ODCM and PCP are controlled by TVA,.so changes to.the ODCM and the PCP must be approved by PORC;iXnktfal~'RC approval of the PCP is required and has been requested.

'h'I~V 0382p RETS Manual Revision 7 Page 5 RETS MANUAL Section II'ADIOLOGICAL EFFLUENT MANUAL'EM For the Browns Ferry Nuclear Plant Limestone County, Alabama Tennessee Valley Authority 03829 RETS Manual Revision 7 Page 6 RADIOLOGICAL-EFFLUENT MANUAL TABLE OF CONTENTS SECTION PAGE NO.REV'.NO.A INTRODUCTION B RESPONSIBILITIES C., 1.LIQUID EFFLUENTS SAMPLING AND ANALYSIS PROGRAM'LIQUID MASTE TREATMENT D 1.GASEOUS EFFLUENTS SAMPLING=AND ANALYSIS PROGRAM 2 GASEOUS WASTE TREATMENT E RADIOLOGICAL ENV IRONMENTAL, MONITORING l.SAMPLING AND ANALYSIS 2~LAND USE CENSUS 3 INTERLAB ORATORY COMPARISON PROGRAM F;REPORT CONTENT 1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 2;SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 3'PECIAL.REPORTS (RADIOLOGICAL ENVIRONMENTAL MONITORING)

A-1 B-1 C-'1 C-5 D-1 E-1-E-'3 E-S F-'l.F-3, 0 0 0 0 0 0 0 0 0 0 0 0 j 0382p

RETS Manual Revision 7 Page 7 I Q l E A INTRODUCTION The purpose of this manual is to provide the sampling and analysis programs which provide input to the-ODCM for calculating liquid and gaseous effluent concentrations and offsite doses.Guidelines are provided for operating radioactive waste treatment systems in order that offsite doses are kept as-low-as-reasonable-achievable (ALARA).The Radiological Environmental Monitoring Program outlined wi,thin this manual provides confirmation that the measurable concentrations of radioactive'ateria1 released as a result of operations at the Browns Ferry Plant.are not higher than.expected., In addition, this manual outlines the information required to be submitted to the MC in both the Annual Radiological Environmental Operating, Report-and the Semiannual Radioactive Effluent Release Report.P 0382p; RETS Manual Revision 7 Page 8 I B;RESPONSIBILITIES All changes to this manual shall be xeviewed by the Plant Operations Review Committee px'ior to implementation All changes to this manual, shall be approved by the NRC.prior to'implementation.

It'.shall be the responsibility of.the.Plant Manager to ensure that this.manual is used in pexformance of the surveillance requirements and administrative controls of the Technical Specifications

.Q382p B>>l

RETS Manual Revision 7 Page 9 C'.L'I UID EFFLUENT SAMPLING AND ANALYSIS PROGRAM C.l Radioactive liquid waste sampling and activity analysis of each liquid waste batch to be discharged shall be performed prior to release in accordance with Table C-l.The results of the analysi's of samples collected from release points shall: be used with the calculational methodology in the ODCM to assure that the concentrations at the point of release are maintained within the limits, of the Technical Specifications.

I~~"~~'<~~0382p C-'L.

0 TABLE C-1 RADIOACTIVE LI ID HASTE SAMPLING ANO ANALYSIS'PROGRAH RETS Hanual Revision 7 Page 10 I-IQUID RELEASE TYPE Re1easest~~

SAHPLING FRE ENCY Each Batch Each Batch Prior to Release a Em!tters<4j gINIHUH ANAI YSIS..=JYPE.OF ACTIVITY FRE ENCY ," ANALYSIS SYSTEH DESIGN CAPABILITY LOHER LIHIT OF DETECTION (LLD)(Cilml)One Batc11 per Honth Honthly Dissolved and Entrained Gases<5)l E-5(3)Honthly Pfopoltiony)

Composite ac)Honthly Tritium Gross a l E-7 Quarterly Proportiony)

Composite~~)Quarterly Sr-B9, Sr-90 Fe-55 C-2~'382p RETS Manual Revision 7 Page ll TABLE NOTATION-TABLE C-l (1)A batch release is the discharge of liquid wastes of a discrete volume.The discharge shall be thoroughly mixed prior to sampling.(2)A proportional composite sample is one in which the quantity of liquid sampled is, proportional to the quantity of liquid waste discharged from the plant and.is representative of the liquid discharged.

(3)The LLD is defined, for the puzposes of these specifications as the smallest concentration of zadioactive material in a sample that will yield a new count (above system background) that will be detected with 95K probability with only 5X probability of falsely concluding that a-blank observation represents a"zeal" signal.For a particular measurement system (which may include radiochemical separation):

Where 4e66 Sb E+V*2.22 x 10~T+exp'(-Xht)'

\e'LLD is the"a, pziori" lower limit of, detection as defined above (as microcuries per unit, mass or volume), U sb is the standard deviation of the.background counting rate or of the, counting rate of a blank sample-as appropriate (as counts per minute), E's: the counting efficiency'as counts per disintegration), V is the sample size (in units of mass or volume), 2;22 x 106 is the number of.disintegrations pez'inute per microcurie, Y'ks.the fractional radiochemical yield (when applicable), X is;the radioactive decay constant for the particular radionuclide, and dt.for plant.effluents is the elapsed time between the midpoint of sample: collectionand.

time of counting..

Typical values of E;, V;Yp.and At should be used'n the-calculation.

Zt should he reootuised that the ILD is defiued as a priori (hedore the fact)limit representing the capability of a measurement system and not as au a posteriori (after the fact)limit for a particular measuremect.

0382p C-3:

TABLE'OTATION

-TABLE C>>l Continued RETS Manual Revision 7 Page 12 (4).The principal gamma emitters for which the LLD specification will.apply are exclusively the following radionuclides:

Zn65, Co60, Csl37, Mn54, Co58, Cs134, Cel41,, Cel44, Mo99, and Fe59 for;liquid releases.This list does-.not mean that only these nuclides are to be detected and reported.Other: nuclides detected within a-95X'onfidence level, together with the above nuclides, shall also be identified and reported as being present.Nuclkdes which are below the LLD for the analysis.may not be reported as-being, present at the LLD Level for that nuclide.I-131 shall have a LLD of<1 E-6.(5)Gsmma Ead.t ters On?y.

i RETS Manual Revision 7'age 13 C 2.LI UID RADIOACTIVE WASTE TREATMENT This section requires that the appropriate portions of the liquid radwaste treatment system be used when specified.

This provides assurance.

that the releases of radioactive materials in liquid effluents will be kept"as low as.is.reasonably achievable"..

This specification implements the requirements of'0 CFR Part: 50.36a, General Design Criterion 60 of Appendix, A to 10 CFR Part 50 and design objective Section.II;D of Appendix I to 10 CFR Part 50.The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as a.suitable fraction of the guide set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.

This section also requires submittal of a special report if the limiting values are exceeded and unexpected failures of non-redCmdant radwaste processing equipment halt waste treatment.

The-liquid radwaste.system shall be-used to reduce the radioactive materials in.liquid wastes prior to their discharge from the site when the:-projected monthly dose would.exceed: 0.06 mrem to the total body or 0'.21.mrem to.any organ per.unit.(see Figure 4.8-1b,.Technical Specification).

Doses due to liquid releases.to unrestricted areas shall be projected, at least once per.31 days,.in.accordance with the ODCM., With.radioac'tive.

liquid, waste, being-discharged.

for more than 31 days without.treatment-and when the projected dose is in excess of limits specified above prepare and.submit the Special, Report pursuant to Section 6.7.2" of the Technical, Specifications.

0382p

RETS Manual Revision 7 Page 14 D GASEOUS EFFLUENTS SAMPLING AND ANALYSIS PROGRAM D.l Radioactive gaseous waste sampling and activity analysis shall be performed in accordance with Table D-l.Dose rates.shall be determined to be within limits of the Technical Specifications using methods contained in" the ODCM.Samples of offgas system effluents.

shall be analyzed at least weekly to determine the identity and quantity of the principal radionuclides being released.0382 p.D-l

,'gA TABLE 0-1 RADIOACTIVE GASEOUS HASTE SAMPLING AND ANALYSIS PROGRAM RETS Manual Revision 7 Page 1 5 GASEOUS RELEASE TYPE SAMPLING FRE ENCY MINIMUM ANALYSIS FRE EKCY TYPE OF ACTIVITY ANALYSIS SYSTEM OESIGN CAPABILITY LONER LIMIT OF OETECTION (Ci/ml)A.Containment Purge Prior to Each prior to Each Purge.Principa)gamma Purge Grab Sample Emitters~3~

8-3 E 4(1)1E-6 B.l.Stack Grab Sample 2.Building Grab Sample Ventilation Montq>y(4)

Monthly(4)

Principaj gamma Emitters<3>

H-3 1E 4(l)b.c~Reactorl Turbine Turbine Exhaust Radsaste C.Al 1 Release Points Listed in B.Above Continuous Sampler Charcogf Sample Heeklycw)I-131 particu}ate Sample Principal Gamma<Heekly<<>Emitters<3) and i~I-131 1E-12(2)0382p Continuous Sampler Continuous Sampler Continuous Sampler Compos)te Parti col ate Gross Alpha Sample Monthly Compos)te Particulate Sr-89, Sr-90 Sample Quarterly 0-2 1E-11 1E-12(2)1 E-1 1 1 E-11

RETS Nanual Revision 7 Page 16 TABLE NOTATION-TABLE D-I The LLD is defined, for the purposes of these specifications as the smallest concentration of radioactive material in a sample that will yield a new count (above system background) that will be detected with 95%probability with only 5%probability of falsely concluding that a blank observation represents a"real" signal.For a particular measur ment system (which may include radiochemical separation):

4 66 sb E.+V*2.22 x 10+Y*exp (-'X4t)Where: LLD is the"a priori" lower limit of detection as defined above-(as microcuries per unit mass or volume), sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute), E is the counting efficiency (as counts per disintegration), V is the sample size (in units of mass or volume), 2;22 x 106 is the number of.disintegrations per minute per microcurie, Y.is the fractional radiochemical yield (when applicable), X.is the radioactive decay constant for the particular radionuclide, and 4t.for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.Typical values of E, V', Y, and 4t=should be used in the calculation.

Zt should he recognised that the LLD is defined as an a priori (hefore the fact)limit representing the capability of a measurement system and not as an.a posteriori (after the fact)lhsit for a particular

'easurement., (2)When samples are taken more often than that shown, the minimum detectable concentrations can be correspondingly highere 0382p

RETS Manual Revision 7 Page 17 TABLE NOTATION-TABLE D-1 Continued (3)The principal,.

gamma emitters for which the LLD sjecification will apply are exclusively the following radionuclides:

Kr-87, Kr.-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Ha-54, Fe-59, Co-58, Co-60,.Zn65, Mo-99, Cs-134, Cs-137Ce-141, and Ce 144 for particulate emissions.

This list, does not mean that only these nuclides are to be detected and reported, Other.peak@which are measurable and identifiable,.

togethe'r with the above, nuclides, shall also be identified and reported.Nuclides.which-are.

below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide.h (4)Analysis shall also be performed if the radiation monitor alarm exceeds the setpoint value.I I'l\,~, i e~~038 Rp.D-4 RETS Manual Revision 7 Page 18 D 2 GASEOUS RADIOACTIVE HASTE TREATMENT Doses due to gaseous releases.to areas at and beyond the site boundary shall be projected in accordance with the ODCM at least once per 31 days.1~1 h~pI~l II'I.0382p D-5 RETS Manual.Revision 7 Page 19 E.RADIOLOGICAL ENVIRONMENTAL MONITORING E.1.SAMPLING AND ANALYSIS The radiological monitoring program-required by this section provides measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides, which lead to" the highest potential radiation exposures of individuals resulting from the station operation.

This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measureable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.The radiological environmental monitoring program shall be conducted as specified in Table E-l.r..The radiological environmental monitoring samples shall be collected pursuant to Table E-l from the locations given in the table and figure in the ODCM and shall be analyzed pursuant to the requirement of Table E-1 and the detection capabilities required by Table E-2.With the radiological environmental monitoring program not being conducted as specified in Table E-l, in lieu of a LER, prepare and submit to the Commission, in the Annual Radiological Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing awecurrence.

Deviations are permitted.

from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability or malfunction of automatic sampling equipment.

If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period All deviations form the sampling schedule shall be reported in the Annual Radiological Environmental Operating Report.With the level of radioactivity in an environmental sampling medium exceeding the reporting levels of Table E-3 when averaged over any calendar quarter, in lieu of a LEE, prepare and submit to the Commission within 30 days fr'om the end of the affected calendar quarter, a report vhich identifies the cause(s)for exceeding the limit(s)and defines the corrective action to be taken to reduce radioactive effluents so that the potential annual dose to a member of the public is, less than the calendar year limits of the" Technica1:

Specifications; When.more than one of the radionuclides in Table E-3 are detected in the sam'pling medium, this report shall be submitted.

if:~Canc 1+.~Cone 2+,...>1.0 Limit(1)Limit(2)When radionuclides other than those in Table E>>3 are detected and are result of plant effluents, this report shall be submitted if the potential annual dose to a member of the public is equal to or greater than the calendar year limits of the Technical Specification.

0382p E-1 RETS Manual Revision 7 Page 20 Such reports are not required if the measured level of-radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.With milk or fresh leafy vegetable samples unavailable from one or more of the sample locations required by Table E-1 identify locations for obtaining replacement samples, if available, and add them to the radiological environmental monitoring program within 30 days.The specific locations from which samples were unavailable may then be deleted from the monitoring program.In lieu of a LER, identify the cause of the unavailability of samples and identify the new location(s), if available, for obtaining replacement samples in the next Annual Radiological Environmental Operating Report and also include a revised figure(s)and table(s)for the ODCM reflecting the new locations.'he provisions of Technical Specification 1.0.C are not appUcable.

The detection capabilities required by Table E-2 are state-of-the-art for routine environmental measurements in industrial laboratories.

It should hs rsccgmized that the fdD is defined as an a hricri (hefcrs the fact)limit representing the capability of the measurement system and not as an a peeterieri (aften.the fact)limit for particular measnrement.

Analyses shall be performed in such a manner that the stated LLDs.wi11 be achieved under routine conditions, Occasionally.

background fluctuations, unavoidably small sample sisesp the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable.

In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report.0382p

RETS Manual Revision 7 Page 21 E.2 LAND USE CENSUS A land use census shall be conducted and shall identify the location of the nearest milk animal,, the nearest residence and the nearest garden*,of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles..(For elevated releases as defined in Regulatory Guide 1.111, Revision 1, July 1977, the land use'census shall also identify the locations of all, milk aniraa1s and all gardens.of greater than 500 square feet producing fresh leafy vegetables in.each of the 16 meteorological sectors within a distance of three miles).With a land use census identifying a location(s) which yields a.calculated dose or dose commitment greater than the auuQarum value currently being calculated in section D.2 of this manual, in lieu of a LER, identify the new locations in the next Annual Radiological Environmental Operating Report.rr'ith a land use census identifying a location(s) that.yields a calculated dose or dose commitment (via, the same exposure pathway)20 percent gxeater than at a location from which samples are currently being obtained in accordance with section E.l, add the new location(s) to the radiological environmental monitoring programs within 30 days if the owner consents.The.sampling location(s), excluding the control station location, having the lowest calculated dose or, dose.commitment(s)(via the same exposure pathway)may be.deleted from.this monitoring program after October 31 of the year in which this land use census.was conducted.

In lieu oF a=.LER, identify the new lacatioa(s) in.the next Annua1, Radiological Environmental Operating, Report and provide a revised figure(s)and table for the ODCM reflecting, the new location(s).

• Broad." 1'eaf vegetation sampling: may be performed.

at.the.-site.boundary in the direction section with the highest D/g'n.lieu of the garden census.0382p

RETS Manual Revision 7 Page 22 The land use census shall be conducted at least, once per calendar year between the dates of April 1 and October 1 using the following techniques:

a.'ithin a 2 mile radius.from the plant or within the 15 mxem per year isodose*line, whichever is larger, enumeration by a door-to-door or equivalent'ounting technique.

b Within a.5 mile radius from the plan, enumeration by using appropxiate techniques such as door-to-'door survey, mail survey, telephone survey, aerial survey, or information from local agricultural authorities.

or other reliable sources-.This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifications j:o the monitoring program are made if required by the results of this census.The best survey information from the;door-to-door, mail, telephone, aerial or consulting with local agricultural authorities shall be used.This census satisfies the requirements of Section IV.B.3 of Appendix I to 10'FR'art 50., Restricting the census.to gardens of greater than 500 square feet provides assurance'that significant exposure pathways via leafy vegetables will be identified and monitored, since a garden of this size is the minimum.-required to produce the quantity (26 hg/year)of leafy vegetation assumed in Regulatory Guide 1.109 for consumption by a child To determine-this minimum garden size,, the following-assumptions'ere used: 1)that 20%'f.'he garden,was used fox growing broad leaf vegetation (i.e., similar to lettuce and, cabbage)',.

and 2)a vegetation yield" of.2: kg/square meter;0332p RETS Manual.Revision 7 Page 23 1 E.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Pxogram is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that.the results are reasonably valid..-~=~'Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison.

Program which has been approved by the Commission.

A summary of the results obtained as pact of the above required Interlaboratory Comparison Program and in accordance with the ODCM (or participants.

in the EPA cxoss check program shall provide the EPA progxam code designation-for the unit)shall be included in the Annual Radiological Environmental Operating.

Report'.With analyses.not being performed as, required.above, report the corrective actions taken to prevent a recurrence to.the Commission in the Annual Radiological Environmental Operating Report.0382p E-S TABLE E-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM'ETS Manual Revision 7 Page 24 Exposure Pathway~dl S AIRBORNE Radioiodine an)Particulates 2.DIRECT RADIATION Number of Samp)es and Sam le Locationsa Minimum of 5 locations At least 40 locations with>2 dosimeters at each location.Sampling and Collection Fre uenc Continuous operation of sampler with sample collection as required by dust loading but at least once per 7 days.At least once per 92 days.Type and Frequency of Anal sis Radioiodine canister.Analyze at least once per 7 days for I-131.Particulate sampler.Analyze for gross beta radioactivity

>24 hours following filter change.Perform gamma isotopic analysis on each sample when gross beta activity is greater than 10 times the average of control samples.Perform gamma isotopic analysis on composite (by location)sample at least once per 92 days.Gamma dose.At.least once per 92 days.aSample locations are given in the ODCH.0382p G

~~TABLE E-1 (Continued)

RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH RETS Hanual Revision 7 Page 25 Exposure Pathway and/or Sam le Number of Samples and Sam le Locationsa Sampling and Collection Fre uenc Type and Frequency, of Anal sis 3.HATERBORNE a.Surf ace b.Drinking c.Sedjment d.Groundd 2 locations Hjnimum of 1 downstream location, or al)water supplies within 10 mj les downstream whjch are tpken from the Tennessee Riper.Hinjmum of)location Composite>

sample collected oyer a period of<31 days.Compositeb sample col 1ectedc oyer a period.<31 days.Aj: least once per 184 days.Gamma i'sotopic analysis of each composite sample.Tritium analysis of com-posite sample at least once per 92 days.Gross beta and gamma isotopic analysis of each composite sample.Tritium analysis of composite sample at least once per 92 days.Gamma isotopic analysis of each sample.aSample locations are shoqn in the ODCH."Composite samples sha))be collected by collecting an cComposite samp)es shall be collected over a period of within 3 miles downstream of the plant.dGround water movement in the area has been determined Since no drinking water wells exist between the plant al jquot at interVals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.<14 days for 131I if drinking water is obtained to be from the plant site toward the Tennessee River.and the river, ground water will not be monitored.

E-7 0382p

0 TABLE E-1 (Continued)

RETS Hanual Revision 7 Page 26 RAOIOLOGICAL ENVIRONHENTAL HONITORING PROGRAH Exposure Pathway and/or Sam le 4.INGESTION a.Hilk b.Fish Number of Samp/eq and Sam le Locationsa 3)ocations 2 samples Sampling and Collection Fre uenc At least once per)S days when animals are on pasture;at least once per 31 days at other times.One sample in season, or at least once per 184 days if not seasonal..

One sample of commercial and game species.Type and Frequency of Anal sis I-13l analysis of each sample.Gamma isotopic analysis at least once per 31 days.Gamma isotopic analysis on edible portions..c.Food Productive 2 locations At least once per year at time of harvest, Gamma isotopic analysis on edible portion.aSample locations are shown in the ODCH.eSince water from the Tennessee River in the immediate area downstream is not used for irrigation purposes, the sampling of food products (primarily broad leaf vegetation) is not required unless milk sampling is not performed E-8 0382p

TABI E E-2 HAXIHUH VALUES FOR THE LONER LIHITS OF OETECTION (LLO)a,c RETS Hanual Revision 7 Page 27 Analysis Airborpe Particulate Hater*jir Gaj Fish Hi 1k (pcill)(pci/lLL~)(pci/kg, wet)(pci/1)Food Products (pCi/kg, lItet)Sediment (pCi/kg, dry)gross beta H-3 2000 l 1 xl0 2 N.A, N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.Hn-54 Fe-59 Co-58, 60 2n-65 30 15 30 N.A.N.A.N.A.N,A.130 N.A.260'.A.130 N.A.260.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.2I-95 30 N.A.N.A'.N.AI N.A.N.A.Nb-95 I-131 15 lb N.A.7 x10?g.A.N.A.N.A.N.A.60 N.A.N.A.Cs-134 Cs-137 Ba-140 La-140 15 60 15 5 x 10-2 6 x 10-2 N.A.N.A.j30 150 N.A.N.A.E-9 15 18 60 60 86.N.A.N.A.150 180 N.A.N.A.0382p

RETS Nanual Revision 7 Page 28 TABLE E-2 (Continued)

TABLE NOTATION a.The LX3 is the smallest concentration of radioactive material in a sample that.will be detected with 95K'robability with 5X probability of falsely concluding that a blank observation represents a"real" signal.For a particular measurement system (which may include radiochemical separation):

4.66 sb E+V+2.22+Y+exp (-Xht)Mhere.LLD is the"a priori" lover limit of detection as defined above (as picocurie per unit mass or volume), e sb is the-standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute)p.E'.is the counting efficiency (as counts per disintegration), V'is;the.sample sise (in units.of mass or volume), 2 22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield (when applicable), X is, the.radioactive decay constant fox'.the particular radionuclide, and 4t.is the elapsed time between sample.collection (or end of the ssmple collection period)and time of counting (for environmental samplesp, not plant effluent samples).Zt'hould be recotuized that the LLD is defined as a priori (before the fact)limit representing the capability of a measurement system and not as;sn a posteriori (after the fact)lfmic for a particular measurement.

0382p E-10

RETS Nanual Revision 7 Page 29 TABLE E-2'Continued)

TABLE NOTATION b.The IL3 for analysis.of drinking water and surface'water samples shall be performed by gamma spectroscopy at approximately 15 pCi/L-If levels greater than 15 pCi/L are identified in surface water samples downstream from the plant,, or in the event of an unanticipated release of I-131, drinking water samples viLl be analyzed at, an.LLD of 1.0 pCi/L for I-131.c.Other.peaks vhich are measurable and identifiable, together vith the radionuciides in Table E-3, shall be identified and reported.038 2p.

TABLE E-3 BETS Hanual Revision 7 Page 30 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIROHHENTAL SAMPLES Reporting Levels~Anal sis Hatl.r~(Ci Il)Airborne ParticuJate or*Gases (Ci/m>)Fish Ci/K wet)Hilk~(Ci/1)Food Products (Ci/K wet)H-3 2 x>04<a)Hn-54 1 x)03 Pe-59 4 x 102 Co-58 1 x103 N.A.N.A.N.A.N.A.N.A.3 x 104 1 x 104 3 x104 N.A.N.A.N.A.N.A.N.A.N.A.N.A.N.A.Co-60)x 102 N.A.)x 104 N.A.N.A.Zn-65 3 x102 2r-Nb-95 4 x 102 I-131 2 Cs-134 30 Cs-137 50 Ba-La-1)0 2 x 10?N.A.0.9 10 20 lI.A.2 x102 N.A.N.A, 1 x 103 2 x103 N.A.N.A.N,A, 60.70 34 102 N.A.N.A.1 x 102 1 x 103 2 x103 N.A.l For drinking water samples.This is 40 CFR Part 141 value.(a)E-12'0382p~~'

Fo REPORT CONTENT RETS Manual Revision 7 Page 31'.F'.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Reports covering operation of the plant during the previous calendar year shall be submitted prior to May 1'f each year.The Annual Radiological Enviro'nmental Operating Reports shall include summaries, interpretations, and.an.analysis of trends of the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the.plant operation--------on.the environment.

The-reports shall also include the results of land use censuses required.by section E;2 of this manual.If harmful effects or evidea'ce of.irreversible damage are detected by.the monitoring, the report, shall provide an analysis of the problems and a planned course of action'o alleviate the problem The annual radi'ological environmental operating reports shall include suamazizedand, tabulated results in the format of Regulatory Guide 4.8, December.'197&df'11'adiological environmental samples taken during the report@eood In the event.that some results are not available for incluii'on'with the report, the: report shall be submitted n'oting and explaining the reasons, for the missing.results.The missing data shall be submitted's, soon as possible: in a, supplementary report.The reports shall also include the following:

a summary description of the radiological environmental monitoring program;a map of a11 sampling locations keyed.to a table giving distances and directions from one reactor;and the results of licensee participation in the Interlaboratory Comparison Program, required by section E.3 of this manual.0382p RETS Manual Revision 7 Page 32 a F~2 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT:0 A report on the radioactive discharges, released from the site during, the previous 6 months of operation shall be submitted to the Director of the Regional OfHce of'nspection and Enforcement within 60 days after January 1 and July 1 of.each year.The report shall.include summary of the quantities of radioactive liquid and, gaseous effluents released and solid.waste shipped from the plant as delineated in Regulatory Guide 1.21, Revision 1,'Measuring, Evaluating, and Reporting Radioactivity in Solid Pastes and Releases.of Radioactive Material.s in Liquid and Gaseous Effluents from LightWater-Cooled Nuclear Power Plants," with data summarized on a quarterly basis following the format of Appendix B thereof..The report shaX1 include a summary of the meteorological~conditions concurrent with the.release of gaseous effluents during each quarter.as>, outlined"Xn Regulatory Guide 1.81, Revision 1,, with data summarized on a quarterly basis'following the format of Appendix B thereof.Calculated

'ffsite dose to members of the public resulting from the release of liquid-and gaseous effluents and their subsequent dispersion in the river and.atmosphere shall be reported as, recommended in Regulatory Guide 1.21, Revision 1'.The Radioactive Effluent.Release Report shall include the fallowing i&ormation for each type of solid waste'shipped offs'ite during the report period, (a)container volume,.(b)total curie.quantity,"'(specify whether determined by measurement or estimate),.(c)principal radionuclides.(specify whether determined by measurement.

or estimate), (d)sources.of'aste,.and'rocessing.

employed (e.g., dewatered spent.resins, compacted dry waste, etc.)(e)type of container (e g.>LSA, Type A, Type B,'large quantity), and (f)solidification agent or absorbant (e.g.concrete, urea formaldehyde, etc.).038 2p.F-2.~~

RETS Manual, Revision 7 Page 33 F.3 SPECIAL REPORTS (Radiolo ical Environmental Monitorin If measured levels of radioactivity in an environmental sampling medium are determined to exceed the reporting level values of Table E-3 when averaged over any calendar quarter sampling period, a report shall he submitted to the Commission pursuant to Section, E.l of this Manual.A~~~0382p F-3

RETS Manual Revision 7 Page 34 RETS MANUAL Section III OFFSITE DOSE CALCULATION

~~0382p RETS Manual Revision 7 Page 35 1.0 Gaseous Effluents TABLE OF CONTENTS~Pa e 40 1.1 Alarm/Trip Setpoints 40 1.1.1 Release.Limit.Methodology

-pCils'I Release Rate.Limit Methodology

-Dose Rates,-Noble Gas-Iodine and Particulate Release Rate limit Methodology

-Setpoints 1'.2 Monthly Dose Calculations 1.2.1 Monthly Noble Gas Dose.(Conservative Madel)40 40 42 43 46-Gamma dose to air.-Beta dose to air 47 4&1.2.2 Monthly dose from Iodines, Particulates, and Tritium-(Conservative Model)-Thyroid dose-.Bone-Dose--Gastrointestinal Tract (GIT)-Comparison to Limits 49 50 51 52 1.2.3, Monthly Noble Gas Dose (Realistic Model)52-Gamma dose to air-Beta, dose-to air 53 53 1.2'.4 Iodines,, Particulates.

and Tritium (Realistic Model)53 1.2'.5'umulative Quarterly and.Annual Dose 1.3.Quarterly Dose.Calculations.

55-Population'ose 1.4 Gaseous Radwaste Treatment System Operation 57 1.4.1'.System~Descri'ption.

1.4.2.Dose Projections 57 57 1.5 Gaseous: Releases.-Dose Calculation Equations.

1'.S.l Noble gas-Gamma air dose-1.S.2" Noble gas.-Beta air dose 58-1.5.3 Radioiodine, particulate, and tritium-Maxizum organ dose 0382p

TABLE OF CONTENTS 1.6 Gaseous Releases-Dose Factors RETS Manual Revision 7 Page 36~Pa e 61 1.6.1 Pasture Grass-Cow/Goat-Milk Ingestion Dose Factors--RCPi 1.6.2 Stored Feed-Cow/Goat-.Milk Ingestion Dose Factors-RCSi 61 62 1.6.3 Pasture Grass-Beef Ingestion Dose Factors-RMPi 63 1.6.4.StoreLZeed

-Beef Ingestion Dose Factors-RMSi 64 1.6.5 Fresh Leafy Vegetable Ingestion Dose: Factors.~RVFi 65 1.6.6 Stored Vegetable Ingestion Dose Factors-RVSi 66 1'.6'.7'ritium.>>-Pasture Grass-Cow/Goat

-Milk Dose Factors.RCTP I 1.6.8 Tritium-Stored Feed,-Cow/Goat-Milk Dose Factors-RCTS 67 68 1.6-.9 Tritium-Pasture Grass.-Beef Dose Factors,-RMT 69 1.6.10 Tritium-Stored Feed,-Beef Dose" Factors-RMTS 70 1.6.11'ritium

-'resh Leafy Vegetables Dose Factors-RVTF.1".6.12.Tritium-=Stored Vegetables.

Dose Factors-RVTS 1.6.13 Inhalation Dose;-Factors-RIi.1.7'ispersion Methodology'1 72 73 74 l.7".L'ir Concentration

-X.1'.7,.2.'elative Concentration

-X/g'.T.3.Relative Deposition

-.D/g 1.7'.4" Effective Release Height 75 76: 76 77~2.0 Liqui'd:,Effluents 79.1, Release Rate Limit Methodology 79 2.1.1 RETS'equirement 2.1.2 Prerelease Analysis 2.1.3, Release Flow Rate Calculations 79 79 80 0382p 2.2 Instrument Setpoints TABLE OF CONTENTS RETS Manual Revision 7 Page 37~Pa e 81 2.2'Setpoint Determination 2.2'.2 Post<<Release Analysis 2.3 Dose 81&1 82 2.3'BETS Requirement 2.3.2 Monthly Analysis 82 2.3.2.1 Water Ingestion 2.3'2.2'ish Ingestioa, 2.3.2.3*Recreation P.~~4 84~I l>85&6 2.3;2.4 Monthly Summary 2'.3.3 quarterly Dose Calculations 2'.3.3 1.Water Ingestion~))6))~~>')>~87 88 2'.3.3.2'.

Fish-Ingestioa 2;3.3'.Recreation Shoreline.

2'.3.3'4-Total Maximum)Individual, Dose 89 89 90 2;3.3.5'opulation Dose 2'.4"-Operability.-of.

Liquid: Radwaste.Equipment 2.5 Liquid;Dose Factor Equations.

2'.5.L Water Ingestion Dose Factors 2.5.2 Fish Ingestion Dose Factors, 2'.5 3: Shoreline Recreation Dose Factor.91 93 93 93 93 94 3'.0: Radiologi'caZ Environmental.

Monitoring; 3;1 Monitoring Program 3.2 Detection Capabilities 3.3 Nonroutiae Reports 4.0'nnual.

Maximum Individual Doses-To tal, 0382p 94 95 95 95 0

c~ATable Number LIST OF TABLES Title BBf-Offssite Receptor Location Data RETS Manual Revision 7 Page 38 1'.2 Expected Annual Routine Atmospheric Gaseous-Releases from One Unit at BFN 1.3'Sheets 1-22)Joint Percentage.

Frequencies of Wind Speed by-Wind Direction for Stability Class 1.4.Dose Factors for Submersion in Noble Gases 1.5 1.6.1.7'(Sheets 1-8)1.8 (Sheets 1&2)1.9 (Sheets 1.&2)1 10.(Sheets, 1-8)t 1.11.(Shee'ts, 1&2)2'.1 2.2', Sector Elements Considered for.Population Doses I r BFN 50-Mile Population Within Each Sector Ingestion Dose Factors.-'FL~, Radionuclide, Decay,'and.

Stabl'e EXement Transfer Data Dose: Calculation, Factors Inhalation Dose Factors-DFA External Dose-.Factors for Standing, on.Contaminated Ground:-DFG'eceptors for Li.quid Dose Calculations r Bioaccumulation Factors for Freshwater Fish-B 3.1'Sheets.

1-4)3".2;Radiologica1 Environmental Monitoring Atmospheric.

and Terrestrial Monitoring Station Locations 3.3'mdmum Values for.the.Lower Limit of Detection (LLD)0382p

RETS Manual Revision 7 Page 39 LIST OF FIGURES Fi e Number 1 2 1 3 1.4 (Sheets 1-4)~'I lI 4 i I 5 1.6 (Sheets 1W)2.1 2 0'2 2.3 3.1.3.2 Title.BFN-Land Site Boundary BFN Offgas System and SGTS Effluent Monitoring

~'I BFN Normal Building Ventilation Plume Depletion Effect (All Atmospheric Stability Classes)Vertical Standard Deviation of Material in a Plume (All Atmospheric Stability Classes)Relative Deposition (All Atmospheric Stability Classes)Assumed Liquid Effluent Restricted Area--BFN'iquid=

Effluent Monitors Liquid Radwaste Treatment System Environmental Radiological Sampling Locations within 1 mile of plant Environmental Radiological Sampling Locations, From 1 to 5 miles from the plant Environmental Radiological.

Sampling Locations Greater than 5, miles f'rom the plant~'j3 Q 0382p

1.0, Gaseous Efftuents 1.1 Alarm/Tri Set pints RETS Manual Revision 7 Page 40 Specification 3.8.3.1 requires that the dose rate at or beyond the site boundary (Figure 1.1)due to gaseous effluents from the site shall be limited at all times to the following values: 1..500'rem/y to the total body and 3,000 mrem/y to the skin from noble gases.2'<<1:,500 mrem/y to any organ from radioiodines and particulates.

I~~Specification 3.2.K.1 requires gaseous effluent monitors to have alarm/trip setpoints to ensure that the, above dose rates are not exceeded.This section of the ODCM describes the methodology that will be used to determine these setpoints.

Figures 1.2 and 1.3 show the Offgas System, the Standby Gas-Treatment System and normal, building ventilation with effluent monitor locations.

The.methodology for determining alarm/grip setpoints is divided into two major parts.The first consists of.backcalculating from a dose rate-to a release rate limit, in pCi/s, for each nuclide and release point.The second consists of using the release rate limits to determine the physical settings on the monitors.The.methodology for the latter is contained in Technical Instruction 15.1.1'.1.Release.Rate Limit Methodolo Ci s Release Rate Limit Methodolo-Dose Rates First, a dose rate is calculated based on the design-objective source-term mix used, in the licensing of the plant;Dose rates are determined for (1)noble gases, and (2)iodines and particulates.

Release Rate Limit Methodolo-Dose Rates-Noble Gas Dose rates;are calculated for total body and skin,.due to submersion within a cloud of noble gases, using.a semi>>infinite.

cloud model.The use of a finite cloud model would result.in.calculated doses of 0 to 10 percenthigher than those calculations using the semi-infinite cloud model for BFN.The dose rates are evaluated.

at the offsite locations with the highest expected concentrations,, i.e., the nearest.land site boundary points in each sector (from Table 1.1)and at.other locations expected to be the maximum exposure points..The: noble gas radionuclide mix,used in.this.calculation.

is based on the design objective source term given in Table 1.2'.Dispersion of the released radioactivity's handled as.described in Section 1.7 using historical annual average-meteorological data given in Table 1.3.No credit is taken for shielding by residence.

0382p

RETS Manual Revision 7 Page 41 To calculate the dose rate from radiological effluents discharged from a given release point for any one of the potential maxianun-exposure points, the following equations are used.Total Bod Dose Rate Xi.DFBi.where.~total body dose rate, mrem/y.(1.1)Xi~air concentration of radionuclide i, pCi/m3.Aim~concentrations are calculated as: described by Equation 1.14.DFBi~total body dose factor due to gamma radiation, mrem/y per pCi/m3.(Table 1.4).Skin Dose Rate~~Ds.g Xi (DFSi+1~11, DFgi)(1-2)where: Ds.Xi.~-skin dose rate mrem/y.~air'oncentration of radionuclide i,.pCi/m3.Air concentrations.

are.calculated.

as.described by.Equation 1.14.DFSi~skin dose factor due to beta radiation;, mrem/y.per pCi/m>-(Table 1.4).~the average ratio of'issue to air energy absorption coefficients, mremjmrad.

DFgi~gamma-to-air dose: factor.for radionucl'ide-i, mrad/y per pCi/ms'Table*

1.4).The total, body and'kin dose'.rate calculations are.repeated for each release point.Dose.rates.for releases from;all.building vents: are summed..The.maximum stack and building, vent total body and skin dose rates.will be used to determine release rate limits 0382p,.

RETS Manual Revision 7 Page 42 0 ReLease Rate Limit Methodolo-Iodine and Particulate Dose Rates For setpoints, the iodine and particulate dose rates are calculated for the design objective source term given in Table 1.2.Dose rates are calculated for the critical organ, thyroid, of the critical.age group, infant.Pathways considered are inhalation, ground contamination and milk ingestion.

The dose rates are evaluated at the offsite locations with the highest.expected concentrations, i.e., the.nearest.land site boundary points in each of the 16 sectors (from Table 1.1)and at other locations expected to be the maximum exposure points.This calculation assumes that a (hypothetical) cow is at each of these Locations.

These cows are assumed, conservatively, to obtain 100 percent of their food from, pasture grass.The inhalation, ground contamination, and milk ingestion dose, rates (in mrem/year) for the-selected.organ (thyroid)and age group (infant)are calculated using Equation 1.13 as described in section 1.5.3.For determining the total thyroid dose rate from iodines.and particulates:

DTH~DTHI.+DTEG+DTHM (1.3)where:.~wz DTEC~.total.thyroid dose rate,, mrem/yr.~thyroid dose rate due to inhalation, mrem/yr.,~total.body dose rate due to ground contamination, mrem/yr.The: thyroid dose rate is assumed to be equal to the total body dose rate for this pathway..~thyroid, dose rate.due to.pasture grass-cow-milk ingestion, mrem/yr., The above dose rate" calculation;is'epeated for'ach release point..Dose rates: for.releases.from all building vents are summed.The maximum stack and building, vent thyroid.dose rates wilX be used to determine release rate.Limits;..0382p

RETS Manual.Revision 7 Page 43 Release Rate Limit Methodolo-Set pints The dose rate limits of interest (Specification 3.8.B.1)are: Total Body~500 mrem/yr Skin~3000 mrem/yr Mmcimum Organ~1500 mrem!yr These limits.are divided by the corresponding calculated, dose rates (from Equations 1.1,.1.2, and 1.3): DTB (vent or stack)Skin Dose Rate Limit DS (vent or stack)Kucimum Organ Dose Rate Limit RS(vent, or stack)RTH(vent or stack)~(vent or.stack)Total Body Dose Rate Limit RTB(vent or stack)These ratios represent how far above or.bel'ow the guidelines the dose rate.calculations, were..A total release rate, g, for each nuclide type (noble gas or iodine/particulate) and release point" (building vent or stack)is calculated, using the source term data in Table 1.2.Thus,.four total release rates are calculated:

Qngv,~Total noble gas release rate Ci/s., from building exhaust vents,~Total noble gas release rate from main stack,.Ci/s.~Total iodine and particulate release rate from.building exhaust vents, Ci/s.Qips~Total iodine and particulate release rate from-main stack,, Ci/s..To obtain a release: rate limit,, r, for each nuclide type and release point, the total release rate, g, for that nuclide type and release point is.multiplied by the corresponding.

ratio, R: 0382p t For noble gases released from building vents: ngv R~v Qngv~or RSv~ngv whichever is more restrictive, i.e., smaller.RETS Manual Revision 7 Page 44 where rngv~Calculated release rate limit for noble gases released from building vents.RTSv~Ratio of total body dose rate limit to total body dose rate for building vent releases, as calculated above gn~'Total Table 1;2 noble gas-release rate from building vents.RSv~Ratio of skin dose rate limit to skin dose rate for building vent releases, as calculated above.For noble gases released from the stack: rngs Res Angs i~'Ss Rngs whichever is more restrictive

,.i.e., smaller.~Calculated release rate limit for noble-gases released from the stack..Res~Ratio of: total body dose rate limit to total body dose rate.for stack rel eases , as calculated above.qngs~Total Table 1.2 noble gas release rate from stack.RSs'Ratio of skin dose rate limit to skin.dose rate for stack releases,, as.calculated above., 0 0382p RETS Manual Revision 7 Page 45 For iodines and particulates with half-lives greater than 8 days released from building vents: ripv RTHv Qipv where ripv~Calculated release rate limit for iodines and particulates released from building vents.RTHv~Ratio of maximum organ dose rate limit to mmcimum organ dose rate for building vent releases, as calculated above.Aipv~Total Table 1.2 iodine and particulate release rate from building vents.For iodines and.particulates with half-lives greater than 8 days released from the stack: ips RTHs~ips~~where rips~Calculated release rate limit for fodines and particulates released from the stack.Res~Ratio of maximum organ dose rate limit to amdmum organ dose rate for stack releases, as calculated above.pips~Total Table 1.2 iodine and particulate release rate f rom stack.The release rate limits,, r,, calculated for BFN using this methodology are: Noble Gas Iodine and Particulate Stack.Building, Vents rngs~1.44E+Ol Ci/s.rngv~1.50E-'OL'i/s.

rips~3 57E&5 Ci/s ripv~-2 19E-'06 Ci/s The values.listed, are used as administrative guidelines for: operation and for development of alarm/trip setpoints (see Technical 0382p s e~s s N~4~hh-~s~s~: I h~~RETS Manual Revision 7 Page 46 Instruction 1.5)to ensure that instantaneous dose rates do not exceed release rate limits.Instantaneous release rates, q in Ci/s,.for each nuclide type and release point are limited by the following equations:

For.noble gases,+'1 gsgv gags, 0.15 14.4 For iodines and particulates, qipv qips'19E-06 3.57E&5 where s qngv~instantaneous.

noble gas release rate from building vents, Ci/s..qngs qipy~instantaneous noble gas release rate from the, stack, Ci/s.~instantaneous iodine and particulate release rate from building vents, Ci/s.qips:~instantaneous iodine and particulate release rate from the stackg~Ci/st s 1.2.Monthl Dose Calculations Dose-calculations will be performed once per 31.days to determine compliance with specifications, 3.8.B.3'nd.

3.8.B.5.These specifications require that the dose at or beyond.the site boundary due.to gaseous effluents from each reactor at the site.shall be 1'imited.'o the.following:

For.noble.gases,, 1..During any calendar quarter,, 5 mrad.to air for gamma.radiation-and 10 mrad,to air for.beta.radiation..

2'uring.any calendar year, 10 mrad.to air for gamma radiation and.20.mrad to air for beta radiation..

0382p

RETS Manual Revision 7 Page 47 For I-131, I-133, Tritium and, particulates with half lives greater than 8 days, 1.During any calendar quarter, 7.5 mrem to any organ.2.During any calendar year, 15 mrem to any organ.This<<section of the ODCM describes the methodology that will, be used to perform these monthly calculations.

Doses will be calculated using the conservative model described in Sections 1.2.1 and 1.2.2.If the monthly fraction of the annual one-unit-Technical Specification Lait is exceeded, a realistic model, described in Sections 1.2 3 and 1.2.4, will be used.1.2.1.Monthl Noble Gas Dose (Conservative Model)Doses to be calculated are gamma and beta air doses due to exposure to a semi-infinite cloud of noble gases.The use: of a finite cloud model would result in calculated doseS of 0 to 10 percent higher than those calculations using the semi-infinite-cloud model for BPÃ.'eleases of Ar-41, Kr-85m, Kr-85, Kr-87, Kr-88, Ze-131m, Ze-133m, Ze-133, Ze-135m, Ze-135, and Xe-138 are considered.

Because only these nuclides are considered, the dose is divided by 0.9, to account for a possible 10 percent contribution of dose from other nuclides.The dispersion factor used will be the highest annual-average X/g based.on 1977-1979 meteorological data (Table 1.3).Dispersion factors are calculated using the methodology described.

by Equation 1.15.Stack releases, are considered elevated releases.All other vent releases will Qe treated as ground level.No credit, is taken.for radioactive decay.Monthl Conservative Model-Gamma dose to air Dg (X/0)0.9 DF'.15x10~(1.4)where:: Dy~gamma.dose to.air,, mrad..x/a~highest land-site boundary annual-average relative concentration,.s/ms (from Table 1.1).~1.84x10~for ground level releases,.

~2.08x10 8 for elevated releases (stack).0382p

0'RETS Manual Revision 7 Page 48~fraction of total gamma dose expected to be contributed by the assumed nuclides.10~~pCi/Ci conversion factor.3.15x10~~s/yr conversion factor.Qi~monthly release of radionuclide i, Ci-DFgi~gamma-to-air dose factor.for.radionuclide i,, mrad!yr per pCi/m~'Table 1.4).Monthl Conservative Model-.-Beta dose to air (X/Q)10 0.9 3.15xLO.T (1.5)where: Dg X/Q~beta dose to air, mrad.~highest Land-site boundary annual-average relative concentration, s/ms (from Table 1.1).~-1.84x106 for ground.level releases,~: 2.08xl0 8 for elevated.releases (stack).~-fraction of total beta dose expected to be, contributed, by the assumed.nucl ides.:~pCi/Ci conversion.

factor.3.15x10~~s!yr conversion factor.Qi Dpi~monthly release of.radionuclide i', Ci..~beta-to-air dose factor for radionuclide i, mrad/yr per pCi/m~'Table 1.4).

RETS Manual Revision 7 Page 49 1.2.2'onthl dose from Iodines Particulates and Tritium (Conservative Model)Doses are to be calculated for the infant thyroid from milk ingestion and for the child bone and teen gastrointestinal tract (GIT)from vegetable ingestion.

Releases of H-3, I-131,.and 1-133'are considered for the milk pathway.H-3,.Sr.-89, Sr-90,, Cs-134, and Cs-137 releases are considered for the vegetable pathway to.the child bone.H-3,, Co-58, and Co-60 releases are considered for the vegetable.

pathway to the teen GIT.tract.The most critical real cow location is considered for the milk pathway and the most critical.location with.a,home-use garden is considered for the vegetable pathways (see Table 1.1).The cow is assumed to graze on pasture grass for the whole year.The highest annual-average X/Q and D/Q based on 1977-1979 meteorological data (Table 1.3)will be used for ingestion pathway locations.

Dispersion values are.calculated as described by Equations 1.15 and 1.16.Stack releases are considered elevated releases.All other vent releases will be treated as ground, level.No credit is taken.for radioactive decay.Doses are divided by 0.9 to account for a possible 10 percent contribution from other nuclides.Monthl Conservative Model-Infant Th oid Dose from Milk In estion The monthly thyroid dose from milk, ingestion is calculated using the following.

equation: (~i'CPi)D/g'0+'gT RCPT)X/g 0.9': 3.15x10~'here~'onthly release of iodine nuclide i, Ci.~monthly release.of H-3,.Ci..~I-'31 or I-133 pasture grass-cow-milk ingestion.

dose factor for, infant;thyroid, mrem/yr per pCi/m>-s.Dose.factors are.calculated as, described.

in.Section 1.6.1.RCpT:~H-3: pasture grass-cow-milk ingestion dose factorfor infant thyroid, mrem/yr;per pCi'/cc.The dose factor is calculated as: described in Section 1.6.7'..0382p

~q~~v RETS Manual Revision 7 Page 50 D/Q~.highest relative deposition rate for a location.with an identified milk cow, m"~(from Table 1.1).~3.16x10 10 for ground level releases,~2.30xl0 10 for elevated releases (stack).X/Q~highest relative air concentration for=a location with an identified milk cow, s/m~(from Table 1.1).~: 1 47x1007 for ground level, releases,~1.69xlO~S for.elevated.releases (stack).0.9'fraction of, dose.expected to be contributed by I-l.31, I-133 and;H-3.3.15x10~~s/yr.10 s pCi/Ci.Monthl Conservative Model-Child Bone Dose from Ve etable In estion The monthly bone dose from vegetable iqgestion is calculated using.the following equation: E (Qi DFi)D/Q-10+.QT DFT X/Q DBC, 0.9'3'5x10~(1.7)where.~monthly'elease of Sr.or Cs nuclide i,, Ci.~monthly release oE H-3,, Ci..DFi~Total vegetable ingestion dose factor.to,child bone for Sr-89,, Sr-90,, Cs-134 or Cs-137,.mrem/yr per, pCi/m~-s.~R~i'RySi, where RgFi is the dose factor for fresh leafy vegetables:(as calculated.

in Section.1.6.5)and RgSi is-the, dose factor.-for stored vegetables (as calculated in Section.1.6.6)-DFT~Total.vegetable ingestion dose factor.for child, bone for'-3, mrem/yr per pCi/cc.~RyFT+EST, where.R~is.the.tritium.dose factor for~fresh leafy vegetables, (as calculated, in Section;1.6;11)and RqSi is.the.tritium-dose factor: for stored.vegetables (as.cal'cul'ated".

in, Secti'on'.

1.6.,12)".'.

D/Q RETS Manual Revision 7 Page 51~highest relative deposition rate for a location with an identified home use garden, m>(from Table 1.1).~4.46x10 09 for ground level releases,~1 13x10~9 for elevated releases (stack).X/Q~highest relative air concentration for a location with an identified home use garden,.s/m>(from Table 1.1).~1.57x10 06 for ground level re1eases,~9.50x10 09 for, elevated releases (stack).3.15x10~~.s/yr..pCi/Ci., 0.9~fraction of total child bone dose expected to be contributed by H-3, Sr89, Sr-90,, Cs-134, and Cs-137.~~~f~Monthl Conservative Model-Teen Gastrointestinal Tract GIT Dose from Ve etable In estion~I I(The monthly teen GIT dose from vegetable ingestion is calculated using the: following equation: (QiDFi)D/Q, 10+QT DFT X/Q DGT 0.9: x 3~15x10>(1.8)here.~monthly release of cobalt nuclide i, Ci.~monthly release: of H-3",.Ci.,~Total vegetable ingestion dose factor to the teen GIT for Co-58 or Co-60, mrem/yr per pCi/m-s~Rgpi+-RgSi, where R~i is.the dose factor for fresh leafy vegetables-(as calculated.

in Section 1.6-5)and RySi is the dose factor for stored vegetables (as calculated in Section 1.6.6)., DFT~Total vegetable ingestion dose factor, to the teen, GIT for H>>3,.mrem/yr per pCi/cc.~R~+EST,, where Rgpg is.the.tritium dose factor for fresh.leafy vegetables'as calculated in Section 1.6.11)and.EST i'sr the tritium dose factor for.stored, vegetables.(as.calculated.

in Section 1.6.12).0383p

4 t D/Q RETS Manual Revision 7 Page 52~highest relative deposition.

rate, for a location with an identified home use garden, m~(from Table 1.1).~4.46xlO 09 for ground level releases,~1.13xlO"09.

for elevated releases (stack).x/0~highest relative air concentration for a location with an identified home use garden, s/m3 (from Table 1.1).~1.57x1006 for ground level releases,~9.50xm~9 for elevated releases (stack).3.15x10>s/yr.10~~pCi/Ci 0.9~fraction of total teen GIT dose expected to be contributed by H-3, Co>>58, and Co-60..~~I'e',i~>g Total Monthl Dose-.Co arison to Limits;t The calculated gamma-air and beta-air doses are compared to the monthly fraction of the annual one-unit limit'for-these doses, i.e., 0.83 mrem for gamma-air and 1.67 mrem,for beta-air.The.mmdmum monthly organ dose is the highest of the three doses calculated; it is, compared to the monthly fraction of, its annual limit, i.e., 1.25 mrem.If any of the doses calculated by the.conservative monthly dose model exceed the monthly fraction of the-one-unit annual Technical Specification limits, a more comprehensive dose assessment will'be performed as described below.For: doses calculated.

to be less than these limits, the results-'f the conservative monthly model will be used to determine.

cumulative quarterly and annual doses as described in Section 1.2.5.'1.2.3 Monthl Noble Gas Dose (Realistic Model)In.the.real'istic model, all measured radionuclides are used to calculate gamma and beta air.doses.The dose is evaluated at the nearest land site boundary point in each sector and at.other locations expected to be maximum exposure points using a semi-infinite cloud model..The use of a finite.cloud.model would result in, calculated:

doses of.0 to 10 percent'.higher.than=those.calculations using the semi-infinite cloud model for BFN.Historical onsite meteorological data from, the period 1977-1979 (Table 1.3)will, be used to calculate" dispersion factors-as-.described in section 1.7'., Stack releases will be considered elevated releases., Radwaste and reactor building releases, will be considered, split-level releases..

Turbine building releases will be treated as ground.level.Radioactive decay is, considered in this calculation.

The monthly release is averaged over one year to obtain an average release rate.0383p

RETS Manual Revision 7 Page 53 Realistic Model-Gamma dose to air 7 Xni Dpi i where:,~-gamma dose to air for sector n, mrad'.Xni.~air concentration of'adionuclide i in sector n, pCi/m~'.Air concentrations are calculated as described by Equation 1.14.~gamma-to-air dose factor for radionuclide i, mrad/yr per pCi/ms (Table 1.4).I~time period over.-which the release is averaged, yr.Realistic Model-Beta dose to air Dan~tm.7 Xni DFni (1.10)where: Dan.~beta, dose to.air for sector: n, mrad..~air concentration of radionuclide i in.sector n, pCi/ms., Air concentrations are calculated as described by.Equation 1.14..~beta to air dose: factor.for radionuclide i, mrad/yr per pCi/ms'Table..

1.4).tm.~time: period-over which.the release-is: averaged, yr.The.highest gamma-air and beta-air doses calculated:, will.be used.in the cumulative quarterly and, annual dose: determination.

to check compliance.

with Specification 3.8.B;3., 1.2;4 Zodines Particulates and Tritium,(Realisti'c.

Model)Doses for releases, of iodines,-, particulates, and: tritium will be calculated using Equation 1.13 given in Section 1.5.3.The caLculation will consider all measured radionuclide releases., The dose will be evaluated for all organs.and all age groups, and the maximum organ dose selected.Actual land use survey data and grazing information will be'sed to determine the dose for real individuals and pathways.0383p

~"--~f RETS Manual Revision 7 Page 54 Historical onsite meteorological data from the period 1977-1979 (Table 1.3)will be used to calculate dispersion factors as described in section 1.7.Stack'releases will be considered elevated releases.Radwaste and reactor building releases will be considered split-level releases Turbine building releases will be treated as ground level.The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination; inhalation,.

vegetable ingestion (for identified garden locations), cow and/or goat milk ingestion (if a cow or goat is, identified for the location),.

beef ingestion (the beef ingestion dose for the location of highest beef dose for all receptors will be considered the beef dose for all receptors).

The receptor having the highest organ dose is then used in the cumulative quarterly and annual dose determination to check compliance with Specification 3.8.3.5.1.2.5 Cumulative uarterl and Annual Doses Cumulative calendar quarter doses are estimated by summing the doses calculated for each month in that quaiter.Cumulative calendar year doses.are estimated by summing the doses calculated for each month in that year.The cumulative calendar quarter and calendar year doses are compared to their respective one-unit.Technical Specification limits to determine compliance.

If'ny limit is exceeded, a determination

'will be made to apportion the dose.between the reactor units in accordance with the.releases.that.can be assigned to each.

1.3 uarterl Dose Calculations RETS Manual Revision 7 Page 55.A complete dose analysis utilizing the total estimated gaseous releases for each calendar quarter will be performed and reported as required in Specifications 6.7.5.Methodology for this analysis is that which is described in Section 1.5, using the quarterly release values reported by the plant personnel.

For iodine releases, it will be assumed that half the iodines released are organic iodineswhich contxibute only to the inhalation dose.All real pathways and receptor locations (as identified in the most recent land use survey)are considered.

In addition, actual meteorological data representative of each corresponding calendar quarter will be used to calculate dispersion factors as described in section 1.7.Stack releases will be considered elevated releases.Radwaste and reactor building releases will be considered split-level releases.Turbine building releases will be tx'eated as ground level.The highest gamma-air and beta-air doses calculated will be used to check compliance with the quarterly Limits of Specification 3.8.B.3.The highest organ dose for a real receptor is determined by summing the dose contribution from all real pathways including ground contamination, inhalation, vegetable ingestion (for identified garden Loqations), cow and/or goat milk ingestion (if a-cow or goat is identified for the location), beef ingestion (the.beef ingestion dose for the location of highest beef dose for all xeceptors will be considered the beef dose for all receptors).

The receptor having the highest organ dose is then used.to check compliance with the quarterly limits of Specification 3.8.B.5.Po ulation Doses For determining.

population doses to the 50-mile population around the plant, each compass sector is broken down into elements.These elements are defined in Table 1.5.For each of these sector elements,.

an average dose is calculated, and then multiplied by the population in that sector element.Dispersion factors are calculated for the midpoint of each sector element (see Table 1.5).For population doses resulting from ingestion, it is conservatively assumed that all food eaten by the average individual is grown locally..The general equation used for calculating the population dose in a given sector element is: Dosepop 7 RATIOP.*'OPN*AGE*0 001+DOSEP P where;RATIOp~ratio of average to maximum dose for pathway P.(Average ingestion rates ax'e obtained from Regulatory Guide 1.109, Table.E-4.)~0.5 for submersion and ground exposure pathways, a shieLding/occupancy factor.0383p

~1.0 for the inhalation pathway.RETS Manual Revision 7 Page 56~0.515,, 0.515, 0.5, and 0.355 for milk, for infant, child, teen and adult,.respectively.(It is assumed that the ratio of average to maximum infant milk ingestion, rates is the same as, that for child)~1.=0,', 0'.90,, 0.91,, 0.86 for.beef ingestion,, for infant, child, teen and adult,, respectively.

~1.0,, 0 38, 0'38,.0.37 for vegetable ingestion, for infant, child,.teen and.adult, respectively.(It is assumed that the average individuaL eats no fresh vegetables, only stored.vegetables.)

POPN~the population of the sector element, persons (Table 1.6).~fraction of the population belonging; to each age group.~0.015,.0.168, 0.153,.0.665 for infant, child, teen and adult, respectively (fractions taken from NUREG/CR-1004, Table 3.39).0.00L~conversion from mrem.to rem., DOSEp~the dose for.pathway P.to the maximum=indivkdual at the location-under consideration, mrem.For ingestion pathways,.

this'ose is multiplied by an average decay correction to account for decay as.-the food is moved through the food distribution cycle.This average decay correction, ADC, is defined.a': ADC,~exp(-'hit),.

for: milk."and, vegetables,, where~decay constant, for: nuclide i', seconds'~distribution-time for.food product under consideration (f'rom, Regulatory Guide 1.109, Table D-l).~K.21E+06 seconds (14 days)for vegetables..

~-3;46E+05 seconds (4 days)for milk.exP(-Kit)Kitch ADC'.l.-exP(>>kitch)

, for meat,.where Xi~decay constant.for nuclide i, seconds.0383p

RETS Manual Revision 7 Page 57 H additi,onal distri.bution time-for meat, over and above the time.for slaughter to consumption described in Section 1.6.3,.7 days (from Regulatory Guide 1.109, Table D-2).tcb~time to consume a whole beef,, as described in Section 1.6.3.For beef ingestion, the addi.tional factors in the calculation of ADC negate the integration of the dose term over the period during which a whoLe beef is'onsumed, for the calculation of populati.on dose.This assumes that the rmuciamn individual freezes and eats a whole beef, but the average individual buys smaller portions at a time.PopuLation doses are summed over all sector elements to obtain a total---population-.

dose for the 50~Le populati'on.

~<<iii/ii~i i 1.4 Gaseous Radwaste Treatment S stem 0 eration The gaseous radwaste treatment system (GRTS)described below shall be maintained and operated to keep releases,CLARA.

~~'+~~~1.4.L-S stem Descri tion A.flow diagram for the GRTS is.given in Figure 1.3.The system includes the-subsystems that process and dispose of the gases, from the main condenser-air ejectors, the.staxtup vacuum pumps, and the gland seal condensers.

One gaseous radwaste treatment system-is provided fox each unit The processed gases.from*each unit are routed to the plant stack for dilution and elevated release to the.atmosphere-The airejector off-gas line of each.,uni.t and the stack: are continuously monitored by radiation monitors.In accordance with.Section D;2 of the: REM,.dose: projections'ill, be performed..

This: wi.ll be done by-averaging-the calculated dose.for the most recent month and, the calculated.

dose for the previous month and assigning that.average dose as.the projection for the current month.If: the: results.of'he dose projection..

indicate.potential doses'n excess of: the-monthly fraction-of the.annual Technical'pecification dose Limit, efforts will.be: x'ecommended.

to minimize future releases..

0383p RETS Manual Revision 7 Page 58 I I I~~1.5 GASEOUS RELEASES-Dose Calculation Equations 1.5.1 Noble as-Gamma air dose I Gamma air doses due to exposure to noble gases will be estimated with the following equation: DY~Xim DFY (1.11)whexe: DFYi~Gamma air dose, mrad~concent'.ration

'of nuclide i at.location m, pCi/m3.Air: concentrations.

axe calculated as described by Equation 1.14.~~.'dose conversion factor for external gamma for nuclide i, mrad/yeax'er microcurie/m3 (Table 1.4).1 5.2 Noble as-Beta air dose'I~Beta air doses due.to exposure to noble gases will be estimated with the-t following equation: DS~Xim Dpi (1.12)whexe:~Beta air dose, mrad~concentration of nuclide i at location m, pCi/m3.Aix concentrations are calculated as described by Equation 1.14.Dpi~dose conversion factor for external beta.for nuclide i, mrad/year per microcurie/m3 (Table 1.4).0383p e*~~~~"';~~',et~~-','.~N C~~vow~,?a w'", bw=~w~i 4~-~~-,,~~1.5.3 Radioiodine articulate and tritium-Maximum or an dose RETS Manual Revision 7 Page 59 Organ doses due to radioiodine, particulate and tritium releases are calculated using the following equation: Dorg~3+17E&8 (E (X/Q~RPi+D/Q Rgi+X/Q RIi)Qi+(X/Q RPT)QTl p where: Dorg~Organ doseg mrs'.17E-08

~conversion factor, year/second.

X/Q~Relative concentration for, location under Relative concentrations are calCulated as Equation 1.15.A~consideration, sec/m3.described by Rpi~ingestion dose facto>>for.pathway'P.

for each identified nuclide i (except tritium), m2-mrem/year per microcurie/second.

Ingestion pathways available for con'siderati'on include: pasture grass-cow-milk ingestion stored.feed-cow-milk ingestion pasture grass-goatmilk ingestion stored feed-goat-milk ingestion pasture: grass-beef ingestion stored feed-beef ingestion fresh, leafy vegetable ingestion stored vegetable ingestion D/Q RZi Equations for calculating these ingestion dose factors are given in sections 1.7..L through 1.7.6.~Relative deposition for location under consideration, m~.Relative deposition is calculated as described in Equation 1.16.~Dose factor for standing on contaminated ground, m2-mrem/year per microcurie/second., The equation for calculating the ground.plane dose factor.is given in Section 1.6.14.~Inhalation dose factor, mrem/year per microcurie/m3.

The equation for calculating the inhalation dose factor, is.given in Section-1.6.13.0383p 1RETS Manual Revision'7 Page 60~adjusted release rate for nuclide i for location under consideration, pCi./sec.The initial release rate is adjusted to account for decay between the release point and the location, depending on the frequency of wind speeds applicable to that sector.Hence, the adjusted release rate is equal to the actual release rate decayed for an average travel time during the period.9~Qi0 E f j exp(-Xi x/uj)j~l where Qio I~initial average release rate for nuclide i,over the'eriod, pCi/sec.r,~joint, relative frequency'of'occurrence of winds in windspeed class j blowing toward this exposure point, expressed as a fraction.Xi~radiological~decay<constant,for'nuclide i, sec 1.~"~downwind.di'stance, meters'j~midpoint value of wind speed class interval j,.m/s.~ingestion dose factor for pathway P for.tritium;m2-mrem/year per microcurie/second.

Ingestion pathways available for consideration are the same as those listed above for Rpi.Equations for calculating ingestion dose factors for tritium are given in sections 1.7.7 through 1 7.12.QT~adjusted.release rate for tritium for location under.consideration, pCi/sec.Calculated.

in the same.manner as.Qi above.0383p

1.6 GASEOUS RELEASES-Dose Factors RETS Manual Revision 7 Page 61 1.6.1 PASTURE GRASS-COW/GOATWILK INGESTION DOSE FACTORS-RCpi (m2-mrem/year per microcuries/second) 6 r(1~(%Etc)).Biv(1~(-Xitb))

RCPi~10 DFLiaoUapFm<QfexP(" Xitfm)fp(Yp E e v P where: 106~conversion factor, picocurie/microcurie..

DFLiao Uap, Fmi~ingestion dose conversion factor-for nuclide i, age group a, organ.o,.mrem/picocurie (Table 1.7).~milk ingestion rate for age group a, liters/year

~transfer factor for nuclide i from animal,'s feed to milk,, days/liter (Table 1;8)..Rf tfm f'p,~animal's consumption rate,'g/day.

~decay constant.for nuclide i,, seconds, 1 (Table 1.8).,~transport.

time: from milking, to-receptor, seconds.~fraction of time.animal.spends, on, pasturedimensionless.

~fraction of activity retained.on.pasture grass, dimensionless.

tep Yp~: the.effective decay constant,.

due, to.radioactive decay and weathering, seconds ,, equal to'Ai+Xw.~.weathering.

decay constant.for.leaf and plant, surfaces, seconds 1.~time.pasture is.exposed to.deposition,, seconds.~:agricultural productivity by.unit area of pasture grass, kg/m2,~transfer.;

factor for nuclide: i.from soil to vegetation,, picocuries/kg (wet.weight-of vegetation) per picocuries/kg.(dry soil): tb.~: time.period over which accumulation on the ground;is.evaluated,, seconds'e-

~effective surface, density of'oil~kg/m~.NOTE: Factors defined, above, which do not reference.a table for their numerical values, are listed in.Table 1.9..0383p I

e 1 6.2'TORED FEED-CON/GOAT-MILK INGESTION DOSE FACTORS-RCSi (m2-mrem/year per microcuries/second)

RETS Manual Revision 7 Page 62" ((-X~l)(+P>sf E where 6 (~(->itcsf))

RCSi~10 DFLiao Uap Fmi Qf fs exP(-Xitfm) tcsf i LO6'conversion factor, picocux'ie/microcurie.

DFl iso~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7).~milk ingestion rate for*age group a, Liters/year.~'

transfer factor for nuclide i from animal's feed to milk, days/liter (Table.1.8)..~animal's consumption rate,.kg/day., fs'-fraction of time animal spends on stored feed, dimensionless.

~: decay constant for nuclide i, seconds 1 (Table 1.8).~: transport:, time fxom-milking to receptor, seconds.tcsf~time between harvest of stored feed and consumption by animal, seconds.~fraction of activity retained on pasture grass, dimensionless.

tesf>sf:~iv~the effective decay constant, due to radioactive decay and weathering,, seconds , equaL to'hi+Xw.~weathering decay constant for'eaf and plant surfaces, seconds 1.~time;stored feed ixposed to deposition,, seconds..~agricultural productivity by unit area of stored feed, kg/m2.~transfer.factor fox'uclide i from soil to vegetation, picocuries/kg (wet;weight of vegetation) per: picocuxies/kg (dry soil)..~time period over: which accumul'ation on the: ground, is evaluated, seconds.~effective surface.density of soil, kg/m2.!NOTE:.0383p Factors defined above which do not reference a table for their numerical values, are listed in Table L.9.

RETS Manual Revision 7 Page 63 1~6'PASTURE GRASS-BEEF INGESTION DOSE FACTORS-~i (m~mrem/year per microcuries/second) 6 (1-exP(-Xitcb))

~i~10 DFLiao Uam Ffi Qf exP(-Kits) i tcb f{r(1 (-X t g))~B (1 (-'A t))p Q-)where:]Q6~conversion factor, picocurie/microcurie.

DFLiao Usm,, Ffi~ingestion dose conversion factor for nuclide i, age group a, organ o, mrem/picocurie (Table 1.7).A~~meat.ingestion.

rate for age group a, kg/year..~: transfer factor for nuclide i from cow's feed to meat, days/kg (Table.1.8).tcb.~cow's consumption rate, kg/day.~-decay constant for nuclide i, seconds 1 (Table 1.8).~time for receptor to donsume a whole beef, seconds.~transport time fromm slaughter to consumer, seconds.~.fraction of time cow spends on pasture, dimensionless.

~fraction of activity retained on pasture.grass, dimensionless.

~: the-effective decay constant, due to radioactive decay and weathering, seconds , equal to Xi+Xw.~weathering decay constant for leaf and.plant, surfaces, seconds 1..tep~time pasture is exposed to deposition, seconds.,~agricultural productivity by unit area of pasture.grass, kg/m~.Biv.~transfer factor for nuclide i from soil.to vegetation, picocuries/kg (wet weight, of vegetation) per picocuries/kg,(dry soil).tb P': time over.which accumulation'n the ground is evaluated, seconds.~effective surface density of soil, kg/m~..NOTE:: Factors defined above which do not reference" a.table for their numerical values,, are listed.in Table 1.9.0383p li6 4 STORED FEED-BEEF INGESTION DOSE'ACTORS

-RMSi~~(m~-mrem/year per microcuries/second)

RETS Manual Revision 7 Page 64 (1-exP(-'Aitcb)

)RMSi~10 DFLiao Uam Ffi Qf exp(-Kits) i tcb s (L~(A t))r x'(1 (X t~))B (1 (-'X t))i tcsf.>sf E+P where: 106'conversion factor, picocurielmicrocurie.

DFliao~ingestion dose convex'sion factor for nuclide i, age group a, organ.o, mrem/picocurie (Table 1.7).Ffi.~meat ingestion rate for age group a, kg/year.r'transfer factor for nuclide i from cow's, feed to meat, days/kg (Table.1.8).~cow's consumption rate, kg/day.Xi~decay constant for nuclide i, seconds 1 (Table 1.8).tcb~time for recePtor to consume a whole beef, seconds.t ts~transport time from slaughter to consumex',.

seconds.fs~.fraction=of time cow spends on stored.feed, dimensionless.

tcsf tesf.>sf~time between harvest of stored feed and consumption by cow, seconds.~fraction;of activity xetained.on pasture grass, dimensionless.

~time stored feed is exposed to deposition, seconds.~agricultural.

productivity by unit.area of stoxed feed, kg/m~.,'AE Biv~the effective decay constant, due to radioactive decay and weathering, seconds 1, equal.to Xi+Xw.~weathering decay-constant for leaf and plant surfaces,, seconds 1.~transfer.factor for nuclide.i from soil to vegetation, picocuries/kg (wet weight of vegetation)'er picocuries/kg (dry soil)..tb~-time over which accumulation on the ground is evaluated, seconds.,~effective surface density of soil,.kg/m~.NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 1.9.0383p

RETS Nanual Revision 7 Page 65 1.6 5 FRESH LEAFY VEGETABLE INGESTION DOSE FACTORS RVF (m2-mrem/year per microcuries/second) 6 r(1~(->Etc)

)Biv(1~(->itb)

)(~*~)Yf E P where: 106 I~conversion factor, picocurie/microcurie.

DFLiao thc.a ingestion dose conversion factor for nuclide i, age group a, organ.o,.mrem/picocurie (Table 1.7).~decay: constant for nuclide i, seconds 1 (Table 1A).,~.'average.

time between harvest.of vegetables and their consumption and/or storage, seconds'~1~consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.fL~fraction of fresh leafy vegetables grown locally, dimensionless.

~fraction of deposited activity retained on vegetables, dimensionless.

~the effective decay constant, due to radioactive decay and weathering, seconds 1.i+.tw~decay constant for removal of activity on leaf and plant surfaces by weathering, seconds 1-~exposure time in garden for*fresh leafy and/or stored vegetables, seconds.~vegetation areal density for fresh leafy vegetables, kg/m2.Biv~transfer factor for nuclide i from soiL to vegetables, picocuries/kg (wet weight.of vegetation) per picocuries/kg (dry soil).tb~-time.period over which.accumulation'n the ground is evaluated, seconds.~effective surface density of soil', kg/m~.NOTE Factors defined above which do not reference a table for their numerical values, are 1'isted in Table 1.,9.0383p 4

0 1.6 6 STORED VEGETABLE INGESTXON DOSE FACTORS RVS modem/year per microcuries/second)

RETS Manual Revision 7 Page 66 6 (1-e(-Ai t))t-1 i.tsv.~r(1-e(-X t))B (1-e(-X t))>sv E+P 6'here:~decay constant for nuclide i, seconds 1 (Table-1.$).I~1 l)~~10~conversion.,factor,.

picocurie/microcurie.

DFLiao~ingestion dose-conversion factor for nuc 1 i de i,, age group a, organ o, mrem/picocurie (Table.1.7).thc.~average time between harvest of" vegetables and their consumption and/or storage,seconds..Usa~consumption rate of stored, vegetables by the receptor in age group a,.kg/year.tsv~.~fraction of stored vegetables grown.locally, dimensionless.

~time between storage of vegetables and their consumption, seconds.~fraction of;deposited., activity.retained: on, vegetables, dimensionless.

~the.effective decay.constant,.

due to radioactive decay and weathering, seconds, 1.,~'Ai+X.w.~decay'onstant for: removal.of'ctivity on.leaf and;plant surfaces by weathering,.

seconds, 1..~exposure-time in;garden, for-fresh leafy and/or stored vegetables, seconds.,>sv.Biv~vegetation areal density for.stored vegetables;, kg/m2.~.transfer.

factor for: nuclide;i from soil to vegetables, picocuries/kg (wet..weight.of" vegetati'on) per picocuries/kg (dry.soil)', tb,~time period, over which, accumul'ation on the.ground is;evaluated,, seconds..~-effective surface density of.soil,.kg/ln2.NOTE:.0383p Factors defined above which do,not reference a table for their numerical.

values,, are listed, in Table 1.9..

1.6.7 TRITIUM-PASTURE GRASS-CON/GOATMILK DOSE FACTOR-RCpT (mrem/year per microcuries/m3)

RETS Manual Revision 7 Page 67 RCPT~10 10 DFIvgao FmT Qf Uap[0.75(0.5/H)]

fp exP(-XTtfm) where: 103 106~conversion.

factor,.grams/kg-~conversion factor, picocuries/microcuries.

DFLTao FmT~ingestion dose conversion factor for tri,tium for age group a, organ o, mrem/picocurie (Table 1.7).~transfer factor for.tritium from animal's feed to~milk, days/liter (Table 1 8)-Uap 0.75-~animal.'s consumption rate, kg/day.~: milk ingestion rate for age group a,, liters/year.

~the fraction of total feed, that is water.0.5~the ratio of.the specific activity of the feed grass water to the atmospheric.

water~absolute humidity of.the.atmosphere,, g/m3..fp tfm,~fraction of time animal spends on pasture, dimensionless.

~decay constant'or tritium, seconds 1 (Table 1-.8)..~transport time from milking to receptor, seconds.NOTE:*Factors defined.above which-do not reference a table for their numerical values,.are listed in Table 1.9.0383p

RETS Manual Revision 7 Page 68 1.6.8 TRITIUM-STORED FEED-COW/GOAT-HILK DOSE FACTOR-RCTS (mrem/year per microcuries/m3)

./)I,~(-'I 3 6 (1-exP(-'ATtcsf

))Ttsf where: 103 106 D~ao~conversion factor, grams/kg.~conversion factor, picocuries/microcuries.

~ingestion dose conversion factor for tritium for age group a, organ o, mrna/picocurie (Table 1.7).~transfer factor for tritium from animal's.feed to milk, days/liter (Table 1.8).,~animal's consumption rate,'kg/day.

Uap~'s.tcsf,~milk ingestion rate for age group a, liters/year.

~P~the fraction.of total feed that is water.~the ratio of the*specific activity.of the feed grass water to the atmospheric water.~absolute humidity of the atmosphere, g/m3.~.fraction of time animal spends on stored feed, dimensionless.

~decay constant for.tritium, seconds 1 (Table 1.8).~time between harvest of stored feed and consumption by animal,, seconds.~transport time from mil'king to receptor,, seconds.NOTE." Factors defined above-which do not reference a: table for their numerical values, are.listed.in.Table 1.9 0383p

1~6.9 TRITIUM-PASTURE GRASS-BEEF DOSE FACTOR-RMTP (mrem/year per microcuries/m3)

RETS Manual Revision 7 Page 69 10 10 DFLTao FfT gf Uam[0.75(0 5/H)]fp exp(-XTts)

(1 (-X t))(1-ex (-X t))T tep T tcb where: 103 106 DFLTao~-conversion factor, grams/kg.~conversion factor, picocuries/microcuries.

A~~ingestion dose conversion factor for tritium for age group a, organ o,mrem/picocurie (Table 1.7)..FfT~transfer factor for tritium from cow's feed to meat, days/kg (Table 1.8).~cow's consumption rate,, kg/day.~meat ingestion rate for age group a, kg/year'.0 75~the fraction of total feed that is water.0.5'p ts tep tcb~the.ratio of the specific.activity of the feed grass water to the atmospheric water.~absolute humidity of the atmosphere, g/m3.~fraction of time-cow spends on-pasture, dimensionless.

~,decay constant for tritium,, seconds.1 (Table 1.8).~transport time from slaughter to consumer, seconds.~time pasture is exposed to deposition, seconds..~time for receptor to consume a whole.beef, seconds.NOTE:: Factors defined above.which do not reference a table for their numerica1; values, are-listed'n Table 1'.9 0383p RETS Manual Revision 7 Page 70 1 6 10 TRITIUM-STORED FEED-BEEF DOSE FACTOR-~S (mrem/year per microcuries/m3)

~S~10 10 DFLTao FfT Qf Uam[0.75(0.5/H)]

fs exp(->Tts)

(1 (-X t))(1 (-X t))T tep T tcb where: 10~conversion factor, grams/kg..

106 D~ao~conversion factor, picocuries/microcuries.

~ingestion dose conversion factor for tritium for age group a, organ o, mrem/picocurie (Table: 1.7).FfT~transfer factor for tritium from cow's feed to meat, days/kg (Table 1.8).Qf~cow's consumption rate, kg/day.Uam 0 75~meat ingestion rate for age group a, kg/year".~-the fraction of total feed.that, is water.0.5 tep tcb~the ratio of the specific activity of the feed grass water to the atmospheric water.~absolute Humidity of.the atmosphere, g/m3.~-fraction of time cow spends on stored feed, dimensionless.

~decay constant for.tritium, seconds (Table.1.8).~transport time from.slaughter to consumer, seconds..~time pasture is exposed to deposition, seconds.~time for receptor to consume a whole beef, seconds.NOTE: Factors defined above.which do not reference a table for their numerical values, are-listed in Table 1.9 0383p

1.F 11 TRITIUN-FRESH LEAFl VEGETABLES DOSE FACTOR-RVFT (mrem/year per microcuries/m3)

RETS Hanual'evision 7 Page 71 RVFT~10 10 DFLTao[Oo 75(0.5/H)]

UFLa fL exP(-'ATthc) whexe:.103.106~conversion factor, grams/kg.~conversion factor, picocuries/microcuries.

DFLTao 0.75~ingestion dose conversion factor for txitium for age.group a, organ o, mrem/picocurie (Table 1.7).,r~: the fraction of total.vegetation that is water;.0.5': the ratio of the specific, activity of the vegetables water to the atmospheric water.,~absolute humidity of the atmosphexe, g/m3.~consumption rate of fresh leafy vegetables by the receptor in age group a, kg/year.fL~fraction: of fresh leafy vegetables grown.locally,, dimensionless.

~decay constant for.tritium,.seconds 1 (Table 1.8).thc.~time between harvest of vegetables and their consumption and/or storage, seconds.NOTE:: Factors defined above which,do not reference; a table for.their-numerical values,, are listed in-Table 1.9..0383p

" t 1~6'2 TRITIUM-STORED VEGETABLES DOSE'ACTOR

-RVST (mrem/year, per microcuries/m3)

RETS Manual Revision 7 Page 72 I)I 3 6 (1-exP(XTtsv))T tsv where: 103 106~conversion factor, grams/kg.~conversion factor, picocuries/microcuries.

DFLTao~ingestion dose conversion factor for tritium for age group a, organ o, mrem/picocurie (Table 1.7)..0.75'.5~the fraction of total vegetation that is water.~the ratio of the specific activity of the vegetation water to the atmospheric water..~absolute humidity of the atmosphere, g/m3.~'consumption rate of., stored vegetables by the receptor in age group;a,.kg/yeari a fraction of stored'egetables grown locally, dimensionless.

~decay constant for tritium, seconds 1 (Table 1.8)..tsv~.time between harvest of stored vegetables and their consumption and/or storage, seconds.thc~.-time:between harvest: of vegetables and their: storage, seconds.NOTE'actors, defined above which do not, reference:

a table.for their numerical values, are listed in Table 1.9., i 3 I 0383p

RETS Manual Revision 7 Page 73 1.6 13 INHALATXON DOSE FACTORS-RZi (mrem/year per microcuries/m3)

Rli~DFAiao BRa 10 where: DFAiao~inhalation dose conversion.

factor for nuclide i, age group a and organ o,, mrem/picocurie (Table 1.10).BRa 106~breathing rate for age group a, m/year (Table 1.9).~conversion factor, picocurie/microcurie.

1.6 14 GROUND PLANE DOSE FACTORS-RGi (m2-mrem/year per microcuries/second)

RGi~DFGio 1/Xi 106 8760[1-exp(-Xitb)l where DFGio.106 8760~dose conversi'oa factor for standing.on contaminated ground for nuclide i and organ o (total body and skin), mrem/hr per picocurie/m2 (Table 1.11)..~decay constant.of.nuclide i,.seconds 1 (Table 1.8).~conversion factor,.picocurie/microcurie..

~conversion factor, hours/year..

~time period over which the ground accumulatioa is, evaluated,'seconds.(Table 1.9)., 0383p

RETS Manual Revision 7 Page 74 1.7 Dis ersion Methodolo Dispersion factors are calculated for radioactive effluent releases using hourly average meteorological data collected'nsite.

Meteorological data for ground level releases consist of windspeed and direction measurements at LOm and temperature measurements"of 10m and 4S m.Hourly average meteorological data for the ground level portion of a split level release consist of wind speeds and directions measured at the 10m level and temperature measurements at.10m.and 45m.The elevated portion of the split level release uses wind speeds and directions measured at the 46m level and temperature measurements at 45m and 90m.Raw meteorological data for the elevated releases consist of wtndspeed and.directions measured at 93m.Stability class D is assumed to persist during the entire period for elevated releases, except for the quarterly dose calculations

'described in Section 1.3 when all stability classes will be used to evaluate the elevated releases..

Meteorological data are expressed as a'joint-frequency distribution of wind speed, wind direction, and atmospheric stability for each release level (ground, split and elevated).

The joint-frequency'istributions which represent the historical meteorological data for the period January 1977 to December 1979 are given in Table 1.3.t The wind speed classes that are used are=as follows: Number I>I<0.3 0.13 6.0.3-0.6 0.7-'.5 1.6-2.4-2.5-3'3.4-S.S 5.6&.2 8 3<<10.9>10.9 0.45 1.10'.99 2.88~4.45 6.91', 9.59 10.95 The stability classes that will be used are the standard A through G classifications.

The stability classes 1-7 will correspond to A~1, B~2,~...G=7.

RETS'anual Revision 7 Page 75 A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used.The dispersion model considers plume depletion (using information from Figure 1.4), and building wake effects.Terrain effects on dispersion-are not considered except for reducing the effective height of, an elevated, release=by the terrain height.1.7.1 Air Concentration

-(pCi/m3)9'(2/~)x/fjk.Qi p exP(-'Xi x/uj)exP(-h/2ozk)j~l k~1 Zzk uj (2~/n)where fjk (1.14)~joint relative frequency of, occurrence of winds&windspeed class, j, stability class, k, blowing.toward.this exposure point, expressed as a fraction..

~average annual release rate of radionuclide i, pCi/s.Qi Air.concentrations.

of nuclides at downwind locations are calculated using the following equation: 'I P I~fraction of radionuclide remaining in plume (Figure 1.4).~vertical dispersion coefficient for stability class k which includes a building.wake.adjustment,~(<zq+cA/~)>/>~.l3'lk, whichever is smaller (for ground level releases).

where ezk is: the vertical.dispersion coefficient for stability class, k (m)(Figure 1.5), c is.a: building shape factor (c&.5), A is.the minimum building cross-sectional area (2400 m~).uj'm/n~midpoint.value: of wind speed class interval j, m/s.~downwind distance,, m.~number of sectors,.16.~radioactive decay.coefficient of.radionuclide i,, s~=sector width at point of.interest, m;he.~effective release height., m.The effective release height is calculated as described in.Section 1.7.4..0383p

RETS Manual Revision 7 Page 76 7 1k 1.Z'.uj-(2m/)~joint relative frequency of occurrence.

of winds in windspeed class j, stability class k, blowing toward this exposure point, expressed as, a, fraction.(1.15)where fjk I 1.7.2.Relative Concentration

-/(sec/m3)I Relative concentrations of nuclides at downwind locations are calculated using the following equation: 9 x/0 Ezk~vertical dispersion coefficient for stability class k which includes a.building'wake adjustment,~(e k.+cA/c)/or~Z3 ezk, whichever is smaller (for ground level releases).

where azk is the vertical dispersion coefficient for stability class k (m)(Figure.1.5), c is a: building, shape factor (c&.5), A~is the minimum, building cross-sectional area (2400 mz')..n~midpoint value of wind speed class interval j, m/s.~downwind distance>m~number of sectors,.16.2~/n~-sector width at point.of interest, m.he.~effective release height,m..The effective release height is calculated as.described, in.Section 1.7.4..1.7;3;Relative De osition-D/(m 2)Relative.deposition of nuclides.at downwind locations is calculated using the following equation: 9 7jk DR j~1.kA., (2~/n)(1.16)0383p

RETS Nanual.Revision 7 Page 77 where DR~joint relative.frequency of occurrence of.winds in windspeed class j and stability class k, blowing toward this exposure point, expressed as a fraction.~relative deposition rate, m 1 (from Figure 1.6).The.choice of figures is.governed by the effective release height calculation described in Section 1.7.4.A linear interpolation is used for-effluent release heights that fall in between the: given curves.~downwind distance, m.2'/n~number of sectors, 16~sector.width at point of interest, m.1.7.4 Effective Release Hei ht-he For effluents exhausted from release points that are higher than twice the height of adjacent structures (elevated releases)the.effective release height is determined by the following equation, consistent with Regulatory'uide 1;Ill.h~'hs+hpr.-ht-c where.c~downwash correction factor for low relative exit velocity, 3(1~5-Wo/u)d,, where Wo,~-the vertical plume exit velocity, m/s.u.~mean wind speed at the.height of the release, m/s..d'insi'de diameter of'he release point,, m.hpr~plume rise above the release point, m..hs~physical height.of'elease.

point, m.ht~maximum terrain height between release-point" and receptor location, m.03839

RETS Manual Revision 7 Page 78 For effluents released from points less than the.height of adjacent structures, a ground level release is assumed (he=0).For effluents released from points at the level of or above'adjacent structures, but lower than elevated release points, releases are treated as follows: Case 1-elevated if Wo/u>5.Case 2.-ground level (he~0)if Wo/u<l.Case 3-split level if 1<wo/u<5.Under Case 3 a split level dispersion approach is implemented using a model that requires for each release point two JFDs, one for elevated releases and one for ground level releases.The summation of the elevated and ground level JFDs account for the total period.of~ecord.Releases are considered to be elevated 100(l-Et)percent of the time and ground level 100 Et percent.of the time where the entrainment coefficient, Et, is, defined by Et~~2 58,-1 58(Wo/u)for 1<Wo/u<1 5 I Et.~0~3'0 06(Wo/u)for 1.5<Wo/u<5 0383p 5~~

2.0 Li uid Effluents RETS Manual'Revision 7 Page 79 2.1 Release Rate Limit Methodolo 2.1.1.RETS Re uirement Specification 3.8.A.1 of the Radiological Effluent Technical Specifications (RETS)requires that the concentration of radioactive material released at any time from the site to unrestricted areas (Figure 2.1)shall be limited to the Euchnum Permissible Concentration (MPC)specified in 10 CFR 20, Appendix B, Table II, Column 2 for nuclides other than dissolved or entrained noble gases.For dissolved or entrained noble gases, the concentration shall be limited to 2x10 4 pCi/ml total activity.To ensure compliance, the following approach will be used for each release.2.1.2 Prerelease Anal sis Prior to release, a grab sample will be analyzed to determine the concentration (Ci)of each gamma emitting radionuclide i in the radwaste tank.The following equation is used to calculate MPC fractions (Mi).where: Mi=-i-C MPCi (2.1)~MPC fraction of radionuclide i.~concentration of radionuclide i in the radwaste tank, pCi/ml.MPCi~MPC of radionuclide i as specified in Section 2.1.1, pCi/ml.0383p The sum of the ratios (R)will be calculated by the following relationship:.

RETS Manual Revision 7 Page 80 R~7 Mi where:.Mi~'he sum of the ratios.~MPC.fraction from equation 2.1., 2.1.3 Release Flow Rate Calculations There.is one liquid release point into the discharge canal by oae of, three possible.modes: Radwaste open.--3 pumps 8 200,000 gpm/pump helper-3 pumps 8 180,000 gpm/pump closed-50,000 gpm Dischaxge conduit t The sum of the ratios at the-diffuser pipes: must-be<1 due to.the releases from the above-soux'ce;.

The following relationship will assuxe this criterion is, met: f (R-1)<F where:.~the.effluent flow: rate (gallons/minute) before dilution;.

~.the sum.of.the.ratios as determined by Equation.2'.2.~minimum dilution.flow rate for prerelease analysis.The all'owabI'e:

release rate is calculated:

before each release and the release rate is continuously monitored, during.the release.so that the MPC'imit;is: not.exceeded..

0383p'

RETS Manual Revision 7 Page 81~~~~2.2 Instrument Set pints 2.2.1 Set oint Determination The setpoint for each liquid effluent monitor will be established'.

using.plant instructions'.

Concentration, flow rate, dilution, principal gamma emitter, geometry, and, detector efficiency are combined to give an equivalent setpoint in.counts per minute (cpm).The-locations and identification numbers for each liquid effluent.radiation detector are shown in figures 2.2'nd 2.3..The respective alarm/trip setpoints will be set such that Equation 2.3 is satisfied.

The methodology describing the setpoint determination is contained in Technical Instruction.

45.2.2.2 Poet-Release Anal sis.A post-release analysis will be done-using, actual release data to ensure that the limits specified in Section 2.1.1'were not exceeded.A composite list of'concentrations (Ci)by isotope, will be used, with actual,'liquid radwaste (f)and dilution (F)flow rates (or volumes)during the release.The data.will be substituted into Equations 2.1, 2.2 and 2;3 to demonstrate compliance with the limits ia Section 2.1.1.This data=and setpoints.

will be recorded in auditable records by plant personnel., 0383p I e RETS Hanual Revision 7 Page 82 2.3 Dose 2.3.1 RETS Re uirements Specification 3.8.A.3 of the.Radiological Effluent Technical Specifications (RETS)requixes that dose or dose commitment to an individual from radioactive material in liquid effluents released to unrestricted areas (Figure 2.1)from each.reactor shall be limited: a During any calendar quarter to c 1..5 mrem to the total body and to<5 mrem.to any organ, and.b During any calendar year to<3 mrem to the total body and to c 10 mrem to any organ.To ensuxe compliance, cumulative dose calculations will be performed at least once per month according to the following methodology.

0383p i

2.3 2.Monthl Anal sis RETS Manual Revision 7 Page 83 Principal radionuclides will be used to conservatively estimate the monthly contribution to the cumulative dose.If the projected dose calculated by this monthly method exceeds the monthly fraction of the annual limits in section 2.3.1, then the methodology in Section 2.3.3 will be implemented.

The: 20.nucli'des (listed below), based on operational source terms, contribute more than 95, percent of the total estimated dose to the total body and the most critical organ for both the water and fish ingestion pathways.The organs considered for both water ingestion and fish ingestion are the gastrointestinal.

tract (GIT), bone, thyroid, and liver.H-3 Na-24.Cr-51'n-54 Fe-55 Fe-59 Co-58'o-60 Zn-65 Sr-89'r-90 Zr/Nb-95 Mo/Tc-99m.

'Ag-110m Sb-124 I-131 I-133,>Cs-134 Cs-136 Cs-137 A'.conservative calculation of the monthly dose will be done.according to the following procedure.

First, the monthly operating report containing the release data will.be obtained and the activities reported (if any)for each of the above 20 radionuclides will be noted..This information will then be used in the following calculations.

0383p 2.3.2.1 Water In estion RETS Manual Revision 7 Page 84 The dose to an individual from ingestion of water is described by the following equation.20 101 2 Dgk~~$(D L)i>k rikmrem i~1 where: Dgk~dose for the jth organ and the kth age group from the 20'adionucl'ides, mrem.t~I l~~k 10~~0.95~the organ of interest (bone, GIT, thyroid, liver or total body).r~the age group being, considered, child or adult.~conversion factor, pCi/Ci.~conservative correction factor, considering only 20 radionuclides.

~DFLi>k~ingestion dose commitment factor for the i.th radionuclide for the jth organ for the kth age group, mrem/pCi (Table 1.7)~monthly.activity ingested of the ith radionuclide by the kth age group,.Ci.The activity ingested due to drinking, water, Iik, is described by: 10'i Uwa, (1/12)F'.(7.34 x 10io),.Ci where..10,s'conversion factor,, ml/L.~:activity released of ith radionuclide during the month, Ci.Uwa~maDarum individual water consumption rate corresponding to the kth age group (Table 1.9),, L/yr., 1'/12'~conversion factor, yr/month., 0383p'

RETS ManuaL Revision 7 Page 85~average river flow rate for the month (cubic feet per second)~.fraction of river flow available for dilution (0.30)7 34x1010~conversion from cubic feet per second to milliliters per month.Inserting:

this for Iik in equation 2;4,.the.dose equation for water ingestion then becomes: 20 3.98 x LORY Dgk~'Uwa DFLi>k Ai, mrem F'~1 2.3.2.2'ish In estion The dose to an individual from the consumption of fish is described by Equation 2.4.In this case the activity ingested of the ith radionuclide due to eating.fish (Iik)is described by 10~'i Bi Ufa (1/12)Iik~, Ci.Fd, (7.3~x 10~o)where:: (2.7)10,s'conversion factor,.g/kg.~activity released of the ith radionuclide during the month,.Ci Bi~bioaccumulation factor of ith radionuclide, pCi/g per;pCi/ml.(Table 2.2)Ufa:~amount of fish eaten yearly by the kth age group (Table 1.9), kg/yr..1/12~.conversion, factor,, yr/month..

~average river flow rate for the.month, cubic feet per second-~frac'tion of.river flow available for dilution, 0.30'.7;34xLOxo~conversion from cubic feet: per second'.to milliliters per.month.0383p

0 RETS Manual Revision 7 Page 86 Inserting this for Iig in equation 2.4, the dose equation for fish ingestion then..becomes.:

20 3.98 x 10s D)g$Ai Bi Ufa.DFLigg i~1 203'03 Recreation For the.recreation dose calculation, the total dose is estimated based on a calculation of the shoreline dose for Co-58, Co-60,.Cs-134,, and Cs-137.The shoreline:

dose due to these four nuclides is, expected to contribute over 95 percent of the total recreation dose.The total body and maximum organ dose to an individual via the shoreline recreation pathway are assumed to be equal., The recreation dose is described by the following equation: 4, Dr.~10 7[42+DFGi+~'.], mrem 0 95 i01.where:~P (2.9)Dr~recreation dose.from plan't releases, mrem.10>>'conversion factor, pCi/Ci.0 95~conservative correction factor for considering only, 4 radionuclides.

DFGi~dose commitment factor for.standing on contaminated ground for the ith radionuclide, mrem/hr per pCi/m~(Table 1.11).~concentration of: ith radionuclide in shoreline sediment,, Ci/m~,.as described by the following equation (based on equation A-5 in Regulatory Guide 1.109)..gi~10'6.94E-04~100+.RHLi~Ci~N[1-exp(-Xitb)]

where: 10'00~.conversion:

factor;, ml/L'transfer constant defined'n Regulatory'uide 1.109 equation A-4L.per ms-day.~radiological half-life of the ith radioisotope,.

minutes;(Table 1.8)'.~concentration of ith radionuclide.

in the Tennessee River,.Ci/ml.~Ai/(F~d o'.34 x 10)0383p RETS ManualRevision 7 Page 87 where: d 7 34 x 10xo tb~activity released of ith radionuclide during the month, Ci.~average river flow for the month, cubic feet per second.~fraction of river flow available for dilution, 0.30.~conversion from cubic feet per second to milliliters per month.,~shoreline width factor (Table 1.9).~decay constant.of the ith radionuclide, sec>(Table: 1.8).~buildup time in sediment, seconds (Table 1.9)42~assumed monthly exposure time for maximum individual,~500 h/year-'12 months/year.

The recreation dose.equation then.becomes: Dr~-(29.8 Al+1690 A2+539 A3+812 A4)1~,>Pl r.p where:.~~'h\\Al,.A2, A3, A4,,~the activities.

of Co-58, Co-60,Cs-134, and Cs-137,.respectively,.

Ci.2 3'.2'Monthl Summa To obtain the total monthly dose to the total body, sum the total body dose from water ingestion, the total body dose from fish ingestion, and the recreation dose.This value will be compared to the Technical Specification limit, for total body dose.To obtain the total monthly dose to the maximum organ, sum the maximum organ dose from water ingestion, the maximum organ dose from fish ingestion, and the recreation dose.This value will be compared to the Technical Specification limit for maximum organ dose.Calendar quarter doses are first estimated by summing the doses calculated for each month in that quarter;Calendar year doses are first estimated by summing the doses calculated for each month in.that year..However,.if the annual doses determined in this manner.exceed or approach the specification limits, doses.calculated for.previous quarters.with the methodology of, Section 2.3.2 will be used, instead of those-quarterly doses estimated by summing monthly-results..An, annual check will.be made to ensure that the monthly dose estimates account for at least;95-percent of the dose calculated by the method described in Section 2.3.3..If: less than 95 percent.of the dose has been estimated,, either a.new list if principal isotopes will, be prepared or a;new correction factor will.be used., The.latter option wi11 not be used.if.less than.90 percent of the total dose is predicted.

0383 p'

RETS Manual Revision 7 Page 882.3.3 uarterl Dose Calculations A complete dose analysis utilizing the total estimated liquid releases for each calendar quarter will be performed and reported as required.in Section F.2 of the REN.Methodology for this analysis is.that which is described in this section using the quarterly release values reported by the plant personnel..

The releases are assumed,=for this calculation;, to be continuous over the 90 day period.The average dilution factor, D,, used for the quarterly calculations is: RF*0.30 (for receptors upstream of Wheeler Dam)(2.13a)where: (for receptors'-:downstream of Wheeler Dam)(2.13b)RF~the average actual riverflow for the location at which the dose is being determined, cfs..0.30~the fraction of the riverflow'available for dilution in the near field, dimensionless.

2.3.3.1 Water Xn estion Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream, of BFN (Table 2.1).Mater ingestion doses are calculated for the total body and each.internal organ as described, below: Dorg,~10'+8E-09 AMit Qi D exp(8 64E+04'Ai td)where.(2.14)10'conversion.

factor,, pCi/Ci.9.8E-09>>~conversion.

factor,.cfs per ml/hour.~Dose factor for.water ingestion for nuclide i, age group t, mrem/hour per pCi/ml,, as calculated., in.Section 2.5.1.~guantity-of.nuclide i released during-the quarterCuries.~dilution factor,, as'escribed, above;.cfs~radiological decay constant of nuclide i, seconds (Table 1.8).0383p

td RETS Manual Revision 7 Page 89~decay time for water ingestion,.

equal to the travel time from the plant to the water supply plus one-half day (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)to account for the time of processing at the water supply (per Regulatory Guide 1.109), days., 8.64E+04=conversion factor, seconds per day.Fish ingestion doses are calculated fox each identified reach within a 50 mile radius downstream of BFM (Table 2.1)., Individual fish ingestion doses are calculated for.the total body and each internal organ as described below: Dorg~10 9.8E&9 0.25 AFit Qi D exP(&.64E+04 Xi td)~where 10~~conversion factor, pCi/Ci.9.8E-09 0.25~conversion factor, cfs pet ml/hour.~fraction of the yeaxly fish consumption eaten in one quarter, dimensionless.

AFit~Dose factor for-fish ingestion for nuclide.i,.age group t,.mrem/hour per pCi/ml, as calculated.

in Section 2.5.2.~Quantity of nuclide i.released during the quarter, Curies.~dilution factor, as described above, cfs~radiological decay constant of nuclide i, seconds (Table 1.8).td~decay time for fish ingestion,.

equal to the travel time from the plant to the center of the reach plus, one day to account for transit through the food chain and food preparation time (per Regulatory Guide 1.109),, days.8.64E+04~convexsion factor, seconds per day.2.3.3.3 Recreation Shoreline Recreation doses are calculated for each identified reach within, a 50 mile radius downstream of BFN (Table 2.1).It is assumed that the maximum exposed individual spends 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> per year;on the shoreline at, a location immediately downstream from the diffusers.

Individual 03&3p recreation shoreline doses described below: RETS Manual Revision 7 Page 90 are calculated for the total body and skin as Dorg~10 9 o 8E&9 rf ARit Qi D exp (M o 64E+04 Xi td)where (2.16)10'conversion factor, pCi/Ci..9.8E-09~conversion factor, cfs per ml/hour.~recreation factor, used to account for the fact that the same amount of time will not.be spent at a recreation site during each quarter.Recreation factors used are: 1st quarter-0.1 2nd quarter-0.3 3rd quarter-0.4-4th quarter-0.2.I~I L~ARit~Dose factor for shoreline recreation for nuclide.i,, age group t,.mrem/hour per@CD/ml, as calculated in Section 2.5.3.~:Quantity" of nuclide i released during.the quarter, Curies.~dilution factor,.as described.

above~.cfs~:radiological decay constant of nuclide i, seconds (Table 1.8).td~decay time for recreation, equal to.the travel time from the plant to the center.of the.reach, days.8'.64E+04~conversion factor,, seconds per day.2 3.3.4 Total Maximum Individual Dose The total.maximum individual total body dose is obtained.by summing the following, for each: age group:, the highest.total body'ater ingestion dose from;among all the public water.supplies;.

the highest total body fish ingestion dose from among all the reaches;and the.total body maximum shoreline recreation dose..The.total mmcirmun individual organ dose is obtained.by summing the following for each organ.and.each age group: that organ's.highest water ingestion.

dose: from among all, the" public water supplies;that organ's highest.fish ingestion dose from among all the reaches;and the total body.maximum shoreline recreation dose.The total maximum individual, skin dose.i'.that skin dose calculated.

for the maximum shoreline dose.

RETS Manual Revision 7 Page 91~~~2.3.3.5 Po ulation Doses I For determining population doses to the 50-mile population around the plant, an average dose is calculated for each age group and'ach pathway and then multiplied by the population.

For water ingestion, the general equation used for calculating the population doses, POPWTR,, in man-rem for a given PWS is:, 5 4 POPWTRt~10 g POPm g POPa>ATMWa*TWDOSamt m 1 a~1, where:, (2.17)POPWTRt~water ingestion population dose to organ t, man-rem..POPa~fraction of population in each age group a (from.~NUREG CR-1004table 3.39).Adult.~0.665 Child='.168 Infant~0.015 Teen~,0.153 POPm.~population at PNS m.The 3 PWSs and, their populations are listed in Table 2.1..ATMNa,~'ati'o of average to maximum.water ingestion rates for each age" group a.Maximum, water ingestion.

rates are given in Table 1-9-.Average water ingestion rates,, in Llyear, (from R.G'.109'able E-4)are: Adult~370 Child.~260 Infant~260 Teen~260.TWDOSamt~total individual water ingestion dose to organ t, at PWS m, to the age group a,, as described in Section 2.3.3.1, mrem.10>~conversion factor for rem/mrem.For.population doses:, resulting from.fish ingestion the calculation'ssumes; that all, fish caught within a.50-mile radius.downstream of BFN are consumed by'ocal population..

An additional.

7-'day decay term is added-due-to distribution time of sport fish..The general equation for calculating; population doses, POPF, in man-rem.from" fish ingestion of.all fish.caught within a~.50-mil'e..

radius, downstream is:.453 6VST APR., TFDOSart*'OPa 4.3, POPFt 10'10'FISH,+POP r~l.a~1 a (2.18)0383p

RETS Nanual Revision 7 Page.92 where: 7 POPFt HVST APR TFDOSart=total fish ingestion population dose to organ t, man-rem.~fish harvest for the Tennessee River, 8.32 lbs/acre/year.

~.size of reach, acres (Table 2.1).~total fish ingestion dose to organ t for reach r, for the age group a, as described in Section 2.3.3.2,.mrem.a POPa FISHa 453.6 10s 10s~fraction of population in each age group a, as given above.~amount of fish ingested by each age group a, kg/year.The average fish ingestion rates (R.G.1.109 Table E-4)are: Adult~6.9 Child~2.2 r Teen i 5 2~conversion factor, g/lb.~conversion factor, mrem/rem'.

~conversion factor, g/kg.(2.19)For recreation-shoreline, the general equation used for calculating the population doses, POPE, in man-rem is REQFRA POPRt TSHDOSrt SHVISr HRSVISr 10s'8760 where: POPRt~total recreation population dose for all reaches to organ t, man-rem..~fraction of.yearly recreation which occurs in that quarter, as given in Section, 2.3.3.3.TSHDOSrt=total shoreline dose.rate for organ t, in reach r, mrem/h.SHVISr~shoreline visits-per year at each reach-r, (Table 2.1).HRSVIS~~length;of shoreline recreation visit at reach r, 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.8760~: conversion factor, mrem/rem..

~conversion:

factor;, hours/year."'383p RETS Manual Revision 7 Page 93 2.4 0 erabilit of Li uid Radwaste E ui ment The Radiological Effluent Manual (REM)requires that.the liquid radwaste system (Figure 2.3)shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected dose due to liquid effluent releases*to unrestricted areas (see Figure 2.1)when averaged over 31 days would exceed 0.06 mrem to the total'body or 0.21 mrem to any organ.Doses wil'1 be projected monthly.Dose projections will be done by averaging the calculated dose for the most recent month and the calculated dose for the previous month and assigning that average dose as the projection for the current month.2.5 Li uid Dose Factor E uations 2.5.1 WATER INGESTION DOSE FACTORS-AWit (mrem/hr per pCi/m)1.r DFI,iat Uwa 10 10~8760'here:

DFLiat, Uwa 108760~ingestion dose conversion factor for nuclide i,.age group a,.organ t, mrem/pCi, (Table,l.7).

~water consumption rate for age group a,, L/year,, (Table 1.9).~.conversion factor, pCi/pCi.~conversion factor, ml/L.~conversion.

factor, hours per year..2.5.2 FISH, INGESTION DOSE FACTORS'.-AFit.(mrem/hr per.pCi/ml)DFLiat Ufa Bi 10 10 AFit~8760 where: DFLiat Ufa Bi~ingestion dose conversion factor, for nuclide.i,.age group a, organ.t,, mrem/pCi,, (Table 1..7)..~fish.consumption rate for age group, a,, kg/year(Table 1.9).~bioaccumulation factor-for nuclide i,.pCi/kg per.pCi/L',, (Table 2;2).*Per operating reactor unit.0383p

~conversion factor, pCi/pCi.~conversion factor, ml/L.RETS Manual Revision 7 Page 94 8760~conversion factor, hours per year.2 5.3 SHORELINE RECREATION DOSE FACTOR-ARit (mrem/hr per pCi/ml).where: DFGit Kc: M W 103 10~U[1~~(-Xi tb)]8760~3600 Xi DFGit~dose conversion factor for standing on contaminated ground for nuclide i and organ t (total body and skin), mrem/hr per pCi/m~, (Table 1.11).~transfer coefficient from water to shoreline sediment, L/kg-hi, (Table 1.9).103~-3600~mass density of sediment, kg/m~, (Table 1.9).~shoreline width factor, dimensionless, (Table 1.9).~conversion factor, ml/L.~.conversion factor, pCi/pCi.~conversion factor, seconds/hour.

~decay constant for nuclide i, seconds~, (Table 1.8).tb~time shoreline is exposed to the concentration in the water, seconds, (Table 1.9).8760~: usage factor, 500 hour0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />s/year.

~conversion factor,.hours!year..

3.0 Radiolo ical Environmental Monitorin 3.1 Monitorin Pro ram An environmental radiological monitoring, program as described in Tables 3.1 ancE 3.2 and in Figures 3.1, 3.2, 3.3, and 3.4 shall be-conducted-Results of this program shall he reported in accordance with Section F-1 of the REM.The atmosphexic environmental xadiologica1 monitoring program shall consist of 10 monitoring stations from which samples of air particulates and radioiodine shall be collected.

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RETS Manual ,Revision 7 Page 95 The terrestrial monitoring program shall consist of the collection os milk, soil,.drinking water, and food crops.In addition,, direct gamma radiation levels will be measured at 40 or more-locations in the vicinity of the plant.The reservoir sampling program shall consist of the collection of samples of surface water, sediment, and fish.Deviations are.permitted from the required sampling schedule if specimens are unobtainable=

due to hazardous conditions, sample unavailability, or malfunction of sampLing equipment.

If the latter, every effort shall be made to complete corrective action prior to the end.of the next sampling, period.3.2 Detection Ca abilities Analytical techniques shall be such that the detection capabPities listed in Table 3'.3 are achieved.3.3 Nonroutine Re orts Nonroutine reports shall, be submitted, pursuant to Section F-3 of the REM.4.0 Annual Maximum Individual Doses-Total To determine compliance with 40 CFR 190, the.annual dose contributions to the;maximum individuil from BFN radioactive effluents and all other nearby uranium fuel cycle, sources will be considered..

The annual dose to the amximum individual wilL be conservatively estimated by: first, summing the total body air submersion dose, and the critical organ dose (except thyroid)from gaseous effluents; the total body dose, and dritical organ dose (except thyroid)from liquid effluents for.each quarter calculated in accordance with sections 1.3 and 2.3.3.Then to this sum.for each quarter is added any identifiable increase in direct radiation.

dose.levels.attributable to the plant as determined by the, environmental monitoring program outlined in section 3.0.These quarterly sums are:then conservatively summed for the four calendar quarters, to estimate the maximum individual dose for the year.This dose is compared to, the limit.of Technical Specification 4.8.C, i.e., 25 mrem per.year to the-totaL body or any.organ.(except thyroid), to determine compliance.

The total-annual'hyroid dose to the: maximum individual will be.conservatively estimated in.the following, manner;For, each calendar quarter, a totaL',dose.

will be obtained.by summing, the-total body gaseous submersion, dosethe gaseous thyroid dose, the liquid.total body dose, and the liquid thyroid dose.To this sum for each quarter i.s, added any identifi'able increase in.direct radiation dose levels attributable to the E 0383p

0 RETS Manual Revision 7 Page 96 plant as'determined by the environmental monitoring program outlined in section 3.0.These quarterly sums are then added together to estimate the maximum individual thyroid dose for the year.This dose is compared to the limit of Technical Specification 4.8.C, i.e., 75 mrem per year to determine compliance.

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Table 1.1 BFN-OFFSITE RECEPTOR LOCATION DATA RETS Manual Revision 7 Page 97 GROUND LEVEL ELEVATED DISTANCE Elev above X/Q D/Q X/Q D/Q POINT from plant plant grade (s/m~)(1/m>)(s/ms)(1/m2)m m Site.Boundary Site." Boundary Site Boundary Site Boundary Site Boundary Site.Boundary'ite Boundary Site.Boundary'ite Boundary Site Boundary Site Boundary Site.Boundary Site Boundary Site Boundary Site Boundary Site.Boundary Air.Dose Point Garden Garden-Milk.Cow.Milk'-Cow 1525 1300 1250 1450 1375'575 5600 2875 2550 2425 2300 2500 2550 3325 2275 1650 6100 4437 1830 8045 10975'7 NNE 4 NE 7 ENE 0 E 0 ESE 0 SE SSE S-6 SSW SW WSW-6 M'-6 MNW-6 NW-6 NNW-6 E 19 NNW.N: NNW~1.60EW6 7.88E-07 4.52EW7 7.30E-07'.24E-07 4.56E-07 7.61E-OS 4.86E-07'.

27E&7 1.08EM6 6.87E-07 6 38E-07 6.70E-07 3.69E-07'.69E&6 1.84E-06 N/A N/A.1.57E&6 1.47E&7'/A 5.64E-09 1.97E-09 1.56E-09 2.92E&9 4.04E-09 3.28E-09 3.63E-10 1.77E-09 2.24E-09 2.92E-09~'.75E-09 1.14E-09 1.25E-09 9.07E-10 4.92E&9 5.29E-09 N/A N/A 4.46E-09 3.16E-10 N/A-N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N!A N/A N/A N/A 2.08E-08 9'0E-09 N/A N/A 1..69E>>OS N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4.75E-10 N/A 1.13E-09 N/A N/A NOTE: For quarterly dose calculations, doses will also be calculated for all locations identified in the most recent land use census, and for any additional points deemed necessary.

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RETS Manual Revision 7 Page 98 Table 1.2 OUTINE ATMOSPHERIC, RELEASES Vents Ci/r/Unit)EXPECTED ANNUAL R FROM ONE UNIT AT BFN Ci/r/Unit Buildin Reactor Complex Stack Turbine Building Vent 2E+0 9.5E+1 1.02K+2 5.03E+2 OE+0 5 81E+2 4.64E+2 6.72E+2 3.86E+2, 1 18E+3 1.56E-2 1.79E-1 1.23E-1 2.67E-2 1.23E-1 6.5E-3: 7.44E-2 5'.13E-2 1.11E-2 5'3E-2 lE-3 2E-3 9E-5 4E-4 3E-3 4E-4 9E-6 8E-6 2E-4 6E-5 5E-4 1E-4 2E-3'E-2'E-'3

• s OE+0 OE+0 OE+0 Radvaste Building Vent 1 1 1 3.4E+1 6.0E+1 2.94E+2 6.67K+2'.28E+2 1.13E+2 2E+0 5.0E-3 5.0E-2 2.5E-2 1.25E-l 5.0E-2 2.9E-2 2.9E-1 1.45E-l.7.25E-l 2.90E-1 9EW 5E-3'E-4 SEW 6E-3 2EW 3E-1 4E-3 2E-4 1EW.1EM 3E-4 3EM 5E-5 4E-4 5E-4 2E-4*'E+0 OE+0 9.5E+0 Gland Seal and~Off as~Zsoto e Kr-85m Kr-85 Kr-87 Kr-8&" Kr-89" Xe-1.31m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 I-131 I I-1.32 I ,I-133 I I-134 I I-135 I'-131 0 I-132 0 I-'133 0 1-134: 0 I-135'Cr-51 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Sr-89 Sr-90 Nb-95 Zr-95, Ru-103 Ag-110m Sb-124.Cs-134 Cs-136 Cs-137'a-140 Vent 6K+0 6E+0 9E+0 1E+0 OE+0 1.03E+2 1.11E+2 1.73E+2 7.8E+1 1.2E+1.5.94E-2 5.94E-1 2.97E-1 1.49E+0 5.94E-1 3 16E-2: 3.1.6E-l 1 58E-1 7.90E-1 3.1'6E-l 3E-3 3E-'3 2E-3 1E-4 3E-2 3E-'3 1E-2 2E-3 3E-4 1E-4 3E-5 7E-6 3E-5-5E-3'E-3 7E-'3 4E-3 4EM 5E-6 2.5E+1 OE+0 OE+0 lable.1.66E+4 6.3E+2 7.47E+2 1.35E+4 4.10E+3 3.09E+2 8.51E+2 9.47E+4 9.17K+2 5.99K+2 5.04E+3 3.15E+3 4.1E-3 4.69E-2 3.23E-2 7.0E-3 3.23E-2 3.32E-2 3.80E-1 2.62E-1 5.68E-2 2.61E-1.1E-4 4E-5 2E-5 2EM 1E-5 9E-5 SE-5 SE-5 lE-4 8E-'5 2E-5 9EM 7E-4 SE-3.2E-5 4E-6 OE+0 9.5E+0 OE+0 Ce-14L Ce-144.Ar-41 C-14*'ot avai I denotes organ nonorganic iodine (elemental, particu1.ate, HIO), 0 denotes ic iodine.0383p MVP O.OE+0 O.OE+0 O.OK+0 O.OE+0 O.OE+0 O.OE+0 3 OE+2 O.OE+0 2.0E+2 O.OE+0 O.OE+0 8.5E-3'9.73E-2 6.?1E-2.1.45E-2 6.71E-2 2.74E-1 3.14E+0 2.16E+0 4.69E-1 2.16E+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OE+0 O.OK+0 O B OE+0 O.OE+0 0 AL OE+0 0.0E+0 O B OE+0 Q.OE+0 O.OE+0 O.OE+0 0 OE+0 O.OE+0 O.OK+0 O.OE+0 O.OE+0 O.OE+0 0

TABLE 1.3 (Sheet)of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS A (DELTA-T<-1.9'C/100 H)BROWNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Hanual Revision 7 Page 99 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.6-1.4 0.0 0.0 a.o 0.0 0.0 0.0 0.0 0.0 0.0 a.o 0.0 O.Q 0.0 0.0 0.0 0.0 1.5-3.4 0.0 0.0 0.0 0.0 0.0 0.0'1 0.03 0,04 0.01 0.0 0.0 o.a 0.0 0.0 0.0 0.0 HIND S 3.5-5.4 5.5-7.4 0.04 0.05 0.04 0.01 O.Q 0.17 0.40 0.10 0.11 0.05 0.04 0.07 0.05 0.03 0.02 0.01 0.0 0.0 0.0 0.0 0.0 O.l)1.11 0.52 0.3B 0.04 o.as o.a4 0.01 0.02 0.0 Q.ot PEED (HPH)7.5-12.4 0.12 0.19 0.06 0.0 0.01 0.02 0.02 0.02 0.04 0.01 o.a 0.04 0.05 0.09 0.17 0.06 0.05 0.10 0.0 O.O 0.0 Q.O 0.0 0.0 0,0 0.0 0.0 0.0 0.01 0.06 0.11 0.09 0.0 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.0 0.0 a.o 0.0 0.0 0.0 0.02 12.5-1B.4 1B.5-24.4>~24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 a.o 0.0 0.0 TOTAL 0.21 0.34 0.10 0.01 0.01 0.31 1.56 0.6B 0.54 0.10 0.09 0.15 0.12 0.20 0.30 0.19 SUBTOTAL 0.0 0.09 2.29 1.19 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS OF VALID HIND DIRECTION-WINO SPEED-STABILI'P CLASS A TOTAL HOURS CALH 0.90 ALL COLUMNS AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 0.42 25935 1262 1259 0 0.02 0.0 4.91 HETEOROLOGICAL FACILITY: LOCATED ABOUT 1.3 KH SH OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASUREO BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL HEAN HIND SPEED 6.8 HPH 03B4p

TABLE 1,3 (Sheet 2 ot 22)RETS Manual Revlslon 7 Page 100 HIND DIRECTION NN NNE NE ENE E ESE SE SSE S SSH SH HSH H.HNH NH NNH 0.6-1.4 0.0 0.0 0.0 0.0 0.0 Q.Q O.Q 0.0 0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.0 Q.Q4 0.05 0.01 0.0 0.0 0.0 0.0 0.0 O.D 0.0 0.0 0.01 0.03 0.08 0.13 0.12 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.04.O.Q1 0.0 30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR sTQBILITY cLAss B (-1.9<DELTA-T<-1.7'c/100 M)BROHNS FERRY NUCLEAR PLANT 3AN 1, 77-DEC 31, 79 HIND SPEED (MPH)1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4 12.5-1B.4 18.5-24.4 0.0 0.05 0.09 0.30 0.0 0.05 0.07 0.27 0.0 0.04 Q.Q2 0.09 0.01 0.01 0.01 0.01 O.Q 0.02 0.01 0.0 o.a2 o.lo o.o4 o.o 0.13 0.64 0.09 Q.Q2 0.09 0.31 0.02 0.01 0.05 0.42 0.07 0.02 0.02 0.07 0.01 0.0 0.0 0.17 0.02 0.0 0.0 0.11 0.13 0.05 0.02 0.04 0.17 0.17 0.0 0.07 0.11 0.23 0.0 0.0'I 0.07 0.27 0.0 0.0 0.07 0.19)24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 ,o.a 0.0 TOTAL 0.49 0.44 0.16 0.04 0.03 0.16 Q.BB 0.43 0.56 0.10 0.19 0.30 Q.43 0.53 0.49 0.3B SUBTOTAL 0.0 0.34 2.11 1.00 1.63 0.47 0.06 o.a 5.61 TOTAL HOURS TOTAL AMOURS TOTAL HOURS TOTAL HOURS OF VALID STABILITY OBSERVATIONS OF STABILITY CLASS B OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS B CALM 25935 1445 1440 0 ALL coLUMNs AND cALM TQTAI 100 pERcENT 0F 30INT vALID 0BsERvATIGNs METEOROLOGICAL FACILITY;METEOROLOGICAL FACILITY LOCATED 1.3 KM ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 METERS'IND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL.MEAN HIND SPEED~7.2 MPH 6 TABLE 1.3 (Sheet 3 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS C (-1.7<DELTA-T<-1.5'C/loo M)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS ManUal Revision 7 Page 101.HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.6-1.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o'.0 0.0 0.0 0.0 O.O 0.0 0.0 1.5-3.4 0.01 0.0)0.0 0.0 O.O 0.01 0.17 0.12 O.ll 0.03 0.03 0.0 0.0 0.01 020 O.'0 3.5-5.4 0.08 0.07 0,03 0.02 0.03 0.05 0.29 0.17 0.25 0.06 0.12 O.1 1 0.05 0.12 0.05 0.02 HIND SPEED (MPH)5.5-7.4 7.5-12.4 0.11 0.21 0.09 0.17 0.08 0.05 0.02 0.0 0.02 0.0 0.02 0.0 0.09 0.01 0.04 0.01 0.04 0.02 0.01 0.0 0.03 0.01 0.07 0.07 0.12 0.10 0.13 0.17 0.09 0.22 0.08 0.18 0.02 0.20 0.0.0.0 0.0 0.0 0.0 0.0 O.D 0.0 0.0 0.0 0.02 0.07 0.10 0.10 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.04 0.01 0.0 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.43 0,36 0.16 0.04 0.05 0.08 0.56 0.34 0.42 0.10 0.19 0.25 0.30 0.54 0.47 0.38 SUBTOTAL 0.0 0.50 1.52 1.04 1.22.0.33 0.06 0.0 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 25935 TOTAL HOURS OF STASIS.lTY CLASS C 1202 TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS C 1197 TOTAL HOURS CALM 0 ALL COLUMNS AND CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KM ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.03 AND 45.30 METERS HIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL MEAN WIND SPEED 7.0 MPH 0384p 4.67 TABLE 1.3 (Sheet g of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS D (-1.5<DELTA-T<-0.5'C/100 H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 RETS Hanual Revlslon 7 Page 102.HIND DIRECTION N NNE.NE ENE E ESE SE SSE S SSH SH HSH H-HNH NH NNH 0.6-1.4 0.0 0.01 0.01 0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.5-3.4 0.19 0.20 0.12 0.26.0.20 0.24 1.16 0.99 0.92 0.45 0.24 0.32 0.18 0.13 0.04 0.13 3.5-5.4 0.41 0.56 0.38 0.23 0.31 0.51 1.31 0.99 1.17 0.29 0.29 0.70 0.55 0.39 0.28 0.40 HIND SPEED (HPH)5.5-7.4 7.5-12.4 0.53 1.00 0.58 1.18 0.43.0.52 0.15 0.05 0.17 0.05 0.30 0.08 0.83 0.26 0.26 0.11 0.34 0.17 0.0&0.04 0.09 0.02 0.29 0.33 0.62 0.63 0.42 1.10 0.3&1.01.0.55 1.54 0.37 0.18 0.01 0.01 0.0 0.0 0.0 0.02 OA 0.0 0.01 0.11 0.22 0.82 0.&7 0.74 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.03 0.22 0.14 0.05 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.02 Q.Q TOTAL 2.51 2.72 1.47 0.'70 0'3 1.13 3.58 2.38 2.60 0.86 0.65 1.75 2.23 3.09 2.74 3.41 SUBTOTAL 0.05 5.77 8.77 6.02 8.09 3.36 0.46 0.03 32.55 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS 0 TOTAL HOURS OF VALID PIND DIRECTION-HIND SPEED-STABILITY CLASS TOTAL HOURS CALH 25935 843&0 8341 1 ALL COLUMNS AND CALH TOTAL 100 PERCENT OF JOINT VALID.OBSERVATIONS HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATEO 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLAN/STABILITY BASED ON LAPSE RATE HEASURED BETHEEN 10.03 AND 45.30 HETERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL HEAN HIND SPEED=7,1 HPH 03&4p TABLE 1.3 (Sheet 5 of 22)30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS E (-0.5<DELTA-T<1.5 C/100 H>BROHNS FERRY NUCLEAR PLANT 3AN 1, 77-OEC.31, 79 RETS Manual Revision 7 Page 103 HIND OI RECTION N NNE-NE ENE E ESE SE SSE S SSH SH H HNH NH NNH 0.6-1.4 0.04 0.05 0.05 0.05 0.04 0.03 0.11 0.07 0.05 0.02 0.04 0.01 0.02 0.03 0.02 0.05 1.5-3.4 0.47 0.61 0.57 0.71 0.61'.76 2.04 1.16 1.03 0.52 0.30 0.53 0.37 0.15 0.17 0.41 3.5-5.4 0.54 0.7$0.63 0.45 0.74 1.01 1.75 0.78 0,74 0.14 0.07.0.60 0.77 0.13 0.20 0.48 HIND SPE 5.5-7.4 0.43 0.55 0.42 0.17 0.16 0.53 0.92 0.48 0.44 0.08 0.02 0.14 0.42 0.11 0.14 0.54 FO (MPH)7.5-12.4 0.4)0.4)0.27 0.08 0.07 0.16 0.55 0.33 0.63 0.06 0.03 0-'l l 0.27 0;22 0,'25 0.59 Q.05 0.04 0.02 0.02 0.0 0.01 0.02 0.04 0.14 0.01 0.0 0.04 0.04 0.09 0.09 0.09 0.01 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.02 0.02 0.01 12.5-18.4 18.5-24.4)~24.5 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.95 2.46 1.96 1.48 1.62 2.50 5.39 2.86 3.04 0..83 0.46 1.43 1.89 0.75 0.89 2.17 SUB',ii 0.68 10.41 9.7)5.55 4.50~0.70 C 0.07 0.0 31.68 TOTAL HOURS OF VALID STABILITY OBSERVATIONS 25935 TOTAL HOURS OF STABILITY CLASS E 8264 TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS E 8098 TOTAL HOURS CALM 3 ALL COLUMNS AND CALM TOTAL 100 PERCENT OF 30INT VALID OBSERVATIONS METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATEO'l.3 KH ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 METERS HIND SPEED AWO DIRECTION MEASURED AT THE 10.42 METER LEVEL.MEAN HIND SPEED 5.0 MPH 0384p

TABLE 1.3 (Sheet 6 of P2)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS F (1.5 (DELTA-T<4.0'C/10Q H)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 RETS Hanual Revt,sion 7 Page 104 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.6-1.4 0.05 0.05.0.07 0.03 0.01 0.0 0.09 0.05 0.03 0.03 0.0 0.0 0.02 0.01 0.01 0.05 1.5-3.4 0.36 Q.51 0.34 0.53 0.59 0.52 0.97 0.54 0.29 0.13 0.09 0.09 0.09 0.08 0.08 0.27 3.5-5.4 0.52 0.66 0.27 0.33 0.52 0.22 0.4&0.34 0.18'.03 0.03 0.07 0.06 0.01 0.04 0.27 HIND SPEED (HPH)5.5-7.4 7.5-12.4 0.28 Q.06 0.34 0.11 0.18 0.01 0.05 0.0 0.03 0.0 0.0 0.0 0.17 0.13 0.17 0.25 0.20.0.27 0.0 0.01~0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.16 0.05 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.02 0.01 0.0-0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.27 1.67 0.87 0.94 1.15 0.74 1.85 1.38 0.9&0.20 0.12 0.16 0.18 0.1Q 0.14 Q,SO SUBTOTAL 0.50 5.48 4.03'1.59 0.90 0.04 , 0.01 0.0 12.55 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS F TOTAL HOURS CALH 25935 3268 3223 2 ALL COLUMNS AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATEO 1.3 KH ESE OF BRONNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE HEASUREO BETHEEN 10.03 AND 45.30 HETERS HIND SPEED ANO DIRECTION HEASURED AT THE 10.42 HETER LEVEL HEAN HIND SPEED 4.0 HPH'0384p TABLE 1.3 (Sheet 7 of 22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR RETS Manual Revlslon 7 Page 105 HIND DIRECTION tl NNE NE EtlE E ESE SE SSE S SSH SH HSH H, HNH NH NtN 0.6-1.4 Q.07 0.05 0.04 0.04 0.02 0.01 a.o&0.03 0.05 0.05 0.0 0.02 0.01 0.01 0.04 0.05 1.5-3.4 0.76 0.83 0.3$0.48 0.52 0.18 0.43 0.44 0.09 0.05 0.01 0.02.0.01 0.02 0.04 0.23 STABILITY CLASS G (DELTA-T>BROHNS FERRY NUCL)AR JAN 1, 77-DEC'.,31, I HIND SPEED (HPH)3.5-5.4 5.5-7.4 7.5-12.4 0.32 0.02 0.0 0.51 0.1&0.02~0.12 0.02 Q.Q 0.18 0.02 0.0 0.34 0.0 0.0 0.01 0.0 0.0 0.09 0.04 0.03 0.31 0.16 0.08 0.12 0.10 0.04 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o o o o'a o o 0.12 0.03 0.0 4.0'C/100 H)PLANT 79 0.0 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0..0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0,0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12.5-18.4 18.5-24.4>24.5 O.O 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.17 1.59 0.52 0.72 0.88 0.20 Q.67 1.02 0.40 0.11 0.01 0.04 0.02 0.03~0.08 0.43 SUBTOTAL 0.57 4.45 2.13 Q.57 0.17 0.0 0.0 0.0 7.89 TOTAL HOURS OF VALID STABILITY OBSERVATIONS TOTAL HOURS OF STABILITY CLASS G TOTAL HOURS OF VALID HIND DIRECTION-HIND SPEED-STABILITY CLASS G TOTAL HOURS CALM 25935 2056 2019 4 ALL COLUMNS AND CALM TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS HETEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATEO 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON LAPSE RATE MEASURED BETHEEN 10.03 AND 45.30 METERS HIND SPEED AND DIRECTION HEASUREO AT THE 10.42 HETER LEVEL HEAN HIND SPEED 3.2 HPH 03&4p TABLE).3I (Sheet 8 of f2)JOINT PERCENTAGf FRE ENCIES OF HIND SPEED BY HIND DIRECTION DISREGARDING STABILITY CLASS BROHNS FfRRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Hanual Revision 7 Page 106 HIND DIRE CT ION NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH 0.6-1.4 0.02 0.0 0.0 0.02 0.0 0.01 0.02 0.01 0.02 0.0 0.02 0.01 0.02 0.01 0.02 0.01 1.5-3.4 0.19 0.13 0.12 0.14 0.22 0.23 0.36 0.38 0.40 0.31 0.$8 0.26 0.20 0.17 0.19 0.22 3.5-5.4 0.38 0.33 0.35 0.32 0.47 0.53 1.26 1.20 0.90 0.65 0.66 0.69 0.66 0.46 0.49 0.28 HIND SPEED 5.5-7.4 7 0.64 0.60 0.64 0.36 0.45 0.66 1.36 1.22 1.05 0.69 0.69 0.68 0.81 0.69 0.70 0.$1 (HPH).5-12.4 2.07 2.46 2.16 1.15 0.99 1.79 3.25 2.97 2.53 1.73 1.55 1.15 1.76 2.03 1.80 1.66 2.47 2.69 1.85 0.95 0.43 1.63 3.20 2.59 2.40 1.77 1.62'I.05 1.04 1.54 2.01 2.13 0.61 0.50 0.58 0.34 0.08 0.42 1.54 1.16 1.03 0.73 0.50 0.36 0.42 0.76 0.96 0.70 12.5-18.4 18.5-24.4>24.5 0.06 0.04 0.02 0.04 0.01 0.09 0.69 0.59 0.43 0.19 0.14 0.17 0.35 0.30 0.28 0.13 TOTAL 6.44.6.75 5.72 3.32 2.65 5.36 11.68 10.12 8.76 6.07 5.56 4.37 5.26 5.96 6.45 5.54 SUBTOTAL 0.19 3.90 9.63 11.65 31.05 29.37 10.69 3.53 100.01 TOTAL HOURS OF VALID QIND OBSERVATIONS TOTAL HOURS OF OBSERVATIONS RECOVfRABILITY PERCENTAGE TOTAL llOURS CALll ALL COLUMNS AND CALH TOTAL 100 PERCENT OF JOINT VALID OBSERVATIONS 25784 26280 98.1 2 METEOROLOGICAL fACILITY:METEOROLOGICAL FACILITY LOCATfD 1.3 KH ESE Of BROHNS FERRY NUCLEAR PLANT HlltD SPfED AND DIRECTION HEASURfD AT THE 92.63 HETER LEVEL MEAN HIND SPEED=12.0 HPH

~~TABLE).3 (Sheet 9 of 22)I JOINT PERCENTAGE FRE UENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS A (DELTA-T(-1.9'CllQQ N)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE JAN 1, 77-DEC 31, 79 RETS Hapual Revision 7 Page 107 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH WSH.H HNH NH NNH CALM 0.0 0.0 0.0'0.0 0,0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.0 Q,Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.0 Q.O 0.0 0.0 0.0 0.6-1.4 1.5-3.4 HIND SPEED (MPH)3.5-5.4 5.5-7.4 7.5-12.4 1 0.0 0.0 0.02 O.Q Q.Q 0.01 0.0 0.0 0.01, 0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.02 0.0 0.05 0.04 0.01.0.03 0.02 0.01 0.02 0.02 0.01 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.01 0;Ol Q.Q O.Q.-0.01 0.0 0.0 O.Q1 0.0 0.0 0.02 0.0 0.0 0,01 0.01 0.02',Q.0.0 0.0-0.0 0.0 04 0.0 0.0 0.0 O'.O 0.0 0.01 0.02'0.02 0.0 0.0 0.0 O.O 0,0 0.0 0.0 0.0 0.0 0:0 0.0 0.0 0.0 0.0 0.0 0.02 2.5-18.4.18.5-24.4

>24.5 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0.0.0 0.0 0.0 0.0 0.0 0.0 O.Q TOTAL 0.03 0.05 0.01 0.0 0.0 0.02 0.10 0.06 0.05 0.01 0.0 0.02 0.01 0.02 0.04 Q.OS SUBTOTAL 0.0 0.0 0.0 0.10 0.12 0.15 0.08 0.02 0.0 0.47.TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABII ITY CLASS A TOTAL HOURS OF GROUND LEVEL STABILITY CLASS A 25482.0 2832.4 133.1 127.5 HETEOROLOGICAL FACILITY: HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 METERS HIND DIRECTION HEASURED AT 10.42 HETER LEVEL HIND SPEED HEASURED AT 10.42 HETER LEVEL ,EFFLUENT VELOCITY=12.60 H/S I~0384p

RETS Hanual Revision 7 Page 108 TABLE 1,3 (Sheet 10 of 22)SPLIT 30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY WIND DIRECTION FOR HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSR H HNH NH NNH CALH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.6-1.4 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 STABILITY CLASS B (-1.9<Delta T<-1.7'-C/1 BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE HODE JAN 1, 77-OEC 31, 79 4 HIND SPEED (HPH).1.5-3.4 3.5-5.4 5.5-7.4 7.5-12.4'.

12-5-18.4 0.0 O.Q 0.01 Q.05'.01 0.0 0.0 0.01 , 0.05,-Q.ol 0.0 0.0 0.0 0.01-.0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0..0.0 0.0 0.0 0.01 0.0 0.0 Q.a O.Q2 O.Q2 0.01-0.0 0.0 0.01 0.01 0.0 0 Q 0.0 0.02 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,0 0.0 0.0-0.0 0.0 0.0 0.02 0.01 0.0 0.0 0.0 0.01 0.02 0.02 o.o o.o o.ol a.'o3 o.o2 0.0 0.0 0.01 0.04 0.03 0.0 0.0 0.0 0.03 0.04 OOH)':.1 8;5-24.4 0.01'.Q'.0 0.0 0.0 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.01 0.03 0,0 0.0>24.5 O.a'.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 o.a 0.0 0.0 TOTAL 0.08 0.07 0.01 0.0 0.0 0.01 0.05 0.02 0.04 0.0 0.0 0.03 0.06 0.09 O.QS 0.07 SUBTOTAL 0.0 0.0 0.0 0.05 0.12 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS 8 TOTAL HOURS OF GROUND LEVEL STABILITY CLASS B 0.26 0.13 254S2.0 2832.4 185.1 163.4 0.05 0.0 0.61 METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 AND 45.30 HETERS HIND DIRECTION HEASURED AT 10.42 HETER LEVEL HIND SPEED HEASUREO AT 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0384p RETS Hanual Revision 7 Page 109 TABLE 1.3 (Sheet ll of 22)SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY WIND DIRECTION FOR STABILITY CLASS C (-1.7<DELTA-T<-1.5'C/100 H)BROWNS FERRY NUCLEAR PLANT PART'I OF 2 GROUND LEVEL RELEASE QOOE JAN 1, 77-OEC 31, 79 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALH 0.0 0.0 0.0 ,0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.6-1.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q Q.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 1.5-3.4 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HIND SPEED 5.5-7.4 0.01 0.01 0.01 0.0 O.Q 0.0 0.01 0.01 0.01 0.0 0.0 0.01 0.01 0.01 0.01 0.01 3.5-5.4 0.0 0.0 0.0 0.0 0.0 0.0 Q.al 0.01 0.01 0.0 0.0 o.a 0.0 0.0 0.0 0.0 0.03 O.ll 0.03 0.02 0.01 0.0 Q.O 0.0 0.0 0.01 0.01 0.0 0.0 0.01 0.01 0.02 0.03 0.02 0.17 0.0 0.0 Q.Q o.a 0.0 o.'a o.a.0.0 0.0 0,0 0.0 0.0 0.01 0,02 0.02 0,03 Q.OB Q.Q 0.0 0.0 0.0 0.0 0.0 a.o 0.0-0.0.0.0 0.0 , 0.0 0.01~-0.03--0.01 0.0 0.05 (HPH)7.5-12.4 12.5-1B.4 18.5-24.4>24.5 0.0 o.a o.a 0.0 a.'o 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.04 0.03 0.02 0.0 0.0 0.0 0.02 0.03 0.03 0.0 0.0 0.02 0.04 0.08 0.07 0.06 0;0 0.44 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS C TOTAL HOURS OF GROUND LEVEL STABILITY CLASS C HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATED 1.3 STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 HETERS HIND DIRECTION HEASUREO AT 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 25482.0 2B32.4 259.0'06.3'H ESE OF BROHNS FERRY NUCLEAR PLANT RETS Hanual Revision 7 Page llo TABLE 1.3 (Sheet 12 of 22)SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED.BY WIND DIRECTION FOR STABILITY CLASS 0 (-1.S<DELTA-T<-0.5'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE HODE DAN 1, 77-DEC 31, 79 WIND DIRECTIO N CALH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 N NNE NE ENE E ESE SE SSE S SSW SW WSH W WNW NW NNg WIND SPEED (HPH)0.6-1.4 1.S-3.4 3.5-S.4 5:5-7.4 7.5-12.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o 0.01 0.02 0.02 Q.ol 0.0 0.0-0.0 0.0 0.0 0.0 0.01 0.04 0.01 0.05 0.01 0.04 0.01 0.01 0.01 0.02 0.03 0.04 0.11 0.13 0.09 0.06 0.09 0.06 0.02 0.01 0.01 0.01 0.03 0.03 0.02 O.Q6 0.0 0.030.0 0.03 0.01 0.05 0.15 O.18 0.08 0.01 0.01 0.01 0.06 0.05 0.06 0.01 0.0 0.06 0.10 0.16 0.15 0,25 SUBTOTAL 0~0 0.0 0.6 0.46 0.67 1.34 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS D TOTAL HOURS OF GROUND LEVEL STABILITY CLASS 0 12.5-18.4 18.5-24.4 0.10 O.ol 0.05 0.01 0.0.0.0 0.0 0.0 0.0.0.0 0.0*0.0 O.O.O.O 0,.02.0.0 0,0.0.0 0.0.-0.0 0,01 0.0 0.04 0'.0 0.09 0.02 0.19 0.14 0.23 0.10 0.19, 0.04 0.92;0.32 25482.Q 2832.4 13904.1 968.6>~24.5 O.o 0.0'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q1 0.02 0.0 TOTAL 0.31 0.30 0.13 0.03 0.04 0.0&0.31 0.24 0,23 0.05 0.03 0.16 0.29 0.53 0.53 0.54 0.03 3.80 HETEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED l.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 10.03 ANO 45.30 HETERS WIND DIRECTION HEASURED AT 10.42 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S TABLE 1.3 (Sheet 13 of 22)RETS Manual Revision 7 Page ill SPLIT JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR sTABlLITY cLAss E (-0.5(DELTA-T<

1.5'cllaa M)BROHNS FERRY NUCLEAR PLANT PART 1 OF 2 GROUND LEVEL RELEASE MODE DAN 1, 77-DEC 31, 79 QINO DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALM 0.6-1.4 1.5-3.4 0.0 0.0~0.0 0.0 0.0 0.01 0.0 0.0 0.01 a.a o.o o.o2 0.0 0.0 0.02 0.0 0.0 0.02 0.0 0.0 0.08 0.0 0.0 0.05 0.0 0.0 0.06 Q.Q 0.0 0.02 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.01 0.0 0.0 0.0 a.o o.o o.o Q.Q 0.0 0.0 HIND SPEED 3.5-5.4 5.5-7.4 0.04 0.06 0.06 0.07 0.06 0.06 0.04 0.03 0.07.O.Q2 0.08 0.07 0.22 0.16 0.12 0.12 0.10 0.09 0.02 0.02 0.0 0.0 0.05 0.02 0.06 0.05 0.01 0.01 0.01 0.02'.03 0.07 0.07 0.08 0.05 0.01 a.al 0.03 0.18 0.19 0.27 0.02 Q.al 0.03 0.05 0.04 0.04 0,10 0.02 0.02 0.01 0.01 0.0 0.0 0.02 Q..04 0.13 0.01 Q.Q 0.02 0.01 0.02 0.03 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 O.'a 0.0 0.0 0.01 0.01 0.01 0.0 0.20 0.0 0.24 0.0 0.19 0.0 0.11 0.0 0.12 Q.Q 0.20 0.0 0.66 0.0 0.52 0.0 0.66 0.0 0.09 0.0 0.02 0.0 0.13 0.0 0.18 0.0 0.09 0.0 0.11 0.0 0.23 (MPH)7.5-12.4 12.5-18.4 18.5-24.4)24.5 TOTAL SUBTOTAL 0.0 0.0 0.32, 0.97 0.87 1,18 0.36~0.05 0.0 3.75 TOTAI HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS OF VALID OBSERVATIONS OF GROUND LEVEL RELEASE OF STABILITY CLASS E OF GROUND LEVEL STABILITY CLASS E 25482.0 2832.4 7920.6 957.9 METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 10.03 AND 45.30 METERS HIND DIRECTION MEASURED AT THE 10.42 METER LEVEL HIND SPEED MEASURED AT 10.42 METER LEVEL EFFLUENT VELOCITY 12.60 MIS 0384p RETS Hanual Revision 7 Page 112 TABLE 1.3 (Sheet 14 of 22)SPLIT 30INT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS F (1.5 c DELTA-Tc 4.0 C/100 H)PART 1 OF 2 GROUND LEVEL RELEASE HODE BROHNS FERRY NUCL'EAR PLANT JAN 1, ll-DEC 31, 79 HIND-OI RECTION CALM N 0.0 NNE 0.0 NE o.o ENE 0.0 E 0.0 ESE 0.0 SE 0.0 SSE 0.0 S 0.0 SSH-0.0 SH 0.0 HSH 0.0 H 0.0 HNH 0.0 NH 0.0 NNH 0.0 0.6-1.4 1.5-3.4 3.5-5.4 0,01 0.01 0.01 0.02 0.01 0.02 0.05.0.04 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.01 0.06 0.08 0.03 0.03 0.04 0.02 0.06 0.06 0.03 0.0 0.0 0.0 0.01 0.0 Q.o 0.03 0.0 0.0 O'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HIND SPEED 5.5-7.4 0.04 0.05 0.03 Q.01 0.0 0~0 0.03 0.05 0.04 0.0 0.0 0.0 0.0 0.0 Q.O 0.02 (HPH)7.5-12.0.01 0.02 0.0 0.0 0.0 0.0 0.06 Q.18 0.11 0.0 0.0 0.0 0.0 0.0 Q.O 0.01 4 12.5-18.4 0.0 0.0 0.0 0.0 0.0 0.0 0.01 Q.02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 18.5-24.4 Q.o 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0>RR24 5 0.0 0.0 0.0 O.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 TOTAL 0.12 0.16 0.07 0.06 0.05 0.04 0.21 0.36 0.21 0.01 0.0 Q.O 0;01 0.0 0.0 0.07 SUBTOTAL 0.0 0.0 0.21'.45 0.27 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS F TOTAL HOURS OF GROUND LEVEL STABILITY CLASS F 0.39 0.04 25482.0 2832.4 2385.0 357.0 0.01 0.0 1.37'ETEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED QN DELTA-T BETHEEN 10.03 ANO 45.30 HETERS HIND SPEED MEASURED AT THE 10.42 HETER LEVEL.EFFLUENT VELOCITY-12.60 H/S 0384p

>4~A~--~~I>~TABl.E).3 (Sheet 15 of 22}RETS ManUal Revision/Page 113 SPLIT QOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS G (DELTA-T>4.0'C/100 M}PART)OF 2 GROUND LEVEL RELEASE MODE BROHNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH.HSH W HNH NW NNW CALM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0:0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.6-1.4 1.5-3.4 3.5-5.4 0.02 0.02 0.01 0.01 0.01 0.01 0.03 0.04 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.04 0.06 0.01 0.01 0.01 0.0 0.01 0.05 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.01 HIND SPEED 5.5-7.4 0.0 0.03 0.0 0.0 0.0 0.'0 0.01 0.03 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.08 (Mphil}7.5-12.4 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.06 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL Q.Q&0.11 0.02 0.02 0.02 0.01 0.07 0.18 0.06 0.0 0.0 0.0 0.0 0.0 0.0 0.02 SUBTOTAL Q.Q 0,0 0.17 0.22 0.09 0.09 0.0 0.0 0.0 0.57 TOTAL HOURS OF VALID QBSERVATIONS TOTAL HOURS OF GROUND LEVEL RELEASE TOTAL HOURS OF STABILITY CLASS G'OTAL HOURS OF GROUND LEVEL STABILITY CLASS G METEOROLOGICAL FACILITY:METEOROLOGICAL FACILITY LOCATEO 1.3 KM STABILITY BASED ON LAPSE RATE MEASURED BETWEEN 10.Q3 ANO 45.3Q HIND SPEED AND DIRECTION MEASURED AT THE 10.42 METER LEVEL EFFLUENT VELOCITY 12.60 M/S 0384 p'25482.0 2832.4 694.7 151.7 ESE OF BROHNS METERS FERRY NUCLEAR PLANT TABLE 1.3 (Sheet 16 of 22)RETS Hanual Rev1sion 7 Page 114 SPLIT JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY WIND DIRECTION FOR STABILITY CLASS A (DELTA-T<-1.9'C/100 H)PART 2 OF 2 ELEVATED RELEASE HODE BROWNS FERRY NUCLEAR PLANT JAN 1, 77-OEC 31, 79 WIND DIRECTION N NNE NE ENE E ESE SE SSE S SSW SW WSW.W WNW NW NNW CALH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0;0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.6-1.4 1.5-3.4 WIND SPEED 3.5-5.4 5.5-2.4 0.0 0.0 0.0 0.0'.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 (HPH)7.5-12.4 12.5-1B.4 1B.5-24.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 Q.Q 0.0 O.Q 0.0 Q.Q 0.0>24.5 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 O.Q Q.Q Q.Q 0.0 Q.O Q.O Q.O 0.0 TOTAL 0.0 0.0 O.Q 0.0 0.0 Q.Q O.Q 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 SUBTOTAL 0.0 0.0 0.0 0.0 0.01 0.0 0.0 Q.O O.Q 0.01 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAL HOURS OF STABILITY CLASS A TOTAL HOURS OF ELEVATED STABILITY CLASS A HETEOROLOGICAL FACILITY:HETEOROLOGICAL FACILITY LOCATEO 1.3 STABILITY BASED ON DELTA-T BETWEEN 45.30 AND 89.60 HETERS WINO DIRECTION HEASUREO AT 45.67 HETER LEVEL WIND SPEED HEASURED AT 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 03B4p 254B2.0 22649.6 133.1 5.6 KH ESE OF BROWNS FERRY NUCLEAR PLANT TABLE).3 (Sheet 17 of 22)RETS Hanual Revkslon 7 page 115 SPLIT JOINT PERCENTAGE FRE ENCIES Of WIND SPEED BY HIND DIRECTION FOR STABILITY CLASS B (-1.9 (DELTA-T<-1.7'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATEO RELEASE HODE JA(1, 77-OEC 31, 79~~WINO DIRECTION N NNE NE ENE E ESE SE SSE S SSH SW WSQ H WNH NH NWH SUBTOTAL CALH 0.0 0.0 0.0 0.0 0.0 0.0~0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.6-1.4 1.5-3.4 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0.O.O 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.01 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 HIND SPEED 3.5-5.4 5.5-7.4 O.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0,01 0.0 0.0 0.0 O.O O.O O.'0 O.O 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 (HPH)7.5-12.4 12 0.0 0.0 0.0 0.0 O.O O.Q 0.0 0.0 0.0 0.01 0.0.0.02 0.0 0.0 Q.Q 0,0 0.03.5-18.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 18.5-24.4 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0)24.5 O.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 TOTAL 0.0 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.01 Q.ol 0.02 0.0 0.0 0.0 0.0 0.0 0.0 0.06 t 4 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAI HOURS OF STABILITY CLASS B TOTAL HOURS OF ELEVATEO STABILITY CLASS B HETEOROLOGICAL FACIL'ITY:

HETEOROLOGICAL FACILITY LOCATEO 1.3 KH ESE STABILITY BASED ON DELTA-T BETWEEN 45.30 AND 89.60 HETERS HIND DIRECTION HEASURED AT 45.67 HETER LEVEL HIND SPEED HEASURED AT 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0384p 25482.0 22649.6 185.'1.21.8 OF BROHNS FERRY NUCLEAR PLANT TABLE 1.3 (Sheet 18 of 22)3OINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILIQ CLASS C (-1.7<DELTA-T<-1.5'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 2 OF 2 ELEVATED RELEASE NODE 3AN 1, 77-DEC 31, 79 RETS Hanual Revision 7 Page 116 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H tNH NH NNH CALM 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.6-1.4 1.5-3.4 3.5-5.4 0.0 0.0 Q.O 0.0 0.0 0.01 0.05 0.04 0.01 0.02 0.05 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q Q.Q 0.0 0.0 0.0 0,0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.O 0.0 0.0 0.0 0.0 0.02 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 HIND SPEED 5.5-7.4 0.0 0.01 0.0 0.0 Q.o 0.01 0.01 0.0 0.0 0.02 0.05 0.03 0.01 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.01 0.0 0.0 0.0 0.01 0.02 0.05 0.03 Q.02 0.0 0,0 0.0 0.0 0.0 Q.O 0.0 Q.O 0.0 0.0 0:0 0.0 0.01 0.01 0.02 0.02 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.o 0.0 0.0 0.0 0.0 0.0 0.02 0.0 0.0 0.0 (HPH)7.5-12.4 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 0.0 0.01 0.0 0.0 0.0 0.03 0.08 O.04 O.Q2 0.05 0.13 0.09 0.08 0.04 0.01 0.0 SUBTOTAL 0.0 0.0 0.03 0.18 0.14 0,14 0.07 0.02 0.0 0.58 TOTAL HOURS OF VALID'OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAL HOURS OF STABILITY CLASS C TOTAL HOURS OF ELEVATED STABILITY CLASS C 25482.0 22649.6 259.0 152.7 METEOROLOGICAL FACILITY: HETEOROLOGICAL FACILITY LOCATED 1.3 KN ESE OF BROWNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 45.30 ANO 89.60 METERS HIND SPEED AND DIRECTION MEASURED AT THE 45.67 NE/ER LEVEL EFFLUENT VELOCITY 12.60 H/S 0384p TABLE 1.3 (Sheet 19 of-22)JOINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS D (-1.5<DELTA-T<.-0.5'C/100 M)BROHNS FERRY NUCLEAR PLANT JAN 1, 77-DEC 31, 79 RETS Manual Revision 7 Page 117 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH H HNH NH NNH CALM 0.6-).4 1.5-3.4 0.0 0.0.'.12 0.0 0.01:.0.13 0.0 0.0 , 0.09 0.0 0.01 0.1)0.0-0.01 0.10 0.0 0.0)0.22 0.0 0.01 0.67 0.0 0.01 0.48 0.0 0.0 0.34 0.0 0.01 0,20 O.O Q.O)0.24 Q.Q Q.02 0.16 0.0 0.0 0.07 0.0 0.0 0.09 0.0 0.0 0.07 0.0 0.0 0.09 3.5-5.4 0.40 0.46 0.36 0.24 0.20 0.52 1.66 0.90 0.99 0.52 0.79 0.51 0.36 0.33 0.36 0.29 HIND SPEED 5.5-7.4 0.62 0.72 Q.4&0.23 0.28 0.68 0.89 0.63 0.67 0.37 0.43 0.57 O.BO Q.48 0.55 0.53 1.49 1.88 1.04 0.23 0.25 1.07).75).49 0.99 0.69 0.49 0.57 1.34 1.25 1.40 1.36 0.&7 0.9)0.14 0.04 0.05 0.16 0.84 1.08 0.93 0.34 0.32 0.27 0.55 0.94 1.44 1;15 0.12 0.05 0.02 0.01 0.01 0.0 0.16 0.26 0.33 0.11 0.05 0.08 0.16 0.32 0.37 0.19 0.0 0.0 O.o 0.0 0.0 0.0 0.01 0.02 0.02 0.0 0.0 0.0 0.01 0.01 0.01 O.o 3.62 4.16 2.)3 0.87 Q.BQ 2.66 5.99 4.87 4.27 2.24 2.33 2.18 3.29 3.42 4.20 3.61 (MPH)7.5-12.4 12.5-18.4 18.5-24.4)24.5 TOTAL SUBTOTAL 0.0 0.10 3.18 8.89 8.93)7.29;10.03 2.24 0.08 50.74 TOTAL HOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TJTAL HOURS OF STABILITY CLASS D TOTAL HOURS OF ELEVATED STABILITY CLASS D 25482.0 22649.6 13904.1 12935.5 METEOROLOGICAL FACILITY: METEOROLOGICAL FACILITY LOCATED 1.3 KM ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 METERS HIND SPEED AND DIRECTION MEASURED AT THE 45.67 METER LEVEL EFFLUENT VELOCITY 12.60 M/S 0384p

TABLE 1.3 (Sheet 20 of 22)JOINT PERCENTAGE FRE ENCIES OF WIND SPEED BY WIND DIRECTION FOR;STABILIP'LASS E (-0.5<DELTA-T<1.5'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 2 of 2 ELEVATED RELEASE HODE JAN), 77-DEC 31, 79 RETS Manual Revision.7 Page 118 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SH HSH.H HNH NH NNH CALM o.a 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 a,o 0.0 0.0 a,o 0.0 0.0 Q.Q 0.6-1.4 1.5-3.4 3.5-5.4 0.13 0.15 0.11 o.2a o.a9 0.29 a.41 0.23 0.14 O.ll 0.17 0.12 0.09 0.06 0.09 0.12 0.22 0.2$0.25 0.2'l 0.24 0.58 1.04 0.60 0.49 a.'28 0.27 0.25 0.19 0.13 0.14 0.21 0.0 0.0 0.01 0.0 0.0 0.01 o.02 0.01 O.ai 0.0 0.01 0.01 0.0 0.0 0.0 0.0 HIND SPEED 5.5-7.4 0.31 0.39 0.39 0.33 0.30 0.86 1.02 0.54 0.32 a.'3o 0.28 0.24 0.26 0.11 0.13 0.16 0.80 1.04 0.88 0.39 0.55 1.10 1.37 0.87 0.70 0.48 0.29 0.28 0.34 0.20 0.31 0.52 0.15 0.28 0.18 0.10 0.06 0.09 0.55 0.59 0.3.4 0.19 0.09 0.06 0.05 0.04 0.08 0.16 0.0 0.0 0.0 0.0 0.0 0.01 0.08 0.14 0.05 0.01 0.0.0.0 0.0 0.01 0.0 0.0 (MPH)7.5-12.4 12.5-18.4 18.5-24.4>24.5 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 TOTAL 1.61 2.10 1.82'1.23 1.24 2.94 4.50 2.99 2.05 1.37 l.ll 0.96 0.93 0.55 0.75 1.17 SUBTOTAL 0.0 0.08 2.51 5.34 5.94 10.12 3.01 0.30 0.02 27.32 TOTAL HOURS OF VALID OBSERVATIONS 25482.0 TOTAL HOURS OF ELEVATED RELEASES 22649.6 TOTAL HOURS OF STABILITY CLASS E 7920.9 TOTAL HOURS OF ELEVATED STABILITY CLASS E 6962.9 HETEOROLOGICAL f'ACILITY:

HETEOROLOGICAL FACILITY LOCATED 1.3 KH ESE OF BROHNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-,T BETHEE(45.30 AND 89.60 METERS HIND SPEED AND DIRECTION HEASURED AT THE 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 N/S Oz TABLE 1.3 (Sheet 21 of 22)JOINT PERCENTAGE FRE UENCIES OF WIND SPEED BY HIND DIRECTION FOR STABILIQ CLASS F (1.5<DELTA-T<4.0'C/100 M)BROHNS FERRY NUCLEAR PLANT PART 2 of 2 ELEVATED RELEASE MODE JAN 1, 77-DEC 31, 79 RETS ManUal Revision 7 Page 119 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSH SW WSH H HNH NH NNW CALM 0.6-1.4 1.5-3.4 0.0 0.0 0.03 0.0 0.0" ,0.04 O.O O.o O.O4 0.0 O.Q-'.04 0.0 0.0 0.03 0.0 0.0'.13 0.0 0.0 0.13 0.0 0.0 0.09 0.0 0.0-0.08 0.0 0.0 0.04 0.0 0.0-0.04 0.0 0.0 0.03 0.0 0.01 0.04 0.0 0.0 0.02 0.0 0.0 0.03 0.0 0.0 0.02 HIND SPEED 3.5-5.4 5.5-7.4 0.08 0.06 0.06 0.11 0.10 0.15 O.ll Q.ll 0.07 0.11 0.26 0.24 0.38 0.30 0.11 0.12 Q.1 1 0.13 0.12 0.14 0.09 0.10 0.07 0.06 0.04 0.05 0.04 0.01 0.04 0.03 0.02 0.04 (MPH)7..5-12.4 12 0.34 0.42 0.40 0.29 Q.32 0.24 0.19 0.14 0.21 0.24 0.06 0.05 0.04 0.01 0.02 0,10 0.05 0.21 0.12 0.07 Q.02 0.0 0.0 a.03 0.03 0.01 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 O.Q 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0.5-18.4 18.5-24.4)24.5 0.0 0.0 0.0 0.0 O.o 0.0 0.0 0,0 0.0 0.0 0.0 Q.O<0.0 0.0 0.0 0.0 TOTAL 0.56 0.54 0.81 0.62 0.55 Q.&7 1.00 0,49 0.56 0.55 0.29 0.2'1 0.18 0.08 0.12 0.18 SUBTOTAL 0.0 0.01 0.&3 1.7Q 1.76 3.07 0.54 0.0 0.0 7.91 TOTAL HOURS TOTAL HOURS TOTAL HOURS TOTAL HOURS OF VALID OBSERVATIONS OF ELEVATED RELEASES OF STABILITY CLASS F OF ELEVATED STABILITY CLASS F 25482.0 22649.6 ,2385.0 2028.0 METEOROLOGICAL FACILITY: METEOROLOGICAI FACILITY LOCATED 1.3 KM ESE OF BRONNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETWEEN 45.30 AND 89.60 METERS HIND SPEED AND DIRECTION MEASURED AT THE 45.67 METER LEVEL EFFLUENT VELOCITY 12.60 M/S I 0384p TABLE 1.3 (Street 22 of 22)3OINT PERCENTAGE FRE ENCIES OF HIND SPEED BY HIND DIRECTION FOR STABILITY CLASS G (DELTA-T>4.0'C/100 H)BROHNS FERRY NUCLEAR PLANT PART 2 of 2 ELEVATED RELEASE HODE DAN 1, 77-DEC 31, 79 RETS Hanual Revision 7 Page 120 HIND DIRECTION N NNE NE ENE E ESE SE SSE S SSN SN HSN H HNN NH NNH CALH 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.01 0.0 0.0 0.0 0.0 0.0 0.0 Q.Q 0.0 0.0 0.0 0.0~0.01 0.02 0.0 0.0 0.05 Q.12 0.03 0.02 0.0 0.01 O.Qi 0.01 0.02 0.0 0.01 0.6-1.4 1.5-3.4 HIND SPEED 9.5-5.4 5.5-9.4 0.0 0.02 0.02 0.04 0.02 0.03 0.02 0.02 0.02 0.01 0.15 0.07 Q.2Q 0.13 0.06 0.06 0.07 0.06 0.02 0.02 0.01 0.03 0.0 0.0 0.0 0.01'.0 0.0 0.0 0.0 0.01 0.0 0.06 O.1 l.0.12 0.07 0.04 0.01 0.04 0.02 0.01 0.06 0.02 0.0 0.0 0.0 0.0 0.01 0.01 0.04 0.02 0.02 0.0-0.0 0.0 QA 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0 (HPH)7.5-12.4-12.5-18.4 18.5-24 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 Q.O 0.0 0.0 0.0 0.0 0.0 0.0 0.0 0.0.4>24.5 TOTAL 0.0 0.09 Q.O 0.22 0.0 0.21 0.0 0.13 0.0 0.07 0.0 0.29 0.0 0.49 0.0 0.17 0.0 0.16 0.0 0.10 0.0 0.07 0.0 0.01 0.0 0.02 0.0 0.02 Q.O 0.0 0.0 0.03 SUBTOTAL 0.0 0.01 0.31 0.60 0.50 TOTAL MOURS OF VALID OBSERVATIONS TOTAL HOURS OF ELEVATED RELEASES TOTAL HOURS OF STABILITY CLASS G TOTAL HOURS OF ELEVATED STABILITY CLASS G 0.57 0.09 0.0 25482.0 22649.6 694.7 543.1 0.0 2.08 HETEOROLOGICAL FACILITY: HETEOROLOGICAI FACILITY LOCATED 1.3 KH ESE OF BRONNS FERRY NUCLEAR PLANT STABILITY BASED ON DELTA-T BETHEEN 45.30 AND 89.60 HETERS.HIND SPEED AND DIRECTION HEASURED AT THE 45.67 HETER LEVEL EFFLUENT VELOCITY 12.60 H/S 0384p

'Submersion dose mrem/yr per pCi/m~DFBi DFSi Air dose mrad/yr per pCi/m~DFVi DFBi RETS Manual Revision 7 Page 121 Table 1.4 DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Kr-83m Kr-85m Kr-85 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m, Xe-135 Xe-137'e-138 7,56E-02 1.17E+03 1~61E+01 5 92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02'.94E+02 3'.12E+03'.81K&3 1'.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.01E+04 7'9K+03 4.76E+02 9.94E+02 3.06E+02.7.11E&2 1.86E+03 1.22E+04 4.13E+03 2.69K+03 1 93E+01 l.23E+03.'-72E+Ol 6.17E+03 1 52E+04 2.88K+02 1.97E+03 1 95K+03 1.03E+04 2 93E+03 1".63E+04 1 56E+02, 3.27E+02 3.53E+02.3.36E+03'.

1.92E+03'.51E+03 9~21E+03 9.30E+03 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7'9E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03.1.73E+04 A 1.06E+04

Reference:

Regulatory Guide 1.109, Table B-l.0384p

'RETS Manual Revision 7 Page 122 Table 1.5 SECTOR ELEMENTS CONSIDERED FOR POPULATION DOSES Range of Sector Element Site boundary-1 mile 1,-2 miles 2-3 miles.3,-4 miles 4-5 miles 5-.10'iles 10-20 miles 20-30 miles 30-40 miles 40-50 miles Midpoint of Sector Element 0.8 mile 1.S miles 2.5 miles 3 5 miles 4.S miles 7.5 miles 15 miles 25 miles 35 miles.45 ad.les.0384p

RETS Manual , Revision 7 Page 123 Table 1.6 BFN 50WILE POPULATION WITHIN EACH SECTOR ELEMENT Distance to Midpoint of Sector Element 0.8 1.5 2.5 3.5 4.5 7 5 15 25 35 45 N NE 0 10'5 35 85 670 1515.2615 10660 3690 0 5'5 65 55 915 2990 2230 3125 3420 0 5 25'5 88 4180 14180 6625 5385 12625 0 15'0 40 70 1310 4990 9615 13860 5425 0 0 30 10 40 945 1910 73405 75125 4610 ESE 0 0'0.0 165 1880 7465 9575 SE'SE 0 0 0 0.20.10390'0945 4660 6230 13850 0 0 0 0 50 1630 6250 11630 15175 18945 0 0 20 35'6 1250 3805 1800 4475 3730 0.0 60 75 ,175'45 5895" 1270 1490 2535 020 , 35 35 15'0 685 2970 135 295 3060 2280 2725 10675 3005 11545 3755 0'0 625 2960 6830 35070 4785 WNW, Qi 0 25 55'0 885.9300 39875 5545 0 0 0 5 345 4345 5215 5485 3260 0 5 35 25'0 625 2090 2440.12350 7360 0384p

0 Table 1.7 (1 of 8)INGESTION DOSE FACTORS-DFL (mremlpCi ingested)RETS Manual Revision 7 Page 124 H-3 C-14 Na-24 P-32.Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co>>57 Co-5&Co-60 Ni-63 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb&9 Sr&9 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-l.10m bone 1 058&7'.84E-06 1 7OE-06 1 938&4 0.00E+00 O.OOE+00 0.008+00 2 75E-06 4.34E-06 0.008&0 0.00E+00 0 008+00 1.30E-O4 5.28E-07 O.QQE+00 4.84E-06 1.03E-08 1.70E-07 O.QOE+OQ 0~OOE+00 0 OQE+00 O.OQE+00 0 OOE+00 0.00E+00 0 OOE+00 3 08E-04 7 588&3 5 678-06 2 158-06 9.62E-09 9.09E-11 1.418&7 8 45E-10 2.68E-09 3 04E-08 1.688-09 6 22E-09 5.22E-11 0.00E+00 2.478-10 2 54E-10 1 85E-07 1.54E-OS 2.75E-'06 1.60E-07 liver 1.05E-07 5.68E-07 1.70E-O6 1.208&5 0.008+00 4.578-06 1.158-07 1.90E-06 1.02E-05 l.75E-07 7.458&7 2 148-06 9.018-06 6.86E-08 8.33E-08 1.548&5 1.978&8 4.08E-07 O.QOE+QQ 0.008+00 0.008+00 O.OOE+00 2.118-05 6.058-08 4.018-08 O.OOE+00 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 Q.QQE+00 0.008+00 0 QQE+00 O.OQE+00 9~758-09 3 398>>10 3.468-09 1.328-11 4.31E-O6 6.988-10 3.66E-10 0.008+00 0.008+00 0.008+00 1.48E-07 t body 1.05E-07 5.68E-07 1.70E-06 7.46E-06 2.66E-09 8 72E-07 2.04E-08 4.43E-07 3.91E-06 2.91E-07 1.67E-06 4.728-06 4 368&6 3.138-08 3 91E-08 6 968&6 l.378-09 3.73E-08 2.2&8&6 4.02E-08 5.21E-OS 2.148&9 9.83E-06-3~218-08 2.828-08 8.848-06 1.86E-03 2.29E-07 9.308&8 2.58E-10 3.528-12 3.778-09 2 478-11 7.40E-11 6.6Q8-09 1.S58-10 1.86E-09 4.828-1.2 8.20E-07 8.89E-09 3.59E-09 7.97E-08 6.088-09 3.48E-07 8.79E-08 ADULT thyroid 1.05E-07 5.68E-07 l.708&6 0.008+00 1.59E-09 0.008+00 0 OOE+00 O.QOE+00 O.OOE+00 0 QOE+00 0~OOE+00 0 008+00 0.008+00 0.008+00 0 OOE+00 Q.OQE+OQ O.OOE+00 0.00E+00 O.QOE+00 0.00E+00 0 QOE+00 0.008+00 O.QOE+00 0.008+00 O.OQE+00 O.QOE+00 0.008+00 0.008+00 0.00E+00 O.OOE+00 Q.OOE+00 O.OQE+00 O.QOE+00 0.00E+00 Q.OOE+00 O.OOE+00 0.008+00 0.008+00 O.QOE+00 O.OOE+00 0 QOE+00 0.008+00 0.008+00 0 QOE+00 0.008+00 kidney lung 1.05E-07 1.05E-07 5.68E-07 5.68E-07 1.70E-06 1.70E-06 0.00E+00 O.OOE+00 5.86E-10 3.53E-09 1 36E-06 O.OQE+00 1.468-07 O.OOE+00 0 F 008+00 1.06E-06 0.008+00 2.858&6 Q.QQE+00 0.008+00 0.00E+00 0 OOE+00 0.008+00 O.OOE+00 0~OOE+00 0~OOE+00 0~OOE+00 0~OOE+00 2.108-07 0.00E+00 1.03E-Q5 Q.QOE+00 1.28E-08 0.00E+00 2.47E-07 0.00E+00 0 OOE+00 0~OOE+00 0 F 008+00 0~QOE+00 0.008+00 0.00E+00 0.008+00 0.008+00 0.008+00 O.OOE+00 0.00E+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.008+00 O.OOE+00 0.00E+00 0.008+00 O.OOE+00 0~OOE+00 0.00E+00 0.008+00 O.OOE+00 0.00E+00 O.QOE+00 0.008+00 0.00E+00 1.538-08 O.OOE+00 5.128-10 0.00E+00 3.42E-09 O.OOE+00 1.548-11 O.OOE+00 9 768&6 0.00E+00 1.06E-08 3.42E-10 6.S9E-09 1.87E-10 7.06E-07 O.OOE+00 1 99EW7 0.008+00 5.31E-06 0.00E+00 2.91E-Q7 Q.QQE+QQ gi-lli 1.05E>>07 5.68E>>07 1.708-06 2.17E-05 6 69E-07 1 40E-05 3.67E-06 1.098-06 3.40E-05 4.44E-06 1.S18-05 4.02E-05 1.88E-06 1.74E-06 7.10E-06 9.70E-06 2-96E-09 2 49E-05 2.59E-06 5'79E-08 4.09E-13 Q.QOE+00 4.168-06 8.36E-19 2.338-21 4.94E-05 2.19E-04 2.70E-05 4.26E-05 1.02E-04 2.67E-10 7.768-05 l.488&5 8.50E-05 3.098>>05 1.05E-04 2.10E-05 4.87E-08 9.99E-06 4.13E-07 1.10E-21 2.16E-OS 9.42E-06 1.78E-04 6 Q4E-05 0384p

8)S-DFL ed).7 (2 of SE'ACTOR Ci ingest Table 1 NGESTION DO (mrem/y RETS Manual Revision 7 Page 125 Sb-124 Sb-125 Te-125m Te-127m Te<<127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132;I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142.L'a-140 La-1.42.'e-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147'-187'p-239 bone 2.808-06 1.79E-06 2.6SE-06 6.77E-06 1.10E-07 l.15E-05 3.14E-OS 1.738&6 1 978&8 2.528-06 7.56E-07 4.16E-06 2.03E-07 1.428&6 1.06E-07 4.43E-07 6~228&5 6.518&6 7.978&5 5.528-08 9.708&8 2'.03E-05 4.71E-OS.2.13E-08 2.50E-09 1.28E-10.9.36E-09 1.658-09-4.88E-O7 9~208&9 3.01E-11 6.298&9 1.03E-07'.

198&9 liver 5.298-08 2.008-08 9.718-07 2.428-06 3.958&8 4 29E-06 1.18E-08 8.46E-07 8.23E-09 1.638&6 2.238-06 5.958&6 5.43E-07 2.478&6 2.888-07 1 168&6 1.48E-04 2.578-05 1.098&4 1 098&7 6'18-11 2 558-08 3.56E-11 2.19E-ll 1.268&9 5.828-11 6 338-09 1.228-06 2 04E-07 3 698-09 1 258-11, 7.278-09 8.61E-O&1~17E-10.t body 1.118&6 4.268&7 3.59E-07 8.25E-07 2.388-08 1 828&6 T.65E-09 7.058-07 6~228&9 1.53EW6 8.808-07 3.418-06 1.908W7 7.538-07 1.03E-07 4.288-07 1.21EW4 1.85EW5 7.148-05 5.408&8 2.84E-09 1.33E-06 1.598&9 1.34EM9" 3.338-10 1'.458-11 7.18E-10 1.35E-10 2.628&8 4.568-10 1.538-12 4.35E-10 3.Q1E>>OS 6 458-1X.ADULT'hyroid 6.79E-09 1 828-09 8.06E-07 1 73E-06 8.158&8 3 958-06 2 418-08 1 34E-06-1 62EWS 1.808-06 1~89EW4 1 958&3 1.908&5 3 63E-04 4 99E-06 7.658-05 0 OOE+00 Q.OOE+00 0.008+00 0 008+00 0 OOE+00 0 OOE+00 O.OQE+00 0 008+00 O.OOE+00 O.OOE+00 0.008+00 0 OOE+00 0.00E+00 O.OOE+00 0 OOE+00 0.00E+00 O.OOE+00 0.00E+00., kidney 0 00E-00 0.00E-OO 1.09E-05 2 75E-05 4.488-07 4.80E-05 1.32E-07 8.57E-06 8.638&8 1.57E-05 3 48E-O6 1.02E-05 8.658-07 4.31E-06 4.58E-07 1'.86E-06 4.79E-05 1.43E-05 3.708-05 S 018-08 6.468-11 8.67E-09 3 31E-ll 1 85E-"ll'.00E+00 0.00E+00 2.948&9 5.37E-lQ 1.218-07 2.138&9 7.05E-12 4.258-'09 0;008+00 3.65E-IO lung 2.18E-06 1.38E-06 Q.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.008+00 0;OOE+00 O.OOE+00 O.OOE+00 Q.QOE+00 1.598&5 1..96E-06 l.23E-05 7.918&9 3.92E-11 1.46E-OS 2'2E-11 E,248-11 0.00E+00 0 00E+00 0.008+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 gi-lli 7.95E-05 1.97E-05 1.07E-05 2.27E-05 8.68E-06 5.79E-05 2.37E-QS 8.40E-05 2.79E-09 7.71E-05 1.92E-06 1.57E-06 1.Q2E-07 2.22E-06 2.518-10 1.31E-06 2.59E-06 2.92E-06 2.11E-06 4.65E-13 1.72E-07 4.18E-05 2.22E-17 3.00E-26 9'25E-05 4.258-07 2 42E-05 4.56E-05 1 6SE-04 4 038-05 4.33E-18 3.49E-05 2.828-05 2 40E-05

References:

Regulatory; Guide 1.109, Table E-ll.Dose Factors for Co-57,, Zn-69m,.Br-82, Nb-97,, Sb-124 and Sb-125 are from" NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1977Table 4..NOTE: The tritium dose factor for bone is.assumed.to be equal'.to the total body'ose factor.0384p Table 1.7 (3 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 7 Page 126 H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Ma-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni&3 Ni&5 Cu-64.Zn&5 Za-69 Za>>69m Br-82 Br-83 Br-84 Br-8S Rb-86 Rb-88 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101 RQ-103 Ru-105 Ru-106 Ag-110m bone 1.068-07 4.068&6 2.308&6 2 768&4 0 008+00 0.008+00 0.00E+00 3 788-06 5.878-06 0.00E+00 0.00E+00 0.00E+00 1.778-04 7'498-07 O.OOE+00 5.768-06 1.478-08 2.408-07 0.00E+00 O.OOE+00 0.008+00 0.00E+00 0.008+00 O.OOE+00 0.00E+00 4.408-04 8 30E-03 8 078-06 3.05E-06 1.37E-08 1 298-10 2 01E-07 1 21E-09 3.838-09 4.12E-08" 2 37E-09 8 228-09 7.37E>>ll 0.008+00 3 32E-10 3.60E-10 2.55E-07 2.188-08 3.92E-O6 2.05E-07 liver 1.06E-07 8.12E-07 2.30E-06 1.718&5 O.OOE+00 5.90E-06 1'58E-07 2.688&6 1.37E-05 2.38E-07 9.728&7 2.818-06 1.258-05 9.578-08 1.15E-07 2.00E-05 2.80E-08 5.66E-07 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 2 98E-05 8 528&8 5.508-08 O.OOE+00 0.008+00 0.00E+00 0~OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 1.308&8 4.698-1.0 4.568-09 1.83E-11 6.03E-06 9.26E-10 5.128-10 0.00E+00 0~OOE+00 0.00E+00 1.94E-07 t body 1.068-07.8 128-07 2.308-06 1.078&5 3.60E-09 1 178-06 2.818-08 6.25E-O7 5.298&6 3 998&7 2 248&6 6 338&6 6 008&6 4 36E-08 5.418-08 9.338&6 1 968-09 5 198-08 3.048-06 5 748-08 7.228-08 3.05E-09 1.408-05 4.548&8 3'898-08 1.268&5 2 058-03 3 218-07 1 308-07 3.69E-10 4 938-12 5.398-09 3.50E-11 1 05E-'10 8.948-09 2.168-10 2 51E-09 6.68E-12 l.158&6 l.20E-08 5.03E-09 1.09E-07 8.468&9 4.948&7 1 188&7 TEEN thyroid 1.06E-07 8.12E-07 2.30E-06 0.00E+00 2.00E-09 0.00E+00 O.OOE+00 O.OOE+00 0.008+00 O.OOE+00 0.00E+00 0.00E+00 0.008+00 0.008+00 O.OOE+00 0.00E+00 0.00E+00 , 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.008+00 0.008+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.008+00 0.008+00 0.00E+00 0.008+00 0.008+00 0.008+00 0.008+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0~OOE+00 0.00E+00 0.00E+00 kidney 1.06E>>07 8 12E-07 2.30EM6 O.OOE+00 7.89E-10 1.768-06 2.00E-07 O.OOE+00 0~OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.008+00 0.00E+00 2.91E-07 1.28E-05 1.83E-08 3.44E-07 0.00E+00 0.00E+00 O.OOEMO O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.008+00 0.00E+00 0.00E+00 0.00E+00 0.008+00 0.00E+00 0.00E+OQ 1 918&8 7.11E-10 4.42E-09 2.14E-11 1.38E-05 1.38E-08 9.26E-09 8.99E-07 2.7SE-07 7.56E-06 3.70E-07 lung 1.06E-07 8.12E-07 , 2.30E-06 0.00E+00 5.14E-09 0~OOE+00 0.00E+00 1.70E-06 4.32E-06 0'OE+00 O.OOE+00 0~OOE+00 0;OOE+00 0.00E+00 0.00E+00 0.00E+00 0~OOE+00 0'0E+00 0.008+00 O.OOE+00 0.00E+00 0~OOE+00 0.00E+00 0.00E+00 0.008+00 0.00E+00 0.00E+00 O.OOE+00 0~OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0~OOE+00 O.OOE+00 5.14E-10 3 12E-10 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 gi-lli 1.06E-07 8.12E-07 2.30E-06 2.32E-OS 6.05E-07 1~21E-05 1.04E-05 1.16E-06 3.24E-05 4.44E-06 1.348-05 3.66E-05 1.99E-06 S.19E-06 8 92E-06~8.47E-06 5.16E-08 3.11E-05 0.008+00 O.OOE+00 O.OOE+00 0.00E+00 4.41E-06 7.30E-15 8.43E-17 5.24E-05 2.33E-04 3.668-05 7.77E-05 1.13E-04 6.09E-09 8.24E-05 3.328-05 l.1?EM4 3.00E-05 1.27E-04 1.95E-05 4.37E-07 1.088&5 6.088&7 8.?5E-17 2 13E-05 1.76E-05 1.88EW4 5.45E-05 0 0384p

Table 1.7 (4 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 7 Page 127 bone Sb-124 3.&TE&6 Sb-125 2.4&E-06 Te-125m 3.83E-06 Te-127m 9.67E-06 Te-127 1.5&E-07 Te-129m'.63E&5 Te-129 4.4&E-O&'e-131m 2.44E-06 Te-131 2.79'&-Te-132 3.49E-06 I-130 1.03K&6 I-'31 5.85E-06 I-'132 2 79E&7, I-135.01E&6-'I, 134~c.l a.46EWT I-135'6.10E&7's 134 8.37E-05 Cs-136 8.59E-06.Cs-137', 1.12E-04 Cs-138 7.76E-08.Ba-139 , 1.39E-07 Ba-140 2;84E-05 Ba 141.~6 71E&8 Ba-142 2.99EWS L'a-140'.48E-09 Ea-142'.79E-IO Ce-141'.33E&8 Ce-143 2.35E09 Ce-144 6.96E-'7 Pr-143, 1.31E-'08 Pr-144 4.30E-11 Nd-1473&E-'9 W-'187 1.46E&7'p-239 l.76E-'09-liver 7.13E-08 2'.71E-08 1.38E-06 3.43E-06 5.60E-O&,6.05E-06 1.67E-08 l.17E-'06 1.15E-O&2.21EM6 2.9&E-06 8.19E-06 7.30E-OT 3'.41E-06 3.87E-07 1.57E-'06 1.97E-04 3.3&E-05-1.49E-04 1.49E-OT'9.78E-11 3.4&E-'08 5'.01E-11 2'9E-11 l.71E-09';95E-11 8.88E-09 1.71E-06 2'.8&E-07 5.23E-'09 1.76E-11 1.02E-"08 1.19E-OT 1.66E-'.0' body 1.51E-06 5.&OE-07 5.12E&7 l.15E-06 3'.40E-08 2.58E-06 1.09E-08 9.76E-07 8.T2E-09 2, 0&E-06 1.19E-O6 4.40E-06 2.62E-O/1.04E-06 1.39E&7'.82E&7 9.14E&5 2.27E-OS 5.19E&5'.45E-'08 4.05E-09 1 83E-06 2'4E-09 1.84E-09 4.55E-10 1.98E-'l 1.02E-09 1.91E-10 3.74E-O&6.52E-10 2.1&E-12 6.11E-10 4-17E-'08 9.22E-ll TEEN thyroid.8 7&E&9 2.37E-09 1'.07E-06 2.30E-06 1 09EWT 5~26E&6 3.20'&1 76E06-2.15E-'08 2.33E&6 2.43E-04 2.39E-'03 2.46E-'05 4.76E&4 6 45E-06 1'.01E-04 0.00E+00 0.00E+00 0'OE+00 0.00E+00 0.00E+00 O.OOE+00'.OOE+00 0.00E+00, 0.00E+00 0'.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00EWO 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 kidney O.OOE-OO 0.00E+00 O.OQE+00 3.92E-05 6.40E-OT 6.82E-05 1.88E-OT 1.22E-05 1.22E-OT 2.12E-05 4.59E&6 1.41E-05 1.15E-06 5.9&E&6 6.10E-07 2.4&E-06 6.26E-OS 1.84E-05 5.07E-05 1.10E-07 9.22E-ll 1.18E-08 4.65E-11 2'53E-1I'.OOE+00 0.00E+00 4.18E-09 7.67E-10 1.,72E-07 3.04E-09 1.01.E-ll 5.99E-09 0.00E+00 5.21E-10 lung 3 38E-06 2.1&E-06 Q.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 0 OOE+00 O.OOE+00 0.00E+00 0'OOE+00 O.OOE+00 0 OOE+00 0 OOE+00 2.39E-05 2.95E-06 1 97K&5 1.2&EM&6 74E-11 2.34E&8 3.43E-11" 1.99E-ll.0 OOE+00 0 OOE+00 O.OOE+00=0 OOE+00 0 OOE+00 0 OOE+00 O.OOE+00 0.00E+00 0 OOE+00 0.00E+00 gi-lli 7.80E-05 1.93E-05 1.13E-O5 2 41E-05 1.22E-05 6.12E-05 2.45E-07 9 39E-05 2.29E&9 7.00E-05'.29E&6 1.62E-06 3.18E-07 2.5&E-06 5.10E-09 1.74E-06 2.4SE-06 2.72E-06 2.12E-06 6.76E-ll 1.24E-06 4.3&E-05 1.43E-13 9.1&E-20 9.82E-05 2.42E-06 2.54E-05 5.14E-05 1.75E-04 4.31E-05 4.74E-14 3.6&E-05 3.22E-05 2.67E-05

References:

Regulatory Guide 1'.109, Tabl'e E-'2.Dose Factors for Co-5T,, Zn-69m, Br&2, Nb-97;Sb-124 and Sb-125 are from.NUREG-0172." A e S ecific.Radiation Dose Commitment Factors for a One Year Chronic Intake , November, 1.977', Table 3..NOTE" The triti'um dose factor.for bone-is, assumed total body dose-factor.to be equal to the 0384p I'g

Table 1.7 (5 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 7 Page 128~'~~I'~ae t H-3 C-14 Na-24 P-32, Cr.-51'n-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58-Co-60 Ni&3 Ni-65~+,Cu-.64.Zn-65 Zn-69 Zn-69m Br-82 Br-83'r&4 Br-'85-Rb&6 Rb-88-Rb&9 Sr-89 Sr-90 Sr-9l Sr-92: Y-'90'-91m Y-91.Y-'92'.Y-'93 Zr-95'r-97'b-95 Nb-97'o-99 Tc-99m: Tc-101.Ru-103.Ru>>105'u-106 Ag>>110m bone 2.03E&7 l.21E-05 5.80E-06 8.25E-04 0.00E+00 Q.QOE+00 Q.QOE+00 1.15E-05 1.65E&5 O.OQE+00 O.OOE+00 O.OOE+00...5.38E-04 2.22E-06 0.00E+00 1.37E&5 4.38E-08 7.10E-07 0.00E+00 Q.QOE+00 O..QOE+00 O.OOE+00 0.00E+00 O.QOEKO 0'QOE+00 1.32E-O3 1.70E-02 2.40E-05 9.03E&6 4.11E-08 3 82E-10 6.02E-07 3.60E-'09 1.14E-'08'.16E-07'~99E&9 2.25E-08 2.17E-10.0.00E+00 9.23E-'10 1.07E-'09 7'1E&7'.45E&8 l.17E-05'.39E&7 liver 2 03E-07 2.42E-06 5 80E06 3.86E-05'.00E+00 1.07E-'05 3 34E-'07 6 10E-'06, 2 67E-05 4 93E-07 1 80E&6 5 29E&6 2'8E-05 2'09E&7 2'5E-07 3~65E&5 6'3E-QS l.21E&6 0 OOE+00 0'OE+00 Q.QOE+00 Q.OOE+00 6'0E-05 1.90K&7'17E-07 O.QOE+00 O.QOE+00 O.QOE+00 0 OOE+00 O.OQE+00 0.00E+00 0 OQE+00 O.OOE+00 0;OOE+00'.55E-O&

1.01E-09 8.76E-09-3.92E-II.l.33E-'05 1.81E-09 1.12E&9 0'.OOE+00 0;QOE+00 0.00E+00 3.64E-07'body 2.03E-07 2'2E-06 5.80E-06 3.18E-05 8.90E-09 2.85E&6 7;54E-08 1.89E-06 1.33E-05 9.98E-07 5.51E-06 1.56E-05 1.83E-05 1.22E-07 1.48E-07 2.27E-05 5.85E-09 1.43E-07, 7.55E-06 1.71E-07 l.98E-07 9.12E-09 4.12E-05 l.32E-07'.04E-07 3.77E-05 4.31E-03.9.06E-07 3'62E-07 1.10E-09 1.39E-11 1.61E-08 1.03E-10 3.13E-10 2.27E-08 5.96E-10 6.26E-09 1.83E-11 3'.29E-06 3'QOE-'08 1.42E-08 2'.81E-07 2'.34E-08 1.46E-06 2.91E-07'HILD thyroid 2.03E-07 2 42E-06 5.80E-06 O.QQE+00 4.94E-09 O.OOE+00 0.00E+00 O.QOE+00 Q.OQE+00 0.00E+00 O.OOE+00 0.00E+00 O.QOE+00 0.00E+00 0.00E+00 Q.OOE+00 O.OOE+00'Q.OOE+00 O.QOE+00 0 OOE+00 Q.OOE+00'O.OOE+00 O.QOE+00 O.OOE+00 0 OOE+00 Q.QQE+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 O.QOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00K+00 Q.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Q.OOE+00 kidney 2.03E-07 2.42E-06 5.80E&6 O.OOE+00'l.35E-09 3 OOE&6 4.04E-07 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0'OE+00 O.OQE+00 5.92E-07 2.30E-05 3.84E-08 7.03E-07 0.00E+00 O.QOE+00 0.00EKO O.QOE+00 0 OOE+00 O.QOE+00 0.00E+00 O.QOE+00 0.00E+00 O.OOE+00 0.00E+00 0'QE+00 0~OOE+00 O.OOE+00 O.QOE+00 O.QOE+00 3.65E-08 1.45E-09 8.23E-09 4.35E-ll 2.84E-05 2.63E-'08 1'.91E-08 1.84E-06 5.67E-07 1.58E-05 6.78E07 lung 2.03E-07 2.42E-06 5.80E-06 0.00E+00 9 02E-09 O.OOE+00 0.00E+00 3.45E-06 7.74E-06 0.00E+00 0 OOE+00 O.QQE+00 O.OOE+00 O.QOE+00 0.00E+00 O.QOE+00 O.OOE+00 O.OOE+00 O.QOE+00 0.00E+00 O.QQE+00 O.QOE+00 0.00E+00 0.00E+00 O.OOE+00 O.QOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0~OOE+00 0.00E+00 O.OQE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 9'19E-10.5.92E-10 O.OOE+00 0.00EWO 0.00E+00 0.00E+00 gi-lli 2.03E-07 2.42E-06 5.80E-06 2 28E-05 4 72E-07 8 98E-06 4.84E-O5 1 13E-06 2.78E-05 4.04E-06 1 05E-05 2 93E-05 1 94E-"06 2 56E-O5 1 15E-05 6.41E&6 3.99E-06 3.94E-05 0.00E+00 O.QOE+00 0.00E+00 O.QOE+00 4.31E-06 9.32E-09 1.02E-09 5.11E-05 2.29E-04 5 30E&5 l.71E-04 1.17E-04 7'.48E-07 8 02E-05 1.04E-04 1.70E-04 2.66E-05 1.53E-04 1 62E-05 1.21E-05 1.10E-05 1.03E-06 3.56E-09 1~89E&5 4.21E-05 1.82E-04 4.33E-05 0384p

Table 1.7 (6 of 8)INGESTION DOSE FACTORS-DFL (mrem/pCi ingested)RETS Manual Revision 7 Page 129 Sb-124 Sb-125 Te>>125m Te-127m Te-127 Te-129m Te-129 Te<<131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-1.35 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba>>142'a-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nii-147 W-187 Np-239 bone 1.118-05 7 168-06 1.148-05 2.898-05 4.718&7 4.878-05 1.348-07 7-208-06 8.308&8 1.018&5 2.92E-06 l.728&5&008&7 5.928-06 4.19E>>07 1 758&6 2 348&4 2.358'-05 3 27E-04 2 288W7 4.14E-07 8.318&5 2'008&7 8'48'-08 1.018&8 5 248-10 3 978&8 6.998&9 2.08E-06 3.93E-08 1.298-10 2'798-08 4.29E-07 5.258-09 liver 1.44E-07 5'2E-08 3.09E-06 7.78E-06 1.27E-07 1.36E-05 3.74E-08 2 49E-06 2.53E-OS 4'47E-06.5.90E-06 1.73E-05 1.478-06 ,7.32E-06 7.78E-07 3.15E-'06 3.84E-04 6.46E-05 3.13E-04 3.17E-07 2.21E-10 7 28E-08 1.12E-10 6.298-11 3.53E-09 1.67E-10 1.98E-OS 3.79E-06 6.52E-07 1.188-08 3.998-11 2-268-08 2.54E-07 3.77E-10 t body 3.898-06 1.50E-06 1.52E-06 3.43E-06 1.018-07 7.56E-06 3.18E-OS 2.65E-06 2.47E-OS 5'.40E-06 3.048-06 9.838-06 6.768&7'.778-06.3.58E-07 1.498&6 8.108-05 4'188-05 4.628-05 2 018-07 1.20E-08 4.85E-06 6.518-09 4.888-09 1.19E-09 5.23E-11 2 94E-09 5.49E-10 1.118-07 1 958-09 6 498-12 1.758-09 1.148-07 2-658-10 CHILD thyroid 2.458-08 6.63E-09 3.208&6 6.918&6 3.26E-07 1.57E-05 9.56E-08 5.12E-06 6.35E-OS 6.51E-06 6.508-04 5.728&3 6.828&5 (1 36E-03 1.79E-05 2.798-04 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.008+00 O.OOE+00 0.00E+00 Q.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.QOE+00 O.OQE+00 O.QOE+00 0.00E+00 Q.OOE+00 0.00E+00 O.OOE+00 kidney 0.008+00 0.00E+00 O.OOE+00 8.24E-05 1 34E-06 1.43E-04 3.92E-07 2.41E-05 2.51E-07 4.15E-05 8.82E-06 2 84E-05 2.25E-06 1.22E-05 1.19E-06 4.83E-06 1.19E-04 3.44E-05 1.02E-04 2.23E&7 1~93E-10 2 37E-08 9.69E-.ll 5~09E-Il 0.00E+00 O.OOE+00 8.68E-09 1 59E-09 3.61E-07 6-398&9 2 11E-11 1.248-08 O.OOE+00 1.098-09 lung 6.16E-06 3 99E-06 0~OOE+00 0~OOE+00 0 OOE+00 0.00E+00 0.008+00 0.008+00 0 OOE+00 0.00E+00 0.00E+00 0~008+00 0'OE+00 0 OOE+00 0.00E+00 O.OOE+00 4 27E-05 5.13E-06 3 678&5 2 40E-08 1.308-10 4.34E-OS 6.58E-10 3'0E-11 0 OOE+00 0.00E+00 0.00E+00 Q OQE+QQ O.OOE+00 0.00E+00 0.00E+00 0 OOE+00 0'OE+00 0 QOE+00 gi-lli 6.94E-OS 1.71E-05 1.10E-05 2.34E-05 1.84E-05 5.94E-05 8.34E-06 1.01E-04 4.36E-07 4.50E-05 2.76E-06 1.54E-06 1.73E-06 2.95E-06 5 16E-07 2 40E-06 2.07E-06 2.27E-06 1 96E-06 1.46E-07 2.39E-05 4.21E-05 1.14E-07 1~14E-09 9'4E-05 3 31E-Q5 2.478-05 5.55E-05 1.70E-04 4.24E-05 8.59E-OS 3.58E-05 3.57E-05 2 79E-05

References:

Regulatory Guide 1.109, Table E-13.Dose Factors for Co-57, Zn-69m, Br-82, Nb>>97,, Sb-124 and Sb-125 are from NUREG-0172 e S ecific Radiation Dose Commitment Factors for a One Xear Chronic Intake , November, 1977, Table 2.NOTE: The tritium dose factor total body dose factor.for bone is assumed to be equal to the 03849 IM,

Table 1.7 (7 of 8)INGESTION DOSE FACTORS-DFL (mremlpCi ingested)RETS Nanual Revision T Page 130 K-3 C-14'a-24 P-32, Cr-51 Na-54.Ha-56 Fe-55 Fe-59 o Co-57 Co-58 Co-60.Ni-63 Ni-65:<Cu-64 Zn-65 Zn-69 Zn-69m'r-82..

Br-83 Br-84 Br-85.Rb-86.Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92.Y-90'-91m.

Y-'91, Y-92'-Y-'93'r-95 Zr-97'b-95 Nb-97 Mo-99-Tc-99m Tc-101 Ru-103 RQ-105 Ru-106 Ag-110m bone 3.08E-07 2.37E-05 1 01E&5 1 TOE&3 O.QOE+00 0.00E+00 Q.QOE+00 1.39E-OS 3.08E-OS 0.00E+00 O.OOE+00 Q.QOE+00 6 34E-04 4'.70E-06.Q.OOE+00 1.84E-05 9.33E-08 1 50E-06: 0.00E+00-Q.OOE+00 O.QQE+00 O.QOE+00 0'.QOE+00 0 OOE+00 0 OOE+00 2 51E-03 1..85E-02 5 OQE-05 1.92E-05 8.69E-OS 8.10E-10 1.13E-'06:

7.65E-09 2 43E-08 2'.06E-07 1 48E-08 4.20E-08 4.59E-10 O.OOE+00 1 92E-09 2.27E-09 1.48E-06.l.36E-'07 2.41E-05 9.96E-07 INFANT liver t, body thyroid 3.08E-07 3.08E-07 3.08E-07 5'6E-06 ST 06E-06 5'6E-06 1.01E&5 1.01E-05 1.01E-05 1.00E-04 6.59E-O5 O.OOE+00 0.00E+00 1 41E-08 9.20E-09 1.99E&5 4 51E-06 O.OOE+00 8.18E&7 1 41E&7 O.OOE+00 8~98E-06 2'0E&6 O.OOE+00 5.38E&5 2.12E&5 0.00E+00 1.15K&6 1 87E-06=0.00E+00 3.60E-06 8.98E-06 O.OOE+00 1.08EWS 2'S5E-05 O.OOE+00.,3:92EWS0E-05 O.OQE+00 5'32E&7'.42E-'07 O.OOE+00 6.09E&7'2.82E-OT O.QOE+00 6.31E-05'91E-05 O.QOE+00 1.68E'07 1.25E-08 O.OQE+00 3.06EM6 2" 79E-07'O.OOE+00 0 OOE+00-1.27E-05 O.QOE+00 0.00E+00 3 63E-'07 O-OOE+00 O.QOE+00 3.82E-OT Q.OOOO O.OOE+00 1'>>94E-08 Q.OQE+00'.70E-04 8 40E-05, O.OOE+00 4.98E-07 2i73E&7 O.QOE+QQ 2.86E&7'" 97E-07 O.QOE+00 0.00E+00 7'20E-05 0.00E+00 0.00E+00 4.71E&3 O.OOE+00 0.00E+00 1.81E-'6 O.OOE+00 O.OQE+00 7'13E&7'.00E+00 0.00E+00 2'33E-09 Q.OOE+00 0.00E+00 2 76E-11 O.OOE+00 O.OOE+00 3.01E-'08 O.OQE+00 0.00E+00" 2.15E-10 O.OOE+00 0.00E+00 6.62E-10 Q.OOE+00 5.02E&8 3.56E-'08 O.OOE+00 2.54E&9 1 16E-09 O'OOE+00 1.73E-08 1 OQE-08'.QQE+00 9.79E-11 3'53E-'1;1 O.OOE+00 3.40E-05-6.63E&6 O'OOE+00 3.96EW9'.10E&8 O.OOE+00 2 86EW9 2.83K&8 0 QOE+00 0 OOE+00 4 95E&7 O.QOE+00 0.00E+00'.58E&8 0.00E+00 O.OQE+00 3 01K&6 Q.QOE+QO 7.27E-07 4.81E-07 O.OOE+00 kidney 3.08E-07 5 06E&6 1.01.E-05 O.OQE+00 2 01E&9 4.41.E-06 7.03E&7 O.OOE+00 O.OOE+00'O.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.03E-06 3.06E-05 6.98E-08'1.24E-06 0.00E+00 0 OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.QQEWQ O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OQE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 5.41E-O8 2.56E-'09 l.24E-08 7.65E-ll 5.08E-05 4.26E-08 3 40E-08 3 08E-06 1.00E-06 2 85E-05 1 04E-06 lung 3.08E-07 5.06E-06'1.01E-05 0 OOE+00 1.79E>>OS 0 OOE+00 O.OOE+00 4.39E-06 1 59E-05 O.OOE+00 0'QE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 Q.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 Q.OOE+00 0.00E+00 0.00E+00 Q.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0 AQE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 2.07E&9 1.56E-O9" 0.00E+00 0.OOE+00 O.OOE+00 O.OQE+00 gi-ll.i 3.08E-07 5.06E-06 1.01E-05 2.30E-05 4.11E-07 7 31E-06 T.43E-05 1.14E-06 2 57E-05 3 92E-06 8.97E-06 2 57E-05 1.95E-06 4.05E-05 1.25E-05 5'3E-05 1.37E-05 4.24E-05 O.OOE+00 O.OQE+00 O.OOE+00 O.OQE+00 4.35E-.06.4.85K-OT 9.74E-08 5.16E-OS 2.31E-04 5.92E-05 2.0TE-04" 1.20E-04 2 70E-06 8.10E-05 1.46E-04-1.92E-04 2-SOE&5 1.62E-04 1.46E-05 3.09E-05 1 12E-05 1 15E-06 4.86E-07 1.80E-05 5.41E-'05 1.83E-O4.3.77E-05 0384p

Table.1.7 (8 of 8)INGESTION DOSE FACTORS-DFL'(mremlpCi ingested)RETS Manual Revision 7 Page 131 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te<<129 Te-131m Te-131.Te-132: I-130 1-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136.Cs-137's>>138.

Ba>>139 Ba-140'a-141 Ba-142 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143" Pr-144 Nd-147'-187 Np-239'one 2.14E-05 l.23E&5 2 33E-05 5'.85E&5 1'.OOE&6 1.00E-04 2.84E-07 1.52E-05 1.76E-07 2 OSEW5 6.00E-06 3.59E-OS 1.66E&6 l.25E-'05 8 69E-07'.64E-06 3.77E-04 4.59E-05 5.22E-04 4.81E&7'.81E-07 1.71E&4 4.25E-07 1.84E-07 2 11E&8'.10E-09 7;87E-OS, 1.48E-OS 2;.98E&6, 8;13E-08.74E-10 5'.53E&8 9'.03E-07 1.11E&8 liver 3 15E-07 1.19E-07 7.79E&6 1 94E&5 3.35E&7 3.43EWS 9.79E-OS 6.12E-06 6.50EWS 1 03E&5 1 32K&5 4.23E&5 3.37E&6 1.82E&5 1 78E&6 7.24E-06 7'.03E-04 1.35E-04 6~11E&4-7.82E-07 5.84E-10 l.71E&7 2.91E-'0 1.53E-10 8.32E&9 4.04E-10 4.80EOS 9.82E&6 1 22E&6 3.04E-OS, 1 06E-10 5'8E-08 6.28E-07 9.93E-10'body 6.63E&6 2 53E-06 3.15E-06 7.08E-06 2.15E&7 1 54E&5 6.63E-OS 5 05E&6 4.94E-OS 9 61E-06 5.30E-06 1~86E&5 1.20E-.06 5.33E-06 6.33E&7 2.64E-06 7.10E-05 5'4E-05 4.33E-05 3.79E&7 2.55E&8 8.81E&6 1.34E&8 9.06E-09 2.14E&9 9.67E-ll 5.65E&9 l.12E&9.l.67E-07'.03E-09 1.38E-ll 3.48E-09 2.17E&7 5.61E-10 INFANT thyroid 5 68E-08 1 54E-08 7.84E-06 1 69E-05 8 14E-07 3 84E&5 2.38E-07 l.24E&5 1.57E&7 1>>52E-05 1.48E-03 1>>39E-02 1 58E-04 3 31E-03 4 15E-05 6 49E-04 0 OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 0 DOE+00 0.00E+00 O.OOE+00 0 OOE+00 0.00E+00 O.DOE+00 0.00E+00 0 OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 kidney 0 OOE+00 O.OOE+00 0 OOE+00 1 44E-04 2 44E-06 2.50E-'04 7.07E-07 4.21E-05 4.50E-07 6 44E-05 1.45E-05 4.94E-05 3 76E-06 2'.14E-05 1'99E-06 8.07E-06 1 81E-04 5 38E-05 1 64E-04.3'90E-07 3 51E<<10 4 06E-08 1 75E-10 8.81K-'ll 0'OE+00 0.00E+00 1.48E-08 2'86E&9 4.93E-07'.13E-08 3.84E>>'l 2.19E-OS 0.00E+00 l.98E&9 lung 1 34E-05 7.72E-06 0 OOE+00 0 OOE+00 0 DOE+00 0 OOE+00 O.DOE+00 0.00E+00 O.OOE+00 0.00E+00 0 OOE+00 0 OOE+00 D.OOE+00 0 OOE+00 O.OOE+00 O.OOE+00 7.42E-05 1 10E-05 6 64E-05 6.09E-OS 3 54E-10 1 05E-07 1 77E-10 9'26E-ll O.DOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0'OE+00 O.OOE+00 0.00E+00 gi-lli 6.60E-05 1 64E-05 1.11E-05 2 36E-05 2.10E-05 5.97E-05 2 27E-05 1.03E-04 7'1K-06 3.81E-05 2 83E-06 1.51E-06 2 73E-06 3.08E-06 1~84E-06 2 62E-06 1.91E-06 2 05E-06 1 91E-06 1 25E-06 5 58E-05 , 4'20E-05 5 19E-06 7.59E&7 9.77E-05 6.86E-05 2.48E-05 5.73E-05 1 71E-04 4.29E>>05 4.93E-06 3.60E-05 3 69E-05 2.87E-05

References:

Regulatory Guide 1.109,.Table E-'4.Dose;Factors for.Co<<57, Zn-69m,.Br-82, Nb-97;, Sb-124 and Sb-125 are from NURE~172, A e S ecific Radiation Dose Commitment Factors for a One Year Chroni'c Intake ,.November, 1977Table l.NOTE:: The.tritium dose factor'or;-

bone is;assumed total, body dose factor.to be equal to the 03849

RETS Manual Revision 7 132 Page Table 1.8 (1 of 3)RADIONUCLIDE

'DECAY AND STABLE ELEMENT TRANSFER DATA8-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56.Fe-55 Fe-59 Co-5?Co-58 Co-60 Ni-63.Ni&5 Cu-64 Zn-65-Zn-69m Zn&9 Br-82.Be-&3 Br-84 Br-85 Rb&6 Rb-88, Rb&9 Sr89 Sr-90 Sr-91'r-92 Y-90 Y-91m: Y-91 Y-92.Y-93: Zr-95'Zr-97'b-95 Nb-97-'o-99'c-99m'-

Tc-101 Ru-103 Ru-105'LL-106 Ag-110m Half-Life (minutes)6.46E+06 3.018+09 9 008+02 2.06E+04 3.99E+04 4.508&5 1.558+02 1.428+06 6.43E+04 3.908+OS 1.028&5 2.77E+06 5.278+07 1.51E+02, 7'.62E+02'.52E+05 8.268+02 5.56E+01 2.12E+03 1.43E+OZ 3.18E+01 2.878+00 2.69E+04" l.788+01.1.54E+OL 7.28E+04 1.50E+07 5.70E+02 l.638+02.3.858+03 4.97E+Ol 8.43E+04 2'.128+02.

6.06E+02'.228+04 1.01E+03 5.05E+04.7'.21E+01 3;96E+03 3.618+OR 1 42E+01'.5;67E+04 2.66E+02 5'0E+05 3.60E+05 (Lls)1.79E-09 3.84E-12 1.28E-05 5.61E-07 2.90E-07 2.57E-08 7.458-05 8 13E-09 1 80E-07 2.968-0&1.13E-07 4.178-09 2 198-10 7.658&5'528-05 3 28E-08 1.40E-05 2.08E-04 5.45E-06 8 088&5 3 63E-04 4 028-43 4.298&7'.498-04'.508&

1 598&70E-'10 2 038&5 7 098-05 3 00E-06 2'32E-04 1.37E-07 5.458-05 1 918&5 L.25E-07'.148-05 2.29E-07 1.608-04 2;92E-06 3 208-05 8 13E-04-2 048-07, 4.34E-05 2 LSE&8 3 21E-08 Biv 4.808+00 5.50E+00 5.20E-02 1.10E+00 2.50E-O4 2.908-02 2.90E-02 6.60E-04 6.60804.9.408-03 9.40E-03 9.408W3 1.90E-02 1~90E-02 l.20E-OL 4.OOEWL 4.008-01 4.00E-OL 7.60E-Ol'.608-'01 7.60EWL 7.60E-01 1.308&1 1.30E-OL 1.30E-OL 1.70E-OR 1.708-02 1'.708-02 l.70E-02 2.60E-03 2.60E-03 2.60E-03 2'608-03 2.608-03 1'.708-04 l.708-04 9.40E-03 9.4OE-O3 1.208-01 2.508-01 2;508-01 5.OOE-02.5.008-02;:

5.00E-OZ 1.50E-OL Fmi (cow)1.00E-02 1.20E-02 4.00E-02 2.50E-02 2.20E-03 2.SOE-'04 2.508-04 l.20E-03 1.20E-03 1 008&3 1.008-03 1 008&3 6.708-03 6.708&3 1 408&2 3.908-02 3.90E-02 3.90E-02 5.00E-02 5.00E-OR 5.008-02 5 00E-02 3 OOE-02 3 008-02 3 008&2 1.408-03 1.408-03 1.408-03 1 408&3 1.008-05 1.00E-05 1.00E-05 1 008-OS 1'008&5 5.008-06 5.008-06 2.508-03 2.508M3 7.508-03.2.508-02 2.508&2'.008-06-1.008-06 1.008&6 5'0E-02 Fmi (goat)1.70E-Ol 1.00EWL 4.00E-02 2.50E-OL Z.20E-03 2.50E-04 2.50E-04 1.308-04 1.30E-04 1.008-03 1.00E-03 1.00E-03 6.70E-03 6.708-0a'.30E-02 3.908-02 3.90E-02 3.90E-02.5.00E-02 5.008-02 5~OOE-02 5.b0802.3.008-02 3.008-02 3'.00E-02 l.40E-02, 1.40E-02 1.40E-02 1.408-02 1.00E-OS 1.00E-OS 1.00E-O5 1.00E-05 1.00E-05 5.00E-06 5.00E-06 2.50E-03'.50E-03 7.50E-03 2.50E-02 2.50E-02 1.00E-06 1.00E-06 1.00E-06-, 5 00E-02$Ffi (beef)1.20E>>02 3 10E-02 3.00E-02 4.608-02 2.40E-03 8 OOE-04 8'OE-04 1.208-02 1.20E-02 1.30E-OR 1.30E-02 1.30E-OZ~5.308-02 5.30E-02 9.708W4 3.008-02 3.00E-02 3.008-02 2.60E-02 R.608-02 2.60E-02 2.60E-02 3 LOE&2 3.10E-02 3.10E-02 6.00E-04 6.00E-04 6.00E-04 6.008&4 4.60E-03 4.60E-03 4.60E-03 4.60E-03 4.60E-03 3.40E-02 3.40E-OR 2.80E-01 2.80E-OL 1.10E-03 4.00E<<01 4.00E-OL 4.00E-OL 4.00E-OL 4.00E-OL 1.70E-02'0 0384p

RETS'anual Revision 7 Page 133 Table 1.8 (2 of 3)RADIONUCLIDE DECAX AND STABLE ELEMENT TRANSFER DATA Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te>>131m Te-131 Te-132 r-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 Ba-142 La-140 La-142, Ce-141 C0-143 Ce-144 Pr-143 Pr>>144 Nd-147'-187 Np-239 Ar-41 Kr-83m Kr-85m Kr-85 Kr-87'r-88 Kr-89 Kr-90 Xe-131m Xe-133m.Half-Life (minutes)8 67E+04 1.46E+06 8.35E+04 1.57E+05 5.61E+02 4.84E+04 6.96E+01 1.80E+03 2.50E+01 4.69E+03 7.42E+02 1 16E+04 1.38E+02 1 25E+03 5.26E+Ol.3.97E+02 1;08E+06 1 90E+04 1.59E+07 3.22E+01 8 31E+Ol 1.84E+04 1.83E+Ol 1,07E+Ol 2 41E+03 9.54E+Ol 4.68E+04 1.98E+034.09E+05 1.95E+04 1.73E+Ol 1.58E+04 1.43E+03'.39E+03 1.10E&2 1.10E+02 2.69E+02 5.64E+06 7'.63E+01.1.70E+02.3.16E+00 5.39E-01 1.70E+04 3.15E+03 (1/s)1.33E-07 7.91E-09 1.38E-07 7.36E-08 2.06E-05 2.39E-07 1.66E-04 6.42E-06 4.62E-04 2.46E&6 1.56E-05 9.96E-07 8 37E-05 9.24E-06 2.20E-04 2.91E-05 1.06E-08 6.08E-07 7.26E-10 3.59E-04 l.39E-.04 6.28E-07 6.31E-04 1 08E-03 4.79E-O6 1.21E-04 2.47E-07 5.83E-06 2.82E-08 5.92E-07 6.68E-04 7.31E-07 8.08E-06 3.4IE-06 1.05E-04 1.05E-04 4.29E-05 2.05E-09 1.51E-04 6.79E-05'.66E-03, 2'14E-02 6.79E-07 3'67E-O6 Biv N/A N/A 1.30E+00 1.30E+00 1.30E+00 1 30E+00 1.30E+00 1.30E+00 1.30E+00 1.30E+00 2.OOE-02.2.00E-02 2.00E-O2 2.00E-02 2 OOE-02 2.00E-02.1.00E-02 1.00E-02 1.00E-02 1.00E-02 5.00E-03 5.00E-03 5 OOE-03 5.00E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2.50E-03 2 50E-03 2.40E-03 1.80E-02 2.50E-03 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A Fmi (cow)1.50E-03 1.50E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1 OQE-03 1.00E-03 1.20E-02 1.20E-02 1.20E-O2 1.20E-02 l.20E-02.1.20E-02 8.00E-03 8.00E-03 8.00E-'03 8.00E-03 4.00E-04 4.00E-04 4.00E-04 4.00E-04 5.00E-06 5.00E-06 1.00E-04 1.00E-04 1.00E-04 5.00E-06 5.00E-06 5.00E-06 5.00E-04 5.00E-06 N/A N/A N/A N/A N/A N/A N/A.N/A N/A N/A Fmi (goat)1.50E-03 1.50E-03 1.00E-Q3 1.00E-03 1.00E-03 1.00E-03 1.0QE-03 1.00E-03 1.00E-03 1.00E-03 4.30E-01 4 30E-Ol 4.30E-01 4 30E-GI 4.30E-01 4.30E-01 3 OQE-Ol 3.00E-01 3.00E-01 3.00E-Ol 4.00E-04 4.'OQE-04 4 QQE-04 4 OOE-04 5'QE-06 5 QQE-06 1 QQE-04 1 QQE-04 1 OOE-04 5.00E-06 5 QQE-06 5 OQE-06 5.QOE-04-5.00E-06 N/A N/A N/A N/A NIA N/A NIA N/A.NIA.N/A (beef)NIA N/A 7.70E-Q2 7.70E-02 7.70E-02 7.70E-02 7.7QE-02 7.70E-02 7.70E-02 7.70E-02 2.90E-03 2.90E-03 2 90E-Q3 2.90E-03 2.90E-03 2.90E-03 1.50E&2 1.50EW2 1.50E-02 1.50E&2 3.20E-03 3.20E-03 3.20E-03 3.20E-03 2.00E-04 2.00E-04 l.20E&3 1.20E-03 1.20E-03 4.70E-03 4.70E-Q3 3.30E-03 1.30E-03 2.00E-04 N/A N/A N/A N/A N/A N/A N/A N/A NIA N/A 0384p RETS Manual Revision 7 Page 134 Table 1.8 (3 of 3)RADZONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA~Half-Life (minutes)Biv Fmi Fmi (1/s)(cow)(goat)Ffi (beef)Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 7 55E+03 1.54E+01 5.47E+02 3.&3E+00 1.41E+Ol 1.53E-06 7.50E-04 2 11E-05 3 02E-03 8'9E-04 N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A'/A N/A N/A N/A N/A N/A N/A

References:

Half lives for all nuclides: DOE-TZC-11026,"Radioactive Decay Data Tables-A handbook of Decay Data for Application to Radiation Dosimetry and Radiological Assessment," D.C.Kocher, 1981.Transfer factors for Sb-isotopes are from ORNL 4992,"Met6odology for Calculating Radiation'Doses from Radioactivity Released to the Environment," March 1976, Table 2-7.V~Cow-milk transfer factors for Zodine, Strontium, and Cesium nuclides are.from NUREG/CR-1004, Table 3 17.Goatmilk transfer factors for Zodine nuclides are from NUREG/CR-1004, Table 3.17.Beef transfer factors for Zron, Copper, Molybdenum, and Cesium nuclides are.from NUREG/CR-1004, Table 3.18.All other nuclides'ransfer factors are from Regulatory Guide 1.109, Tables E-l and E-2.

Table 1.9 (1 of 2)DOSE CALCULATION FACTORS RETS Manual Revision 7 Page 135 Factor BRa (infant)BRa (child)BRa (teen)BRa (adult)fg.fL fp.fs 8 K M'(co%)Qf (goat)r tb tcb tcsf.te.tep, tesf tfm, thc ts tsv U~(infant)Uam (child)U~.(teen)U.(adult)Uap (infant)U'child)Uap (teen)Uap.(adult)Value Units ms/year ms/year ms/year ms/year 1400 5500 8000 8100 1 1 1 0 9"g/ms 0.072, L/kg-hr 40 kg/m>240 kg/m~64 kg/day 08 kg/day 0.47'.73E+08 seconds (l5 years)7".78E+06 seconds (90'ays")1.56K+07'econds (180 days)5'.18E+06 seconds (60 days)2.59E+06 seconds, (30 days)7'.78E+06; seconds (90'ays)8'.64E+04 seconds (1 day)8.64E+04 seconds (1 day)1.12E+06 seconds(13 days)2.38E+07'econds (275 days)0 kg/year 41, kg/year 65 kg/year: 110'g/year.

330 L/year 330 L/year.400 L/year, 310 L/year Reference.

ICRP 23 ICRP 23 ICRP 23 ICRP 23 TVA Assumption R.G.1.109 (Table E-15)'VA Assumption TVA Assumption TVA Value R.G.1.109 (Section 2.C.)R.G.1.109 (Section 2.C.)R.G.1.109 (Table E-15)NUREG/CR-1004 (Sect.3.4)NUREG/CR~1004 (Sect.3.4)NUREG/CR-1004 (Sect.3.2)R.G.1.109 (Table E-15)SQN FSAR Section 11.3.9.1 SQN FSAR Section 11.3.9.1 R.4 1.109 (Table E-15)R'.G.1.109 (Table E-15)R..G.1.109 (Table E-15)SQN FSAR Section 11.3-9.1 NUREG/CR-1004, Table 3.40 NUREG/CR-1004, Table 3.40 SQN FSAR Section 11.3.9.1 R-G.1.109 (Table E-5)R.G-1.109 (Table E-5)R.G.1.109 (Table E-5)R..G..1.109 (Table E-5)R..G;1.109 (Table E-5)-R.G'.1.109 (Table E-5)R.G.1.109'(Table E-5)R'.G.1.109 (Table E-5)0384p iFactor Table 1.9 (2 of 2)DOSE CALCULATION FACTORS Value Uni ts Reference RETS Manual Revision 7 Page 136 Ufa(infant)

Uf a(child)Ufa(teen)Ufa(adult)

UFL (infant}UFL'a (child)UFI (teen)UFL (adult)USa (infant)US~.(child)USa (teen)USa (adult)Uwa(infant)

Uwa(child)

Uwa(teen)Uwa(adult)

W-Yf T,~sf<sv Xw (iodines).+(particulates) 0 6.9 16 21 0 26 42.64 0 520 630 520 330 510 510'30 0 3 1.85 1.18.0.64 0 57 kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year kg/year.kg/year kg/year kg/year L/year L/year L/year L/year none'kg/m>kg/m>.kg/m>kg/m>7'1K-07, sec>(15 4 d half'-life) 5.21E-07 sec>(10.4 d half-life)

R.G..1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E<<5)R., G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1..109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5).R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G 1.109~(Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5)R.G.1.109 (Table E-5).R.G.1.109 (Table E-5)R.G., 1.109 (Table A-2)NUREG/CR-1004 (Table 3.4)NUREG/CR-1004 (Table 3.3).NUREG/CR-1004 (Table 3.3)NUREG/CR-1004 (Table 3.4)(value selected is for non-leafy vegetables)

NUREG/CR-1004 (Table 3.10)NUREG/CR-1004 (Table 3.10}0384p , I' Table 1.10 (1 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 7 Page 137 8-3 C-14 Na-24 P-32 Cr-Sl Hn-54" Mn-56.Fe-55 Fe-59 Co-57'o-58 Co-60 Ni&3 Ni-65 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb>>86 Rb-88'h-89 Sr&9 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-9L Y-'92.Y-'93.Zr-95'r.-97 Nb-95 Nb-97 Mo-99 Tc-99m Tc-101.Ru-103 Ru-105 Ru-106 Ag-110m bone 1.58E-07 2.27E-06 1.28E-06 l.658&4 0 QOE+00 O.OQE+00 0.008+00 3.07E-06 L.47E-06 O.OOE+00 O.OOE+00 0 OOE+00 5.40E-05 1.92E-10 Q.OQE+00 4 05E-06 4.238-12 1.028-09 0 OOE+00 0.008+00 0.00E+00 0.00E+00'OOE+00 0 OOE+00 0.008+00 3.80E-05.1 24E-02 7 74E-09 8.438-10-2 618-07 3 26E-Ll 5.78E-05 1.29E-'09 1 188-08 1.348&5 1>>218-08 1.768&6 2.78E-ll.0.00E+00 1 298-13 5.22E-IS'.91E-07 9.88E-11.8 64E-06 1.358&6 liver 1.58E-OT 4.26E>>07 1~28E-06 9.64E-06 0.008+00 4 95E-06 1.55E-IO 2 L2E&6 3.47E-06 8.65E-08 1.988-07 1.44E-06 3 93E-06=2 62E-11 1.838-10 1 29E-05 8 14E-12 2 458-09 0.00E+00 0.008+00 0 QOE+00 0.008+00 1 69E-05 4'84E-08 3 20E-08 0 008+00 0 OOE+00 Q.QOE+00 0.00E+00 0.00E+00 0 QOE+00 0.00E+00 O..OOE+00 0.00E+00 4 3086 2.458-09 9.77E-07 7.03E-12'.51E-OS 3.648-13 7.52E-15'.00E+00 O.QOE+QQ 0.008+00 L.258-06 t body 1.58E-07 4.26E-07 1~28E-06 6'6E-06 1.25E-08 7.87E-07 2.29E>>11 4.93E-07 1.32E-06 8 39E-08 2 S98-Q7 1.858-06 1.818&6 1 148-11 7.69E-11 5.828&6 5.65E-13 2.24E-10 1.698-06 3.018&8 3 9LE&8 1.608-09 7'378-06 2.4LE&8'2 128-08 1.09E-06 7.62E-04 3 13E-IO 3 64E-11 7.01E-09 1 278-12 1.55E-06 3.77E-LL 3 26E-LQ 2 9LE&6 l.138&9 5.268&7 2.56E-'12 2.878&9 4.63E-12.7".38E-I.4 8.23E-08 3.898-1L 1~098&6 7.43E-07'DULT thyroid 1.58E-OT 4.26E-07 1.28E-06 0.008+00 7.44E-09 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 0.008+00 Q.OQE+QQ 0.00E+00 O.OOE+00 0.OOE+00'.008+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00, O.OOE+00 O.OOE+00 0.00E+00 0.008+00 0.008+00.0.008+00'OOE+00 O.OOE+00 0.008+00 0.00E+00 0.00E+00 O.OOE+00 0.008+00 O.OOE+00 0.008+00 0 008+00 O.OOE+00 0.008+00'.OOE+QQ 0.008+00 0.008+00 0.008+00 0.00E+00 Q.QOE+00-0.008+00 0.008+00 kidney 1.58E-07 4.268&7 1.28EW6 Q.QOE+00 2'.85E-09 1.23E-06 1.638-10 0.00E+00 0 OOE+00 0.008+00 O.QQE+OQ 0 008+00 0.00E+00 O.OOE+00 5.78E-10 8.62E-06 5 278-12 1.488-09 0 008+00 0 OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OQE+00 0.00E+00 0.00E+00 O.QOE+00 0 OOE+00 0.00E+00 0 OOE+00 O.OOE+00 0.008+00 0.00E+00 6 778-06 3 71E-09 9.678-07 8-18E-12 3.64E-08 5.52E-12 1..35E-13 7.29E-07 1'<<27E-10 1.67E-05 2.46E-06 lung 1.588&7 4.26E-07 1.28E-06 O.OOE+00 1.80E-06 1.75E-04 1.18E-06 9.0LE&6 1.27E-04 4.628-05 1 16E-04 7~46EW4-2;.23E-05 T.OQE-07 8.48E-07 1.08E-04 L.LSE-07 2.388&6 O.OOE+00 O.OOE+00 O.OOE+00 0~OOE+00 O.OOE+00 0.OOE+00'.008+00 1.75E-04 1.20E-03 4.568-06 2 06E>>06 2.12E-05 2.40E-07 2.138-04 1.968-06 6.06E-06 2.21E-04 9.848-06 6.31E-05 3.OOE-07'.14E-OS 9.558&8 4.998&8-6.31E-05 1.37E-06 1.178-03 5.79E-04 gi-lli 1.58E-OT 4.26E-07 1.28E-06 1.08E-05 4.15E-07 9.678-06 2.53E-06 7.54E-07 2.358-05 3.93E-06 1.338-05 3.S6E-OS 1.678&6 1.54EW6 6.12E-06 6.6&E-06 2.04E-09 1.71E-05 1.30E-06 2.90E-08 2.05E-13 0.00E+00 2.08E-06 4.18E 19 1~16E-21 4.37E-05 9.02E-05 2.398-05 5.38E-06 6.32E-05 1.66E-10 4.81E-05 9.I.98-06 5.278-05 1.88E-05 6.54E-05 1.30E>>05 3'.028-08 3'.108-05 5.20E-07.1.368-21 1.388-05 6.028-06 1.14E>>04 3.788-05 0384p

RETS Manual Revision 7 Page 138:0"~Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m.Te-131 Te-132 I>>130 I-131 I-132 I-L33 I-134 I-135 Cs-134 Cs-136.Cs.-137 Cs-138 Ba-L39 Ba-140 Ba-141 Ba-142 La-140 La-142.Ce-141 Ce-143 Ce-144 Pr-143.Pr-144.Nd-147 M-L87 Np-239 bone 3'0E-06 6.67E-06 4.27E-07 1.58E-06 1.758-10 1 22E-06 6.22E-L2 8.74E-09 1 39E-12 3.25E-OS 5 728-07 3'5E-06 1.45E-07 1.088-06 8.05E-OS 3.35E-07 4.668-05 4.88E-06 5.9&E-05 4.14E-08 1..17E-10 4.888-06 1.258-.11 3'9E-1230E-O&.

8 54E>>LL 2.49E-06 2.33E-08 4 298-04" 1 178-06 3.76E-L2 6 59E-07 1 06E-09 2'.87E-OS liver 7.36E-OS 7.44E-08 1.9&E-07 7.218&7 8.03E-11 5.848&7 2.998-12.5 458&9 7.44E-13 2.698&8 1.688&6 4.478&6 4 078&7 1.858-06 2.168&7 8.73E-07 1.068&4 1.838&5, 7.768-05 7.768&8 8.32E-14 6 138&9 9.418-15'38E-15 2;17E-08 3 88E-11 1.69E-06 1 728-08 1 79E-04 4 698&7 1.56E-12 7.62E-07 8.85E-10 2.82E-09 ADULT t body thyroid 1.558-06 9.448&9 1.58E-06 6.75E-09 5'4E-08 L.31807 1.96E-07 4.118-07 3.87E-11 1.32E-10 1 988-07 4.30E-07 1 55E-L2 4.S7E-12 3 638-09 6.8&EW9 4.49E-13 1 17E-12 2.028-'8 2.378-08 6 60E-07 1.428-04 2.568-06 1 498-03 1.45E-07 1.438-05 5.65E-07 2.69E-04 7.69E-OS 3.738-06 3'21E-07 5'.60E-05 9 lOE-05 O.OOE+00 1 38E-05, 0.00E+00 5.358&5 0.00E+00 4.05E-OS O.OOE+00 3.42E-12 O.OOE+00 3 21E-07 0 OOE+00 4.208-13 O.OOE+00 2.078-13 O.OOE+00 5'38&9 O.OOE+00 9.658-'2 0 OOE+00 1.9LEM7 O.OOE+00 1~918-09 O.OOE+00 2;308-05 O.OOE+00 5'.SOE-08 0.008+00 1 918-13 0.008+00 4.568-08 O.OOE+00 3.10E-LO 0.008+00 1.55E-09 O.OOE+00 kidney O.OOE+00 0.00E+00 1.55E-Q6 5.72E-06 6.378-10 4.578-06 2.348'-ll 3.868-08 5.468-12 L.828&7 2.6LE&6 7.668-06 6.488-07 3 238&6 3;448-07 1 398&6 3.598-05 1.078&5 2.788&5 6.008-08 7.78E-14 2.098&9 8.75E-'15 2.86E-L'5 0.00E+00 O.OOE+00 7.83E-07 7.608-09 1.068-04 2.70E-07'.81E-L3 4.45E-07'.00E+00 8.75E-09 Table 1.10 (2 of 8)INHALATION DOSE FACTORS-DFA (mremlpCi inhaled)lung 3.10E-04 2.18E-04.3.928&5 1.20E-04 8.14E-07 1.45E-04 2.42E-07 1.82E-05 l.74E-07 3.60E-05 O.OOE+00 O.OOE+00 0;OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 1.22E-05 1.50E-06 9.40E-06 6.07E-09 4.708-07 1.59E-04 2.428-07 1.49E-07 1.70E-05 7 91E-07 4.52E-05 9.97E-06 9.728-04 3 51E-05 1.27E-07 2.76E-05 3.63E-'06 4 70E-06 gi-l.li 5 OSE-05 1.26E-05 8.838&6 1.87E-05 7.17E-06 4.79E-05 1.96E-08 6.95E-05 2.30E-09 6.37E-05 9.61E-07 7.85E-07 5.08E-OS 1.118-06 1.268-10 6.56E-07 1.30E-06 1.46E-06 1.05E-06 2.338-13 1.12E-07 2.73E-05 1.45E-17'.96E-26 5.73E-05 2 64E-07'.50E-05 2.83E-05 1.02E-04 2.50E-05 2.69E-18 2.16E-05 1.94E-05 1.49E-05

Reference:

Regulatory.

Guide 1 109~Table 8-7..Dose Factors, for Co-57,.Zn-69m, Br-&2,'b-97, Sb-124 and Sb-125 are from NUREG-0172.

A e S ecific Radiation Dose Commitment Factors for a..One Year Chronic Intake November 1977, Table 8.NOTE: The.tritium dose factor'or bone.is assumed total'ody dose factor..to be equaL to the'0384p

Table 1.10 (3 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 7~Page 139 H-3 C-14 Na-24 P-32.Cr-51 Ma-54 Ma-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni&5 Cu-64 Zn-65'n&9 Zn-69m Br-82 Br&3 Br-84-Br-85 Rb&6.Rb-88 R~9 Sr-89 Sr-90 Sr-91 Sr-92'-90 Y-91m Y-9L Y-92 Y-93 Zr-95'r-97'b-95 Nb-97 Mo-99.-TcŽ99m-Tc-10L Ru-103'Q-105 Ru-106 Ag-l.10m bone 1.59E-07 3.25E-06 1.72E-06 2.36E-04 0.00E+00 Q.OOE+00 0.00E+00 4.18E-06 1 99E-06 0.00E+00 0.00E+00 0.00E+00 7.25E-OS 2.73E-10 O.OOE+00 4.82E-06 6.04E-12 1.44E-09 O.OOE+00 0 OOE+00 0.00K+00 0.00E+00 O.OOE+00 0 OOE+00 0 OOE+00 5.43E-05 1.35E-02 1.10E-08 1 19E-09 3.73E-07 4.63E-11 8.26E-05 1.84E-09 1 69E-08 1.82E&5 1.72E-08 2.32E-06 3.92E-ll Q.QOE+00 1.73E-13 7.40E-15 2.63E&7 1.40E-10 1 23E-05 1 73E>>06 liver 1.59E07 6.09E-07 1.72E-06 1.37E-05 0.00E+00 6.39E-06 2 12E-10 2.98E-06 4.62E-06 1.18E-07 2.59E-07 1.89E-06 5.43E-06 3.66E-lL 2.54E-10 1.67E-05 1.15E-ll 3 39E-09 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 2.38E-05 6 82E-08 4.40E-08 O.QOE+00 O.OQE+00 O.OOE+00 0.00E+00 0.00E+00 0~OOE+00 O.OOE+00 0.00E+00 0~OOE+00 5.73E-06 3.40E-09 1.29E-06 9.72E-12 2.11E-08 4.83E-13 1.05E-14 0.00E+00 O.OOE+00 O.OOE+00 1.64E-06 t body 1.59E-07 6.09E-07 1.72E-06 8.95E-06 1.69E-08 1.05E-06 3 15E-11 6.93E-07 1~79E&6 1 15E-07 3.47E07 2.48E-06 2.47E-06 1.59E-11 1 06E-10 7.80E-06 8.07E-13 3 11E-10 2.28E-06 4 30E-08 5 41E-08 2 29E-09 1.05E-05 3.40E-'0&2.91E-OS 1 56E&6 8.35E-.04'39E-10 5 08E-ll 1.00E-08 1 77E-l.2 2 21E-06 5 36E-11 4 6SE-10 3.94E-06 1.57E-09 7.08E-07 3.55E-12 4.03E-09 6.24E-12 1.03E-13 1.12E-Q7 5 42E-11 1.55E-06 9.99E-07 TEEN thyroid 1.59E&7 6.09E-07 1 72E-06 0.00E+00 9.37E&9 O.OOE+00 0 OOE+00 0 OOE+00 0.00E+00 0 OOE+00 0 OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OQE+00 0.00E+00 O.QOE+00 O.OOE+00 O.QOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 Q.OOE+00'0~OOE+00 O.QQE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OQE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 kidney 1.59E-07 6 09E-07 1 72E-0'6 O.OOE+OQ 3.84E-09 1.59E&6 2.24E-10 0.00E+00 0~OOE+00 O.OOE+00 0.00E+00 0~OOE+00 0.00E+00 0.00E+00 8.01E-10 1.08E-05 7.53E-12 2.06E&9 O.OOE+00 0.00E+00 O.CON+00 O.OOE+00 O.OOE+00 O.QQE+00 0~OOE+00 G.OOE+00 0.00E+00 O.OOE+00 0.OOE+00-O.OOE+00 0.00E+00 0.00E+00 0~QOE+00 0~OOE+00 8.42E-06 5.15E-09 1.25E-06 1.14E-ll 5.14E-08 7.20E-12 1.90E-13 9.29E-07 1.76E-IO 2.38E-OS 3.13E-06 lung 1.59E-07 6.09E-07 l.72E-06 Q.OOE+OQ 2.62E&6 2.48E-04 1.90E-06 1.55E-05 1.91E-04 7.33E-05 1.68E-04 L.09E-03 9.84E-05 1.17E-06 1.39E-06 1.55E-04 1.98E-07 3.92E-06 0.00E+00 O.OOE+00 0.00K+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.02E-04 2.06E-03 7.59E-06 3.43E-06 3.66E-05 4.00E-07 3.67E-04 3.35E-06 1.04E-05 3.36E-04 1.62E-OS 9.39E-05 4.91E-07 1.92E-05 1.44E-07 8.34E-08 9.79E-05 2.27E-06 2.01E-03 8.44E-04 gi-l.li 1.59E-07 6.09E-07 1.72E-06 1.16E-Q5 3.75E-07 8.35E-06 7.18E-06 7.99E-07 2.23E-05 3.93E-06 1 19E-05 3.24E-OS 1.77E-06 4.59E-06 7.68E-06 5.83E-06 3.56E-08 2.14E-05 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 2.21E-06 3.65E-15 4.22E-17 4.64E-05 9.56E-05 3.24E-05 1.49E-05 6.99E-OS 3 77E-09 5.11E-05 2.06E-05 7.24E-OS 1.86E-05 7.88E-05 1.21E-05 2.71E-07 3.36E-05 7.66E-07 1.09E-I6 1.36E-05 1.13E-05 1.20E-04 3.41E-05 0384p Table 1.10 (4 of 8)INK%ATION DOSE FACTORS-DFA (mremlpCi inhaled)RETS Manual Revision 7 Page 140 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs>>138 Ba-139.Ba>>140 Ba-141 Ba-142'a-140 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd-147'-'187 Np-239: bone 5.38E-06 9.23E-06 6.10E-07 2.25E-06 2.51E-10 1 74K&6 8.87E-12 l.23E-08 1.97E-12 4.50E&8 7'.80E-07 , 4 43E-06 1.99E-07 1.52E-06 1.11E&7 4.62E-07 6.28E-05 6.44E-06 8.38E-05 5.82E-08 1.67E 10 6.84E-'06.

L.78E-11, 4.62E-12'.99E-08 1.20E-10 3.55E-06 3.32E-08 6.11E-04'.67E-O6~

5 37E-12 9.83E-07 1.50E-09 4.23E-08 liver 9.92E-08 1.01E-07 2.80E-07 1.02E-06 1.14E-10 8.23E-'07 4.22E-12 7.51E-09 1.04E-12.3.63E-08 2.24E-06 6'4E-06 5'.47E-07 2.56E-06 2.90E-07 1.18E-06 1;41E-'04 2.42E-05 1.06E-04 1.07E-97 1.18E-13 8.38E-09 1'.32E-14 4.63E-15 2.95E-08'.31E-11.

2".37E-'06 2 42E-'08 2.53E-O4 6.64E-07 2.20E-12.1.07E-O6 1.22E-09 3 99E-09 t body 2.10E-06 2.15E-06 8.34E-08 2.73E-07 5'.52E-ll 2.81E-07 2.20E-12 5.03E-09 6.30E-13 2.74E-08 8 96E-07 3 30E-06 1.97E-07 7.78E-07 1.05E-07 4.36E-07 6.86E-05'.71E-05 3~89E-05'.58E-08 4.87E-12 4.40E-07 5.93E-,13.84E-13 T.82E-09'.32E-'l 2'.71E-07.,70E-09 3.28E-05 8.28E-08 2.72E-13.6.41E-OS 4.29E-10 2;21E-09 TEEN thyroid 1.22E-08 8.80E-09 l.7SE-07 5.48E-07 1.77E-10 5.72E-07 6.48E-12 9.06E-09 1 5SE-12 3.07E-08 1.86E-04 1.83E-03 1.89E-05 3.65E-04 4.94E-06 7.76E-05 0 OOE+00 O.OOE+00 O.OOE+00 0'OE+00 O.OOE+00 O.OOE+00 Q.OOE+00 0.00K+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0" OOE+00 0~OOE+00 0.00E+00 kidney O.OOE+00 0 OOE+00 0.00E+00&.17E-06 9.10E>>10 6 49E-06 3.32E-ll 5.49E-08 7.72E-12 2.44E-07 3.44E-06 1.05E-05 8.65E-07 4.49E-06 4.58E-07 1.86E-06 4.69E-'05 1.38E-05 3.80E-05 8 28E-08 1'.11E-13 2.85E-09 1.23E-14 3.92E-15 0.00E+00 O.OOE+00 1.11E-06 1.08E-08 1.51E-04 3.86E-07 1.26E-12 6.28E-07 O.OOE+00 1.25E-08 lung 4.81E-04 3.42E-04 6.70E-05 2 07E-04 1.40E-06 2 47E-04 4.12E-07 2.97E-05 2 92E-07 5'1E-05 0.E+00 0:OOE+00 0.00E+00 0.00E+00 0.00E+00 0 OOE+00 1.83E-05 2.22E-06 1.51E-05 9.84E-09 8.08E-'07 2.54E-'04 4.11E-07 2.39E-07 2.68E-05 1.27E-06 7.67E-05 1.63E-05 1.67E-03 6.04E-05 2 19E-07 4.65E-05 5.92E-06 8 11E-06 gi-lli 4.98E-05 1.24E-05 9.38E-06 1.99E-05 1.01E-05 5.06E-05 2.02E-07'7.76E-05 1.89E-09 5.79E-05 1.14E-06 8.11E-07 1.59E-07 1.29E-06 2.55E-09&.69E-0?1.22E-06 1.36E-O6 1.06E-06 3.38E-11 8.06E-07 2.86E-05 9.33E-14-5.99E-20 6.09E-05 1.50E-06 1.58E-05 3 19E-05 1.08E-04 2.67E-05 2.94E-14 2.28E-OS 2'1E-05 1.65E-05

Reference:

.

Regulatory Guide.l.109,, Table E-.Dose Factors for Co-57, Zn-69m, Br-82, Nb>>97, Sb>>124 and Sb-125 are from NORE~172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 7.NOTE: The tritium dose factor.for bone is assumed total.body dose factor.to be equal to the 0384p e

Table 1.10 (5 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Msnual Revision 7 Page 141 H-3'-14 Na-24 P-32'r-51, Ha-54 Fe-55 Fe-59-Co-57 Co-58 Co-60 Ni&3 Ni&5 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb&6 Rb&9 Sr-89 Sr-90 Sr-91 Sr-92 Y-90'-91m Y-91'-92 Y-93'r-95 Zr-97 Nb-95 Nb-97 No-99 Tc-99m'c-101'u>>103 Ru-105 Ru-106 Ag-110m bone 3.04E-07 9.70E-06 4.35E-06 7.04E-04 O.QOE+00 O.QOE+QQ 0 OOE+00 1.28E-OS 5.59E-06 O.OOE+00 O.QOE+00 O.OQE+00 2.22E-04 8 08E-10 O.OOE+00 1.15E-05 1.81E-l.l 4.26E-09 O.OQE+QO O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00 O'OOE+00 l.62E-Q4.2 73E-02 3.28E-08 3'.54E-09 1.11E-06 1.37E-10 2 47E-04=-5.50E-'09 5.04E-08 5'.13E-05'.07E-08 6.35E-06 1.16E-'10 0 OOE+00 4.81E-13 2 19E-14 7.55E-07 4.13E-'0 3.68E-05 4 56K-06 liver 3.04E-07 1.82E-06 4.35E-06 3.09E-OS O.OQE+00 1 16E-05 4.48E-10 6.80E-06 9.04E-06 2.44E-,07 4.79E-07 3.55E-06 1.25E-05 7'99E-ll.5.39E-10 3.06E-05 2.61E-ll.7.28E&9 O.OQE+QO O.OOE+00 O.OOE+00 O.OOE+00 5.36E-05 1 52E&7 9.33E-08 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.13E-05 7.34E-09 2.48E-06 2.08E-11 4.66E&8 9.41E-13 2.30E-14 O.OOE+00 O'QE+00 0.OOE+00'.08E-06 t body 3.04E-07 1.82E-06 4.35E-06 2.67E-05 4.17E-08 2 57E-Q6 8.43E-11 2 10E-06 4.51E-06 2.88E-07 8.55E&7 6.12E-06 7.56E-06 4.44E-ll 2 90E-10 1 90E-05'.41E-12 8 59E-1.Q S 66EQ6 1.28E-07 1.48E-07 6.84E-09 3.09E&5 9.90E&8 7.83E-08 4.66E-06 1 74E-03 1.24E-09*1.42E>>10 2.99E-08 4.98E-12'.59E&6 1.57E-10 1.38E-09 1.00E&5 4.32E-09 1'.77E-06 9.74E-12',15E'-08 1.56E-'l.2'.91E-13 2.90E-07 1.50E-10 4.57E-06 2.47E&6 CHILD thyroid 3.04E-07 1 82E-06 4.35E-06 0.00E+00 2.31E&8 Q.OOE+00 0.00E+00 Q.QQE+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 0 OOE+00 0.00E+00 0.OOE+00*O.OOE+00 O.OQE+00 O.OOE+00 O.OOE+00 0.00E+00 O.OOE+00 O.QOE+QO=O.OOE+00 O.OOE+00 0.00E+00 O,OOE+00 0~OOE+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.QOE+QQ 0.00E+00 Q.OQE+00 kidney.3.04E-07 l.82E-'06 4-35E-06 O.OQE+00 6.57E-09 2.71E-06 4.52E-10 O.OOE+00 O.OOE+00 O.OOE+00 O.OQE+00 0.00E+00 0.00E+00 O.QOE+00 1.63E-09 l.93E-05'.58E-ll.

4.22E-09 O.OOE+00 0 OOE+00 O.OQE+OO 0.00E+00 0.00K+00 0.OOE+00'.OQE+00 O.OOE&0 0.00E+00 O.QOE+00 0 QOE+00 O.QOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 1.61E-05 1.05E-08 2.33E-06 2'1E-ll 1.06E-07 1.37E-'l 3.92E-13.l.90E-06.3.63E-10 4.97E-05 5.74E-06 lung 3.04E-07 1.82E-06 4 35E-06 O.OOE+00 4.59E-06 4.26E-04 3.55E-06 3.00E-05 3'3E-04 1.37E-04 2 99E-04 l.91E-03 ,Ã43E-05 2 21E-06 2 59E-06 2 69E-04 3.84E-07 7.36E-06 O.OOE+00 0 OQE+00 Q.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0'OOE+00'.83E-04 3.99E-03 1.44E-OS 6.49E-06 7.Q7E-05 7.60E-07 7.10E-04 6.46E-06 2.01E-05 6 03E-04 3.06E-05 1.66E-04 9.23E-07'.66E-'05 2.57E-07'.58E-07 l.79E&4 4.30E&6 3.87E-03 1.48E-03 gi-lli 3 04E07 1.82E-06 4.35E&6 1.14E-05 2 93E-07 6 19E-06 3 33E-05 7.75E-07 1 91E-05 3.58E-06 9.29E-06 2.60E-05 1.71E-06 2.27E-'05 9.92E-06 4.41E-06 2.75E-06 2.71E-05 0 OOE+00 O.OOE+00 O.OOE+00 0 OOE+00 2.16E-06 4 66E-09 5.11E-10 4.52E-05 9 28E&5 4.70E-05 6.55E-05 7.24E-05 4.64E-07 4.97E-05 6.46E-05 1.05E-04 1.65E-05 9.49E&5 1.00E-05 7.52E-06 3 42E&5 1.30E-06 4.41E-09 1.21E-05 2.69E-05 1.16E-04 2.71E-05 0384p

Table 1.10 (6 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 7 Page 142 Sb-124 Sb-125 Te-L 25m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132.I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139.Ba-140 Ba-141.Ba-142.L'a-140'a-142 Ce-141 Ce-143 Ce-144.Pr-143 Pr-144 Nd-147'-187 Np-239 bone.1.55E-05 2.66E-05 1.82E-06 6.72E-06 7.49E-10 5.19E&6 2.64E-LL 3.63E-08 5 87E-12 1.30E-07 2 21E-06 1 30E&5 5 72E&7 4.48E-06 3 17E-OT 1.33E-06 1.76E-04 1.76E-O5 2;45E-04 l.7LE&7 4 9&E-10 2 QOE&5, 5.29E-11.1.35E-11 l.74E-07'.50E-LQ 1.06E&5 9 89E8 1.83E-03 4.99E-06 1.6LE-LL 2 92E&6 4.41E-09 1 26E-07 liver 2.00E-07 2 05E-07 6.29E-07 2.31E-06 2.57E-10 1.85E-06 9.45E-12 1.60E-08 2 28E-12 7..36E-08 4.43E-06 1.30E-05 LelOE-06 5.49E-06 5.84E-07 2'6E&6'-2.74E-04*4.62E-05 2.23E-04.2;27E-07 2 66E-13 1.75E-OS 2.95E-LW 9.73E-15 6.08E&8.1.11E-'LQ 5.28E-06 5.37E-08'72E-04 1.50E-06 4.99E-L2, 2.36E-06 2 61E-'09 9.04E-09 t body 5.41E-06 5 59E-06 2.47E-07 8 16E-07 1.65E-10 8.22E-07 6.44E-12 1.37E-OS 1 78E-12 7.12E-OS 2 28E-06 7'.37E-06 5.07E-07 2 OSE-06 2.69E-'07 1.12E-06 6.07E-05 3.14E-05 3.47E-05 1'.50E-07 1.45E-LL 1~17E-06 X.72E-12 7.54E-13 2'.04E-08.49E-LL 7'3E&7 7'77E&9 9.77E&5 2;47E-'07'.10E-13 1.84E-07 1 17E-09 6 35E&9 CHILD thyroid 3.41E-08 2 46E-08 5.20E-07 1.64E-06 5.30E-10 1.71E-Q6 1.93E-LL 2.64E-08 4.59E-12 8 58E-08 4.99E-04 4.39E-03 5.23E-05 1.04E-03 l.37E-'05 2.14E-04'.OOE+00.0.00E+00 0.00E+00 0~QOE+00 Q.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 0~QOE+00 0.OOE+00'.QOE+00 0.00E+00 0.OOE+00'.QOE+00 0 QOE+00 O.QOE+00 0.00E+00 O.OOE+00 kidney O.OQE+00 0.00E+00 O.OOE+00 l.72E&5 1.9LE&9 1.36E-Q5 6'.94E-11 1.08E&7 1 59E-LL 4.79E&7 6 61E-06 2.13E-05 1.69E-06 9.13E-06 8.92E-07 3.62E-06 8.93E-05 2.58E-05 7.63E-05 1.68E-07 2.33K-'L3 5 71E-09 2'.56E-14 7.87E-15 0.00E+00 O.QOE+00 2.31E-'06 2.26E-08 3.17E-04 8.11E-07 2.64E-12 1.30E-06 0.00E+00 2;63E-08 lung 8.76E-04 6.27E-04 1.29EW4 4.00E-04 2.71E-06 4.76E-04 7.93E&7 5.56E&5 5.55E&7 1.02E-04 Q.OOE+00 0.00E+00 Q;OOE+00 0.00E+00 0.00E+00 O.QOE+00 3.27E-05 3.93E&6 2.81E-05 1.84E-OS 1.56E&6 4.71E-04 7.89E-07 4.44E-07 4.94E-'05 2.35E-06 1'.47E-04 3.12E-05 3.23E-03 1.17E-04 4.23E-07 8.87E-05 L.LLE-05 1.57E-05 gi-lli 4.43E-05 1.09E-05 9.13E-06 l.93E&5 1.52E-05 4.9LE-05 6.89E06 8.32E-05 3.60E-07 3.72E-05 1.38E-06 7.68E-07 8.65E-07 1.48E-06 2.58E-07 1.20E-06 1.04E-06 1.13E-06 9.78E-07 7.29E-OS 1.56E-05 2 75E-05 7.44E-OS 7'41E-10 6.10E-05 2.05E-05 1.53E-05 3.44E-05 1..05E-Q4 2.63E-05 5.32E-OS 2.22E-05 2.46E-05 L 73E-QS

Reference:

Regulatory Guide-1.109, Table E-9..Dose.Factors for: Co-57:,.-Zn-69m, Br-82, Nb-9T,.Sb-124 and Sb-125 are from NUREG-0172'A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977,.Table 6.NOTE:.The: tritium.dose facto>>for bone is assumed total body-dose factor.-to be equal to the:~0384p It RETS Manual Revision 7 Page 143'H-3 C-14 Na-24 P-32 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-63 Ni-65 CLI-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y>>93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 Tq-99m Tc-101 Ru-103 Ru-105 Ru-106 Ag-110m bone 4.62E-OT 1.89E-05 7.548&6 1.45E-03 0.008+00 0.008+00 0.00E+00 1.41E-05 9 69E-06 0 OOE+00 O.OOE+00 0.00E+00 2.428-04 1.71E-09 0.008+00 1.388&5 3.85E-11.8.98E-09 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 O.OOE+00 0.008+00 2.848-04 2.92E-02 6.83E-08 7.508-09 2.358&6 2.91E-10 4.20E-04 1.17E-08 1.078-07 8 24E-05 1.07E-07'.

12E-05 2.448-'0 0.008+00 9.98E<<13 4'65E-14.1.448-06 8'4E-10 6.20E-05 7'.138-06 liver-4.62E-07 3 79E-06 7.54E-06 8.03E+05 0.00E+00 1.81E-05 1.10E-09 8.398-06 1 68E-05 4 65E-07 8.718-07 5.738-06 1.46E-05 2 038-10 1 348&9 4 478-05 6 91E-ll 1.84E-08 0~OOE+00 0.00E+00 0.00E+00 0~OOE+00 1 368-04 3.988-07 2.29E-07 0.008+00 0.00E+00 0.00E+00 0.008+00 0.00E+00 0.008+00 0.008+00 O.OOE+00 0~OOE+00 1.99E-05 1.83E-OS 4.5.98-06 5.21E-ll l.188-07'.06E-12.

5.88E-04 0.00E+00 0.00E+00 0.008+00 5.16E-06 t body 4.62E-07 3 79806 7 54E-06 5.538-05 6.39E-08 3 568&6 1.58E-10 2.38E-06 6.77E-06 4.58E-07 1.30E-06 8.41E-06 8.29E-06 8 798-11 5.53E-10 2.22E-05 5 13E-12 1.67E-09 9.498&6 2.72E-07 2.86E-07 1.46E-08 6'0E-05 2 05E-07 1.47E-07 8 15E-06 1.858-03 2.47E-09 2 79E-10 6.30E-08 9.90E-12 1.12E-05 3.298-10 2.91E-09 1.45E-05 8 36E-09 2.70E-06 1.88E-11 2 31E-08 2.66E-11 5.80E-13 4.858&7 2".93E-10 7.77E-06 3.57E-06 INFANT thyroid 4.62E-07 3 79E-06 7 54E-06 0.00E+00 4 llE-08 0.00E+00 0~OOE+00 0.00E+00 0.00E+00 0 OOE+00 0 OOE+00 0.00E+00 0 OOE+00 0.008+00 0.00E+00 O.OOE+00 0 OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0~OOE+00 0.00E+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.008+00 0.00E+00 O.OOE+00 0 00E+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0'OE+00 0.00E+00 O.OOE+00 kidney 4 62E-07 3.79E-06 7.54E-06 O.OOE+00 9.45E-09 3.56E-06 7.86E-10 0.00E+00 0 008+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.008+00 2.84E-09 2 328-05 2.87E-11 7.45E-09 0.00E+00 0.008+00 O.OOE+00 O.OOE+00 0.00E+00 0.008+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E+00 0.00E+00 O.OOE+00 0 00E+00 0.00E+00 O.OOE+00 2 22E-05 1.85E-08 3 37E-06 4.07E-11 1.89E-07 2.22E>>11 6.998-13 3.03E-06 6'2E-10 7.61E-05 7.80E-06 Table 1.10 (7 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)lung 4.62E-07 3.798&6 7.54E-06 0 OOE+00 9 178-06 7 14E-04 8.958-06 6'1E-05 7 25E-04 2 71E-04 5.558-04 3 22E-03 V49E-04 5.80E-06 6 64E-06 4 62E-04 1 05E-06 1 91E-05 0 OOE+00 0.00E+00 0 OOE+00 0.00E+00 0.008+00 0.00E+00 0 OOE+00 1.45E-03 8 03E-03 3 76E-05 1.70E-05 1.92E-04 1 99E-06 1 758-03 1 75E-05 5.46E-05 1.25E-03 7.88E-05 3 42E-04 2 37E-06 9.63E-05 5.79E-07 4.178&7 3.94E-04 1.12E-05 8.26E-03 2.62E-03 gi-lli 4.62E-07 3.79E-06 7.54E-06 1 15E-05 2 55E-07 5.04E-06 5.12E-05 7.82E-07 1.77E-05 3 47E-06 7.95E-06 2.28E-05 1.73E-06 3.58E-05 1.07E-05 3.67E-05 9.44E-06 2.92E-05 0.00E+00 0 OOE+00 0.00E+00 0.00E+00 2.17E-06 2.42E-07 4.87E-08 4.57E-05 9 36E>>05 5.248&5 1.00E-04 7.43E-05 1.68E-06 5.02E-05 9.04E-05 1.198-04 1.55E-05 1.00E-04 9.05E-06 1.92E-05 3.48E-05 1.45E-06 6.03E-07 1.15E-05 3.46E-'05 1.17E-04 2.36E-05 0384p Table 1.10 (8 of 8)INHALATION DOSE FACTORS-DFA (mrem/pCi inhaled)RETS Manual Revision 7 Page 144 Sb-124 Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132 I-130 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136.Cs-13T Cs-138 Ba-139 Ba-140 Ba-141 Ba-142.La-140 La-142 Ce-141 Ce-143 Ce-144.Pr-143 Pr-144 Nd 147 8-1&T Np-239 bone 2.71E-05 3.69E-05 3.40E-06 1.19E-05 1.59E-09 1.01E-05 5.63E-11 T.62E-OS 1.24E-11 2-66E-OT 4.54E-06 2.71E-05 1 21E&6 9.46E-06 6.5&E-OT 2.76E-06 2.83E-04 3.45E-05 3 92E&4 3.61E-07 1.06E&9 4.00E-05 1.12E-10 2.84E-ll 3.61E-OT 7.36E-10 1.98E-05 2.09E&7 2.28E-'03 1.00E-05 3;42E-11 5.67E-06 9.26E-09 2.65E-OT liver 3.97E-07 3.41E-07 1.42E-06 4.93E-06 6.81E-10 4.35E-06 2 4&E-ll 3.93E-O8 5'7E-12 1.69E-07 9~91E&6 3.17E-05 2.53E-06 1 37E&5 1.34E-06.5 43E&6 5.02E-04 9.61E-05 4.37E-04 5.5&E-07 7.03E-13 4.00E-OS 7.70E-14 2 36E-14 1.43E-07.2 69E-10 l.19K&5 1.3&E-07 8.65E&4 3.74E&6 1.32E-ll 5.81E-O6 6.44E&9 2.37E-08 t body 8.56E-06 7.7&E-06 4.70E-07 1.4&E-06 3.49E-10 1.59E-06 1.34E-ll 2.59E-OS 3.57E-12 1.26E-O7 3'&E-06 1.40E-05 8.99E-OT 4.00E06 4.75E-07 1.98E-06 5.32E-05 3.T&E-05 3.25E-05 2.84E&7 3.07E-11 2.07E-06 3.55E-12 1.40E-12 3'.6&EBS 6.46E-11 1.42E-06 1.58E-O&1.26E-04 4'99EMT 1.72E-12 3.57E-O7 2.23E&9 1.34E-08 INFANT thyroid 7.1&E-08 4.45E-OS 1.16E-06 3.4&E-06 1 32E&9 3.91E-06 4.82E-ll 6.38E-08 1.13E-11 1.99E-07 l.14EW3 1.06E&2 l.21E&4 2.54E-03 3.1&E-OS 4.97E-04 O.OOE+00 0~OOE+00 0.00K+00 0.00E+00 0.00E+00 O.OOE+00 Q.QOE+00 0 OOE+00 0.00E+00 0 OOE+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0 OOE+00 0.00E+00 kidney O.OOE+00 0.00E+00 0.00E+00 2.6&E&5 3.47E&9 2.27E&5 1.25E-IO 1.89E-OT 2&5E-ll 7 39E-07 1.09E-05 3.70E-OS 2.82E-06 1.60E-05 1.49E-06 6.05E-06 1~36E-04 4.03E-05 1.23E-04 2.93E-07 4.235-13 9.59E&9 4.64E-14 1 36E-'14 0.00E+00 0.00E+00 3.75E&6 4.03E-OS 3.84E-04 1.41E-06 4.&OE-12 2.25E&6 0.00E+00 4.73E-08 lung 1.89E-03 1~17E-03 3'9E-04 9.37E-04 7.39E-06 1.20E-03 2.14E-06 1.42E-04 1.47E-O6 2.43E-04 0 OOE+00 0.00E+00.0;OOE+00 O.OOE+00 O.OOE+00 0.00E+00 5.69E-05 8.40E-06 5.09E-05 4.67E-OS 4 25E-06 1.14E-03 2.12E&6.1~11E&6 1.20E-04 5'7E-06 3.69E-04&30E-05 7.03E-43 3.09E-04 1.15E&6 2.30E-04 2 83E-05 4.25E-05 gi>>lli 4'2E-05 1.05E-05 9.22E-06 1.95E-05 1.74E-05 4.93E-05 1.8&E-05 8.51E-05 5.87E-06 3.15E-05 1.42E-06 7.56E-07 1.36E-06 1.54E-06 9.21E-07 1.31E-06 9.53E-07 1.02E&6 9.53E&7 6.26E-07 3.64E-05 2.74E-05 3.39E-06 4.95E-07 6.06E-05 4.25E-05 1.54E-05 3.55E-05 1.06E-04 2.66E-OS 3 06E-06 2.23E-05 2 54E-05 1.78E-05

Reference:

, Regulatory Guide 1.109, Table E-10.Dose Factors for Co-57", Zn-69m, Br&2, Nb-97, Sb-124'nd Sb-125 are from NUREG-0172 A e S ecific Radiation Dose Commitment Factors for a One Year Chronic Intake November 1977, Table 5-NOTE: The tritium dose factor total body dose factor.for bone is assumed to be equal to the 0384p

Table 1.11 (1 of 2)EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED (mrem/h per pCi/m2)RETS Manual Revision 7 Page 145 GROUND-DFG Nuclide H-3 C-14 Na-24 P-32 Cr-51 Rx-54 Ha-56 Fe-55 Fe-59 Co-57*Co-58 Co>>60 Ni&3 Ni.-65 Cu&4 Zn-65 Zn-69 Zn-69m Br-82 Br&3 Br-84 Br-85 Rb-86, Rb-88,~9: Sr&9'r-91.

Sr-92 Y-90 Y-91m Y-'9l Y-92 Y-'93 Zr-95 Zr-97'b-95 Nb-97 Mo-99 Tc-99m, Tc-101 RLL-103 Ru-105'u-106 Ag-, 110m Sb-124 Total Body 0.0 0.0 2.50E-08 0.0 2.20E-1.0 5 80E-Q9 1 10E&8 0.0 8.00E-09 1.77E-09 7.00E-Q9 l.70E-Q8 0.0 3.70E-09 1.50E-09 4.00E-09 0;0 , 5.50E-09 3 18E-08" 6 40E-ll 1.20E-OS 0'0 6.30E-10 3.50E-09 1.50E-'08.

5.60E-13 7.10E-09 9.OOE'-09 2.20E-12, 3'SOE-09 2;40E-11 1.60E-09 5.70E-10 5.00E-09 5;50E-09 5.10E-09 8'11E-09 1".90E>>09 9.60E-10 2'.70E-'09 3.60E&9 4.50E-09 1 50E-'09 1.80E-'08 2.17E-08'kin 0.0 0.02.90E-OS 0.0 2.60E-10 6.80E-09 1 30E-08 0.0 9.40E-09 2 21E-09 8.20E-09 2.00E-OS 0 0" 4.30E-09 1.70E-09 4.60E-09 0.0 6 59E-09 3.90E-08 9 30E-11 1.40E-08 0.0 7~20E-10-4.00E-09~1.80E-OS 6.50E-13 8.30E-09 1.OOE-OS 2.60E-12 4.40E-09 2.70E-ll 1.90E-09 7;80E-10 5'.80E-09 6.40E&9 6~OOE-09 1.00E-08 2.20E-09 1.10E-09 3.00E-09.4.20E-09 5.10E-09 1.80E-09 2..10E-08 2.57EWS I~t f~~M~1 g 0384p

'Nuclide Total Body Skin RETS Manual Revision 7 Page 146 Table 1.11 (2 of 2)EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND-DFG (mrem/h per pCi/m2)Sb-125 Te-125m Te-127m Te-127 Te-129m Te-129 Te-131m Te-131 Te-132, I-130 I-131 I-132 I-133 I-134 I-'135 Cs-134 Cs-136, Cs-137 Cs-13&Ba-139 Ba-140 Ba-141 Ba-142 La-140 la-142.Ce-141 Ce-143 Ce-144 Pr-143 Pr-144 Nd>>147 W-187 Np-239'488-09'SOE-11 1 10E-12 1 OOE<<ll 7 70E-10 7.108-10 8.40E-09 2 208-09 1 7QEW9 1 40E-OS 2 808-09 1 708-'08 3 708&9 1 608-'08 1 20E-08 1 20E-08 1.50E-08 ,4'.20E-09 2 108&8 2.40E-09 2 108-09 4.308&9 7.908&9 1.508&8 1'08&8 5.50E-10 2'08&9 3.20E-10 0.0 2.008-10 1.008-09'.

10E-09 9.508-10 6 808-09 4 SOE-11 1 30E-12 1 108-1.1 9 OOE-10 Si408-10 9.908-09 2'08-06 2.008-09 1 708-08 3.408-09 2.00~8 4.50E-09 I 908-08 1 40E-08 1.408-08 l.708-08 4.90E-09 2.40E-OS 2 708-09 2 40E-09 4 908-09 9'008-09 1.708&8 1.80E-OS 6 208-10 2.50E-09 3.70E-10 0.0 2'.30E-10 1.20E-09 3.60E-09 1.10E-09 l~C

References:

Regulatory Guide 1 109,.Table E-'.Dose Factors for Co-57, Zn69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Dose-Rate Conversion Factors for-External Ex osure to Photon and Electron Radiation from Radionuclides Qccurrin in Routine Releases from Nuclear Fuel C cle Facilities D.C.Kocher,.Health Physics Volume: 38,.April 1980.0384p

Table 2.1 RECEPTORS FOR LIQUID DOSE CALCULATIONS RETS Manual.Revision 7 Page 147 Name Beginning Ending TRM TRM Tennessee River Reaches Within 50 Mile Radius Downstream of BFN Size Recreation (acres)visits/year Wheeler Lake below BFN 294.0'75 0 26076 1%4080600 Wilson, Lake Pickwick Lake 275.0 260.0 230.0 15048 705,500 260+0 15930 3,816~800 Public Water Supplies Within 50 Mile Radius Downstream of BFN Name Muscle Shoals, AL Sheffield, AL Cherokee, AL TRM!259.6 254.3, 239i2.Population-10, 740 13i065 3,400." 0384p k 4 Nuclide RETS Manual Revision 7 Page 148 Table 2.2 BIOACCUMULATION FACTORS FOR FRESHWATER FISH-B (Page 1 of 1)Nuclide 8-3 C-14 Na-24 P-32 Cr-51 Mn-S4 Mn-56 Fe-55 Fe-.59-Co-S7 Co-58 Co-60 Ni&3 Ni&5 Cu-64 Zn-65 Zn-69 Zn-69m Br-82 Br-83 Br-84 Br-85 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Nb-97 Mo-99 9.0E-Ol 4.6E+03 1.0E+02 1.0E+05 2.0E+02 4.0E+02 4.0E+02 1.0E+02 1.0E+02 5.0E+01 5.0E+01 S.OE+01 1.0E+02 1.0E+02 5.0E&l 2.0E+03 2.OE+03 2.0E+03 4.2E+02 4.2E+02 4.2E+02 4.2E+02 2.0E+03 2.0K+03 2.0E+03 5.6E+Ol 5.6E+01 5.6E+01 5.6E+01 2.5E+01 2.5E+Ol.2.5E&l 2.5K+01 2.5E+Ol 3.3E+00 3.3E+00 3.0E+04 3.0E+04 1.0E+Ol Tc-101 RQ-103 Ru-105 Ru-106 Ag-110m Sb-124 Fb-125 Te-1.25m Te-127m Te-127 Te-129m Te<<129 Te-131m Te-131 Te-132 I-130 I-131 I-'132 I-133 I-l.34.I-135 Cs-134-Cs-136 Cs-137 Cs-138 Ba-139 BK-140 Ba 141'Ba-1.42 La-140 La-142 Ce-141 Ce-143 Ce-1.44 Pr-143 Pr-144 Nd-147 I-187'p-239 1.5E+101 1.0E+01 l.OE+01 1.0E+01 O.OE+00 1 OE+00 1 OK+00 4.0E+02 4.0E+02 4.0E+02 4.0E+02 4.0E+02~4.0E+02'OE+02 4.0E+02 4.0E+Ol 4.0E+01 4 OE+01 4.0E+Ol 4.0E+Ol 4';OE+01 1 9E+03 1 9E+03 1 9E+03 1 9E+03 4 OE+00 4.0E+00 4.0E+00 4.0E+00 2 5E+01 2 SE+Ol 1 OE+00 1 OE+00 1.0E+00 2 5E+01 2 SE+Ol 2 SE+01 1 2E+03 1.0E+01

References:

Bioaccumulation factors for Sb-nuclides are from ORNL-4992,"A Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment, March 1976, Table 4.12A.Bioaccumulation factors for Iodine, Cesium, and Strontium nuclides are from NUREG/CR-1004, Table 3.2.4.All other nuclides'ioaccumulation factors are from Regulatory Guide 1.109, Table A-l..0384p TABLE 3.1 (Sheet 1 of 4)ENVI RONHENTAL RADIOLOGICAL MONITORING RETS Manual Revision 7 Page 149 SOIL Samples from same locations as air particulates Exposure Pathway Number of Samp)es and.~l AIRBORNE'articulates 6 samples from locations (in.'I i different sectors)at or neat the site boundary (LH-l, LH-2, LM-3, LM-4, LH-6, and LH-7)2 samples from control locations greater than 10 miles from the plant (RH-1 and RM-6)3 samples from locations in communities approximately 10 miles from the plant (PM-l, PM-2 and PH-3)Radioiodine Same locations as air particulates Sampling and Collection Fre uenc Continuous sampler operation with sample collection as jequired by dust loading but at least once per 7 days.~\Continuous sampler operation with charcoal canister col-lection at learnt once per 7 days Once every year~Type and Frequency of Anal sis='articulate sampler.Analyze:for gross beta radioactivity I>24 hrs following filter l change.Perform gamma isotopic analysis on each sample when gross beta activity is>10;times the average of control.samples.Perform gamma isotopic analysis on composite (by location)sample at least once per 31 days.I-131 every 2 days Gamma scan, Sr-S9, Sr-90 once per year DIRECT 2 or more dosimeters placed at locations (in different sectors)at or near the site boundary in each of the 16 sectors At least once per 92 days Gamma dose once per 92 days 2 or more dosimeters placed at stations located>5 miles from the plant in each of the 16 sectors At least once per 92 days.Gamma dose once per 92 days.03B4p

0 0 TABLE 3.1 (Sheet 2 of 4)ENVIRONMENTAL RADIOLOGICAL.

HONITORING RETS Manual Revision 7 Page 150 Exposure Pathway~dl Number of Samples and Locations 2 or more dosimeters jn at least 8 additional locations of special interest I Sampling and Collection Fre uenc Type and Frequency of Anal sis HATERBORNE Surface Drinking 1 sample upstream (TRH 305.0)1 sample immediately down-stream of discharge (TRH 293.5)1 sample downstream from plant (TRH 285.2)1 sample at the first potable surface water supply downstream from the plant (TRH 282.6)2 additional samples of pot-able surface water downstream from the plant (TRH 214.9 and TRH 259.5)1 sample at a control location (TRH 306)Collected:

by automatic..sequenti a'1-type sampl er-wi th composite sample'aken at least once per 31 daysa..Coll ected by-automatic sequential-type sampler with, composite salgple taken at least once per 31 daysa c Grab sample taken at least once per 31 days Gamma scan at least once per 31 days.Composite for tritium at least once per 92 days Gross beta and gamma scan at least once per 31 days.Composite for Sr-89, Sr-90, and tritium at least once per 92 days.Gross beta and gamma scan at least once per 31 days.Composite for Sr-89 and Sr-90 and tritium at least once per 92 days-b c Composite samples shall be collected by collecting an aliquot at intervals not exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.The surface water control sample shall be considered a control for the drinking water sample.This assumes that the nearest drinking water intake is>3.0 mile downstream of the plant discharge.

If a drinking water intake is constructed within 3.0 miles downstream of the plant discharge, sampling and analysis shall be every 2 weeks.0384p TABLE 3.1 (Sheet 3 of 4)ENVIRONMENTAL RADIOLOGICAL HONITORING RETS Hanual Revision 7 Page 151 GROUND 1 sample adjacent to the plant (well 0'6)1 sample at a control location upgradient from the plant (Farm L)Exposure Pathway Number of Samples and~l 1 additional sgmple at a con-trol location~(TRH 305)\)~~Sampling and Collection Fre uenc Collected by automatic sequential-type sampler with composite sample taken at least once'per 31 days a Collected by automatic se-quential type sampler with composite sample taken at least once per 31 days.Grab sample taken at least once per 31 days.Type and Frequency of Anal sis Composite for gamma scan Sr-S9, Sr-90, and tritium at lease once per 92 days.Composite for gamma scan Sr-&9, Sr-90 and tritium at least once per 92 days.AQUATIC Sediment 2 samples upstream from discharge point (TRH 297.0 and TRH 307.52))sample in immediate down-stream area of discharge point (TRH 293.7)2 additional samples down-stream from the plant (TRH 2SS.7S and 277.98)At least once per 184 days At least once per 1&4 days Gamma scan, Sr-&9, and Sr-90 analyses Gamma scan, Sr-89 and Sr-90 analyses INGESTION Milk 03&4p At least 3 samples from dairy farms in the immediate vicinity of the plant (Farms 8, L and Bn)At least 1 sample from control locations (Farm Gl or Be)At least once per 15 days-Gamma scan and I-131 on each when animals are on pasture;.sample.Sr-S9 and Sr-90 at at least one per 3l.days least once per 31 days at other times.

TABLE 3.)(Sheet 4 of 4)ENVI RONHENTAI RADIOLOGICAL HONITORI NG Exposure Pathway Number of Samples and Sampling and~di Collection Fre uenc Fish 3 samples representing commercial At feast once per 184 days and game species in Guntersvl)le Reservoir above the plant 3 samples representing commercial and game species in Hheeler Reservoir near th'e plant RETS Hanual Revision 1 Page 152 Type and Frequency of Anal sis Gamma scan at least once per 184 days on edible portions, Clams Fruits 5 Vegetables 1 sample downstream from the Pischarge.

• 1 sample upstream from the plant.(No permanent stations established;, depends on availability of clams.)Samples of food crops such as corn, green beans, tomatoes, and potatoes grown at private gardens andlor farms in the immediate vicinity of the plant 1 sample of each of the same foods grown at greater than 10 miles distance from the plant At least once per 1&4 days Gamma scan on flesh only I t At least once per year at ,'amma scan on edible portion time of harvest Vegetation (pasturage) 0384p Samples from farms producing milk but not providing a milk sample (Farm T)Control samples from l remote air monitor (RM-1)and 1 control dairy farm (Farm G-))Once par 31:days--I-131, gamma scan once per 31 days.Sr-89 and Sr-90: analysis on the last monthly'ample of each quarter;

'I~t g~Map Location Number a 1 2 3 4-5 6.7 8 9 10, 11,:12'3...i., r., 14.18'2 23 24: 25 26~27 28 29 30.31'.32'3, 34.36 37 RETS Manual Revision 7 Page 153 TABLE 3.2 A WNS FERRY NUCLEAR P 1 Radiological Moni Sampling Locations Approximate Distance 13.8 10 9&.2.2.1 31.3 24'2 0.97 0.88 0 92 1 7 3 0 6.8 5.0 5.9 35 0.02 11 4d 12'31 3 19.1d 8.8d 0.5d, 11.0d 13.52;0.3d.5.22d 16 02d 28.8 3.2.LANT toring BRO Environmenta Program Indicator (I)or Samples Station NW NE SSE W M E N NNE ENE NNW SSM NNM N ENE WSM NW AP,CF, S AP,CF,S AP,CF, S AP,CF,S AP,CF, S AP,CF, S AP, CF%S AP, CF%S AP, CF, S AP%CF%S AP, CF, S N.N'%W N, V W PW PM PW PW SW SM SW CL, SD CL%SD CL%SD CL%SD M V SD F%CL I I I C I I I I I I I C I C I,~I.I Ce C.'I I C'C I'/C Secto PM-1 PM-2 PM-3 LN-7 RM-1 RM-6 LM-1 LN-2 LM-3 LN-4 LM-6 Farm B.Farm Bn Farm L'arm G1 Mell P6 TRMc 282 6 TRM 303.0 Muscle Shoal's, AL M TRM 274'9 TRN'85.2 TRM 293-5 TRM'05.0 TRN 307.52 TRN 293'7 TRM 288'78 TRM 277 98 Farm Be NW Farm T'NM TRM 297.0 Wheeler Reservoir (TRN 275-349)Guntersville Reservoir (TRM 3I 9-424)c.S~Soil SM~Surface Water V'.Vegetation See.figures 3.1,.3.2,.and.3 3 Sample codes:, AP~.Air particulate filter: CF': Charcoal Filter F.~: Fish W~Mell Water;TRM'Tennessee River Mile Miles from.plant discharge (TRM 294)Also used as a control for public water SD'Sediment CL~Clams PM~Public.Mater 0384p TABLE 3.2.B BROMNS FERRY NUCLEAR PLANT Thermoluminescent Dosimetry Locations RETS Nanual Revision 7 Page 154 Map Location Number 1 2 3 5 6 7 8 9 10 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65'6 67 68 69 Station NW-3 NE-3 SSE-2 W-3 E-3 N-1 NNE-1 ENE-1 NNW-2 N-2 NNE-2 NNE-3 NE-1 NE-2 ENE-2 E-l E<<2 ESE-l ESE-2 SE-1 SE-2 SSE-1 S-l S-2 SSW-2 SSM-2 SW-1 SW-2 SW-3 WSM-1 WSW-2 NW-1 NW>>2 NNW-1 NNW~3 Scccoc NW NE SSE W E N WNW ENE NNW N NNE NNE NE NE.ERE E E ESE ESE SE SE.SSE S S SSW SSW SW SW SW WSW WSM MSW W W M.MNW WNW NW NW NNW NNW Approximate Distance K.les)13.8 10 9 8~2 31.3 24.2 0.97 0.88 0.92 1~7 5.0 0.7 5.2 0.8 5.0 6.2 08 5.2 0 9 3 0 0.5 5 4 5~1 3 I 48 3.0 4,4 1 9 4.7&.0 2.7 5 1 10.5 1~9 4.7'2.1 3.3 4,4 2 2 5'1>>0 5.2'nsite (On)a or Offsite Off Off Off Off'ff Off On On On Off Off On Off Off Off Off Off On Off Off Off Off Off Off Off Off Off Off Off On Off Off Off Off Off Off On Off aTLDs designated onsite are those located two miles or less from the plant.TLDs designated offsite are those located more than two miles from the plant.vr RETS Manual Revision 7 Page 155 TABLE.3.3 Maximum Values for the Lower Limit of Detection (LLD)a~c (Sheet 1 of 2)Airborne Food Particulate Fish Products Sediment'ater or Gases (pCi/kg, Milk (pCi/kg, (pCi/kg,~~leis~CllL~Clime g~wet~Ci/I~wet Strd gross beta H-3 Hn-54 Fe-59 Co-58, 60 Zn-65 Zr-95 Nb-95 I-131 Cs-134.Cs-137 Ba-140 La-140 2000 15 30 15 30 30 15 lb 15 18 60.NIA N/A N/A 130 N/A'260 N/A 130 N/A N/A N/A O.OT 0.05 0.06 N/A N/A 260 N/A N/A N/A 130 150 N/A N/A 0 01 N/A.18 60 60 80 N/A N/A N/A N/A N/A N/A N/A N/4 NIA N/A N/A N/A N/A N/A N/A'N/A NIA N/A.N/A N/A N/A N/A N/A N/A N/A N/A N/A 150 180 N/A N/A 0384p' RETS Manual Revision 7 Page 156 TABLE 3.3 Rucimum Values for the Lower Limit of Detection (LLD)a~c (Sheet 2 of 2)Table Notation The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with 5 percent probabili,ty of falsely concluding that a blank observation represents a"real" signal For a particular measurement system, which may include radiochemical separation:

Where LLD E V 2 22 Y 4.66 s E V 2 22 Y exp(-Xht)~s~t'7 sis the"a pr'iori" lower limit of detection as defined above, (as picocuries per unit mass or volume).is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate, (as counts per minute)~is'the counting efficiency, (as counts per disintegration).

is the sample size (in units of mass or vol.ume).is, the number of disintegrations per minute per picocurie.

isthe fractional radiochemical yield, (when applicable).

is the radioactive decay constant for the particular radionuclide, and for environmental samples is the elapsed time between sample collection, (or end of the sample collection period), and time of counting (for environmental samples, not plant effluent samples).Typical values of E, V, Y,, and ht should be used in;the calculation.

Et should be reoododsed that the LLD ds dedKoed as aa a~rdord (before the fact')limit representing the capability.

of a measurement system and.not as i~LLD for analysis of drinking water and surface water samples shall be performed by gamma spectroscopy at approxhnately 15 pCi/L.Ef levels greater than 15 pCI/L are Identified in surface water samples downstream from the plant, or in the event of an unanticipated release of Z-131, drinking water samples will be analyzed at an LLD of 1.0 pCi/L for I-131.Other peaks which are measurable and Identifiable shall be identified and reported.

0 Figure 1.1 Land Site Boundary RETS Manual Revision 7 Page 157 1~~<<~"/0~0385p

!uo~h gal(.l<u<pV

)uuuAu~p 458EO nws[og dupIn~~>jua 0008$9V II dwig unnamed'ipag AagsuQI)xg Slip'pal QgagS sxauyqmoaag I (uoaauov)SLOS toom'6 So I)uor~!fa 3Vf S zasuapuog 89Y Cbl-06 HS ICE-06IB QQPQS uolQQloo Log j (,00')asuaIa~t pageaaIp 85!a~ed g un~s~hag pA<<i~Siju 6u~sog)uog guant4$3 SXOS pue megsES saoggp N~a-I'e~ng[g V Figure 1.3-BFH Normal Bulleting Ventilation RETS Manual Revision 7 Page 159'*Roof Fans RII 90-249 Turbini Deck AH 90-251 lf RH 90-250 Rofud)Floor.Turbin'a Building (Typical.for each unit)t:I Contro1 Bay From Primary Contaitiment Purge Syitem Reactor Building (Typical for each iidlt)I'rom Raduastu X 0>>ildlnjj to S(ITS (~mar fienl y vc>>t t lnl l>>>>)>Roof Fdns used seasonally tu cniitro1 tempera'>>ro 0385p~':;CS

F)gure 1.4<Sheet l of 4)RETS manual Revls)on 1 page 160 1.0 0.9 0.8 D 0.7 U R z O.B 0.6 z 0 u 0.4 fC 0.3 0.2 0.1 03850~0.1 1.0 10.0 PLUME TRAVEL blSTANCE (KILONtETEAS)

Pfitmo Ooplotlon Effoct for Grotind Lovol Rafoatok f All Atmotpl>orle Stab>lity Clouoe)100.0 200.0 r~l'igure 1.4 (Sheet 2 of 4)RETS Hanual RevisIon 7 Page 161 1.0 Qg (D STAB LE (E,F,G srr 0.8 D" oz U 0.6 Q.S z 0 Q 0.4 LL 0.3 UNSTABL]A,B,C)0.2 0.1 Q3859 0.1'.0 10.0 PLUME TAAVEL DISTANCE)KILOMETEIIS)

Plurne Dcpfction Fffcct)or 30m IIetcases ILettcri ricnoto Pasqrrill Stability Class))00.0 200.0 Figure 1.4 (Sheet 3 of 4)RETS Hanua1 Revl sion 7 Page 162 1.0 STABLE IE,F,G).0.9 nr 0.8 D 0.7 U~R K O.B W pp z 0 g O.4 K 0.3 EU L TtRA tD)UhlSTABLE (A,B,C)0.2 0.1 0385p'.1 i.p 10.0 PLtjME TRAVEL DlSTANCE (KILOMETERS) r PhiIrie Ocpfctlon Etfcct tor 60m Rclcascs fLcttcrs dcnotc Pawpiill Stahility Clasi)100.0 200.0

FIgure 1.4 (Sheet 4 of 4)RETS Hanua1 Revels)on 7 Page 163 1.0 0.9 NEUTR I.to)w O.S D 0.?R 0.6 0.6 z O U~0.4 K STABLE (E,F,G)NO DEPLETION (FRACTION REMAINING o)VN (A STABLE ,B,C)0.2 0.1 0.1 1.o 10.0 PLUME TRAVEL DISTANCE (KILOMETERS) 100.6 zoo.o)0385p Plurne Depietlon EIIect Ior 100m IIofoesos (Letters rfonote Pesqoill Steliility Ciess)

RETS Manual Revision T Page 164 Figure 1.5 I~~I I I I I I I~~~I~I~I I I O.T'.n.10 PLUME TRAVEf OlSTANCE{KlLOMETERS)

Fieure't.Vevioal Standard Qeviation of Material in a Plurne (Lettera denote Patttuill Stability Clast)0385p

RETS Nanual Revision 7 Page 165 Figuc:e 1 6 (Sheet 1 of 4)~~~I~~I I~I I I I I I Ill I I I I I IIII~~~~~~~I~I~~I I I I I I III I I I I I IIII l I l I Ill l I!l l I ill I~~I I I I~I I>~I I I I 1 il>>l I I I!Illl I I I I IIII I I I I!IIII CC W~C O CL'.uk--I~+I I I I I I I I I~~~~~I I I 1 I I I I I I I I I'I I I i I I I II I I I I: I I ll!I l i!Ill I.!I!I I l I i t I~I I I I I Ill I!l!l ll:I~I 1~I I I I I~1 I I~~~~I~I I I I~~~~~I lri I I I I~~I l l IP-I" h.I I I il l l l il'rl I~I I I I III'I I I I I I" I~~~~1~~I I~I I~I I 1 I~I I I III I I~I I I~I I I I Ill I I I I I l l Ill I I I 1111 l I'I I II I TLQ': '-,;:.-....CQQJl.20Q.Q le.'UME TRAV%.DISTANCE (Klf OMETERg RIIatbe Oesciclon lo~~~~RII4aee (All Aanosyherie..

Sadillcy Came)~I~038SB RETS Manual Revision 7 Page 166 Figuxe 1.6 (Sheet 2 of 4)I I~I~~I I I I I I I I I II I I I~I~I~~I I~~~I I~~I I I I I'I I I I I Ills I I I I I IIII oo~Ilail il}l}}li UNSTABLE I (A JR,C tt'us I gg I z Oi (D TRAL I I I I I I I I III STABLE LE (E,F,G 10 7 c~0.1.1.0."..10.0-PLUME.TRAYFL OISTANCE (KlLOMETERS) 100.0.200.0 Relative Oeposition for 30m Releases (Letters denote Pasquill Stability Class}I 0385p Figure 1.6 (Sheet 3 of 4)RETS Manual Revision 7 Page 167~I I I I I I~I I I I I UNSTABLE (A.B C)I I I~~I I I I I I I I I I I I II I I I I lilies I ((Ii)ti l~r~TO B I us~lQ cC'tt;a lM I 0 I NEUTRAL (D)N RAL I I I I I I I I I III'I UNSTABLE'lO.7 STABLE (E;F,G)~I lo-8 O.'T"lO;0100.0 PLUME TRAVEL DISTANCE;(KILOMETERS'elative Deposition ',or 60m Releases (Letters denote Pasquill Stability Class)l 200.0 I I 0385p C ~IW%I W~~a~WW RS 5 E~~~M W%%.~~~MRS~~~MWRSk~~~MWRRSIEI~ SSHMM%5%~~ ~f&%RRSIBW 'IB&W&iWWRESI ~asaaaauwmaarauu~iwa~a~ ~MHRlllllF~MRSRIIII~&tRCIRm MJHIMll~~Illllll M~~~WaaSSR~~~WWWSRS~ N~~NSKERk~~RWSSHS~~RSSSE W~~~~WflSSI~~~~WRSSS~~ S~WKKSSH~~WHSRRII~~ 1~~RRRIII~~WKXIHI~~ <~MRNJR~M%55lll~WS %MIIII%5illllllHSSI ~<~maaa~waar~WIWESS~~~S~ ~N~RSSH~~MWRSSSI~~ ~WtHSBB~WRWJHS~ ~~1SSRIlll~~WHRIIII~~~ %RXllII~MRREHII~ MNiSlll)~RSllllll ~I BETS Hanual Revision 7 Page 369~I~'I oo.-rg>g~o<<'a~boa~g~;o~,~o)o~o oo(~~~~o<<Oo~ot<<r I~/I/~a<<<<ao~~~I o al~~~l~o~~~~~Oh~pa~~h.I~~~~~~a'~c/i S~/j'gI I 4c.~r ('g-r(r~r,~~I or r rr O~-r+~ja (I P'I=I<<~a!I!i".lan rr r'lh)'a r r C aa'rl l~~oo'N~~1~~p~~'~I~~'o I g o~Clt pi~.I IIIhhhh i(EGG<<h L~N I hht GE 0385p i c:(.y p Mal R'CL~, Ikt 1~(4l~(:~<<SIAIIOtI. j<<k<<l<<ho!I!G<<I lQ<<(EE.I.4" 4"~I L3 (4 V tO.py.'I;E Y>4g I-~~'I" I 0 RETS Hanual Revision 7 Figure 2.2-BF(LIQUID EFFLUEHT HOI1ITORS (T i yp<a1 Unit 8 Common Radwaste)Page 170 coNURNsER cooLIHc MhTRR RIIR SRRVlCR MhTRR lHrWF.IlhY~~TURIIIHR Bull.NHO (3)LOOP 1 RIIR LOOP 2 RIIR RII 90l33 90l3$Rx BUlLDlHC RhIMlhSTR (COQlOH)IIH 9Oi3O RhM COOL'lHQ MhTRR TENHESSRE RIVER OPRHlHC I:OI IIRI.i'RR tlOIII.Ill VPIISER 0385p (l)TURBlHE Bull.nlHC Eqlll PATIENT (2)IIEAcTOR BIIII.P)HO li<lllfl'III N'I'3)COHI)I IISEII ,-,.;IO Conl.lNO&P.'i nuuIS balll.AWIMlWII f Pill)H I:OHI.INN'I'OIII'.Iul ~L Figure 2.3-L iquid Radvaste Treatment Syst RETS Hanual Revision 7 Page l7l F.00R DRAlllS FLOOR DRA1N COLLECTOR TANK FMOR DMIN Fl f.TER FLOOR DB'AIN ShllPLE TANKS gk 77-60.i All 90-l30 I~.I~,I LAUNDRY DRAIN TANKS EqulPHEHT DRAINS WASTE COLLECTORt ThNK , l)hSTE Fl 1.TElt lfhSTE DEfl l HL!RALI ZEN MASTE SANVLE TANKS COHllENSATE STORACE'l'AHKS 0385p

.0 Figure 3.1 LaETS Manual Revision 7 Page 172 Environmental Radiolo gical Sampling Locations VYithin t Mile of Plant 328 2 348.75<NNW 1 1.25 NNE 33 75 NE'03.'75 WNW 28 41 C rC rroCr g Xl ENE 2ST 25 W 258.75,.a.~-~-1~l P~t BROWNS FERRY NUCLEAR PLANT 4 44 78,75 10 1.2~5.WSW i asm 238.'25 123.75.S.Vf 213.'75.SS,W 18 1'.25.146%5 SSE 1 68.75'cale.Mlle 0385p Figure 3.2 RETS Manual Revision 7 Page 173 Environmenta1 Radiological Sampfrng l ocatians Fram 0 ta 8 Miles From The Plant~~,~~~4Xf 4~10 LlS e't f 4~5 r.sewn robe~IOJCMAI~t'~I 1 A A'55 2004$lXL75 sa..5C 5 ted~"5L55 0385p Figtlx'e 3.3 RETD~Revision 7 Page L74 Eflvlron~eqg~(R<.~~ioloQical Samplt f7 OlP fllg Qoggglo~>an 8 defiles From T'ge pi ROt 33 76+~~C>>LCC 68,zs z8T CHC:~3 8 SOS<6 c TZ3.76 ter.zs*res,zs IO CC 0385p G RETS Manual Revision 7 Page 175 RETS MANUAL Section XV PROCESS CONTROL PROGRAM PCP 0385p i I RETS Manual Revision 7 Page 176 i+0 INTRODUCTION ~Sco e This, Process Control Program (PCP)is applicable to radioactive waste solidification and dewatering of wet solid radioactive wastes generated as a result of the operation and maintenance of Browns Ferry Nuclear Plant.This PCP is not applicable to the treatment of mixed wastes.1.2~Pm ase The PCP provides those controls necessary to ensure that disposal criteria are met by BFN processing techniques, or by vendor supplied systems,.if'used for dewatering or solid9.f9.cation. 2+0 DEFINITIONS 2.1 Absorb-To take liquid in through pores, or as if through pores or interstices of a material.2 2 Absorbent-Media or material used to'absorb liquid.0 2'Batch-An isolated quantity of waste to be processed having constant physical and chemical characteristics. 2'Container-The primary receptacle in which processed wastes (dewatered, solidified or absorbed)are packaged for disposal.2.5 Dewatered-Wet solid wastes which have had excess water removed.2.6 Free Liquid-Uncombined liquid not bound.by the solid matrix of the solid waste mass;capable of flowing.-2.7'omogeneous -Of uniform composition; the waste is uniformly distributed throughout the container. 2'Liquid waste>>For the purposes, of this PCP, any aqueous or non-aqueous radioactive liquid which requires solidification or absorption before disposal.. This may include oils, chemicals, water or*other liquids unsuitable for in-plant clean-up or treatment., I.0385p.

RETS Manual Revision 7 Page 177 2.9 Mixed waste-Low level radioactive wastes containing chemical constituents which are hazardous under Environmental Protec'tion Agency regulations in 40 CFR Part 261.2.10 Solidification agent-Material, which when mixed in prescribed proportions with liquid or wet-solid wastes, can form a free standing product with no free liquid.2.11 Solidify-To immobilize by use of a solidification agent or method which converts the liquid or wet solid waste to a free standing monolithic solid.2.12 Stability-A property of the waste form such that it is able to maintain its structural integrity under the expected disposal conditions; stabilized waste should maintain its gross physical properties and identity over a 300 year period.2.13 Wet solid wastes.-Spent powdered ion exchange resins, filter aid sludge, bead ion exchange resins, and other sludges or slurries consisting of liquids with'a high insoluble solid content.3~0" REFERENCES 3'.1 Code of Federal Regulations (CFR)Title 10,'Parts 20, 61, and 71[10 CFR 20, 10 CFR 61, and 10 CFR 71]-Energy 3.2 Code of Federal Regulations (CFR)Title 49[49 CFRl-Transportation 3'Browns Ferry Nuclear Plant Final Safety Analysis Report, Volume 4, Chapter 9.3, Solid Radwaste system 3'4 Browns Ferry Nuclear, Plant Technical Specifications (BFN Tech Spec)4.8.F.1,, 3.8.F.1&, 3.8.F.2,, 6.10.l.f,, and.6.11.1, 2 6.3 3'5 TVA Office of Nuclear Power Radioactive Material Shipment Manual (RMSM)3'6 3.7'uclear Regulatory Commission (NRC)Low-Level Waste Licensing Branch Technical Position on Radioactive Waste Classification, May 1983,, Rev.0 Nuclear Regulatory Commission (NRC)Technical Position on Waste Form, May 1983,, Rev..0 0385p

4.0 WASTE CHARACTERISTICS ~~4.1 Waste Streams RETS Manual Revision 7 Page 178 Three general waste streams applicable to this PCP have been identified for Browns Ferry.These are the Condensate Waste Phase Separator (CWPS), Reactor Water Cleanup Phase Separator (RWCU), and Dry Active waste (DAW).Other waste-streams may be established based upon plant operational needs.CWPS is fed by several waste sub-streams, including the Equipment Drain, Chemical Waste, Floor Drain, Fuel Pool Cooling, and Condensate systems.RWCU is fed by Reactor Water Cleanup only.DAW is used for, wastes, generated within the regulated areas of the reactor buildings. and".turbine buildings which cannot be appropriately attributed t'o either RWCU or CWPS.DAW normally includes.paper,, plastic, wood, metal and other such material generated as a: result'f the operation and maintenance of the plant 4.2 Waste Form Wet solid radioactive. wastes consist of bead resins, filter aids (such.as activated charcoals or carbons),. powdered resins, and slurries or-sludges., Wastes.which may require solidification may include, but are not limited to,, liquids which cannot be processed using installed plant systems,.oils, chemicals, aqueous filter media, and decontamination was'tes~Wastes.are processed. as.appropriate to ensure that the minimum physical characteristics required by'0 CFR'nd.disposal site criteria are met..All Class B and Class C.waste is.stabilized; On occasion,, Class A, waste (such as aqueous filter media.with a concentration >1 uCi/cc of.isotopes with half-lives >S years)may be solidified. or stabilized by BFN.Class, A liquid wastes may be either.solidified, or packaged in sufficient; absorbent material to.absorb twice the volume, of the liquid, as.appropriate, to the specific disposal, site criteria or license requirements. Tests are performed. on.those wastes which are solidified. to ensure the adequacy.of, the solidification agent and procedural technique. These.tests.are made;on, a minimum of three samples from each waste batch.to be solidified., I 0385p

4.3 Waste Classification RETS Manual Revision 7 Page 179 Scaling factors which relate hard-to-measuxe isotopes to key isotopes commonly measured at BFN have been developed for each waste stream.These scaling factors are used in the classification of the waste for disposal.Scaling factors may be developed on an as needed basis depending on changing plant operational conditions. Updates: are performed at least every two years fox waste normally considered to be Class A, on an annual basis for other wastes, or when the scaling factors are considered to be high or'low by a factor of.ten.Batch samples, separator samples, or sludge samples are taken for x'adiochemical analysis prior to processing the waste for shipment.DAW samples or area smears are taken to establish the relative percent abundance of isotopes for the DAW waste sgream.'r Materials which do not fit within the scope of existing scaling factors and waste streams are sampled.The samples are sent offsite for analysis and development of scaling factors prior to disposal of the materials. 5.0 SHIPMENT'ANIFESTS 5'.1.Manifest Pre aration Manifests are prepared for each-shipment of radioactive waste for disposal.Programmatic guidance for-manifest preparation is provided thxough the TVA Office of Nuclear Power, Radwaste Branch to ensure that.all 10 CFR and 49 CFR criteria are met.Procedures for manifest, preparation implement the specific requirements of 10.CFR 20.311, Transfer for Disposal and.Manifests. 5.2'.Manifest Trackin Acknowledgment of'eceipt for each.shipment to a disposal site is sent to BFN Water 6 Waste Processing: Group by the disposal site.Shipments for which acknowledgment is not.received within the time limits allowed in 10 CFR 20.311 are traced by the TVA Office of Nuclear Power, Radwaste Branch.IV-5'385p e 6 0 ADMINISTRATIVE CONTROLS Procedures and Surveillance RETS Manual Revision 7 Page 180 Detailed procedures are written and maintained by BFN which cover plant process systems, waste packaging, and shipment requirements. Surveillance Instructions are used to verify that plant Technical Specifications for waste processing are met.Programmatic guidance is provided through the TVA Office of Nuclear Power, Radwaste Branch.The Radwaste Branch maintains the Radioactive Material Shipment Manual and the Package Quality Assurance Program (for packages licensed under 10 CFR 71).6a2 lit Assurance/ ualit Control Quality assurance audits are conducted by the BFN site Quality Assurance organisation, and by the TVA Division of Nuclear Quality Assurance (DNQA).Audit findings axe reviewed by BFN management, ensuring prompt corrective actions when needed.Quality..control measures include quartexly tests of the resin dewatering system performed by BFN personnel upon actual dewatered High Integrity Containers (HICs)or liners,,site review of all radwaste vendor procedures before use, and second party verification by BFN personnel of end.points or acceptance criteria in, vendor: procedures-Quality control af solidification methods is performed.'through controlled testing-of a minimum of three samples from each batch to be solidified. Proportions of solidification agents are established which meet the standards for waste form and free liquid criteria 6a3~Trainin Personnel involved in processing. radioactive waste for shipment are trained in site procedures, regulatory requirements, and disposal site criteria.Training and retraining sessions are held when needed to support operations. Retraining is required on an annual basis to maintain qualification. Personnel found not complying with procedures. may have their.qualifications revoked by the Water and,'aste Processing Group Supervisor, if deemed necessary. Qualifications may be reestablished through completion of retraining, and approval.of the Water'Waste Processing'Group Supervisor.. I 03859 6.4 Retention of Records RETS Manual Revision 7 Page 181 Records are maintained to furnish documentation of items or activities affecting quality.Quality assurance records are stored in accordance with plant instructions and the TVA Nuclear Quality Assurance Manual.Retention times for radwaste records are established in the Radioactive Material Shipment Manual.7.0 APPENDICES 7'Solidification Descri tion Topical Report

Reference:

None System.or method in use: None Plant/Equipment. Interfaces: None 7'.2'ewaterin Descri tion Topical Report

Reference:

DW-11118>>01-P-A, Chem Nuclear Systems, Inc., CNSZ Dewatering Control Process Containers, and.RDS-25506-01-P, Chem Nuclear.Systems,.Inc., RDS-1000 Radioactive Waste Dewatering System, Rev..0NOTE:;-See: appended letter of interim approval.from NRC to TVA.of May 6, 1988., System or method in use: Vacuum dewatering using portable air driven diaphragm pumps, and, 10 HP electric high vacuum pump;and/or, Vacuum;dewatering/high speed drying using the CNSI RDS-1000 Radioactive. Waste Dewatering System Plant/Equipment'nterfaces:. See.appended letters of February 11,, 1987" and October 16, 1987 from TVA to NRC.(RIMS 8L44 870211 808 and 8L44 871016 807)., IV-7: 0385p RETS Manual Revision T Page 182 L-8 e 0>>',~SUP c<<<<4 imp<<<<'t.<<Ruoiaac Regulatory C~o Lcn Atmc Co~one CantmL Oeav Crr'ce oC Iuc'eac.Keae ac'etuLa>>cn. )[~4+<<i an h<<i i<<o t I<<<<i~<i<<ii<<e<<>>tl'Sa Ce Kamic oC che icnnooaee. VaL'.ey Asam~d~y Coe$cet Roe;NO-7~a 40<<75 0 fC<<794-~~3RC<<7'v sJUC>><<LR%At i (SPf)P+C~)<ceuiyaent 5pee'LcatLano. 4~pesal A~.',.<<.Cevatc~.ContmL P~ecaa-Canm'-era t ies,~w tor reference bg L'tenne~~~'~~i<<~~~'~~~~~~~We..enoLqpure provi4cg,'~~thon requLce4 h'R'C'o reviau a L'"-"'E i~to apeeL.Lc LLcenaeoa ao outLine4 Ln t~e~vcLuatLcn.. ~r~ueot that, RC'aaaoeiatce 5atety ppwvaL.oc uae oC this, redo t, HRC'evved the eneioaec}'i option an@<<&v>>ge'ioL pc ifa4 led~neo L<>>Ly Tourism ZSQMCW VAR': A~OR Cc~Fu, cd.:-p.Q.L Qi~y RL.CctcfLeyOLrcetoc'caeLeac'afety'n@ LLcenoLnt 0385p pi IRETS Manual Revision 7 Page 183 U.C ducLoco ReysLataw Caaeiaa jcn~wM~o c (Cccwauee) U 5ÃtacLacc'edcLctaw ~aaLan de)'ea'i Ate: Oe'.4.NeLaan Crace.ReCLancL Zc'4c ctw 5 w~t~$J auiha Ncc~tc.~Lc 5a5za ALRLnLat otal Le C'.Ccrc" l~Fe~~eat.ltccadee'~ 4 SaeLcee'egrate~ Camaiscian. 7f C0 Rot.o4c.brenda.des eacLa i~Loco CCdZd Co Ce Ceaho 4MtocTA.Fvojecm: U;0-'tucLcar RapaLatcey'maatax'on

.":40L Rtr'at~5t~.)M,, CcLta, 4500'a;Ccaegia OClQ~.4 Eterne Fi~Reaident Emy~r:: Levee-..Fatty.'ceLaac'Lancb

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RETS Manual Revision 7 Page 184 ENCLOSURE Dewatering is conducted at BFN using plant equipment and plant personnel. Chem-Nuclear Systems, Inc., (CNSI)high-integrity containers and the.CNSI dewatering procedures are used.1.EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI TOPICAL REPORT DATED DECEMBER 1983.BPN dewaters powdered resin, filter media, and mixtures of powdered resin with small quantities of bead resin (normally less than 10 percent bead resin)using Chem-Nuclear Procedure FO-OP-O22,"Ecodex Precoat/Powdex/Solka-Floe/Diatomaceous Earth Dewatering Procedure for CNSI 14-195 or Small Liners." The dewatering system was fabricated by TVA to-meet the equipment specifications in FO-OP-022. The TVA dewatering system differs from the Chem-Nuclear system in that: (a)TVA's system has no off-gas collector. The high integrity containers are open tothe waste packaging room air during filling and dewatering. Air from this room is normally discharged through the Radwaste Building.ventilation system.This air then flows through a HEPA filter and is released through a monitored release point on the Reactor Building roof..:~(b)The valves on the pump suction manifold are manually operated.The system is not operated remotely.However, the high integrity containers are enclosed behind a shielded wall or inside a shielded cask'uring filling and dewatering to keep radiation levels in the vicinity of the system-near background..(c)There are no vacuum gauges at each inlet connection. A single vacuum gauge is provided at.the flush inlet connection to the.manifold., This vacuum gauge will indicate a break in vacuum in any active (not isolated)- filter set.Loss of vacuum normally occurs in sequence from the top to the bottom set of filters.When vacuum breaks, at a given filter level, that level is isolated.Therefore, vacuum is.monitored continually for all active filter sets.(d)There is no automatic. level control or level indicating. instrument in the TVA dewatering system.Level is determined by visual observations.. TVA has, conducted tests which conclude that mixtures of bead and powdered resin, in proportions, of up to.50-percent, bead, can be adequately dewatered using a-modified procedure for dewatering powdered resin.These tests were conducted using;TVA-fabricated steel liners with dewatering internals similar to: those found in the Chem-Nuclear high-integrity containers and a dewatering; pump which is inferior to th'at 0385p RETS Manual'evision 7 Page 185 specified in FO-OP-022, in that it is limited to a vacuum of 13" Hg and has a.flow rate of six SCFM.In addition, the dewatering procedure used for the tests called for only four hours of bulk dewatering, as opposed to three eight-hour pumping cycles specified in FO-OP-022. The conditions of the test were clearly less conducive to proper dewatering than those specified in FO-OP-022 (this equipment,, and procedure is not used for normal operation). However, results show that adequate dewatering-is guaranteed either by extending the dewatering time in the procedure or by applying an additional dewatering cycle at the end of the bulk dewatering process using a high flow rate (approximately 200 SCFM at 28" Hg)vacuum pump.TVA has modified FO-OP-022 to include two hours of additional dewatering with the 200 SCFM vacuum pump for all resin.2.INTERFACES BETWEEN PLANT AND CNSI EQUIPMENT (a)(b)The high-integrity container is filled with spent resin slurry through a.one-inch flexible hose.Flow through the hose is controlled by way of a diaphragm-operated. valve.The hose is connected to the high-integrity container with an Evertight quick disconnect fitting that has been modified for remote operation. The dewatering pump discharges through a one-inch flexible hose to the;plant waste packaging, drain header which leads to the waste package drain tank.The connection to.the, header is made by an OPW 633 D Kamlock quick disconnect fitting.(c)Radwaste compressed air is supplied, through a A'exible hose with Cbicago connections to the air operated.positive displacement pump.(d)DemineraLized water is provided by a flexible hose with Chicago connections to the flush-inlet valve on the dewatering pump suction manifold..(e)The dewatering system is located inside the: radwaste packaging room (see, figure 1).Any leaks or spills will be contained inside this room by exterior doors which are closed during filling, and collected in radwaste floor drains.Failure of any of these resin processing components will not provide a pathway for radioactive materials into the environment or potable water supply.3 LOCATION AND ARRANGEMENT OF'EWATERING SXSTEM'N PLANT See Figure 1.w+j 0385p

RETS Manual Revision 7 Page 186 4.WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide concentrations. are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis.An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similar behaving isotopes which can be readily measured.Scaling factors are developed on a waste stream specific basis.Scaling factors are periodically reconfirmed through sampling and analysis.A QC program is in place to ensure compliance with 10 CFR 61.55 and 61.56.5~DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used fog packaging resin-The following containers, are used: 8-120, 14-195, 14-170 and are discussed in a topical, report'ated December 1983 entitled,"Chem-Nuclear Systems,.Inc., Topical.Report, Polyethylene High Integrity Containers CNSI-HIC-'14571&1-NP.." 6 CAPABILITY TO MEET 10 CFR 50, APPEND'IX I This dewatering process does, not cause any direct releases to the environment (note l.a above).IV-12'0385p FIGURE 1.t.'..i:..Aeferei.ca! 8rovvns F erry..f."sAR 9.2-)li~~l~~~g$1)04 fl.3 vari:: 0~~~~0l0000000 0000~0 OOOO~000~1001~101 ,~t~0~01100~~1~0~~100101\~0000000~000100100 Cneo Opotalir S'loll>>no-29ft.min.p~Clla-mH<iclao Syatam~~ynllcn~ihls144~I I~1~~~~~I 0'I>>~~~\\~~~II~,'f (~'~~e~~I~~~0 Oo~~~~~~~~~~~I~~~1~~~Wcl Wb':~~~Haste Packaging Room Layout for Cheat Huciear system Plan Elevation 565'V-13 0385p oooooooioooo! RETS H Revisio Page 187 lo lt.yo XQ), 5H&78 Lookout Place RETS Manual Revision 7 Page 188 QGT<t'~ss7 U~Huclear Regulatory Commission Qocument.Control Desk Qashing on, D.C.24555 Centlemen: Zn.the Hatter of Tennessee Valley huthority BRQQRC FEEBLE HUCLEAR PLAHT RKSXH'EQATMXHC Docket Hos.54-259 50 2&4~'50 296/(BFH).PROCESS COHTROC PROCRAE FOR DEHXHERALZ~ By Letter f~me.ta D.R.Huller.dated February V, 1987, TVA described.ts process cental program far demineraLQer resin devaterin8 and reques ad l!RC to reviev an4, approve it as described'in.that letter.This resin devatering process.vas tim~accsumin8. cern-Huclear Systems Znc.(CQSZ)has since improved this process by developing the RDS 1444, Rapid Deva~my System, far accelerating the devatering process.The time savings&this.devater~cg process vtLL allav BFH ta, accammoditn.its spent resin generatecd durw8 pover yaiductian. 'Vh 4ntendi ta hnplement the BDS-1444'-grace'ss.hefore 'unit 2.restart.Therefore~this subad.teal, supersedes. the February..11, 198$letter..aConsecpcenogp, TVA has elected not ta ansver, HRC's recfuest far add~tional information fram J.A Xvolinski to S-A MtCte dated Zuly 21, 1987 concerning BFH's current devate&g pracess in a'separate submittaL. Hovever;these items are addressed in the enclosures, ta this LcLtter for the'RDS LOOO system.DemineralizeŽ resin.dcwaterc~vtLL be performed at BFH using CSSZ equipment. Tha.operating methodology outlined by CSSX: in.topical repor~Du-11118mL-p h,"CtSZ, Dcwatering Control Process-Containers Topical Repoc" and RDS 25546<1 p,"RDS~1444 Radioactive Maote~Devataring System'iLL be used.HRC, accepted C?SX;Topical.Repor", DQ-LII18ML-P-h for reference by license applicants in a, Letter fram C..O'.Thomas (HRC)to L-X'appe (CHSZ)dated June LL.1985..CHSZ TopicaL Report RDS-2554WL-P vas submitted to HRC by CHSZ'oe appraval.by latter'ram'0 B House (CHSZ)to R'Emch (HRC)dated Sarah 26,, 1987 and.a.nonproprietary. copy" is encLased to this Letter (enclosure 2).These CLSZ topical, reports viLl form the basis-of the Bpd deminera~m resin dcwaterin8 process, and., systccm RncLosure 1 provides infonaatian'-recpcired by HRC ta review applicability of.the report, to specific Licensees's outlined.in, the safety evaluation for its Topical Report'V 11118-01-P-A.. Procedures far this new process.and system are scheduled. to be~eternally approved, by-October 1987..Ttfh,.requests, that HRC revi.ev the enclaeed information an4.provide approvaL, vithin this same,-."'-,.~ timeframe, for use of this report-as a process, control program as.defined in.~.the.BFH technical. specification 6.9.---.-";.:-,.... IV-'14 0385p U.S.nuclear Regulatory Cammissian RETS Nanual Revision 7 Page 189 OO-, 6"QQ,, Zf you have any cpaestions concerning,~request, please telephone Turner at (205)719 2853~~~@closed is a, check for-the$150 revier fee required by 10 CH 170.11.Very'ruly yours,~~Subbed-an+~cn to~fo me.n~~r~da af Qk'1987 TEHMESSr~V'~A~a.OR~R dley, D actor Buclear td,ccmking, and Regulatory Af aics Ho~.r*.o~~~J'<<~<<q'0~~'o<<~'Br caaaaisstaa Expkrsa%~~~" 0~~~1~~'~+0~~0',~~~.~~~f cn (Enclosures) %.C..C.Zech, Assistant Directo=Regional ZnspecQons Division of TVA Pro)eats'ffice. of.Special Pcojeccs U-$'acleac'egulatory CocmLissian ReBian ZX, 10X, Bar etta St..~BQ,.Suite 1900 Atlanta, Ceorgia, 30323.~~~0~~~'~~~~~~~~~I~~~~~~<<~~~~~A.Zeslinsld,., Assistant. Director" for Projects Division af TV'A.Pcogects Office of Special.Projects 1'$'uclear Regulatory Commission. 4350 East&est Q,ghsray E44-322;~Bethesda, Earyland.20814 B~'erry Resident'nspectoc" Bra~.Fe~Mucleac" Plant, Route'2,, P'0 Box 31X Athens,.Alahama 35<11.'~IV-'1$0385p -Revision 7 Page 190<P'>>>>'I'Mr Reenlatory C~sion cc CE clo~r~)<-c'-C.Zech, Assistant Oi Regional~nsp=actor nspec ions 4 Division of (k P roj ecta f-ace of SPeciaL Pro ec lhs.Nuclear Reeulaco Region ZZ.-.-14t Baetetta st., mr~.-e~IVw Snite 2904~~30323 4;k.MLinski~has , htsistant Director-Division of tV'VA Pagects,~ce'f$e P caal Fwgects'4354'~tMest Hi~~cLear Reetglato Beth~4a.~lane 20eu~+'$~NAee'ebury Res~...'e Res)gent'Cnapector. r~Mclear'lant. ~2, P 4'.Box'3'thens, A4haaa 35 4~~1~4O 4T-4L: CRC, cc (Enclo~~): RIBS, Rt 4N l~Verse&5R'25lpC Co E'Chrlstenhnrr-, EXX B33 C L-E;-Hannual, BR I?f 1~4 Zppolito, Bethes'LP'4V 45~theseus Ckcensine, Off'4'Who, sac~C-rC Wr;Brmme.re~-~~.BR5s use~'-R-.Nichols, BR 5S X00~-<.~th, L 6v 3'~Millialas", Ml4 BB5, C-JC)ng-~SafetY OU Zt"~7~~bV I I I I~Fll.e QQ ltl lIdf~W I 0385p ZV-16/Qj:>>. ENCLOSURE 1 RETS Manual Revision 7 Page 191 Dewatering will be conducted at BFN using the Chem<<Nuclear Systems, Inc.(CNSI)Rapid Dewatering System (RDS-1000). CNSI high-integrity containers and/or steel liners and plant specific versions of CNSI Procedure FO-OP-O32,"Setup and Operating Procedure for the RDS-1000 Unit" and CNSI Procedure FO-OP-035,"Setup and Operating Procedure.- for Dewatering Pre-Coat Media in a 21-300 Liner Using the RDS-1000" will be used.1 EXCEPTIONS OR DEVIATIONS TAKEN TO CNSI'OPICAL REPORTS DW-11118&1.-P-A AND RDS-25506-01-P TVA's system has no off-gas system connection available for interface with the RDS-1000.The.rapid dewatering skid of the RDS-1000 system has a HEPA filter installed downstream of the safety relief valve and manual bypass valve.Liners will be vented through this HEPA filter to the waste packaging room Air from this room is normally discharged through the radwaste building ventilation system.This air then flows through an installed HEPA, filter before release through a monitored release point on the reactor building roof., Exterior doors from the waste packaging room are closed during liner filling and dewatering operations. 2'NTERFACES BETWEEN PLANT AND CNSI.EQUIPMENT A A plant connection-stand (PCS)is.provided as part of the RDS-1000 system.Its components are: 1.A remotely operated valve.to control'influent to the'liner; 2;.A.diaphragm pump with, connections'o-the liner fillhead for initial gro'ss dewatering; 3.Manifolds for air and service water supplies to control elements and flushing, systems.B., Radwaste building compressed service air will be provided to the PCS at approximately 40 SCFM at 80 psig (+20,-10 psig)through a flexible hose..The connection to plant air and water is made via quick-disconnect fittings.The PCS connection to CNSI equipment is also-a quick-disconnect fitting.IV-'l7 0385p RETS Manual Revisxon 7 Page 192 C.Radwaste building service water (demineralized) will be provided to the PCS at approximately 25 gpm at 80 psig (+20 psig)through a flexible hose.Both connection points (plant and PCS)are equipped with quick-disconnect fittings.D.The dewatering pump discharge is provided by a 1.5 inch flexible hose to the plant waste packaging drain header which leads to the waste package drain tank.The connection to the.drain header is made by a 1-inch Kamlock quick-disconnect fitting.The dewatering pump connection is a 1.5 inch Kamlock quick-disconnect fitting.A 1, to 1.5-inch Kamlock adaptor will be used at the drain header.The connecti'on to the plant waste media line will be made either by a 1.5-inch 150 ANSI flat faced flange connection or by,a flange connection to Kamlock quick-disconnect adaptor utilizing existing flexible hose.A waste isolation valve will be installed downstream of this connection, providing local control by the CNSI operator over the flow of.waste to the liners being filled.The waste isolation is controlled remotely, and is interlocked to close on high waste level, high-high. level, decreasing, air pressure, or loss of electrical power.3 LOCATION AND ARRANGEMENT OF DEWATERING SYSTEM IN PLANT;~See Figure 1 The RDS-1000 system will.be located inside the radwaste packaging room, elevation. 565'.Any'eaks'r spills will be contained inside this room by exterior doors, which are closed during liner filling and dewatering operations. Any spillage will be collected in the radwaste floor drains.Failure of.any of these resin processing components will not provide a pathway for radioactive materials-into the environment'r potable water supply o ZV-18 0385p , RETS Manual Revision 7 Page 193 WASTE CLASSIFICATION TO MEET 10 CFR 61.55 Radionuclide conceritrations are determined by direct measurement. Samples or smears, as appropriate, of standard waste streams are sent offsite for analysis.An inferential measurement program is then established whereby concentrations of radioisotopes which cannot be readily measured are projected through ratioing to concentrations of similarly behaving isotopes which can be readily measured.Scaling factors are developed on a waste stream specific basis.Scaling factors are periodically reconfirmed through sampling and analysis.Computerized calculation of individual container i'sotopic contents is performed. Maintenance, testing, and independent verification of this program.ascertain correct data manipulation. TVA QA audits of the vendor laboratory conducting the periodic sample analysis confirm quality practices at that location.Procedural controls, corporate assessments of the radwaste program, periodic QA audits of the program, and management evaluation of audit findings ensure quality in the plant program.5.DESCRIPTION OF WASTE CONTAINER High-integrity containers manufactured by CNSI are used for packaging resin.The following containers are used:..8-120, 14-195, and 14-170.They are discussed in a topical report dated December 1983 entitled,"Chem-Nuclear Systems, Inc., Topical Report Polyethylene High Integrity Containers CNSI-HIC-14571-01-NP." CNSI 21-300 steel'liners are compatible with the dewatering system and may also be: used.6 CAPABILITY TO MEET 10 CFR 50 APPENDIX I This dewatering process does not cause any direct releases to the environment. FIGURE 2 RETS 1 Revision 7 Page 194 fka for'enco.'. Brogans Parry,...FSnn o.2-1li~rgv~~~..C A ar Q 1 acat i<<h f<<t'c~nl a c<<(il i<<i pvna I'1 l'lnnC caiinccCI<<n tstanil intel luis" lllllll ail'<<call<<<i lllll l<<cat l<<n.tl,'Sill@lacatl<<n (aktcrnati) I~I~I~'L~~~~~~~~~~'IO'I.fl;-3 vari,': "t.S~Q 00~000~00~~00~000000~000000~0~Clotho Oiletolor Plulto<<n I<-20fl.:.3ln.-i 0 zw,wl'I ($y.~.o Cj fnpl-fl.(clnnr baal)I balll A ll'it ir.i<I~000~000L'00)40000 ~0000~00000000000 ~0 000~000000000~0 00~\~0~0~00~0~lii ii.~0'~~0385p Haste Packaging Room Layout for Chem Nuc1ear System Plant Elevation 565'V-20 +>>>>>>)Cy~4~~)$)Nv')>>>>>>>>>>'NITED s)~TES NUCLEAR R 8GULATQ 8 Y CQM MlSS f0)%waSaetd)CraN, a, C, 0$55 RETS Nanual Revision 7 Page 195 Qg~)))g, dfEC Sd))-<r S~'~'acket Hos.50-259/260/296 Hay 6 1988 MAYf 3~~a Mr., S..A.Mhf tc Manacer of Nuclear Pa~cr Tcnncssec Yallcy Authority.6N 38A Lookout Place 1101 Market Street Chattanooaa, Tennessee 37402-2801 Gear Mr.Mhfta: SQLIKCT." fHTPIM APPROYAL QF BRSNS: FKRRY (TAC'.64700'4701, 64702)PROCES, COlPiROL PROtdRAM~Ž I',lCW I)i~)I I I I I~,I V~r Qc have.canolcted. aur revier of'he Brains Ferry revised,"racass cant<proaram (PCP)surf-.ad wfth your letter dated Qcaoer 15, 1987.~~In the Brans Ferry PCP for-.fmplcntcntfna the reoufrcnicnts of Scc:fan 6.9 cf the Technical Specfficatfons, the lfcansce has referenced the falla~fng'-vendor's;lfcensfna topical reports:~~1'V-JH840I-.P-A; Chen-Nuclear Syst'em'ac., CtSI.Oeaterfpa'ant<i: ..access Cantafners Topical Report.'.-*~V~~~~~~~)2'.OS'-ZH06-01 P, Chem>>Nuclear Sysma, Inc, ROS-1000 Radiaactivc Basta Oc~atarfno: System, Rev..0., Taafcal Repas.Ho.1 above has been approved by the, sz,f and accaotad far referencing fn future: licansfna aoolfcatfons. The rcmafnfna topical r ocr (Na.2)fs.under'-revfer by'the.NRC, staff.The NRC't's revfe)r a this toofcal repor has aeneratcd aucstfans. reauirfna thc vendor of the proc ss (Chea Nuclear Systens Inc.)to pravfac: responses.. The vendor responses~cr submitted to thc HRC by letter dated March 31, 1988.The smff's prelfmfnar.- revier of these responses has.fndfcated that this topical repor., is acceptable ~'an)ad for meetfna the requfmnents in Sec:fon;11.4 o Standard Revfev-P](S"p,)Based: on our revierve find the'revised pCP',for Bretons Fart".r', Units 1, 2'.and 3'acceptable as.an interim.approval effec:ivc until'the NRC: staff camp1etcs fts'-revim of the topfcal report: (Reference 2)described above.You may'-"-proceed~fth solidification of radfoac-fve wastes and dmatarfna of-spent resin.in accordance with the revised B~ns.Ferry PCP..The bases for acceptance are conformance ta the licensee's. PCP ta Branch Technical Pasitian ETSB 11-3',, SRP%ection 11.4, and, ta.the rcqufrencnts: @'ectian 6.9 af the.Technical Spccfffcatfons. 03S5p.)XV-21 4 RETS Manual Revision 7 Page 196~y$t988 LS-"ou>"+~ny ouestfons concirnfno ~fs f Hanacer G.Gears et 301492<76 ssue.please conic: your Pw'fncare)y, ccrc See ncxC p40e.~~mann, Acefne Assfsan-.Ofr c-.cr Robert A TVA Progee~Ofvfsfon Cfffm of Specfal progecw IV-22 LAST PAGE 0385p '"1 0}}