ML20090C145
| ML20090C145 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/31/1991 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| W3F1-92-0115, W3F1-92-115, NUDOCS 9203040281 | |
| Download: ML20090C145 (464) | |
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H. F. Dur shi W3F1-92-0115 AI.05 QA February 28, 1992 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Subject : Waterford 3 SES Docket No. 50-382 License No. F'PF-38 Semiannual Itadioactive Effluent Release Report Gentlemen:
Attached is the Semlannual Radioactive Effluent Release Report for the period July 1 through December 31, 1991. This report is submitted in accordance with Waterford 3 Technical Speelfication G.9.1.S.
If you have any' questions, please contact C.J, Thomas at (501) 739-6531.
Very truly yours, we RFB/CJT/ssf Attachment (w/ Attachment) cc: R.D. Martin, NRC Region IV NRC Resident inspectors Office
-(w/o Attachment) cc: D.L. Wiggiuton, NRC-NH H R . B . McGehee N.S. Reynolds 9203040291 911231 PDR: ADOCK'05000382 R pon
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I Semiannual Radioactive Effluent Eelease Report July 1, 1991 - December 31, 1991 Waterford 3 SES Entergy Operations, Inc.
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TABLE OF CONTENTS 1.0 SCOPE
.2.0 ' SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Haximum Permissible Concentrations
-2.3 Average Energy 2.4 heasurements and Approximat. ions of Total Radioactivity 2.5 Batch Releases 2.6 ; Unplanned Abnormal Releases
- 3.0 GASEOUS EFFLUENTS 4.0 LIQUID EFFLUENTS 5.0 -SOLID WASTES 6.0 METEOROLOGICAL DATA E7.0 ASSESSMENT OF DOSES 7.1 Doses due-to Gaseous Effluents 7.2 - Doses due to Liquid Ef fluents 7,3- 40 CFR Part 190 Dose. Evaluation l
~7'.4' Doses to'Public Inside.the Site Boundary-
)
i 8.0 =RELATEDsINFORMATION 8.1 ' Changes to the Process Cont rol Program 8.2_. Changes to the Offatte Dose Calculation Manual 8.3 Unavailability of RE3P Milk' Sampling 8.4 Report of TechnicA Specification. Required Instrun?nt Inoperability q 8.5- Act.ivity Released via Secondary Pathways ;
8.6 - Missed Ef fluent Samples
' 8'.T Additional Information -
- 8.8 CorrectJens to Semiannual Radioactive Release Reports l' 9.0 TABLES l it 10.0 ATTACHMENTS W310526HP 1
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1.0~ SCOPE This Semiannual Radioactive Effluent Helease Report is submitted an -
required by Wnterford 3's Technical Specification 6.9.l.8. It covers the period f rom July 1,199' through December 31,1991. Information in this "
report is presented it, tit format outlined in Appendix B of Negulatory j Guide 1.21. ,
The information contained in this report includen: ,
(1) A summary of the quantities of radioactive liquid and gaseous effluents and solid wastes released from the plant during the reporting period; 3
(2) _ A summary of the meteorological data collecter! during 1991; (3). Assessmenet of radiation dosen due to liquid and gaseous r;.idioactive-effluentn-released during 1991; (4). Explanation of why certain effluent inst rumentation was- not restored ,
l to operable status within the time specified in the ACTION Statement, +
lt i as - per UN't-00%014, Of f nite Dose Calculation Manual -(ODCM), -
Specification 5.6.1 and 5.6.2;
~
i (5) 'A-aummary of the. quantities of radioactive gaseous cffluents released' l
!.- f rom identified miscellaneous accondary release pathways for -1991;
'(6) A? summary of changes to the_Offsite Dose Calculation Manual and the Process Control-Program during-thin reporting period.
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h 2.0' SilPPLEtiENTAL INF0felATION 2.1 R_egulatory Limits The Limits applicable to the telease of radioactive material in
. liquid and gaseous 'ef fluents are described in the following sect ions.
These limits are addressed in UNT-005-014, Offsite Dose Calculation ,
Manual.
2.1.1 Fission and Activation Gases (Noble Gases)
The dose rate due t o radioact.ive noble gases released in gaseous effluents from the alte to areas at and beyond the site boundary shall be limited to less than or equal to 500 mrem /yr to the tot.a1 body and less than or equal to 3000
, mrem /yr to the skin.
The air dose due to noble gases released in gaseous effluents
-from the site to areas at or beyond the site boundary shall be
-limited to the f ollowing:
i
- a. During any calendar-quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad f or beta ridia 4 on and, b, .During'any calendar year: Less than or equal.to 10 mrad
! for gamma ' radiation and less than or equal- to 20 mrad for _
beta radiation.
2.1.2_ lodines; Particulates, llalf Lives > 8 Days; and Trit.ium The dose rate-due to Iodine-131 and 133, ttitium,' and all radionuclides in particulate form with-half lives greater than eight (8) days, released in gaseous effluents from the' site to ' areas' at and beyond the site boundary, shall be limited to'less than or equ'i to a 1500Lmrem/yr to.any organ.
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The' dose to a member of the public from lodine 131 and 133, tritium, and all radioauclides in particulate form with half liveu-greater than:eight (8) days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
- a. During any calendar quarter: Less than or equal to-7.5 mrem to any organ and, i
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
2.1.3 Liquid Effluents The. concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10 CFR l' art 20, Appendix B, Table II,-Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-4 pCi/ml total activity.
The dose or dose commitment to a member of the public f rom radioactive materials in liquid effluent.s released to unrestricted areas shall he limited to the following:
I a. During any calendar quarter to less than or equal to 1.5--
mrem to the total body and less lthan or equal to 5 mrem
, to any organ, and=
- b. During any calendar year to less than or equal to-3 mrem to the whole body _and to less than-or equal to 10 mrem to 4 any organ.
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2.1.4 Uranium Fuel Cycle Sources The dose or dose conunitment to any member of t he public due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited to less than or equal t o 25 f mrem tc, the total-body or any organ (except.the thyroid, which shall be limited t o lesr, than or equal to 75 mrem) over
, 12 consecutive montha.
2.2 ' Maximum Permissible Concent rat ions 2.2.1 Fission and Activation Gasen; lodines; and Particulates, lla l f Lives > 8 Days ,
For gaseous ef fluents, maximum permissible concentrations are not directly used in release rate calculations since the applicable IJmits are expressed in t erms of dose rate at the site boundary.
-2.2.2 Liquid Effluents The maximum permissible concentration (MPC) values specified in 10 CFR Part 20, Appendix lb Table II, Column 2 are used an the permissible concentrations of 1iquid radioactive effluents at the unrestricted area boundary. 'A value of 2,0E-4 pCi/ml is used as the MPC for dissolved and ent rained noble gases in liquid' effluents, 2.3~ Averag,e Energy This is not applicable to Waterford 3's Ef fluent Specifications.
E-flars are not: required to be'calculater1 irom effluent release data, i
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2,4 Heasurements and. Approximations of Tota' Radioactivity i 5
The quantification of radioactivity in liquid and gascoun ef fluents was accomplished by performing the sampling and radiological analysis of _ ef fluents in accordance wi t h the requiretaents of Tables 5.3-1 and 5,4-1 of IJNT-005-014, Offsite Dose Calculation Manual. ;
2.4.1 Fission and Activat. ion Gases (Noble Cases)
For continuous releases, a gas grab saraple van analyzed 1
monthly for noble gases. Each week a Gan Ratio-(GK) war.
~
calculated according to the following equation:
GR = AverageJ'eekly_NoblQs Mordtor_ Read _iny,
. Monitor Reading During Noble Gas Sampling The monthly sample analysis and weekly Gas Ratio were then used to determine noble gases dir. charged continuously-for the +
previous week. For gas decay tank and containment purge batch releases, a gas grab sample was analyzed prior to
. release to determine noble gas concentrations in the batch.
-In all cases the-total radioactivity in gaseous effluents was determined f rom measured concent rations of each- radionuclide present and the total voliune discharged.
2,4,2 Iodines and Particulates
-lodines _and -particulaten discharged were sampled - using a continuous sampler which cont.aine'l a ciarcoal cartridge .and a .
part.iculat e filter. Each we'ek the charcoa: cart ridge and particulate filter were analyzed for gam:na ce r ' ters using gairena spectroscopy. - The determined radionuclide concentrations and effluent.' volume discharged were used to calculate the previous week's actjvity released; W3105261(P _ 6
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The particulate samples were composited and analyzed quarterly for Sr-89 and Sr-90 by a contract laboratory (Teledyne isotopes).
Particulate gross alpha activity was measured weekly using '!
- alpha scintillation count ing techniques. The determined activities were used to estimate effluent concentrations in subsequent releases until the next scheduled analysis was pe rf o rmed ,
Grab semples of continuous and batch releases were analyzed monthly for tritium. The determined concentrations were used to estimate trit.inm activity in subsequent releases until the next r,cheduled analysis was performed.
2.4.3 Liquid Effluents j For continuous releases, samples.were collected weekly and ,
analyzed using gannua spectroscopy. The meat.ured concentra-
.tions were used to determine radionuclide concent rationr Au the previous week's releases. For batch releases, gamma analysis was performed-on the sample prior to release, For both continuous and batch releases, composite rampler.
were analyzed quarterly by'a contract laboratory (Teledyne Inotopes) for Sr-89, St-90,_and-Fe-55, . Samples were composited and analyzed monthly for tritium and grosu~ alpha using liquid _
scintillation and gas flow: proportional counting techniques,-
i respectively. For radionuclides measured in the composite samples, the measured concentrations in the composite samples f rom the previous month or ~ quarter were used to-eitimate t
. released quantitles of Ibese isotoper, in 1Iquid effluents
~
during the current month-or quarter.
u l-p The total radioactivity in liquid' effluent releases van determined from the measured and estimated cencent. rations of L
cach radionuclide-present and the total. volume of the effluent discharged, W31052611P 7 l
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2,. 5 11atch Releasea
-I A summaryJof inf ormation f or gaseous and liquid batch releases -
1 is- included in Table 1. 1
)
2.6 Onplanned Abnormal __ Releases 1
During thin reporting period, there were no instances of Unplanned '
Abnormal releases, i
3.0 GASEOUS EFFLUENTS The quantities of radioactive material releaned in gaseous effluents are I summarized in Tables 1A, IB, and IC. Note that there were no elevated re-l
-leases, since all Waterford 3 releases are considered to be at ground level.
The estimated total error in % is based upon several statist.ical uncertain-ties due to sample counting, ef ficiency, volume, etc. Detailed statistical >
evaluatione of error are not required as per Regulatory Guide 1.21.
- 4.0 LIQUID EFFI.UE _NTS -
The quantitles of radioactive material released in liquid effluents are summarized in Tables 2A and 2B. The estimated tot.al error in % is based :
upon several statistical uncertainties due to' sample counting, efficiency,
-. volume, etc. Detailed statistical evaluations of error. are not required as per Regulatory Guide.l.21.
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5.0 S_OLID WAS_TES.,
The- suramary of radioact ive solid vastes shipped of fsite for elisposal in listed in Tabic 3. For certain waste forms Waterf ord 3 is now using volume reduction services provided by Scientific Ecology Group, Inc. and Alaron Corp. These waste fctms are identified in Table 1 and volumes reported reflect the volume of waste shipped of fsite, not final disposal volumes. Final disposal volun,es are reported au they become available The est imat ed total error in % is based upon several r.tatist ira'i uncert ainties due to sample counting, ef ficiency, volume, etc Detailed statistical evaluations of error are not rettuired ha per Regulat ory Guide 3 1.21.
6.0 ?!ETEOROLOGICAL D.AT.A..
In Table 4 the -hourly met eorological data f rom January 1, 1991 through December 31, 1991, is presented in the form of joint frequency dist ribn-tions of wind speed, wind direction, and atmospheric stability. The .i Waterford-3 ' data recovery results by parameter are as f ollows:
- i Pa ramet er January June July,- December Entire Year i Delta T 90.5% 94.5% 92.7%
Wind-Speed 98.3%. 96.5% 97.4%
Wind Direttion 98.3% 96,5% 97.4%- ,
Overal1*- 88.8% 9I.4% 90. I'l
.1 y
- Simultaneous occurrence of valid data for all t hree parameters. .
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I 7.0 - ASSESfetENT OF DOSES 7, l ' Dose 1)ue to Gascoin fif, flu,en_t g 7.lel Air Doses at the Site lloundary i
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Air doses from gaseous cffluents were evaluated at the closest j ofinite location that could be occupied continuously durlug j the term of plant cperation and that would resu!t in the ;
highest dose. This location was determined by examining the atmospheric dispersion parameters (X/Q'rd at the closest offalte locations that-could be continuously occupied during plant operatton in each of the meteorological sectora surround-ing the plant. The location that would have the highest dose would be that location having the moeit restrictive (targest)
X/Q value, liased on actual meteorological data collected during 1991, this location was determined to he in t he NE sector at. a distance of 966 meters f rom the plant. Doses were assessed at this locat.lon in accordanee with the methodology described in the Waterford 3 Of f sit.e Dose Calculation Manual considering only beta and gamma exposures in air due to avble gas. The results 'of ther.c assesuments for the year 1991 are summarized as follows:
l Ileta air dos'e: 0.88 mrad l
.- Gamma a t r dose: 0.31. mrad L_
l l-The' beta and gamma air doses are 4.4% und 3.1% of the Aunual Dose Limits, respectively. The results of the dose calculations by quarter are t.ummarized in Table 5.
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- 7.1.2 ' Maximum Organ Dose to t he Cri tical Receptor '
The maximum organ dose t-o a MEMBER OF THE PUEilC from I-131, 1-1.$3, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous ef fluents .;
released to areas at and beyond the site boundary was deter-mined for 1991.
An assessment of the maximum organ dose was performed for the ritical receptor. The critical receptor was assumed to Y
be located at the nearest residence to the plant having the most restrictive atmospheric dispersion (y,/Q) and deposition (D/Q) parameters. Furthermore, it was assumed that the receptor living at this residence consumed food products that were either raised or produced a'. this residence. Using land use census and meteorological data for 1991, the residence with the hsghest X/Q and D/Q vaiues was determined to be in the.N sector at a distance of 1448 meters. The dose calcula-tion was perf ormed in accoraance with the methodology described in the Waterford 3 Offsite Dose Calculation Manual considering the inhalat.lon, grotmd plane expt,sure, and ingestion pathways.
The maximum organ' dose to the critical receptor was determined to be 1.86 mrem to the infant thyroid. This represents 12.4%
of.the Annual.Do8e Limit. Duse calculat. ion results are summarized by quarters in Table 5.
7.2 Doses Due to Lir,uid_ Effluents 4
The annual doses -to the maxinium exposed individual resulting f rom exposure to liquid effluents released during.1991 -from kuterford 3 were 0.73 mrem total body -and'O.99 mrem to the maximum exposed organ (liver)..These values are 24 4% and 9 M % respectively, of the Annual Dose Limits. Dose calculation resulta .are sunnarized by quarters .ir; Table 5'. The doses were calculated in accordance with the methodology described'in the.Waterford 3 Of f site Dose' Calculation Manual .
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7.3 40 CFR Part 190 Dose F.valuatio_n In accordance with Waterford 3 Offsite Done Calculation Manual, Section 5'5.2., dose evaluations to demonstrate compliance with Surveil-lance Requirements 5.5.1.a and 5.5,1.b of the ODCM, dealing with dose from the uranium fuel cycle, need to be performed only if quar terly doses exceed 3 mrem to the total body (liquid releases), 10 mrem to any organ (tiquid releases), 10 mrad gamma air dose, 20 mrad beta air dose, or 15 mrem to any organ f rom radioiodines and particulates. :
T At no time during 1991 were any of these limits exceeded; tnerefore, no evaluations were required.
7.4 Doses _to public Inside the Site Boundary The Member of the public inside the site boundary expected to have the maximum exposure due to gaseous effluents would be an employee ,
at Waterford 1 and 2-fossil fuel plants, located in the NW sector, approximately 670 meters from the plant. Based on an assumed occup-ancy of 25% (40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> _ work week) and the fact that all employees are ,
adults, the maximum organ dose would be-less than 0.046 mrem to the ,
thyroid. Total body and skin doses were calculated to be 0.05 and 0.13 mrem, respectively. These doses were calculated according to the methodology described in the Waterford 3 Offsite Dose Calculation ,
Manual considering only the inhalation and ground plane exposure pathways.
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- 8.0 RELATED
- . - . -_. 1_Nf0RMAT10N 8.1 Chynygs to the Process. p n_ trol l ogrgm There were sir,nificant changes to the Process Cont rol Program f or the period covered by this report. In accordance with NRC Generic
' Letter 89-01, the Process Control Program has been removed from the
, Site Technical Specifications and placed in procedure NW-001-210, Process Control Program. This change recieved prior NRC approval and was implemented on September 24, 1991. Copies of the changes to the Process Control Program are included in Attachment 10.2.
S,2 Changes to the Offsite Dose Calculation Manual There were significant changes made to the Waterford 3 Offsite Dose Calculation Manual during the period covered by this report.
In accordance with NRC Generic Letter 89-01, Radiological Ef fluent.
Technical Specifications have been removed frnm the Site Technical Specifications and placed in the Offsite Dose Calculation Manual, UNT-005-014. This cnange received prior NRC approval rind was implemented on September 17, 1991. A revision to the Offsite Dose Calculation Manaal was done on November 29, 1991 to clarify environmental sampling locations, add two food product sampling 4 locations, include list of references to specific factors used in the calculation of A. and R. factors, include bioaccumulation factors, 1 1 correct typographical errors, and change the applicability requirements for the Waste Gas ll61 dup monitor and .the Main Condenser L Evacuation and Turbine Gland Seal. monitor to reflect that monitor operation is not required while the systems are not being operated.
A change to t.he ODCM, done on December 23, 1991 and effective on January l1992, implemented a new value for the bioaccumulation factor in fish for t.he element niobium. Affected dose factors were also changed. Copies of the changes to the Offsite Dose Calculation Manual are included in Attachment _10.1.
- 8 ~. 3 Unavailability of REMP Milk Samples -
Due to the unavailability of three. milk sampling locations within five kilometerr of the plant, Broad Leaf ~ sampling in performed in accordance with ODCM Table 5.8-1, Milk is collected, when avri:lable,-from the control locatioa and two ident ified sampling locations as indicated in Waterford 3 Offsite Dose Calculation Manual, Attachment 6.14, 1310526flP 13
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- 8. 4 Report of_lk<1uiled.Fffluent_1nstrument_) nope;rahi1ity ODDi speci fications, 5.6.1.b and 5.6.2.b requi res report ing '
in the Semiannual Radioact ive Ef fluent -Release Report of why desig-nated inoperable effluent monitoring inst rwnentation wn; not restuned to operability within the tinie specified in t he ACTION Statement.
Thiring the reporting period, there were no cases when lust rument at ion l
was not restored to operability wit hin the time specif leil, 8.5 Activ,ity, Released Via Secondarv Pathways ,
f The following secondary release paths were continuously monitored for radioactivity: 1) the Hot Machine Shop Exhaust (AH-35), 2) Decont.am-inataon Shop Exhaust ( All-34 ) . 3) the rah H&V Equipment Room Ventilation system Exhaust (f.-41 A and E-41B); and 4) the Switchgear/ Cable Vault Area Vent flation System (AH-25). Continuous sampling for these areas is maintained in order to denionstrate the operaleility of int.talled treatment systems and to verify integrity of barriers separating primary and secondary ventilation systems. Sacapliag for these areas-was limited _to continuous particulate and iodine uampling and monthly noble gas grab sampling. The activity released via these secondary pat.hways resulted from routine operations and remained below significant l e vel n -, Table 6 contains a summary of activity released during 1991.
8,6:-M1ssed-f.ffIuent Samples!
8.6.1 lio liquid or gaseous effluent samples were missed during this reporting period.
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1 8,7 Addit ional Informatiori The most. recent Heactor_ Coolant System E-Bar calculation was l.649 MeV/ Disintegration from a sample obtained on June 24, 1991.
Reactor Coolant System E-Bar is supplied for information only and is not used for effluent dose calculations.
I i
88 Corrections to Semiannual Radioactive Release Reports Corrections to Table 3 of Semi Annual Radioactive Release Report '
covering the period from January 1, 1991 to June 30, 1991 are presented in attachment 10.3. These changes are due to submittal of ,
actual burial volumes and activities from volume reduction and disposal f acilities, which was not available when t he last report was submit ted to Ihe Nuclear Regulatory Conunission.
9.0 TABLES -
1 Batch Release Sunnary
_lA _ Semiannual Sunnation of all Releases by Quarter - All Airborne Effluents IB. Semiannual Airborne Continuous Elevated and Ground Level. Releases 1C SemiannualLAirborne Batch Elevated and Ground Level Releases 2A Semiannual' Summation of All Releases by Quarter - All Liquid Effluents 4 2B Semiannual Liquid Continuous and-Hatch' Releases 3' Solid Waste Shipped Offsite for Disposal 4 ' Joint frequency Distribution.of_ Meteorological Data S. - Dose Culculation Results for 1991
- 6. Activity Calculations for Secondary Release Pathways for 1991 10.0 : ATTACitMENTS .
10.1 Changes to Of fsite Dose' Calculation Manual; July 1, 1991 to. ,
December 31, 1991, _(349 pages) m 10.2 Changes to Process Control Program; July 1, 1991 to-December 31, 1991'(11 pages) 10.3 Corrections to Table 3 of' Semiannual Radioactive Release Report of January 1,'- June 30, 1991 Submitt.a1 of burial volumes and-activities f rom volume reduction and disposal f acilities. (3 pages)
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REPORT CATEGORY : BATCH RELEASE SdHnARY RELEASE POINT : ALL TYPE OF RELEACI : BATCH Ll0010 AND GASE0 tis PERIOD START Tine
- 4344:00 HRS = !?:004 ALY 1.1991 PERIOD END TIME 8759:59 HR$ = ll:54P" OECEMBEP 11. 1991
- L10U!D GELEASES
- HuMBER Of RELEASES : 61 e TOTAL ilHE FOR ALL RELEASES : I M ).D dlMJTES '
MAXinun TIME FOR A RELEASE : 370,0 M WJiES-AVERAGE fire FOR A DELEASE : 253.1-NIN'ITES MINIMitt TIME FOR A RELEASE - 2 194.0 nif4JiE AVERAGE STREAM Fl % -t 907539.6 GPn GASE0l$ RELEASEG NunBER OF RELEASES : 0-TOTAL fine FOR ALL FELEASE3 : 9,0 HlHUTES-MAxtf1Jn Tiri FOR A DELEASF : 0,0 MINUTES AVER 4E,E I!ME FOR 4 EELEASE -
0.9--MINUTES MIN! nun ilttE COR A GELEASE : 0.0 nlNUTES
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-1 TABLE 1A 2
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- EPOR1 CATEGDPY
- CEMIAwR SUMMATION OF ALL KLEASES PV OW1fC Type OF 4CTIUlTY : CLL AIRBORNE EFFLUEhTS WEPORTING PE910D : QUMTER 4 3 AND QUARTER t *- -
iTAT10N OR UNIT NUMBER : 1
- UNIT :0UARTER 3 : QUARTER 4 :EST. TOTAL: ,
- : HOURS : HOURS :EPOR %- '
- 24346 6552 :6553-8760 :
TYPEOPEFFLUENT :
A. FISSION AND ACliVATION PRODUCTS
- 1. TOTAL RELEASE : CURIES : 6.e3E 0012.61E 00 : 1 30E 01: .
- 2. AVEPtGE reELEASE EATE FOR PEP 10D :Ut!/SEC : s.35E.01 5 78E.01 :
3, PEREENT OF APPLICABLE L!nli -
% : r/A : N/A :
- B. . PAD 1010 dites .
1< TOTAL 10 DINE.131 CURIES : 6.92E.06 : 2.?6E-05 : 1.50E 01:
2 AVEPACE RELEASE RATE FOR PERIOD :UCl/SEC 0.72E 07 : 3.47E.06 :
2...
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3 PER ENT OF APPLICABLE LIMli : 3 -: N/A : N/A l' ,
' C. PARTICULATES
' I3MIICIiEIE5iUU.TIOE555'EM5I"IClEIE5'"'i'i!5'EE-LEI'i!05E2EI'i!555'5II
- 2. AVERAGE RELEASE RATE FOR PERIOD -:UCl/5EC : 2.?4E.05 : 1.32E.05 ;
.6M 3; PERCENT OF APPLICABLE LIMIT : 4 : N/A -
N/A 4, GROSS ALPHA RA010 ACTIVITY : CURIES : 3.34E.06 : 5.07E.06 :
= 0. TRIT Un
- 1. TOTAL RELEASE : CURIES : 9.34E 01 : 3.43E 02 : 1.90E Clt
- 2. AVERAGE RELEASE RATE FOR PERIOD' :UCl/SEC : 6.72E 00 : 4.32E.01 :
3J PERCENT OF APFilCABLE LIMITL :
.- O
- N/A : N/A i
=...... ................... ............................... ..........
4
{
'a J
- W310526HP 17 m._ .. ._ . - . _ . -_ - . - .. m _ - - - . ~ - - - ~ . - - - -
.~ . .. .. .
4 TABLE IB (1 of 1)
REPORT CATEGORY : SEMIANNUAL AIRBORNE CONTINUOUS ELEVATED AND GWO
- LEVEL RELEASES. TOTALS FOR EACH NUCl.lCE RELEASED.
TYPE Or ACilVITY : FISSION GASES, !0 DINES AND RARTICULATES REPORTING PER100 : JUARlER43NOQUARTEE44 STATION OR UNIT Mr$ER : 1
- ELEVATED RELEASES : GWO RELEASES :
- UNIT : QUARTER 3 :00ARTER 4 :00ARTER 3 :0'J ARTER 4 :
- : HOURS : HOURS : HOURS : HOURS :
- Nutt10E : :4345.+%2 :t%3-B'60 :4345-e%2 6%3-0760 :
FISSION GASES XE.133M : CLRIES : 0.00E.01 : 0.00E-01 : 0.00E-01 : 2.61E 00 :
-XE-133 : CURIES : 0.00E-01 : 0.00E-01 : 4.94E 00 : 0.00E-01 :
- 0.00E-01 : 0.00E-01 : 1.69E 60 : 0.00E.01 :
XE-135
-..... ..................:. _CLRIES TOTAL FOR PERIOD- : CURIES : 0.00E.01 . 0.00E.01 : 6.63E 00 : 2.61E 00 :
IUDINES-1-131 : CURIES-: 0.00E.01-: 0.00E.01 : 6.92E.06 : 2.76E.05 :
-1 133 : CURIES-: 0.00E 01 t 0.00E.01 : 0.00E.01 : 7.36E 06 :
TOTAL FOR PER!00 : CLRIES : 0.00E-01 : 0.00E-01 : 6.92E.06 : 3 A9E. 6 :
PARTICLtATES H-3 : :-- CURIES : 0.00E.01 : 0.00E 01 : 5.34E 01 : 3.43E 02 C5 137 : CURIES : 0.00E.01 : 0.00E.01 : 1.21E.07 : B.00E.01 :
G ALPHA : CURlES : 0.00E.01 : 0,00E 01 3.34F.06 : 5.07E 06 :
BR-82 : CUR!ES : 0.00E-01 : 0.00E.01 : 1.7BE.04 : 1.ME.04 :
TOTAL FOR PERI @ : CURIES : 0.00E.01 : 0.00E.01 : 9.34E 01 : 3.43E 02 :
W31052611P- 13
1 i
Tall!I IC .
(1 of 1) l
-l
.i i
e REPORT CATEGORY : SEN!Mt!AL AIRBORNE BATCH ELEVATED AND GR0'Jto
- LEVEL ECLEASES, TOTALS FOR EACH NIILIGE PELEASED.
TYPE Or ACTIVITY i FISSION GASES, 100lNES. AND PARilCULATES REPORTING PER!DO : OLG TER t ) nND QUARTER t 4 STAlifN OR UNIT NLt0ER 1
- ELEVATED PELEASES : GROUND RELEASES :
- UNii QtARTER 3 :0LM TER 4 :0iMRTER 3 :0tMTER 4 :
- HOURS : HOURS :HOUPS DOJPS !
NilCLl[( : 14 M .6552 teH 3 8760 :4345 6H? :6%)-940 :
FISS!0H GASES-TOE 10 DINES
' FONE PARTICULATES N0tE l::
u i
W31052611P : 19 t
k t v- + , m - -, r .- w -. w - ,w ,
f Tall!I 2A i
(I of !)
l i
i KPfff CATEC/Wf : FIM!AWJ% StnMAllDN Or All. RELE95Ei lif 0#1ER I TYPE OF AC11ViTY 14L L10JiD (FfllEN19 REPOR11% PIRids . OM1ER i ) 40 J#1EG t 4 ;
51A110N OR UNil Mi$ER t 1 totARTER I 200A#tER 4 tf$i.101at!
- 0411 t : 6 95 :C&S tin'fB \ : ,
i 14145 6H216%).0760 t :
1YPE OF EFFLtINI P
A4 FISSION w o ACT1 % TION PP0"JCis J ;
- i : i 1,101AL RELEAM001 INf1UD14 * .
IRiflun,f,ASES,ALPtw tCURIES t 8. hE.02 1 7.H E.02 : 1.5 n 01:
.................................................=............................
- 2. AufREE DILUTED COTEN1 RAT 10N DURi% PERIOD tuCl/HL : 2.7M.08 4.50E.09 1 '
i N/A 1 N/A 1
. ), PEPCENT Of APPLICABLE LIM 11 %
B.TRiflun
- 1. TOTAL PELEASE CURIES t B.0lt 01 1 1.01E U2 : 1.50E 011 t i t
- 2. AVER EE OlLU1ED CONCENTRAll0N .
OURi% PERIOD tlE!/ML ?.24[.0614.0)C.06*
...................................................................... 4/A 1 N/A l
- 1. PEPCEH10F APPLICABLE LIMIT % 1 C. OlS$0LVED 40 ENTRAINED GASES ,
- 1. !31AL PELEASE ICLElES t 4.64E.02 8.46E 02 : 1.H E 01:
i 1 - t
-2. A'KREE DILUTED C0HEENTRA110N O tliCl /ML i 1.)M.09 3 4.B6E.09 i .
....'JRINr. MR100 HA i
- 3. PERCENT [# APPLICAPLE LIMli i % i H- t
..................................................... ................ 1
- 0. GROSS ALPHA RA010ACilVl1Y
- 1. TOTAL RELEASE ICURIES t 0.00E-01 1 0.00E.01 1 1.%E 01:
i 4.35E 05 1 2.95E 05 : I J0E 01:
E. WASTE VOL PELEASED(PRE.DILUT!DN) tGAL ,
tGAL i 9.4)E 09 i 4.60E 09 1.50E B11 F. VOLUME OF DILUtl0N..................................................
WTER L'. SED ,
5 i
- U310526HP 20 g . #w ...~.+4..w~.w r . v a- - -.m-1-% .e-, . . ---
i f
t TAhlI 2H ,
O of 2) ;
i f
f I
l P[Pt1R1 CAffGrFf MMIMtAl i !Wl0 (D1119015 At (4104 PitE6ES 1 101R5 MR (ACH ret.llf Pfl(WD.
1YPE & Atilulf f Att 9ADi[Nti t,l M S ii PEP 091 tT. KPl@ t 2.41ED ) @ QMi[4 44 SM1104 W ir41191RD 1
- CON 11HlOJS MtEASf.S : MtrH etL(Ws , '
t (All :JKMER 3 t0WAffP 4 tot #4tw 1 :OlMit? 4 : r 1 tHOUkh HMS IHOLFS INILFS WL!ti t 14145.tM ? IIAS)4 hD :414%%7 ttM1440
. . . . . . ............................................. P ALL
. .....'llf1MS
...................................................................,...- f 41 : CtRIES t 0.00E.01 1.91E4 4 1 A NA.74 CtFIES : 0.flE41 : 0.00f.011l.01f0111.0lf47: .17E45 t 0.00E41
- i EW4) (W :S I 6.91)E41 10.00041 12.60f 0) t 0.Q0f-01 1 >
tN44 1 CtRRS t 0.0M4) : 0.01E.01 1 2.444) : 4./)f-03 FE.% Ctp :S i9.0R.0110.00F.01i).15E.0?t4.4?F.0)
FE49 i CtFWS 0.0M 41 1 0.00E.01 1 1.9 ff-04 1 0.00f 41 '
C048 CtR ES t 0.00f.01 1 7.26E.07 .??E 0) t C04a 1 cts is : 0.ont.nl t 5,00L 01 : 2.4t.t.07 1,54E.07 : *1.14f42 : :
P +$ 1 Ctp:.ES t 0.0M.01 1 0.00f.01 1 0,00E.01 : ?.18(44 5 '
M 92 1 CtWlES 1 0.0K.01 t 0.00E.01 : 0.6E 04 a.??E 45 1 TWM 1 Cts 1ES : 0.00E.01 1 0.00E 01 1 1.99(-01 1.7?f.01 7R.97 - 1 (UPIES : 0.04 41.1 0.000 01 1.95E44 2.)0i.04 NR 95 : CWlES : 0.00E.01 t 0.00E.01 1 1.91(.01 : .t.600 01 1 Rth10) t nWils : 0.00f 41 1 0.00E.01 1 7.236 0+ 1 0.0 4 01 1 P0 106 : MF1ES-! 0,0 K.01 1 0.00E.8) t 2.04 0) 3.75E.M t AG.110'1 1 DFIFS : 0.0M.Ul 1 fl.00E41 14.HC 01 ! e5E4) 1 o l.131 1 CLPIES 1 0.00(.01 0.00(41 1 4.61 @ t 1. 65E. 64 '
CS.134 t CUPl(S .1 0.00f.01 1 0.00D 01 1 7.76[(.03 1 1.91E.0 :
- CtElf S 10,00i41 10.00E 01 1 1.04f.07 t 2.WF U - i
~05 137 '
94119 1 Ctrl!S 1 0.00E.01 1 0.00E.01 0.0M 01 1 1.77E.M ,
in.140 CLRIES : 0.00E.01 1 0.00f +01 1 3.97f 04 i ?.70E-M i t LA.147 : CtRif 9 1 0.0M.01 1 0.0pE 01 : 1.1M.M 1 pnf.01 1A197 : CWitS : 0.00b 0 e.BJE41 : ?.7?E4417.91E44 :
- YE.131M : Ct91ES ' O.00E 0}1 1 0.00b01 10.004) t 6 4E44 : -
XE.13)?t 1 CtRIES 0.00E41 0.00E-01 1 4.00604 1 8.41t44 '
Xf.1)) i CWlES t 0.00E41 : 0.00D01 1 4.Mf 47 : L Mf.07 1 XF.! n : Cl$lis t 0.orsal : 0.00f 41 ' 4.27E.04 t 1.(444 : ,
, SR.90~ i 0 91E5 t 0.0 E.U1 1 0.0bE.01 1 8.?aG 06 t 9.00E.ill t i i
+
r J
r
- i. 6 I :
,c !
1: ,
L !
11 U31052611P- 23 l
L
F I
i i
TAllLE 211 l' (2 of 2) .
t u
1 i
t r
r y
r r
r h
ktPORTCAtlG0ty : SE'119Nw (10010 m.11cm un FalCH KLEAiE5 [
1 101 A s H* [MH vittif 4tiMIO.
1 4E ry atituity : t.tt FM10Mittf5 i VIV(21[W. Pf31c0 : W ifGt3 ub VSSIEQt4 1 [
STAllCH OR (Nil Wt(9 1 ,
PMCH PitE W S :
- 03411NWd$ REl(Ml51 t LN11 20*pTE9 3 so mofE9 4 : p STER 3 :0t u i[9 a :
! iHOllP9 itOk5 160f5 . IW fai !
ff)Ct lff i 14)4b 6% 7 16H 3d h fi 14145 6M 7 16% ).0h h 1
..... .. ~........... ................ ......................................... :
(OHitRED r ALL MIt.10E9
.....................e.......... .............................,....... ..........
1.?E.04 1.97t.04 :
C0 57 1 tte(5 i0.00(.01: 0.00E.01 ,
% 174 ft* lF5 1 0. MF.01 1 0.00E.61 : 2.77E.04 t 2.19E. % : l 54 11) Ct9 lt$ 1 0.%E.0) 1 0.00(.01 : 7.??E.f4 : 1.06E.03 i i tB 97 : DA!ES : 0.00E.01 t 0.00t.01 8.41f.06 6.39t M t >
% )27 : DAli$ 1 0.Hf.b) 1 0.0 tie.01 1 4.?$[.M i 0 73f.06 6 50 175 CtJPIES : 0.00E.01 : 0.00E.01 : 6.62E.63 1 6.9{ 0) :
F ................-...... ................ U HE.t1 .........................
1 1,04E.04 8.01E 01.............
- 1.0?E 02 !
TOTAL IDR PfR100 : CiflES
(
I ~~ h I' }
f J.
i I
r l' -
I L
I L
o 6 L-U310$26fIPz 22 ,
i4 -
' ,s
,,rme-,...-...-,..n..e , . ~
Tall!.E 3 #
j (1 of 10)
SOLID WASTE SillPPED OITSITE l'OR DISPOSAL r
. Dl!RIMC l'ERIOD 7/1/91 TilRil 12/31/91 i
i WASTE CONTAINER WASTE 10TAL F
TYI'F V01.UME (fL3) VOLUME (ma ) ACTIVITY (Cl) ERROH j- . . . . ~ _ . . _ , . _ _ _ . _ __.
i
- (B) Non Compacted Dry 1040 115.3 2.54E-! *1 125%
Activity Waste Shipped to
{
Scientific Ecology 29.64 1.07E-1 125% ;
Group for Volume llurial Volume 11uried Activity Reduction
- J (D) Non Compacted Dry 1040 117.79 1.15E-1
- 1 125%
Activity Waste i
Shipped to i Alaron Corp for Volume Reduction
- l
.4 P
- Weste volumes _ shipped for volume reduction do not reflect final burial vaste volumer unless otherwise stated. -f
- 1' Activity determined by estimations.
- 2 Acth ity determined by measurements.
t W31052611P - 23 -
v ~w+ .*~.eu
- .c h.2-,,.e ,we v.,.wem-w.,..-e-or,,.ev.wy ,c,.e,--wee.m.,.<.. ewe w. y, - , ,.,,-r#.+.-w .4.=yv.=,w,-e.-e-rm-.wy- s -v. n- n -w-,-*m,,w-,- ~ym.w
1 l
i TAltLE 3 (2 of 10)
.i SOLID WASTE SillPPED OFFSITE FOR DISPOSAL DURING PERIOD 7/1/91 T1180 12/31/91 l
w..- _
e.-...m..-~- -.
WAhTE CONTAINER WASTE TOTAL ;
TYPE a a I VOLUME (ft ) VOLUME (m ) ACTIVITY (Ci) ERROH s
,,,., we me. s.ne neuaus4a i u.e.-.
(A) Resin Wante Management 170.8 4.8 2,97E+02 $2 125% i
. Resin Dewatered in a liigh Integrity
-Container (llend Resin) r (A) tiechanical Filters 120.3 3.4 1. 55 f'4 02 *2 125%
i Dewatered Shipped in a lilgh Integrity Container (A) Liquid Wante Management- 177.5 5.0 3.20E400 *2 125%
Resin Dewatered in a Carlon Steel' Liner (llead Resin) i (D) Waste Oil-Shipped to 7,5 2.97- 1,78E-03 *1 125%
Scientific Ecology Group for Incineration
- f
- Waste volumes shipped'for' volume-reduction do not reflect. final burial waste ,
volumes unless otherwise stated. ,
l *1 Activity _ determined by estip>-tions.
i *2 Activity determined by measurements.
t-
[ W310526HP 24 L _. . . _._ _ _ _ _ _ . _ . . _ . - _ . _ . _ _ . _ . _ . , _ _ _ _ . . . _
Tall!.E 3 (3 of 10)
SOLID WASTE SillPPED Of tSITE 10R DISPOSAL '
DURING PERIOD 7/1/91 TilRD 12/31/91
_ _=
. _ _ _ _ . - _ _ _ _ _ _ _ _ . . _ . . . _ . . _ . _ . . ~ _ _ . . _ _ . . ~
WASTE TYPE NUCLIDE NAME % Ai!UNDANCE CURIES (II) Non-Compact ed - (%-58 71,151 4.02E-02 Dry Activity Waste 63 9 004 5.09E-01 Shipped to Scientifit 13' 4.460 2.52E-03 Ecology Group for ts-!3/ 7.062 L 99E-03 Volume Reduction Co-66 3.770 2.13E-03 Fe-55 2.230 3.26E-03 Mn 1.876 1.06E-03 (ii) Non-compacted Co-58 71.164 1.41E-01 Dry Activity Waste Ni-63 9.009 1.79E-02 Shipped to Scientific Cs-13' 7.051 1.40E-02 Evilogy Group f or Cs-134 4.457 8.83E-03 Volume Reduction- Co-60 3.765 7.46E-03 Fe-55 2.236 4.43E-03 Mn-54 1.876 3.72E-03 2 W31052611P 25
_.~..-,-._.__...,__:.--._.. _ .._ ;. . _ ._ _ _ _ _ _ _ __.
I TABEE 3 Y
(4 of 10) 801.1D WASTE SillPPED OFI' SITE FOR DlSI'0 sal.
DUlt1NG PER10D 7/1/91 TilltU 12/31/91 I
WASTE TYPE NUCl.1Dl; NAttE % ADUNDANCl; CURIES (10. Non Compacted Co 58 71.177 5.88E 02 Dry Activity Waste Ni-63 H.993 7.43E-03 Shipped to Alaron Cn-137 7.064 5.83E 03 Corp for Volume Cs-134 4.451 3.68E-03 Reduction Co-60 3.764 3.I10-03 Tc-55 2.233 1.84E-03 fin-54 1.875 1.55E-03 (B) Non Compacted Co-58 71.164 2.36E-02
-Dry Activity Waste- Ni 63 8.994 2.98E-03 Shipped to Alaron Cs-137 7.068 2.34E-03 C :rp for Volume Cs-134 4.452 1.48E-03 Reduction Co 60 3.766 1.2SE-03 Fe-55 2.236- 7.41E-04 tin-54 ~1.877 6.22E-04 4
K emeess-esangue.aw tee m- w e.w - wN
~-
a i
I W31052611P 26-i
.._;..,,-,c,.,.,,-,__..- . . _ _ . , - -, . . .o .;_.-__________--.. -
'l Allt,0 3 (5 vt 10)
SOLID WASTE Fillitl'.D Oll'Sl'll; Irk DISL'OSAl.
Id'HING l'ERIOD 7/1/91 111RU 12/ 31/91 VASTE lYl'E NUCl ll)E NAMl; "4 ABUNilANCI. CUR!l S
( A) Lli,uid Waste Flanagement Co- l ~3 7 16.925 1.181:+ 00 Resin Dewatered in a Co-58 30.917 9.880-01 Carbon St(el Liner Cs-134 19.276 6.160-01 (llead Resin) l'e-55 4.475 1.43l;-01 Co-60 3.567 1.140-01 11 - 3 1.649 5.27E-02 rin-54 1.496 4.781:-02 Ni-63 1.446 4.62E-02 (A) kesin Waste flanagtm<9t Co-58 30.755 9.12E+01 Resin Dewatered in a On-137 22.965 6.81E*01 lligh Integrity Liner Cs-134 15.748 4.67E+01 (ltead Resin) Ni-63 11.095 3.290+01 Fe-5$ 10.892 3.231;+01 Co-60 3.743 1.11L401 Fin-54 3.315 9.83t+00
_ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ . _ ~ _ _ _ _ . . - . - _ _ _ _ _ _ _ _ .
W31032611P 27
TAllt.E 3 (6 of 10)
SOLID WASIE SillPI'l:D UlTSITE FOR DISPOSAL DlIKING PERIOD 7/1/91 TilkV 12/31/91 WASTE TYPE NUCL1DE NAME % AltDNDaNCE CURIES _,
I (A) Mechanical Filters Co-58 27.484 4,25E+01 i Dewatered in a liigh Fe-SS 24.509 3.79E+01 ,
integrity Container Cr-51 15.391 2.J8E+01 !
Nba95 11.446 1.77E+01 Ni 63 7.372 1.14E+01 :
t Co-60 5.652 8.74E401 i Sb-125 3.725 5.76E400
- Zr-95 1.888 2,92E400 Mn-54 1.080 1.67E+00 (D) Waste oil Sent to Co-58 71.169 1.26E-03 Scientific Ecology Ni-63 8.985 1.60E-04
- Gtoup for lucinesation Cs-137 7.070 1.26E-04 l Cs-134 4.453 -7.9 E*05 Co-60 3.767 6 A/E-05 Fe-55 2.238 3.98E-05 ,
hn-54 1.876 3.33E-05 t
i i -
l l
-W31052611P 28 L
.._....m.-.. ._._.._._.m-._.-_____. _ .... ~..- _ . . _ . _ _ . . _ _ _ . _ . , - _ . . _ . - . _ , . _ _ , . _ . , _ .
. _ = __ ..
TAIll.l; 3 (7 of 10) l l
SOLID WAST!; S!!!PPED UlTSITE l'OR DISI'OSAL
- DURING PERIOD 7/1/91 Tilhu 12/31/91 f
. . . _ _ . _ _ _ _ _ _ _ . . _ _ _ . . ~ . . _ . .. _ _ _ .. --.. - __.._ _ _ . _ . _ . -
NUMi!ER OF SillPMENTS MODE OF TRANSPORTA110N Dl:STINAIlON '
- -.-_.m ___.-...-.,-.....~_---...m--._--~~.-=~m..
t
!! TRUCK J-flarnwell, SC 3-Dakridge,'IN 2-Wampum, PA i
e WASTE f 0F TYPE OF CLASS Silli?!Eni'S TYPE CONTAINER HODE DESTINATION
_- , ., _ _ . _ . - . _ _ , _ _ . _ , . . _ _ _ . . . _ . , _ _ . t A 1 Type A liner Carbon Truck liarnwell, SC Steel B 1 Type A Poly-lllC Truck flarnwell, SC C 1- Type B Poly +111C Truck Barnwell., SC A 1 'LSA S t rong-Ti ght. Truck Oakridge, TN A .) LSA St rong-Ti ght Truck Oakridge, TN Limited 1 Limited- Strong-Tight Truck Oakridge, 1N l
-Quantity Quant i ty_-
~
t A 1 1.SA _ Strong-Tight Truck Wampum, PA L- A' 1 LSA Strong-Tight Truck Wampum,'PA-i
~
s i .W31052611P 29
- t l
L .
_ , . . . . . . - _ ..- . _ . . . , . . . . . , . . . . _ . ~ . _ . . . - _ . , . . . . . . , . . . , , .- - . - . , . - . - , . _ . , . , , . , _ . - . . , - _ . . ,
l 0
TAhl,E 3 l
(8 of 10) l SOLID WASTE SHIPPED OFFSITE F0H DISPOSA1.
Dt' RING PERIOD 7/1/91 Tl!8U 12/31/91 ;
l
SUMMARY
BY MAJOH WASTE TYPES (A)_ Spent Reutna Filter Sludges. Evaporator Bottoms, etc.
I (B) Dry Compressible Wate, Contaminated Equipment. etc. '
(C) Irriaded Components. Control Rods, etc.
4
-(D)- Other (Waste 011) r 4 ,
= WASTE WASTE TOTAL TYPE VOLUME (N ) ACTIVITY (C1) ERROR i
(A) 16.39 4.52E+2 ' 225%
r (B) . 29.64*- 3.69E-1 225%
Burial Volume -
s C' -NONE N/A N/A
- (D) 2.97 1.78E-3 t25%
l
- Does notLinclude all Type'(B) waste volume.
L W310$2611P 30 - i
-%-.e ,,,,-,e .,_,y .4%,, c,%.,y,,.,g7__ -,,m,,--,,,_,.,_,..,.-.w,w, ,._%yg-y--9.,.-y -.p_,,,,,g,,,g.p. mh,,..p_, .,.',.,,,y,%,%,m.,_.-,p..,y...,,-,w,.g ,,,wn., __, 5
I table 3 (9 of 10) ,
i SOLID WASTE SillPI'ED OFFSITE 10R DISPOSAL DURING l'ERIOD 7/1/91 TilHU 12/31/91 f 1
_ . . _ _ _ _ . _ _ . _ . . _ . _ _ _ . _ . _ . _ _ _ - . _ . _ . . _ . _ . , _ . _ - . . - _ . _ . _ _ _ i SUM?tARY DY MAJOR WASTE TYl'E (Cont'd) ;
l WASTE TYPE NUCLIDE NAME % AltUNDANCE CURIES :
t
.1 (A) Co-58 30.08 1.35E+02 !
Co-60 4.46 2.00E+01 Cs-134 10.57 4.73E+01 _
Cs-137 15.47 6.93E+0!
Fe-55 15.71 7.03E+01 I Mn 54 2.58 14 15E+01 l
Ni-63 9.91 4.43E+00 ;
Nb-95 3.95 1.77E+00 Zr-95 0.65 2.92E+00 l
Cr-51 5.32 2.38E+0)
{ Sh-125 1.29 5.76E+00
{
!!- 3 0.01 5.27E-02 i
i (11) Co-58 71.46 2.64E-01 Co-60 3.78 1.40E ;
l Cs-134 4.48 i.65E-02 lt r -Cs-137 7.09 2.62E-02 ;
- t. '
L l'e -2.24- 8.27E-03
- i Mn-54 1,88 6.95E-03 i i
Ni-63 9.06 3.34E-02 W31052611P 31
?
- +,..we ._,,+,-w-m_,rw,,,, -c _ ,% ,w yv,,,.,,m ..w-, y,%,..g,w.,m-.,.,..,w yy,.,.,.,,..w.,m , w . . , , ,,-vi
- Tall!.E 3
- 1 1 (10 of 10)
S01.ID WASTE SHIPPED OFFSITE FOR DISPOSAL DUnlNG PERIOD 7/1/91 Ti!RO 12/31/91 I
l 1 1 3 . . _ _ . _ _ _ _ . _ _ - . _ _ _ _ _ . . _ _ . __
SUMMARY
llY MAJOR WASTE TYPE (Cont.'d) ,
k WASTE TYPE NUCl.lDI: NAME % ABUNDANCE CURIES !
l (D) Co-58 71.I7 1.26E-03 .
Co-60 3.77 6.69E-05 ,
, Ca-134 4.45 7.91E-05 Cs-137 7.07 1.26E-04 i
Fe-55 2.24 3.98E-05 Hn-54 1.88 3.33E-05 Ni-63 8.99 1.60E-04
- * " " .p.sm-. _
f 7
a I
s
= W31052611P 32
l TAlill 4 (1 of 4)
JOINT IR14t'l:NCY DISTRllil! TION 01' METLOR01,0GICA1. DATA 40thf f ellA4kti Ottttsbut tta N wino & Pilo amb t!st(11(a It w196 .
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l L._.____._.._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . . . _ _ _ _ _ _ _ _ _ - - - -
TAltLE 5 (1 of 2)
DOSE CALCULATION RESULTS MS 1991 (DOSES DUE TO GASEOUS ItADIDACTIVE ETTLUENTS)
.. wa t l 1 ee oss i rr u n mii WM FWlM ku010100lNES, PAWilfttAT[n ..
5, MD TGl110M ! .. ov.51rR 7 rr u n ** I l'I (741 ROLLING LOCAll0N DOSE FMe WOl0100lNES, PADilCUL Aff 5. AND TRlille TOTAL. (WI WEN FOR !Of Al CON 1R0tL 1% iOEAll(Ni
?.946?i 0) 101AL (EE (MM) ros (0( )j?!6E.03 TOTAL (GE WEM) FOR lVER . 1.H7R 0?
1014 (OSE WEN FOR (10fAL 000Y 1,615 E 07 101AL DI M ( E m FfG tlVIR t ],1040f 02 TOTAL DOM IMPfm FOR ip0ID 10ft( (EE (MPEM) FOR TOTA E00f i 1 1. 69 b H 101AL DtM Wim (OR INYR010
- 1. 0641E-0?
10itt COSF # fM) F00 Kl W Y t 1,7 6 [ 07 TOTAL 0(N IMPim FDR tlMy $.100lf 04 !
701% fWi WEnl FOR ttM i 1,1914t' . 0 ?
101% (54 (Muim FOR I(Pr. : 1.120lf0?
10tR DOSE WEM) FCW Gidti i 1.401% 92 t 9.) H 0E 01 O E (45 00;f At EliE E0>0ARY: 101AL (MI (MM1 Fl# Gl tLi 9.4141E 01 Chit gas 00W Al s)TE DrtNutRY: .
101AL F@f 09sE TOTAL (MPENs t 7 M149E 01 !
NN (C4 IO1Al thPEMI 1014L BODY (OS[ 101AL WEm t ).5707E 0) ;
i $.9746E 01 $ KIN 00cf TOTAL iMPEN 6.25tti 0)
VRE f4 A!MOSE At Sl?E 90tN0c#Yr 701at furu AIP00c4 (MR%) NTLE Gt6 AIPXM AT SITE E0Att#Y:
?.99 M .0) 101 AL (,WmA AIMWI (MRAD) 4,139f f H '
TCIAL PETA t.!PDOSE W@) t 0.t %T-Ot TOTIA f(TA AIED0?1 Wr0) : 1.1187E-u?
esLNil 1 n Otu1ER 1 or - 1H1 u DOSE FR9M R@l0100lt4S. PARilCUL ATES, fde TRlillM n INil 1 u ovaire 4 Or pn u af EDNTROLLINr.10EAil(Nt DOSE FROM PA010lf0lNES, PMilCUtAIES, AND TRiiltti A1 EINTROLI.1% LOCATIONt TOTAL 0004 WFM1 FOR LOT i ],H47005 TCTALPOSE(MMIFORE0f f?IAL DOSE (MPim FOR t.IVtR 7,99%f 01 : $ 0740F ti 101st 00cf (MPEm FOR TOTAL {0DY TUT 4L [mE (MM) FOR LIUf R t : 9771 -01 t 7.994?E47 +
TOTAL IEE IMPEN FOR THYROID 3.4R0=E 07 TOTAL POSE (MM) FOR TOTAL Fr10Y t : .9266 01 TOTAL FEE WEM) FOR KIINEY t 7,999E 07 TOTAL LGE IMMI FOR TNYP01D 2.l?l0 01 10TAL 00sE WEN) E0R littG TOTAL 00ct (MRIMi FOR ritN!Y 1.9???F 01 t -7.9936E M 101AL WI (MWm FOR ttm TOTAL (UE WEMI r0R GI-LLI i 2.99HE-07 i 1.9265E0]
NORLE GAS EME AT SifE FiodotRY: TOTAL DOSE IMm FOR G14L1 1.926tE-UI 1018( Bf0Y OOSE t0TAL utAEm i 1.71%)E 0) NnftE GAS (FE AT SiiE Fmraft 4 IN ($E TOT AL 8 NREM) TOTAL Dnrif 00SE TOTAL WEm t ?.4916E 04 t 3.H71C 0) 9IN 004101RL tMm 1,347rE. H M E Gas AlPDla Al SITE E0aOARY: i 16TAL-GAttw AIR ( M E (MRAO) 1 1,9001E-01 HnRLE f45 AlPDDSE Al SITE E0VCWf t 10fAL E! ETA AIR (OSE thWA01 TOT AL GATIA AIP009E WADI I M 4GE 04 1 1.H ?5E 05 IDTAL DETA AWJOSE WAD) : 1.4691E<
H LNii 1 u TOTALS (DR 1991 u DOSE FROM P@t010DlHCS, PARilDAATES, it0 TRifltri AT E04100LLi% LOCAll0N:
TOTAL (ME WEM) FOR Br)( t 43369E-0) 101AL DDT (MPfm FOR LitKI< : ?.$104E 01 TOTAL COSE WEM) FOR TOTAL BC0( 1 ?,400)E 01
! TOTAL 00V WEM) FOR THYR 010 t 1.0$ M 00 TOTAL 00SE (MREM F0W KIDHEY t 7,9165E 01 10 Tid. 006E (MPEm FOP tt#G t 7,45HE-01 TOTAL IOSE (MMI EDR GI LLI ?.460?E 01
- NOALE GAS DDT Ai Si1E ROLNDARit TOTAL 90DY [0SE TOTAL WEN
$xlN DOSE TOTAL (MPEMI t ?.h9ff 01 t 6.1096E 01 NDHLE GAS AIPDOSE AT SITE B0tNDARY:
TOTAL f.t# 4 AIM OSE W 60) : 1.0614E 01 '
101 AL BETA AlPW.4 WAD) : 9.7669E 01 t!310526HP - 37
- . _ - _ _ _ . _ _ _ ~ _ _ ~
l l
TA!!LE $
(2 of 2) !
DOSE CALCULATION ItESULTS FOR 1991 (DOSES DUE IV LIQUID RAD 10ACTIVI: i:IT!.UENTS )
H isl1 1 H re pits 1 Or 99) H 6.1941E-07 101AL DDSE IMPEM) FDP lW4E i 9 l?p( 07 1014 D(%F t twf m F OR t ivrp '
101t4, [0%f IMP (Mt FOR 101 AL BODY t 4,6 Filf 07 8
101 AL timi (Mvt Mt if* THf9010 : 4.447tf hl
- ),1077E 0?
TOTK DOLE IMFfM) IfW Kit *4fY 10f tt D0% IMRfMi FOR LtPG t 1.ffl69f 0?
TOTAL C050 f t*[m (OR Gl-til : ?.817?f-0/
to(N)I 1 *
- O!SP tip 2 Of 1991 H TOTAL MSC (MPEMi Ftp 9M : 4,65 el 01 101AL (O T (MRfM) FOR L M G 1 8.377tf 01 1 F 01 101AL 00W tMPtM) FrA 101R (rOf 6.ly!dE 0?
TOTAL MRE tMPEM) f fW THVR010
- 1.0 10itt DOSE It1REN) Fft KIC#4EY : ?.78)*f 01 TOTAL DOT (f9CN FOR Ll#6 1 9.?!!6f 0?
1014 005E (MREM) FDR Gl LLI ?.9920E-01 H (JNlf 1 H QLWRTER 1 0F 1991 H lDitt DOSE (MPfMi FOR 10( : ?.7)?f(4?
101td. DL5E (MRtM) FfR LMV t 4. M 6E U?
TOTAL 00;f (MPfm FOR 10fAL BODY : 1.515)E42 TOTA MEE IMRf M) FOR 1HYR01D t 2.3069[-04 10thi DOSE tMP[m FOR KlDNEY : 1.% 44E 07
, ~
1014L D(EE (MPiM) FOR LtPC 9. 5319f M TOTAL MISE (MPEM) TOR Gl-ttl 1 ?.7 W E-0?
H tNif 1 ** OtM1FR 4 ff 1991 H 10TAL DOSE (MPIM) FOR 90tif 7.5136f 0) 101 AL KFE (MPEm F R t.MW ! 1. )l 4N-('?
TOTAL DOSE tt9tM) FOR 10Ttt 900( i 9.6210F 0) i~ TOTAL N6E ttFEM) FOR THY 40lb : ?.44711 04 TOTAL 005C (t9Em FOR klDktY : 4.a9?vE 03 TOTAL [WE IMPTM) FOR LtJ6 1 1.W4Ed)
TOTAL DOSE (MREnt FOR GI LLI 1 4.3964f-0?
H tiHIT I ** TOT A: S FRR 1991 H l 101AL CEE iMREM) FOR 00HE
- 5,747'f-01 1014L tesE (nWEm FOR LMR t 9.84 ?f 41 l
TOTAt. N6f (MPFM1 FDP TOTAL 900Y : 7.?651E-01 4 I: 2.0?a9E 0?
1014t Otf.E (MPim FOR THYWOID l
101 AL DDSE tt9Em TOR Kl[*4EY t 3.?4??f-01 l
101AL DOM (tWim FlR Ltt6 f 1.09%f 01 TOTAL DOSE tMPEN FOR Gl-lli i 1.9fl9 tf-01 4
i W31052611P 33
a TA!!LE 6 (1 of 1)
ACTIVITY CALCULATIONS FOR SECONDARY RELEASE PAlllWAYS l'OR 1991 ;
. VENTILATION SYSTEM TOTAL ACTIVITY REll:ASED DURING 1991 (Curtes) l-131 1-133 Co-58 Xe-133 lir-82 ,
SWITCilGEAR AREA VENT (All-25). 2.04E-5 (LLD < LIJ) 1.49E-2 (LLD
+46 If6V EQUIPMENT ROOM (E-41ASII) 7.65E 6 (LLD < l,LD <LLD <LLD-llOT MAClllNE Sl10P -(All-35) 3,09E-5 3.21E 7. 1.550-7 (LLD- (LLD ;
DECONTAMINATION S110P (All-34) 4.88E-5 1.05E-6 (LLD <til; 1.16E-6 1.49E-2 1,16E-6 I
-TOTALS 1.0hE-4 ).38E-6 1.55E-7 i
t F
1 l-1.
I W31052611P 39
- c. - .:.-.-.-.-_.-..-. .- . - -..-_ - ,.-..-a.-. . . - , , . - , _ , - . - . , , _ , . . .
1 1
1 ATTACllt!ENT 10,I '
i (349 PAGES) i f
i i
i i
CllANGl:S TO UNT-00$-014, )
i f
CTFSITE 11051; cal.CULATION MANUAL (ODCrl) !
?
t f
July 1,'1991 To December 31, 1991 1
i 4
i l- e
. -)
I ,
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l- .;
I l:
.[
L S31052611P 40 l ,
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. ._ _ _ _ . _ . _ . . . _ _ . ~ - . . _ . - .._._..a.-._.._.. _ _ , . _ ,2..__._-..._. _ . _ . - ,
PORC/ Pelt 0 %
UNT-00S-014 REVISION I ,
EITECTIVE DATE SAFETY-RELATED ADMINISTRATIVE PitOCl;DUltE O.PPSITE DOSE CALCULATION MANUAL, y; a p;c%ns n c. cr ~s ry 1 a O P
'a u O py 11 .1
{~} b;,, p\ ,rs \.
', <L m a.
i;[,I o .., e m ... ,
a u "' " I ' "' ' * ' " " I' UNT+001-002 Revision 12 Attachment 6.3 (1 of 2) .
1 41
i i
PORC ANH-PORS---SpE RFVIEW AND APPROVAL SHEET
_ _ . , _ _ . _ _ . _ ___ _ _ f REVIEW OF: UNT-005_014 - (Change 1) PORC 2 Of f site Dose Calculation Manual __(Hev. 1) PORC - S/C D
_- - _._ -. __ ~: l l
The PORC or PORC S/C has reviewed this item and determined that a Safety /
Commitment Keview was performed (if applicable), that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does not exist, and that nuclear safety is/was not adversely affected.
-~~_. ~ - ~:::._ .___.
MEMBER SIGNATURE
""' ^
MEMBER \ES NO a .#1 Maintenance Superintendent
)
g/h/"j/r /
/g ~
/
Operations ( [, /
Saperintendent l / ,wn.
- ~ ~
^
d Radiation otection o Superintendent '
AA / y Q s_V_u _. . . _ .
Quality At.aurance Member / - [} t -p]{/s
,2
/
Plant Engineering [
Superintendent -.
f[ v-Manager Operations 6 N
Maintenance I
[. 4 f f [ e ..
PORC-S/C Member _ _
PORC-S/C Member . _ _ _
PORC-S/C Member l _ . _ _
Meeting No.91-166 Item No. __ VI-K Date; 12/19/91 This item is recomn. ended f or approval? 2 YES D NO Thir, item requires SRC/NRC review prior to implementation? O YES 2 NO If yes, enture documentation supporting review is attached.
SIGNATURE T IENDED FOR APPROVAL RECO.
YES NO DATE
~
PORC 5/C Chairman PORC Chairman
}(( / ,
Comments:
c:;:- I e l Approved by ,, Date / _ZJk_
(/ neneral Manager Plant Operations f UNT-001-004 Revision 13 Attachment 6.1 (1 of 1) 22 MM
UATERf0RD 3 SES PLANT OPERATING HANUAL Check Block below RE.VisitWEni-4UN REQUEST @PtRCl[lP0HC-S/C Procedure No.3DjT.CO','-d14 TitIe f Hi G 1 C % e : M ,p W y L _ _
Effective Date 1-l-92 (11 different from approval date)
Complete A, it, and C A. Change No. I,_ l[ Permanent l[l Deviation Expiration Date t B. Revision No. I C. Deletion l[ LYES l@NO DESCRIPTION OF CllANGE, REVISION OR DELETION AbM_ PIT _fAEfXE< 2 /0! Idfhts9 A &ok A uba 44 Rwwmhhm lebes Ne aWansLL AuLuLw "ra tk _thwJ 4.L usarI;. Mk drd1.e se x Mcaidy_w._;isnQ.;
wls O GtwLhk L, , & t>iw ~ %_Loik 4 Sus 2 G12 %A26~d y,
. stas d n y _ h dd he sia EWJu m -% tun;-4227 REASON hed.hs b[.[Sf)
& L is w nFOR malz CHANGE, REVISION 08 del.ETION naJde._1&_An u 4 k y A /_ h/ d f ,
a ~4 ta.is n pu. Mw J.o . @acW&BG_,u.dLsound
%d clus 4 A 'kpdfcn du L dLK MidaLhelnGa
.wm AudahlJ i jn ORIGINATOM _
ag DA1E J h @f l SAFETYSCREENING/EVALkATION a ,4 -#.- 4 ~. -:t DA1E ,1- - /r -h TECHNICAL REVIEW . w e ,- a 4 DATE_ hua ,
GROUP llEAD REVIEW P( .__!._ DATE,_/2 9j TEMPORARY APPROVAL * (SR0h DATE TEMPORARY APPROVAL
- UA1E
- Refer to paragraphs 3.2.15 and 5.3.1.10c f or temporary approval requirements, l UNT-001-003 Revision 13 At t aclunent. 6.5 (1 o f 1) 31
PORC AWH-PHHE---8/E REVIEW AND APPROVAL SilELT REVIEW OF: UN1-005-014 - Offsite Dose PORC D:
CalculationManua{(Rev. 1) PORC - S/C U The PORC or PORC S/C has reviewed this, item and determined that a Safety /
Commitment Review was perforiced, (if applicable) that a Saf ety Evaluation was perf ortned (if applicable), t hat an unreviewed saf ety question doer,
' not exist and that nuclear safety is./was not adversely affected.
PORC PLCortMENDED FOR APPROVAL DATE MEMBER SIGNATURE No MEMl!ER Y F.S Maintenance SLperintendent ,w ../ /
pIg-
-g + - :- - -- - -
Superintendent / y T
~
Radiation Psotection -
-T' /
Supe rintendent Operations Quality [ // [
Assurance Manager (/
Plant Engineering Superintendent Assistant Plant \ af Manager [4//)* _
/%
PORC-S/C tieinber _
PORC-S/C Member - -
w PORC-S/C Member .
PORC-S/C Chairman t ORC Chairman 1t?)
Meeting No.91-159 ltem No. Vl-E _ Date: 11/_27]91__
This item is reconsnended f or approval? lC YES O NO This item requires SRC/NRC review prior to implia.cntation? O YES l0 NO If yes., ensure document ation support.ing review is at tached.
PLANT MANAGER-NUCIIAR APPROVAL Comments: _
/O f Approved by - Date f 1
ant Manager-Nuclear UNT-001-004 Revision 12 Att achment 6.1 (1 of 1)
-. - = _ - - . - - - _ _ _ _ _ _
k'ATERFORD 3 SES Pl>JiT OPERATit!G t!ANUAL Clieck 111ock Relow CitANGE/REVIS10N/DELET10N REQUEST lhPORCl ~_l PORC-S/C
' . Procedure No.
o u f', c of-ofYTitle_,g./rc hmg)3Q{.% M .s._, b,_
Effective Date -
(if different from approval date)
,C_omplete A, B, and C j[) Permanent ([lDeviation Expiration Date__ _
A. Clonge No. -
B. Revision No. _f_,__
C. Deletion l[ LYES lMNO '
DESCRIPTION OF CilANGE, EEV1510N OR DELETION _
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J 1 /A ORIGINATOR [%n [. k e - -y DATE DATE e-89 is /,fl\ (
SAFETYSCREENIhG/lhAbuATION M
((M mA T) Afy , a m DATE ///r //9/
l TEC1011 CAL REVIEW DATE [- A/ - 9/
GROUP HEAD REVIE b- M I' N r DATE _
TEMPORARY APPROV M SRO)
_DATE l TEMPORARY APPROVAL *
- Refer to paragraphs 3.2.15 and 5.3.1.10c for temporary approval requirements.
Attachment 6.5 (1 of 1)
UNT-001-003 Revision 13 31 . . ,
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 TAh!.E OF CONTENTS i
1.0 PURPOSE 1
2.0 REFERENCES
3.0 DEFINITIONS i 4._0 RESPONSIBILITIES 4
5,0 PROCEDORE 5.1 Site Characteristics 5.2 Specifications and Surveillance kequirement.s ,
5.3 Liquid Effluents 5.4 ~ Gascoias Ef fluents 5.5 Total Dose ,
5.6 Instrumentation 5.7. Liquid and Ganeous Radwai.te Processes
. 5.8 Radiological Envirotunental Monitoring Program kcquirements 5.9 Technical Specification Cross-Heferences 6.0 ATTAC}DtENTS 6.1 Site Boundary for Radioactive Gaseous and Liquid Ef fluents !
6.2 Historical Average Dispersion and Deposition-Parameta s for Areas at ;
or Beyond- the Unrest ricted Area Boundary 6.3 Site Related Liquid Ingestion Dose Commitment Factors _(A g ) for i
Individual Nuclides ,
6.4 Dose Factors for Exposure to a Semi-Infinite Cloud'of Noble Cases 6.5; Inhalation Pathway Doses Due to Radionuclides Other Than Noble Gases, R g
-6.6 Ground --Plane Deposition Pathway Dose Factors Due to Radionuclides l
Other Than_ Noble Gases, R _ g
'6.7 Cow's Milk Pathway Dose Factors Due to Radionuclides _0ther Than i
l Noble Gasen, Rg :
1 ;
d-N-- -- --
y- p p w r -
,,,.v.-,--,,s r ys y , -- e- - - -w, cc w- e , en-, r-aw, --w-y- ,-, - - - e :m-
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 6.8 Heat Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R g 6.9 Leaf Vegetable Pathway Dose Factors Due to Radionuclides Other Than Noble Cases, R g 6.10 Coat'n Milk Pathway Dose factors Due to Radionuclides Other Than ,
Noble Cases, R g 6.1 Liquid Waste Management System Effluent Sources and Release Pathways and Points 6.12 Gaseous Effluent Sources, Gaseous Waste Hansgement Systems Effluent Sources and Exhaust Release Points 6.13 - Radiological Environmental Monitoring Program
.6.14 Sample _ Location Table 6.15 Sector and Zone Designators for Radiological Sampling and Mon!.toring Points 6.16 REMP Sampling Locations Within 2 Miles of Waterford 3 6.17 REMP Sampling Locations Within 10 Miles of Waterford 3 6.18 RtxP Sampling Locations Within 50 Miles of Waterford 3 6.19 Specifications Cross-Befarance Table 6.20 Technical Specification Cross-Reference Table 6.21 Specific Factors Used to Determine Ag and Rg Values for the Offaite Dose Calculation Manual LIST OF ETTECTIVT.PAGES Title Revision 1 fl 1-198 . Revision 1 2.+ . m .< . a ,,s n,w i j
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9
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manrol Revision 1
-1.0 PURPOSE 1.1 The offaite Dose 0,1culation Manual (ODCM) is a supporting Jocument of the Waterford 3 lechnical Specifications. This docuruent provides (1) The Padiological Effluent Specifications and Radiological Environ-mental Monitoring Program required by Technical Specification 6.8.3; (2) the general characteristics of the Waterford 3 site; (3) the detailed Radiological Environmental Monitoring Program (REMP); (4) the description of the Raalological Environmental Monitoring Inter-laboratory Comparison Program; (5) the liquid and gaseous radwaste block flow diagram; (6) the Radioactive Liquid and Gaseous Waste Sampling and Analysis Programs; (7) the general methodology to be used to calculate dose to individuals due to releases of radioactive gaseous and liquid effluents from ths Waterford 3 site; (8) the general methodology to be used to calculate effluent monitor setpoints {
and allowable release rates to ensure compliance with the Radiological Effluent Controls,10CFR20, and 10CFR50 criteria; (9) the methodology to be used to ensure representative sampling of liquids; and (10) the methodology to be used to comply with 40CFR190 criteria.
1.2 The Offsite Dose Calculation Manual (ODCM) follovs the general models suggested by NUREG 0133 and Regulatory Guide 1.109. However, alternate calculation methods from those presented may be used provided the overall methodology is acceptable and consistent with regulation or provided the alternate methodology is-conservative, in addition, the most up-to-date dose conversion f actors and bioacewnulation factors may be substituted in lieu of Regulatory Guide 1.109 values. }
1.3 Actual step-by-step' dose calculation will be performed by in plant
! procedures which are consistent with the methodology presented in L this document.
l l
3 i .
i UNT-005-014 Administrative Procedure
-Offsite Done Calculation Manual Revision 1
2.0 REFERENCES
2.1 Waterford 3 SES Technical Spec; t 4 cations, Ch art-c 16 of Waterford 3 FSAR.
2.1.1 Technical Specification 6.14.1 2.1.2 Technical Specification 6.14.2 2.2 USNRC Regulatory Guide 1.111, Methods for Enimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Gaseous-Efflaents from Light-Water-Cooled.keactors, July 1977. l 2.3 USNRC Regulatory Guide 1.113, Estimating Aquatic Dispersion of i
-Effluents from Accidental and Routine Re. :or Releases for the Purpose of Implementing Appendix 1, April 1977.
-2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man from. Routine' Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I, Revision 1, October, 1977.
4 2.5- USNRC NUREG_0133, Preparation of-Radiological Effluent Technical'
^
- Specifications for Nuclear Power Plants,Loctober 1978.
2.6 Code of_ Federal Regulations: Title 10, Parts 20, 40,150 and 100; -
JTitle 40,'Part 190, 2'.7. illP-001-215, NRC~and EPA Radiological Reporting Requirements 2.8 ?USNRC Generic Letter 89-01,' Implementation of Programmatic Controls for Radiological Effluent Technical- Specifications in ~ the Administ ra- ,
Live Controls Section of the Technical Specifications and the Reloca-l tion of Procedural Details of RETS-to the Offsite Dose Calculation Manual or to the Process Control Program.
)
2.9 UNT-006-010 Event Notification and Reporting- l
)
4 I
-l j
t..
I
-1 1
Administralise Procedure UNT-003 014 l
' Offsite Dose Calculation Manual . Revision i
2.0 REFERENCES
(ce!'d) l 2.10 International Atomic Energy Agency (IAEA) Safety Series No. 37. Generic Models and Parameters for Assessing the Environmental Transfer of Radionuclides from Routine Releases. Esposures of Critical Groups.
- f.
td to 1 "
k a
't a
4a.
Adtvinistrative Procedure UNT-005-014 Offaite Dore Calculation flanual Revision 1 3,0 DEFINITIONS 3.1 -ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
3.2 CilANNEL CALIB h TION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and l accuracy to.known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the~ sensor and alarm and/or trip functions, and shall include the CHANNEL FUNCTIONAL TEST. The CHANNEL CAllBRATION may be performed by I any series of sequential, overlapping, and total channel steps such that the entire channel is calibrated.
3.3 A_ CHANNEL Cl[ECK shall be the qualitative assessment of channel behavior-during operation by observation. .This determination shall include, where possible, comparison of the channel indicat. ion and/or status with other indications and/or rtatus derived from independent instrument channels measuring the same parameter.
3.4 A CllANNEL FUNCTIONAL TEST shall be:
- a. -Analog channels " the injection of a simulated signal intc.: channel as' close to the sensor as practicable to verify OPERABILITY; including alarm and/or trip f unctions.
- b. B1 stable channels - the injection of a simulated signal
! into the nensor to verify OPERABILITY including alarm and/or trip functions.
4 L
- c. Digital computer channels - the exercising of the digital computer hardware using diagnostic' programs and the injection of r,imulated process data into the channel to verify OPERABILITY including alarm and/or trip function.
5
. . - ..a. . . .
UNT-005-014 Administrative Procedure i Offsite Dose Calculation Manual Revision 1 3.0' DEFINITIONS (cont'd) 3.5 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the following intervals.
NOTATION FREQUENCY '
S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At les-t once per 7 days.
M At leurt once per 31 days.
P Completed prior to each release.
Q At least-once per 92 days
- SA At least once per 184 days.
R At least.once per 18 months.
S/U Prior to each reactor startup.
N.A. Not applicable.
3.6 MEMBER (S) 0F Tile PUBLIC shall include all persons who are not
-occupationally associated with the plant. This category _does not include employees-of the licensee,'its contractors, or vendors. Also excluded' from this category _ are persons who enter the site to service equipment or make deliveries. This _ category does _ include persons _who use pottions of_the site"for recreational, occupational, or'other-purposes. not associated with - the . plant.
3.7 A system, subsystem, train, component,.or' device shall be OPERABLE or_ ,
have OPERABILITY when:it is capable of performing-its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, required for the system, subsystem, train, component, or device to perform'its function (s) are also capable of performing their related support _ function (s).
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UNT-005-014
- Administrative Procedure-Revision 1 Offsite Dose Calculation Manual-J
- 3.0 DEFINITIONS (cont'd) 3.8 An OPERATIONAL NODE (i.e. MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature as specified. ,
REACTIVITY % OF RATED AVERAGE COOLANT CONDIT10N K TilERMAL POWER
- TEMPERATURE OPERATIONAL MODE n df
- 1. POWER OPERATION 3 0.99 > 5% 1 350 F
- 2. 'STARTUP 1 0.99 35% 2 350'T
- 3. Il0T STANEBY. < 0.99- 0 2 350'T
- 4. Il0T SilDTDOWN < 0.99 0 350'F> T avg >200*F
- 5. COLD Sl!UTDOWN < 0.99 0' 1 200*F
- 6. REFUELING **- 5 0.95 0 $ 140*F 4
- Excluding decay heat.
- Fuel in the reactor vessel with the vessel head closure bolts less than-fully tensioned or with the head-removed.
3.9 . PURGE or PURGING shall be the controlled process of discharging
~
- - -air or gas from a" confinement.to maintain' temperature, pressure, humidity,. concentration or other operating condfLion,:in such a '
manner that replacement air or gas is required t.o' purify the confinement.
3.10 -The SITE BOUNDARY'shall'bc that line'beyond which the land-is neither owned,- nor leased, nor otherwise controlled by the licensee. -
~
3.11 A.-SOURCE Cl!ECK shall be the qualttative assessment of' channel response when the' channel sensor is exposed to a source of. Increased radioactivity.
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- . . .- - . . ~ . - . - . - - . . . - . _ - .- ..--.-..- -
.-.--. - --~ -.
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 3.0 DEFINITIONS (cont'd) 3.12 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY, access to which ir, not controlled by the licensee for l purposes of protection of individuals f rom exposure to radiation and 4.dioactive materials, or any area within the SITE Il0VNDARY used for residential quarters or' for industrial, commercial, institutional, and/or recreation purposes.
1
-3.13 A VENTILATION EX1LAUST TREATMENT SYSTEM shall be any system designed and-installed to reduce gaseous radiciodine or radioactive material 4 in particulate.forniin effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or IIEPA filters for the purpose of ' removing iodines or particulates f rom ti--e gasecun exhaust stream prior to the release to the environment. Such a. system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature (ESP) (atmospheric cleanup aystems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
-3.14 VENTING shall .be the controlled process of discharging air or gas ,
from a confinemer.t to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that I
replacement air or gas is not provided or required during VENTING.
Vent, used in system names,.does not imply a VENTING process.
- 3.15 A VASTE' GAS'lI0LDUp SYSTEM shall-be-any system designed and--installed to reduce radioactive ~ car,eous effluents by collecting coolant system-of fgases ' f rom the primary system and' providing for delay or- holdup -
for:the purpose of reducing the- total radioact.tvity-prior to release -
to the environment.
.8
Administrative Procedure UNT-005-014 Offsite Dcse Calculation Manual Revision 1
+- -4.0 RESPONSIBILITIES 4.1 General Manager, Plant Operations has lead responsibility for insuring implementation of the Radiological Effluent Specifications and Radiological Environmetal Monitoring Program as required by Technical Specification 6.8.3 and as set forth in this procedure.
4.2 The Radiation Protection Superintendent is responsible for ensuring Radiological Effluent Specifications and tiie Radiological Effluent Monitoring Program are performed as required according to procedures and methodologies established by the document. He is also responsible for insuring the Land Use Census and Semi-Annual Effluent Release Report are performed and issued as required.
- 4. 3_ Director Operations Support and Assessment is responsible for the l issuance and submittal of the Annual Environmental Report as required by_this document.- He is also responsible for the negotiation and
-mainenance of vendor contracts to supply Sample Analyses and Reports ,
-as required by the Radiological Environmental Monitoring Program.
9
UNT-005-014 Administrative Procedure ~
Offsite Dose Calculation Manual .He"1sion 1 5.0 PROCEDURE 5.1 SITE CHARACTERISTICS ,
Waterford 3 SES is located on the west (right descending) bank of the Mississippi River at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of
- Killona and Taft.
The geographic coordinates for the Waterford 3 reactor are Latitude 29' 5942" North,-and Longitude 90' 28' 16" West.. Based on the UTM
-(Universal Transverse Mercator) Zone 15, the UTM coordinaten are Northing 3,320,743 meters'and Easting 743,962 meters.-
The Mississipp'i River-is the closest prominent natural feature to Waterford 3, while other important nature features include Lac des
.Allemands, about 5.5 miles southwest of the site, and Lake Pontchar-train, about 7 miles northeast of the site. The-land slopes gently from its high points near the Mississippi (10-15 ft. above mean sea-level) to extensive wetlands located 1.5 to 2.5 miles inland from the-river =.
Most of the man-made' features are located on the narrow strip of dry land between the, Mississippi River and the wetlands. Near the Waterford 3 site are.several.large industrial facilities, including Waterford I and 2 (0.4 miles northwest of the- site), 'Little Gypsy.
Steam Electric Station (0.8 miles northeast of~the_ site, across-the-
- river f rom Waterford 3), Agrico, a fertilizer manufacturer. (0.6 miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and. Union Carbide, a chemical manufacturer (1.2 miles-east-southeast). Louisiana _ Power.& Light Company (LP&L) owns and-operates the above-mentioned steam electric stations.
10
Administrative Procedure UNT-005-014 offsite Dose Calculation Manual Revision 1 5.1 SITE CHARACTERISTICS (cont'd)
Attachment 6.1 provides a map of the UNRESTRICTED AREA and SITE BOUNDARY for radioactive ef fluents. LP&L will have full control of all activities conducted within the exclusion area boundary of the Waterford 3 site, All of the property within the designated exclusion area is owned by LP&L with the exception of the bottom
-lands below mean low water of the Mississippi River.
LP&L owns, in title, all surface rights within the exclusion area boundary of_the plant. There is presently no intention to allow ,
-exploration for subsurface minerals from points on the surface of -
the exclusion area.
The-Mississippi River, Louisiana Highway 18, the Missouri Pacific Railroad right-of-way, and the west (right descending) bank levee of-the' Mississippi River constitute traversals of the site exclusion area'as allowed by 10CFR100.3 (a). Refer to the Waterford 3
~
Emergency Plan Implementing Document for the arrangements which have been made'to give LP&L authority <and control over these traversals.
.(Note-that Louisiana Highway 3127 does traverse the SITE BOUNDARY
~but not the exclusion area. However, LP&L does have the' authority
-to control?this_traversaloin accordance with the Waterford 3 Emergency Plan Implementing. Document.)
In addition to Waterford-3,_ there are two fossil-fueled units,-
Waterford SES Units I and 2, which are' owned by_LP&L and which are within the site exclusion area. The plant staff for these-two units-consists of about 60 people. 1Since this includes workers-assigned to
-shifts,--it is a conservative estimate of the maximum number of-fossil plant personnel that would be within the exclusion area at any given-time. Evacuation procedures.for Waterford SES Units.1 and 2 are described in the Waterford 3 Emergency Plant Implementing _
Document.
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y Administrative procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 j f
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]1 5.1 SITE CllARACTER.9 TICS (cont'd)
A portion of the land within the SITE BOUNDARY is utilized for agricultural activities. Farmers presently work the land but can be expected to actually be in the field less than 10 percent of the time.
Fishin6 in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be o
expected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area.
Texaco maintains a gas valve station east-southeast of the Waterford 3 SES island structure just within the radius of the exclusion area. This valve: station is automated and requires only periodic monthly maintenance involving, typically, two persons. Evacuation
. procedures for these maintenance workers are described in the ,
- Waterford 3 Emergency Plan Implementing Document.
The Waterford property in shown:in Figure 5.1-3 of the Waterford 3 b Site Technical Specifications (STS) and includes 3,561.3 acres. -The
.plant area is about 48 acres and is defined as including-the fenced area immediately adjacent to Waterford 3.- The site area in shown in
+ ~ Figure 5.1-3 of t the STS along-with principal station structures and nearby features. The site ' includes only station structures and does
! not include anyntesidential, recreational,'or other-industrial ;
structures. There is a visitor center and adjacent recreational area approximately:1.0fmile SSW of the plant, i'
The SITE BOUNDARIES for establishing effluent. release limits along
.with radioactive effluent release points are given in Attachment-I ~6.1. 'The nearest distances to the boundary'line are shown in
- Attaciunent 6'.2 of this procedure. The. release point elevations for '
p gaseous effluentsiase providedLin Attachment 6.1.
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UNT-005-014 Administrative Procedure Offsite Dose cad;ulation ifanual Revision !
5.1 SITE CHARACTERISTICS (cout'd)
The rest ricted area, defined for the purpose of controlling ingress into and egress from the site, coincides with the plant area which is l enclosed by the plant perimeter fence.
For..the purpose of establishing cf fluent release limits in accordance with 10CFR20 and Appendix 1 to 10CFR50, the concept of the restricted.
area, as defined above for the purpose of ingress and egress control, is-not applicable. The effluent release limits are established in order to ensure'that: (1) the concentrations of the radionuclides in gaseous effluents discharged from the plant stack and exhaust systems do not result in exceeding the limits at the site boundary, with limits set forth in Table 11, Column 1 of Appendix-B to 10CFR20; (2) the concentration of radionuclides in liquid effluent at. the unrestricted area boundary does not exceed the limits set forth in Table II, Column 2 of Appendix B to-10CFR20; and (3) the cumulative liquid and gaseous radionuclide releases do not result in exposures to individuals within the UNRESTRICTED AREA or at the SITE DOUNDARY in excess of the l
. limits set forth in-Appendix 1--to 10CFR50.
1980 population-by annular sectors within 5 miles or'Waterford 3 can be found in the Environmental Report. -Population was estimated for 1977 and projected for 1980. . The methodology for estimating and projecting population is described in detai:1 in section 6.1.4.2 of the Environmental. Report.. The closest town to Vaterford 3-is-Killona,
'0.9 miles west-northwest. 0ther towns near the plant include Norco-2.5 miles east; llahnville,.3.7; miles east-southeast; 'and. Laplace,-4.7 .,
~1 miles north. There are also smaller settlements and homes.along both banks of the: river, the nearest such place to Waterford-3 being- j 1
j Montz, 1.0 mile northeast.
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l UNT-005-014 Administrative Procedure' i
- --Offsite Dose Calculation Manual Revision 1 .l
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5.2 SPF.CIFICATIONS AND SURVElLLANCE REQUIREMENTS 5.2.1 Compliance'with the SPEClflCATIONS contained in the succeeding sections is required during the OPERATIONAL MODES or other conditions specified therein; except that failure to meet the SPECIFICATIONS requires that the associated ACTION requirements .
i shall be met.
5.2.2 Noncompliance with ' procedure shall exist when the require-ments'of the SPEC,/ICATION und/or associated ACTION requirements are not met within the specified time intervals. 1f the:
SPECIFICATION is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
5.2.3 Surveillance Requirements shall be applicable daring all OPERATIONAL NODES or other conditions specified for individual systems unless-otherwise stated in an individual Surveillance Requirement.
t 5.2.41 Each Surveillance Requirement shall be performed within the specified time interval with:
5.1.4.1 A maximum allowable extension not tio- exceed 25% ...
of the surveillance interval.
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UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.5 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a f ailure to meet the OPERAlilLITY requirements f or a Specific System for Operation. Exception:; to t hese requirements are stated in the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment.
5.2.6 Failure to comply wit.h the compensatory ACTION requirements or failure to complete the surveillance requirements within the specified time shall be doctunented and evaluated in accordance with Reference 2.9.
wm 15 i
UNT-005 014' Ad:sinistrative l'rocedure Revision 1-Offsite Dose Calculation Manual l
4 5.3 LIQUID EETLUENTS 5.3.1 Concent ration Specificat ion ;
The concentration of radioactive material released in liquid I effluents to UNRESTRICTED AREAS (see Attachment 6.1) shall be limited to the concentrations specified in 10 CFR Part 20, t
. Appendix U, Table II,' Column 2-for radionuclides other than dissolved or. entrained noble gases. For dissolved or entrained nobic gases, the concentration shall be' limited to 2 x 10'4 microcurie /ml total activity.
APPLICABILITY: -At all times ACTION:
With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS cxceeding-the above-lindts, immediately. restore the concent ration to within the-above limits, and describe the-events leading to this condi-tion in the next Semiannual Radioactive Effluent Release-Report, a
SUREILLANCE REQUIREMENTS
!! a. Radioactive liquid wastes shall be-nampled and analyzed-I .according-to the sampling and analysir.> program of Table 5.3-1.
-b. The results of the radioactivity-analyses shall be used in accordance-with-the methodology and parameters in-
~scetion 5.3.5 to assure that the-concentrations at the
- point of release are maintained within the limits of-Specificat.iott 5.3,1.
L ll l
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UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual TABIE S.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM LOWER LIMIT MINIMUM OF DETECTION '
LlQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a FREQUFNCY ANALYSIS (pCf/mL)
TYPE FREQUENCY A. Eatch Waste P P Each Batch Each Batch Principa} Ganuna 5x10 7 Heleasb'f'8'h'i Tanks Emitters 1-131 1x10 F
- 1. Boric Acid Condensate.
P M Dissolved and lx 10 I' Entrained Gases .
- 2. Waste- One Batch /M (Gamma Emitters)
Condensate P M 11 - 3 1x10 6 d
Each Batch- Composite
- 3. Laundry - Gross Alpha 1x10 ' .
Waste P- Q r-89, Sr-90 Sx10 6 d
- 4. Turbir.e .Each Batch _ Composite _
Building .
Industrial
-Waste- le-55 lx10 6 Sumps *
- 5. Dry Cooling Tower Sumps
-#1 and #2*
- 6. 1Regenerat.1ve Waste-
- 7. Filter Flush 8.- Waste-IWTe5 release'from this-source is batch in nature.
17
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 ,
TABLE 5.3-1 (Continued)
LOWER LIMIT MINIMUM OF DETECT. ION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCI/mt)
B. Continuou W W Release #'g Grab Sample Principa 5x10 7 ,
Emitters} Gamma
- 1. Turbine 1-131 1x10 6 Building Industrial Waste Sumps **b M M Dissolved and 1x10 6
- 2. Dry Cooling Grab Sample Entrained Gases Tower (Gamma Emitters).
- Sump #1**j
~ ~
W M d
- 3. Dry Cooling Grab Sample Composite ,
-Tower
' Suaip #2**I Gross Alpha 1x10 7
~
W Q Sr-6:1,.Sr-90 5x10 "
d
- 4. Circulating g Grab Sample Composite Water Discharge- Fe-55 1x10 6
. Steam Gene-
'rator Blow-TU down'EX'
- 5. Auxiliary Component Cooling Water g
-Pumps
- % en release-from this: source is continuoun in nature.
18
n- 3 A'dministrative Procedure- UNT-005-014 :
Offnite Dose Calculation Manual Revision 1 TAllLE 5.}-1 (Continued)
LOWER LIMIT ,
MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL) 4 B, Continuou W W Principa k d Release *'g Continuous Composite Emitters}Gama 5x10 7
- 6. Steam Generator 1-131 1x10 T Blowdown Discharge 3' M M Dissolved and 1x10
- Grab Sample Enttained Gases (Gamma Emitters)
V H d
H-3 lx10J k
Continuous Composite
-Gross Alpha 1x10 F Sr-89, St-90 5x10 6' 'I W 9 k d
. Continuous -Composite Fe 55 1x10 6 . ;.
e f
19 I
f 1 p e r .+m-
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual TAlLE_5_3-l_fconlint3edl TAh!.E NOTAT 10N "The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 951 probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation: _
LLD = 4.66 s b E.V 2.22 x 16% .Y exp (-ASt) k'here.
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or voltune, s is the standard deviation of the background counting rate or of the b
counting rate of a blank sample as appropriate, as counts per minute, E is the counting officiency, as countn per disintegration, V is the r, ample size in units of mass or volume, 2.22 x 106 is the number of disintegrationa per minute per microcurie, Y is the fraction radiochemical yield, when applicable, _
A is the radioactive decay constant for the particular radionuclide, and at for pl. ant effluents is the elapsed time between the midpoin' of sample collection and the time of counting, Typical values of E, V, Y, and At should be used in t he calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit, for a particular measurement, bA batch release is the discharge of liquid wastes of a discrete voluma.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Section 5.3.6 to assure represen-tative sampling.
20
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 I
TABLE 5.3-1 (Continued)
TABLE NOTATIONS "The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99,
.Cs-134, Co-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.n,1.8.
e'A composite sample is one in which the quantity of Ifquid sampled is ,
proportional to the quantity of liquid waste discharged and in which the l method of sampling employed results in a specimen that is representative of j the liquids released.
'A continuous retcase is the discharge of liquid wastes of a nondiscrete vol tune , e . g . , from a volume of a system that has an input flow during the
-continuous release. i f Prior to analyses,-all samples taken for the composite shall be thoroughly mixed in_ order for the-composite sample to be representative of_the effluent release.
Elf the. contents of the filter flush tank or the regenerative waste tank contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to the liquid radvante treatment system, burbineBuildingIndustrialWasteSump(TBlWS)
- The TBIWS shall.be required to be sampled and analyzed in accordance with this
' table if any of the following conditions exist:
(1) Primary to secondary leakage is occurring;-or,
(
(2) Activity is present in the secondary system as indicated by either _!
the SGB monitors or secondary sampling and analysis; or,
-(3) LActivity was present in the TBIWS during the previous-4-weeks.-
If none of the above situations exists, then the.eampling-tnd analysis of this __
stream.need not be performed.
I Sampling and analysis of the_ dry cooling tower sumps and the auxiliary' component cooling water pump discharge will be required only_when detectable factivity-exists'in the CCW.
Sampling and: analysis of the circulating water discharge-steam generator, blowdown heat exchanger discharge (CW-SCB) will .be required only when
' detectable' activity exists in the secondary system.
21 1
. .. . -_ _ _ . _ _ ~ _ . .. _ ___ . _ _ _ _ _
. Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision I >
TABlf_5.3-1 (Continued)
TAB 11 NOTATIONS 3 Sampling and analysis of the steam generator blowdown will be required only when the blowdovn is directed to the circulating water system or Waterford 3 waste pond.
Steam generator blowdown to the Waterford 3 waste pond will be limited to situations requiring r.econdary chemistry control where the Circulating Water
. System is not available or the secondary chemistry is outside tie requirements '
for Circulating Water System discharge. Blowdown to the waste pond will be '
. terminate upon direction of sample & activity greater than the .I.D levels of Table 5.3-1.
< To be representative of the quantities and concent ration of ralicactiva ,
materials in liquid effluents, samples shall be collected contiauously in proportion to the rate of flow of_the effluent stream.
I Steam generator. blowdown discharge to the waste pond is not available unless ;
radiation monitoring and automatic isolation capabilities are added to the waste pond discharge path.
L 4
l s
l 1-22
'-mi e =wt- g s. f .. w -
1 l
UNT-005-014 Administrative Procedure Of f site Dose Calculation 11anual Revision 1 5,3 LlQUID EFFLUENTS (cent'd) 5.3.2 Dose Specification The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Attachment 6.1) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any crgan, and
- b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identified the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limi.ts. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radio-logical impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.
I 23
l UNT-005-014 T Adainist.rative Procedure *
-Offsite Dose Calculation Manual Revision 1 1
'5.3 LIQUID EFFLUENTS (cont'd)
SURVEII. LANCE REQUIREMENTS: ,
- a. Cumalative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with methodology and parameters in Section 5.3.7 at least once per 31 days.
l
{-
l l
r i
I.
l-L 1
l 24 l.
t- _ ._
. . . -._. -~- - -. . . - - .
-. = - - . - - . .
LAdministrative-Procedure- UNT-005-014 Offsite Dose Calculat. ion tianual Revision 1 ,
5.3 LIQUID EFTLUENTS (cont'd) <
5.3.3 Liquid Radwaste Treatment Syst em Specification The.' liquid radwaste treatment system shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Attachment.6.1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period, ,
s.
' APPLICABILITY: At all times.
< ACTION: .
- a. With radioactive liquid waste being discharged without -
treatment and in excess of the above limits and any
, portion of the liquid tadwaste treatment system not in U operatjon,-prepare and submit-to the Commission within 30 days pursuant to Teclinical Specification 6.9.2 a Op;cial .
Report that. includes the following;information.
- 1. Explanation of-why liquid radwaste was being discharged without treatment, identification of any inoperable -
equipment or subsystems, and the reason for'the-inoperability,
- 2. Action (s) taken to-restore the inoperable equipment to OPERABLE status, and
- 3. - Summary description of act. ion (s) taken to prevent a recurrence.
25
~. , ,.v- ,n. , ,, s ...n,- . . , , , , , . . , ,,-l-e ,.<.,,,n , , , ,A,.,. - - , , , ,w, - . . , , , -,e, <- , e
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.3 LIQUID EFFLUENTS (cont'd)
SURVEILLANCE REQUIREMENTS
- a. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Section 5.3.7.
- b. The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by meeting Specifications 5.3.1 and 5.3.2.
26
Administrative Frocedure UNT-005-014
- Offsite Dose Calculation Manual Revision 1 5.3 LIQUID EFFLUENTS (cont'd) 5.3.4 Liquid Effluent Dose Calculation 5.3.4.1 The dose commitment to an individual from radioactive materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Section 5.3.2 using the following expression:
n U tt*O'fggjggtgg f A C (3) m Dt =p{g'D tf (2)
Where:
D f= the cumulative dose commitnient to the total body or any organ (t) from the liquid effluents for each liquid release in mrem during time I
period (E);
D t = the cumulative dose commitment to the. total:
body or'any organ (t)'from the liquid effluents for all (2) time. periods;- l Ol 2= the length of the12 th time period over which
-the release is made, in hours: I C fg = .the concentration-.of-radionuclide (i) in-undiluted liquid effluent during-time. period Atffrom any liquid release, in pCi/ml; j 27
~ . . . _ . . . - . . _ . - .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.3 LIQUID EFFLUENTS (cont.'d) -
Ah: the site-related liquid ingestion dose commitment factor to the total body or any organ (t) for cuch identified nuclide (i) in mrem-ml/hr-pCi (Attachment 6.3), and; l Fg = the near field average dilution factor for C;f during any liquid effluent release.
Defined as the ratio of the undiluted liquid waste flow during release to the average flow from the site discharge structure to site boundary receiving waters.
Pg liquid radioactive waste flow discharge structure exit-flow
-.The liquid radioactive waste flow is'the maximum flow'from't.be effluent release. The discharge st.ructure; exit flow is the . flow.during disposal from the discharge structure release-point into the i'
.--- ; receiving water body. For-radionuclides not-. determined-
'in each batch or weekly composite,-the dose contribu -
tion'to the current calendar. quarter cumulative sunnaation mayLbe approximated by using;a ratio of concentrations based on'the previous monthly-or quarterly composite analyses.
l-l l-28 l
l- .-. _ . . _ , .~ . _ _ . . _ .,
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.3 LIQUID EFFLUENTS (cont'd) 5.3,4.2 Equation (1) above for calculating the dose contribu-tions required the use of a dose factor, A;t, for each nuclide (i) which embodies the dose f act ors and diluticn factors for the points of pathway origin.
The adult t.otal body dose f actor and the adult organ dose factor for each radienuclide will be used from Table E-11 of P.egulatory Guide 1.109; thus the list contains critical organ dose factors for various '_^
organs. The dose factor it, written:
- (3}
A g =K(W!
0 W f i} i t.
where:
l U = 730 1/yr adult water consumption; D = Dilution factor from near field area to i
potable water intake; i
= 220 for discharges f rom the circulating water discharge into the Mississippi River (based on the ratio of the average Mississippi River flow to the maximum discharge flow); l
=1 for discharges into the 40 Arpent Canal (based on the assumption that dilution from the near field area to a potable water intake is I
negligible);
A = Composite dose parameter for the total body or critical organ (t) of an adult for nuclide (i) for all appropriate pathways (mrem-ml/hr-pCi);
29
WT-005-014 Administrativa Proceduro Rev'ision 1 Offsite Dose Calculation Manual 53 L1 QUID ETTLUENTS (cont'd)
, l K, = Unit conversion factor; E
It l ?
U = 21 kg/yr, adult fish consumption; f
I,'
Bioaccumulation factor for nuclide % d (1) m ine L.u )# J BTi=
fish (pCi/kg per pC1/1) from Tekle A Repietory-GuHe-4r109, and; l DCT gg n Dose conversion factor for nuclide (i) and organ (t) for adults (mres/pci). Values are from Table E-11 of Regulatory Guide 1.109. l NOTE i Tor other liquid pathways, the appropriate dose factors l
l l will be utilized.
i l
l l
30
Administrative Procedure UNT-005 014 j Offsite Dose Calculation Manual Revision 1 l
! i 5.3 L1 QUID EITLUENTS (cont'd) 5.3.5 Liquid Ef fluent _ Honitor Setpoint Calculation Methodology l
Specifications 5.3.1 and 5.6.1 require that the Itquid effluent ;
monitoring instrumentation alarm / trip setpoints be set so that ;
the concentration of radioactive maternal released from the site is limited to 10CFR20, Appendix B, Table 11, Column 2 for i radionuclides other than. dissolved or entrained noble gases.
(For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pC1/ml total activity). This section presents the method to be used for determining setpoints in accordance with Surveillance Requirements 5.3.1 and 5.6.1.
- 5. 3, t l The calculated setpoints for the liquid effluent ;
monitors satisfy the following equationi r n !
c= (SF)(RF)(F+f)g{33 (.4).
C TMPC (f) ,
where; n '
gf3g C = the undiluted effluent gamma concentration pCi/ml for all radionuclides (1). The value ,
vill be derived from radionnalysis of liquid effluent.to be released. 'This value will be
-supplied for each liquid release; l i
e = the setpoint, in pCi/ml, of the-liquid effluent.
monitor measuring the radioactivity concentra- .;
tion in the ef fluent line prior to dilution.
and subsequent release. This setpoint repre-
-sents a value which, if exceeded would result' in concentrations exceeding the limits of 10CFR20, Appendix B, Table 11. Column 2, to an UNRESTRICTED AREA; !
l 31 -l
,.....m..._.- . . . . . _ _ _ . _ _ . . _ .
l UNT-00$-014 Administrative Procedure i llevir.t on 1 Offsite Dose Calculation Manual 5.3 1.lQUID F.rF1.UF.NTS (cont ' d) f = the liquid effluents flow as measured at the I
liquid cffluent monitor location in gpm; F = the dilution water flow as determined via pump curves or other appropriate meanures that determine correct plant operating I
configuration in rpm; b'OTE 1F F is large compared to i then F + f r F, SF = Salety 1 actor to ensure that the cfIluent limit is not exceeded. Actual value it, set I
by procedure (in the range 0,5 - 0.9);
RF = Relear.e fractic.n allocated to this release (to be used only la situations of simultaneovs or concurrent release); l n m N
TMPC = i
- l __C_i Z
- l-1 C
_ j_
= the undiluted nonganna MPC fraction for all MPC nongamma emitting radionuclides (j'); 1 C = undiluted ganea MPC g f raction for all ganna fiPC g emitting radionuclides (i); [
MPC, = Maximum Permissible Concentration for the J
applicable nongamma-emitting isotope (j) from 10CFR20. Appendix 11, Table 11, Column 2; and l MPC = Maximum Pern.issible Concentration for the 3
applicable ganna-emitting isotope (i) f rom 10CTR20, Appendix 11, Table II, Column 2. {
32
Administrative Procedure UNT-005-014 Offsite Dose Calculation Planual Revision 1 5* LIQUID EFFI,UENTS (cont'd) l 5.3.5.2 The values of C j and C) will be measured for each release as appropriate and the parancters for f and F will be supplied based on current plant operating j configurations. The setpoint will be calculated in ;
terms of pC1/ml and the liquid efflucut monitor will bts adjusted-as necessary to ensure that liquid teleases are secured prior to exceeding limits {
specified in 10CFR20, Appendix II, Table 11, Columu 2 l l to an UNRESTRICTED AREA.
f 1
l 1
1 ;
l l
I I
i
'. l l
l 33 ,
UNT-005-014 Administrative Procedure I Offsite Dose Calculation Manual Revision 1 i r
5.3 LIQUID EITLUENTS (cont'd) ,
5.3.6 Representative Liquid Sampling {
Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling. Large volumes of i liquid waste should be mixed in as short a time as possible and uniformly distributed prior to sampling. To determine I
the minimum mixing time for tanks from which relcares are made .the following tests were performed prior to initial use ;
for release purposes.
s I
- a. The tank was filled to a known volume. ,
i
- b. A specific quantity of a selected chemical and/or sediments was added to the tank.
t
- c. Recirculation was initiated through the normal path. .
- d. Periodic samples were taken until equilibrium was reached. [
- e. - The time observed to completely mix the tank is used as a minimum recirculation time prior to effluent sarpling.
Records of the teut will be maintained. ;
s e
34.
.._. ._ . . - - . _ . _ . _ _ . _ . . ..._. _ , _ _ . - _ _ . _ , - - . - . _ . . . _ _ , _ _ . _ _ . . ~ . _
Administrctive Procedure UNT-005-014 Of fs ite Dose Calculation Manual Revision 1
/
5.3 LIQUID ErflAIENTS (cont'd) 5.3.7 Dose Projection for Li3uid Effluents Specification 5.3.3 requires that appropriate subsystems af the liquid radwaste treatment system be used to reduce releases of radioactivity when .he projected doses due to the liquid effluent from each reactor unit to UNkCSTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this dose projection.
At least once every 31 days, the total dose f rom all liquid releases for the quarter-to+date will be divided by the numbe-of days into the quarter and multiplied by 31. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, and the. Liquid Waste Management System has not been operating, it shall be operated, if operation would reduce the monthly projected doses below 0.06 mrem total body or 0.2 mrem any organ. (This is performed in accordance with the Surveil- l lance Requirements of 5.3.3.)
r 5
35
UNT 005-014 Administrative Procedure Revision 1 ;
Offsite Dose Calculation Manual i
S.3 LIQUID Effl,UENTS (cont'd) ,
i 5.3.8 Liquid. Ef fluent _ Eases ;
- a. CONCENTRATION (Section $.3.1) [
This specification is provided to ensure that the concen-tration of radioactive materials released in liquid waste l effluents to UNRESTRICTED AREAS will be less then the concentration levels specified in 10 CFH Part 20, Appendix B, Table II, Column 2. This limitation provides addit.fonal assurance that the levels of radioactive materials in l bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II. A design objectives of Appendix 1, 10 CFR Part 50, to a MEMBER OF THE PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for dissolved or ent rained noble r gases is based'upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) ,
was converted to an equivalent concentration is wat.er I using the methods described-in International Commission on ,
Radiological Protection (ICRP) Pubitcation 2.
The sampling and analysis of the contents of the regenera-tive waste tank and the filter flush tank is performed if i
primary to secondary leakage occurs in a-steam generator.
The contents of these' tanks cannot be discharged to the UNRESTRICTED AREA if any radioactivity is detected in these tanks'since: the discharge from these tanks is ;
unmonitored. When radioactivity is detected in these ,
tanks, the contents from these tanka.must be discharged to
(
theiliquid radwaste system'where the contents may then :
be monitored upon' discharge.
36 ;
UNT-00$-014 Administrative Procedure I
offs.te Dose Calculation Manual Revision 1 l
f 5.3 LIQUID EITI.UENTS (cont 'd)
I
' The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of dete>: tion (LLDs). Detailed discus- l sion of the LLD, and other detection limits can be found !
in !!ASL Procedures Manual, RASL-300 (revised annually),
Currie, L.A., " Limits for Qualitative Detection and l Quantitative Determination - Application to Radiochemistry,"
i Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K.,
j
" Detection Limits for Radioanalytical Counting Techniques," '
Atlantic Richfield llandford Company Report ARil-SA-215 l
i (June 1975).
I'
- b. DOSE (Section 5.3.2) >
This specification is provided to implement the requirements i of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements I .the guides set forth in Section II.A of Appendix 1. The i
ACTION statements provide the required operatina, flexibi-lity and at the same tiree implement the guides set forth in Section IV.A of Appendix I to assure that the releases ,
of radioactive material in liquid effluents to UNRESTRICTED ,
AREAS vill be kept "as low as is reasonably; achievable." ,
.Also, for fresh water sites with drinking water supplies r
that caa be potentially affected by plant operations, there is reasonable assurance that the operation of the .
facility will not result:in radionuclide-concentrations in.
the finished drinking water that are in excess of the '
requirements' of 40 CFR 141.16.
t L
i ,
f 37
-.-. a .- ~ _. - . , . , . - . , . - , . . . , - . . , . - . + - . - , . - . - . - . , . ~ . .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.3 LIQUID EFFLUENTS (cont'd)
- b. DOSE (Section 5.3.2) (cont'd)
The dose -calculation methodology and parameters iniplement-the requirement in Section Ill.A of Appendix 1 that confor-mance with the guides of Appendix 1 be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUhtIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified for calculating the doser, due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculatisu of Annual Doses to Man from Routine Releases of Reactor Eifluents for the purpose of l Evaluating Compliance with 10 CFR Part 50, Appendix 1,"
Revision 1, October 1977 and Regulatory Guide 1.113,
- " Estimating Aquatic Disptralon of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implement-ing Appendix 1," April 1977,
- c. L_I_ QUID RADWASTE TEATMENT SYSTEM (Section 5.3.3) ;
The OPERABILITY of the liquid-radwaste treatment system ensures that this system will be available for use whenever liquid ef fluents require treatment prior to release to- the environment. The requirement that the appropriate portions of this system be used then specified provides assurance that the releases of radioactive materials in 11guld ef flu-
< crits will be kept "as low as is'tensonably achievable." This specificat. ion' implements the requirements of 10CFR Part 50.36a, General Design Criterion 60 of Appendix A-10 CFR Part 50 and the design objective given in Section II.D of Appendix 1 toi 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 dose design objectives set forth in Section II.A of Appendix 1,
\' 10 CFR_Part 50,.for liquid effluents.
38 n a +
Adminirtrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.4 GASLOUS EITLUENTS 5.4.1 Dose kate Specification The dose rate due to radioat Live materiale released in gaseous cf fluents f rom the site to areas at and beyond the SITE BOUNDARY (see Attachment 6.1) shall be limited to the following:
- a. lor noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For iodine-131, iodine-133, f or tritium, and for all radionuclides in particulate forw with half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPI.ICA_ BILI TY : At all tinies ACTION:
With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report.
39
- Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revisin' 1 5.4 GASEOUS EFFLUENTS (cont'd) l I
SURVEILLANCE REQUlREMENTS:
- a. The dose rate due to noble gases in gaseous effluents o shall be determined to be within the above limits in accordance with the methodology and parameters in Section l 4
5.4.5.
- b. Representative samples and analysis of gaseous effluents ,
shall-be obtained in accordance with the sampling and analyses program specified in Table 5.4-1. i
- c. Based upon the sampling and analysis performed in Table 5.4-1 the dose rate due to 1-131, 1-133, H-3, and all !-
other radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology and .,
parameters in Section 5.4.5. .
i
+
?
o d
40
., 6- - - , . - . + , . =._.,,_4 ,,,.s., . , ,.,,r.., _,,,S..,,_,.,m_,_ , . , . -,,m., .,m',.m,'.,_
, , , , , _.w,,d _, .r. , , , ,, , .,,mm,..,_,m., .-+,in,s.i-s.,..m.wd., ,,,
UNT-005-016- 3 hSurveillanceProcedure _
Revision 2 ,
, 0ffsite Dose Calculation Mancal '
i TABLE 5.4-1 i RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM j l.
I l f i LO'wT.R LIMIT OF !
MINIMUM SAMPLING ANALYSIS TYPE OF DETECTION (LLD)* } [
ACTIVITY ANALYSIS (pCi/mL) [
- j. GASEOUS RELEASE TYPE FREQUENCY. FREQUENCY t t
l, P .P Each Tank Each Tank Principal Gesuna Emitters 1x10 * !
i- A. Waste Gas Holdup Grab Sample 4'
Tanks .!
P P .
C Each PURGE C
Principal Canssa Emitters" 1x10 4 [
, B. . Containment' PURGE Each PURGE (Plant Stack) Grab Sample l-M H-3 1x10 6 ,l
! t 3 .
C 'I Principal bNoble Gas Gama Ix10 4 l;C.1 Plant Stack M' Emitters ;
Grab-Sample M l !
11 - 3 1x10 !
I i
Principal Noble Gas Gama 1x10 4 l C.2 Fuel Handling 11 *
- 3 b l Emitters t
-Building Ven- Grab Sample M tilation 1x 10
H-3 1.. (Normal)
+
Exhaust' i i
e' 4
1 5
4 ;
4-l
, t k
i I
4 41 I f 4
UNT-005-014' Survei1 lance Procedum - Revicien'1. .!
'Offsite'Dese Calculation Manual !
. t TABLE 3.4-1 (Coctinued) l PR IOACTIVE GASEGUS WASTE SAMPLING AND AMALYSIS PROGRA*1 MINIMUM LOWER LIMIT OF F
SAMFLING- ANALYSIS . TYPE OF DETECTION (LLD)* -l ACTIVITY ANALYSIS (pci/mL) 4: GASEOUS RELEASE TYPE FREQUENCY FPIQUENCY l
'8 I-131 1:10 rz l'D'.II..All Release Types Continuous * '3 as. listed in Charcoal S3mple I-133 1x10 'O B., C.1,and i: C.2:above
'i' V8 Priacipag Particulate Gamraa 1x10 11
, ' D . 2. Main Condenser Continuous
- Fatticulate Emitters Evacuation and Turbine Gland- Sample L Scaling System- i 1710 12
' Continuous ' '3 M Gross Alpha Composite Particulatt Sample i
Continuousf ,b,j Sr-89, Sr-90 1x10 11 Q !
- Composite l.' Particulate t- Sample !
- Continuous ' '3 Noble Gas Neble Gases lx10 6 !
' Monitor Gross Beta or Gamma [
i
[
I !
- 4. I
- t' j.
42 4 t i
~. . .-. .. - - ~ - . - . - - . . . -. . ..- - .-. - . . . . . . _ _ . - _ . . . - - . - - . -
Administrative Procedure UNT-00$-014 Offsite Dose Calculation Hanual l<evision 1 l
l i
l 5.4-11 Continued) !
TAllE NOTATjoh!~~
~ l
, i "The 1.1D is defined, for purpose of these specificat. ions, as the smallest f concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal, t
For a particular measurement system, which may include radiochemical ;
separationi 8 I LLD = b L , V . 2.22 x 106 . Y . exp (+AAt)
Where:
l.LD is the "a priori" lower limit of detection an defined above, as microcuries per unit mass or volume,
- s g is the standard deviation of the background counting, rate or of the !
c5unting rate of a blank sample as appropriate, as counts per minute, ,
E is the counting efficiency, as couats per disintegration.
Y is the sample size in units of mass or volume, 2.22 x 106 -is the number of disintegrations per minute per microcurie, Y in the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and ,
at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.
__Typt:a1 values of E V, Y, ard At should be used in the calculation.
- It should be recognized that the LLD is defined as an a priori .(before the fact) limit representing the capability of a-measurement. system and not_as an a posteriori (after the fact)-limit for a particular measurement.
6 f
.I i
43 h ,
m _
Administrative procec'ur e UNT-00$-014 Revision 1 offalte Dose calculation Manual 5.4-1 (Continued)
MBLE NOTATIONS bThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Er-88, Xe 133, Xc-133m, Xc-135, and Xe-138 in nobic gan releases and Mn-54, Fe-59, Co-58, Co-60, Zn-65. Mo-99, 1-131, 1-133, Cs-134 Cs-137, Cc-141, and Cc-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Keport pursuant to Technical Specification 6.9.1.6.
cSampling shall also be perf ormed within 24 hourr. f ollowing shutdown, st artup, or a THERiiAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period. Analysis for principle gamma emitters as defined in (b) above shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sampling.
dTrititur. grab samples shall be taken at 1 cast once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
" Tritium grab sampics shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel it, in the spent fuel pool.
fThe ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Section 5.4.1, 5.4.2, and 5.t.3.
E Sr.mples shall be changed at least once per 7 days and analysea shall be completed vithin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, st.artup or TilEpJtAL p0VER change exceeding 15% of RATED THEFliAL p0WER in I hour and analyses rhall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing. When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the correspec. ding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT l-131 concentration in the primary coolant han not increased more than a f actor of 3; and (2) the noble gas monitor shous that effluent activity has not increased more than a factor of 3.
hIf no primary to secondary leakage exists, then only the gross beta or gamma noble gases analysis need be performed for the main condenser evacuation and turbine gland sealing system. 11 a primary to secondary leak exists and the release from the main condenser evacuation and turbine gland sealing system has not been released via the plant stack, then the sampling and analysis must be performed.
Note (c) above is not applicable for the plant stack unless the noble gas monitor shows that effluent activity has increesed by a factor of 3.
3 Fuel Handling Building sampling is required whenevet irradiated inel is in the storage pool.
44
Administrative Procedure UNT-00$-014 l Offsite Dose Calculation Manual Revirion !
t S.4 GASEOUS EITLUENTS (cont'd) f 5.4.2 Dose-Noble Gas Specification :
l The air dose due to noble gases released in gaseous effluents ;
to areas at and beyond the SITE BOUNDARY (see Attaciunent i 6.1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 ,
mrads for gamnia radiation and less than or equal to 10 ,
mrads for beta radi uon aiA , :
During any calendar year: Less than or equal to 10 mrads b.
for gamma radiation and less than or equal to 20 mrads for beta radiation.
APPLICABILITY: At all times.
ACTION:
With t.he calculated air dose from radioactive noble gasco in gaseous effluents exceeding any of the above limits, prepare and submit to the Connission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding.the limit (s) and ,
defines the corrective actions that have been taken to reduce I the releases and the proposed corrective actions to be taken to assure that subsequent releases will be-in compliance with the above limits.
SURVEILLANCE REQUIREMENTS:
l Cumulative' dose contributions for the current calendar-quarter and current calendar year for noble gases shall be
-determined in accordance with the methodology and parameters in-Section 5.4.6 at Icast once per 31 days.
~
45
.-w . - - --e+- e w. .-r -..~e,--. ---m..w, ......,4-----,. -w, - . - - , . - - n s--- - .ir ~rm ,m,v . w r-- ----,+---e = m,-- . c % - -vy--v w - + m --e v..r------ &
l I
Administrative Procedure UNT-005-014 l Offsite Dose Calculation Manual Hevision !
l
}
i 5.4 GASEOUS EFFI,UENTS (cont'd) ,
5.4.3 Dose - loding_131 3 1odine-133, Tritium, and Radionuclides in Particulate l'orm Specification l The dose to MEMBEk 0F Ti!E PUllLIC from iodine -131, iodine-133, tritium, and all radionuctides in particulate form with I half-lives greater than 8 days in gaseous effluents released to areas at and beyond the S.'TE DOUNDARY (see Attachment 6.1) shall be limited to the follcwing:
se During any caiendar quarter:
~
Less than or equal to 7.5 mrems to any organ and, ,
- b. During 'any calendar year: Less than or equal to !$ arems to any organ.
APPLICABILITYt, At all times i
ACTION: ;
o With the calculated dose from.the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents-exceeding any of the above limits, prepare and. submit to the ,
Commission within 30 days, pursuant to Technical-Specification 6.9.2, a Special-Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the. releases and the proposed corrective-actions to be 'aken t to-assure that l
subsequent releases will be in compliance with the above l ;
limits.
L u
46.
l Administrative Procedure UNT-005-014 Offsite Dove Calculation Manual Revision 1 l
5.4 GASEOUS EFFLUENTS (cont'd)
, }
SURVElLIMCC _REjUIREMENTdi ;
i Cumulative dose contributions for the current calendar ,
quarter and current calendar year for lodine-131, lodine-133, ,
tritium, and radionuclides in particulate form with !
t half-lives greater than 8 days s. hall be determined in j accordance with the methodology and parameters in Section 5.4.7 at least once per 31 days.
I h
k
)
D T
t
+
p D
9 47 ,
1 l' '
L .-
_: . _ _ . . . - . . ,a;; , . , .-,..,._,._.-...-,_s......._._.;_.-
. . _ ~ . . .- _. . _ _ . _._ . _ _. _ ._ _ - - _ _ _ _ _ . - _ _ _ _ _ _ _ .
Administrative Procedure UNT-005-014
, Offsite Dose Calculation Manual Revision 1
. i 5.4 GASEOUS EITLUENTS (cont 'd) 5.4.4 Gaseous Radwar.te Treatment Specification ;
The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS ,
MOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity w'.ies. the projected doses in 31 days due to ,
gaseous effluent releases to areas at and beyond the SITE !
P.0UNDARY (see-Attachment 6.1) would exceed either
, i
- a. 0.2-mrad to air from gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of'a MEMBER OF THE PUBLIC.
gPLICABILIT_Y: At all times.
l ACTION:
t 1
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and
- submit.to the Commission wit.hin 30 days, pursuant to 4 '
Technical Specification 6.9.2, a Special Report that includen the following information:
- a. Identification of any inoperable equipment or subsystems, and the reason for the inoperability,. 1
- b. Action (s) taken'to restore the inoperable equipment to j OPERABLE status, and- f l
- c. Sumary description of action (s) taken to prevent a !
1
\
recurrence.
, 48 ,
1
.1
..-~.......,-.,,,.,,._.._,...,,_,,,,,,___,jj
l l
l Administrative l'rocedure UNT-005-014 i i
Offsite Dose Calculation Manual Revision 1 l 5.4 GASEQUS EITLUENTS (cont'd) l SUiWElLIANCE REAVIREMENTS:
- a. Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 ,
days in accordance with the methodology and parameters in l Section 5.4.9.
i i
- b. The installed Caseous Radwaste Treatment System shall be ,
f-demonstrated operable by meeting Specifications 5.4.1, 5.4.2 and 5.4.3. i i .
i b
o 4
i f
9 l-i I
l l' .?
- l. r I.
I i
49
,_ -..-. - ~ . - . . - . . --. . . _ . - - . ~ . - . - - . - - _ . -
UNT-005 014
' Administrative' Procedure Offsite Dose Calculation Manual Revision 1 i
5.4 GASEOUS DTLUENTS (cont'd) l l
5.4.5 Calculational Hethodology for Gaseous Effluent Dose Rate This section presents the calculational methods used for calculating gaseous effluent doses in fulfillment of Specification 5.4.1.
5.4.5.1 The dose rate due the radioactive materials released l I
in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limiteJ to the following values and expressions: !
Release rate limit for noble gaces:
n I
K'.(X/4)yj{3 K Qg ,35500 mrem /yr. total body (5) ,
n K' (X/Q)y g{3 (L; + 1.1H g) Qgy $3000 mrem /yr skin (6)
Release rate limit for Iodine-131, lodine-133, tritium and for all radionuclides in particulate .
form with half-lives greater than 8 days:
n Q 3y $1500 mrem /yr any organ (7)
[X7Q ib1 P gt Wheret K' = a constant of unit conversion, IE6 pCf/pCi; [
-K g '= the total body dose factor due to gamma emissions for each. identified radionuclide (i) in units of arem/yr per pCf /m 3 (Attachment ~6.4);
50' ,
..,)ww.. -wy - , _ , p.,w. - , w-. .
- v. -p w_,4-
. Administrative Procedure UNT-005-014 i Offsite Dose Calculation Manual Revision 1 a
5.4 CASE 00S EFFLUENTS (cont'd)
L 3
a the skin dose factor due to beta emissions ,
1 for each identified radionuclide (1) in >
units of mrad /yr per pCi/m3 (Attachment 6.4); l Hg the air dose factor due to gamma emissions for each identified radionuclide (1) in ,
units of mrad /yr per pCi/m3 (Attachment 6.4). .
The constant 1.1 converts al.r dose to skin i dose; l P
gt
= the thyroid dose parameter for Iodine-131 _
e lodine-133, tritium, and radionuclide in particulate form with half-lives greater than 8 days (i) for the inhalation pathway s only, in mrem /yr per pCi/m3'(Same as R g '
L values for the child receptor listed in Attachment 6.5). The dose factor is base on the most restrictive age group (child) and most restrictive organ (thyroid) at the SITE
}
BOUNDARY; Pg = (child breathing rate of 3700 m8/yr)(DFAg )
(K') where DFA g is the inhalation dose factor'for each radionuclide from ,
Table E-9, Reference 2.4; 1 i
t p~ n .
X -= summatiou for.all identified radionuclides; . l-i=1 .
51
= - _ _ _ . _ . - . _ . _ _ . _ _.; _ _ -_
. u._ _ _ . _ . . . . . . _ _ _ _ . . . - - _ , _ , - . , - _ _ . . - . , _ ._.
UNT-005-014
. Administrative l'rocedure Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd)
Q gy = the average release rate of radionuclides (i) (either noble gas or lodine-131, Iodine-133, tritium, and radionuclides in the particulate form with half-lives greater than 8 days, as appropriate) during the time of release from all vent releases (v).
Value is averaged over one hour and is in units of pC1/sec; and I (X/Q)y = 1.lE-5 sec/m 8 in the ESE sector at 0.6 mile for all vent releases (v) (the highest calculated annual average dispersion factor at the SITE BOUNDARY based on historical data). The actual X/Q for the time of release may be determined and used under certain circumstances. {
NOTE All radiciodines are assumed to be released in elemental form.
52 l
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.6 Calculational Methodology for Noble Gas Doses This section presents the calculational methods used for calculating noble gas effluent done in air in accordance with Surveillance Requirement 5.4.2.
5.4.6.1 The air dose due to noble gar.es released in gaseous effluents to areas at or beyond the SITE BOUNDARY will be determined by the following expressions:
- a. During any calendar quarter, for gamma radiation:
n m D
y (1.14E2) IX/Q7 y ;}; (M;))[3 (otj) (Q 3)y ) (8) and for beta radiation:
n m Dp = (1.14E2) T5TQl y g[3(N,)){3 (At)) (Q g)y ) (9)
- b. During any calendar year, for gamma radiatior.:
n m D e (1.14E2) (X/Q) y j {, M } g (At)) (Q gy) (10) }
and for beta radiatlon:
n m I
Dp = (1,14E2) (X/QJ y {,3(N } g (At. ) (Q y) (11)
Where:
D the total gamma (y) air dose frca gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad I
yearly; 53
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd)
D =
p the total beta (p) air dose from gaseous ef fluents for the total tiu.c period and not to exceed 10 mrad quarterly and 20 mrad yearly; l
=
Qg )y the average release rate of radionuclides (1) in gaseous eliluent from all vent releases (v) in pCi/sec during the time period At); )
)v = 1.lE-5 sec/m3 in the ESE sector at 0.6 mile for all vent releases (v). The actual X/Q for the time of release may be determined and used under certain circumstances; I at)
=
the length of the j u time period over which Q gy are accumulated for all gaseous releases in hours; and l Hg and N = the gamma and beta air dose factors 1
(respectively) for a uniform semi-infinite cloud of radionuclide (i) in mrad /yr per pCi/m3 (Attaclunent 6.4).
1.14E2 = a constant of units conversion
=
(1 yr/8760 hr) (106 pCi/pci) 54
_ _ , _ _ - - - ~~ _
I UNT-005-014 Adrbinistrative Frocedure Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.7 Calculational Methodology for Doses Due to Radioiodines, Tritiun, and Radioactive Materials in Particulate Form This section presents the calculational methods used for j
calculating doses uue to iodine-131, iodine-133, tritiwn, and radienuclides in particulate form in accordance with Surveil-lance Requirement.
5.4.7.1 The dose to an individual from iodine-131, iodine-133, j tritiwo, and radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released to areas at and beyond the SITE BOUNDARY vill be deteruined by the following expressions:
During any calendar quarter:
n Dgt, = 1.14.-4 At I R gt, WQ y 3y. (12) 1:1 During any calendar year:
n D gg = 1.14E-4 At I R g, WQ y 3y (13) i=1 55
Administrative Procedure UNT 005-c14 Offsite Dose Calculat. ion Manual itevision 1 i
5.4 GASEQUS 1:FFLUENTS (cont'd)
Where:
1.14E-4 = a constant of units conversion l
= lyr/8760 hr; ;
Dg = the cumulative dose to an organ (t), age group (a), due to radionuclides (1) in gaseous effluents; not to exceed 7.5 mrem qt.arterly or 15 mrem yearly; l Wy = the dispersion parameter f or estiraating the dose to an individual at the controlling I
location for long term vent releases (.v);
Wy = IX/Q)y for the inhalation pathway from vent releases (v) in sec/m 3 , from historical data, at the location of the critical receptor (Attachment ti.2); I W = (D/QT y for the food and ground plane pathways from vent relcares (v) in m 2 , from historical data at the location of the critical receptor (Attachment 6.2); l 56
. . . _ . _ . _ . _ _ _ _ . _ . . . _ . _ _ . _ . _ _ _ _ _ _ . - _ _ . _ =
UNT*005-014 Administrative Procedure l Offsite Dose Calculation Manual Revision 1 L 5.4 GASEOUS EFF1.UENTS (cont'd)
R g, a the dose factor from each identified radio-nuclide (i), for each applicable organ (t), and age group (a), in mrem /yr per l uC1/m 3 for the Inhalation patbeay (Attachment 6.5) and in mrem /yr per uri/m2 -sec for the food and ground plane pathways (Attaciunents 6.6, 6.7, 6.8, 6.9, and 6.10). For sectors with real pathways within 5 miles of the ;
plant, the values of R are g used based on these real pathways; for sectors with no real patbaays within 5 miles from the plant, R is used assuming that the cow-grass-milk I 3
pathwa', exists at the 5-mile distance.
(Rg 's were calculated using the methodology found in Reference 2.5, pages 31-36.); I
.Q gy a the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec; and l At = the time required for t.he release in hours for all releases per quarter or per year.
+
l l
l l '
'. 57
- . , . . . . _ . - - . - ~ . . - . . . - . . - . ~ . - , - - - - . . .- - . . ~ ~-- --
~.- ... .-. .. . . - - .- - . . - - - . - . - - - . - . ~ . - - . . . - .
Administrative Procedure UNT-00'-014 Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.8 Gaseous Effluent Monitor Setpoint Calculational Methodology 5.4.8.1 Specification 5.6.2 requires that the radioactive gaseous effluens monitoring instrumentation alarm / trip setpoints be set to ensure the limits of Specification 5.4.1 are not exceeded.
5.4.8.2- The calculated high alarm / flow termination setpoint
-is the maximum value for that particular release.
For conservatism,'.an administrative safety factor l (SF) of usually 10%-will be utilized in_t: 1r setpoint calculation. To allow fr. simultaneous releases from common or different release points a Release Fraction (RF) may be used to allocate percentages of the total allowable release.
5.4.8.3 'Since the noble gas dose rates are more limiting _than the radiciodine dose rate, gaseous setpoints will be
. based on: noble gas dose rates (less than or equal to-500 mrem /yr total body, and less than or equal to 3000-mrem /yr-skin); _Specifically, gaseous setpoints will be based on the most limiting of the following.
equations:
- a. Total body (Qtb)
_ (500 mrem /yr.)(RF)(SF) (14)
_q (X/QJy (lE6 pCi/pCi) n-i 91v 1:1 ll i
I l Q*.'
i=1 i.
L
Adrainist rative Procedure UNT-005-014 Offeite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd) k'he re :
n I
i=1 = summation of all nuclides considered; I -
Q tb = maximum release rate all wed to give a limiting total body dose rate of 500 mrem /yr I
an pCi/sec; K
g
= the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of mrem /yr per pCi/m 3 (Attachment 6.4); I Q jy = aserage release rate of isotope (i) from I
the release point (v) in pCi/sec; RF = release fraction allotted to release point-in. consideration; I 3
(X/al y = 1.1E-5 sec/m (in the ESE sector at 0.6 mile). The sector-with highest-value of annual average atmospheric-dispersion factor at the site boundary for the release point '
(v) in question; and :l d
SF- =- administrative safety factor to account for uncontrollable variables (sampling, monitoring errors, etc.). Usually, the SF takes on a value of 0.9.-
59
+ , - -
UNT-005-014 Administrative Procedure-Revision 1 Offsite Due Calculation Manual o
5.4 GASEOUS EFFLUENTS (cont'd)
-b. For Skin (Q skin):-
-Q skin = (3000 mrem /yr.)(RF)(SF) (15)
(X/Q)v(IE6 pCi/pCi) n y (g, 4 3,gg,)q i=1 n -
1 Q iy ,
i=1 where all terms are as defined as above except: I Q skin = maximum release rate allowed to give a limitinF skin dose of 3000 mrem /yr in pCi/sec; I Lg
== skin dose factor due to beta emisalons for each identified radionuclide (i) in units of mretn/yr per pCi/m 3 .( Attachment 6.4); I 1.1: = conversion factor to convert from air-to skin dose; and- {._
Mg = air dose factor _ due to gamma' emissions for identified. noble; gas isotope (i)_in. units 3
of mrad /yr per pC1/m (Attachment 6.4).
d
.p 5.4.8.4 The monitor setpoint_is-calculated lis_the following--
manner:
SN =-- Q (16)-
F,,,
60-l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Marual Revision 1 i
5.4 GASEOUS EFFLUENTS (cont d) .
Where:
SN = maximum monitor setpoint in pCi/cm3 ;
= maximum effluent flow rate (cm 3 /sec); and l F,,,
Q = Minimum value of Q b "# Oskin, 5.4.8.5 Since Kr-88 is the noble gas with the highest dose rate conversion f actors, _ for conservatism, the I preceeding-calculations may be computed using Kr-88 o only. Total body dose becomes more limiting than skin and the release limit is:
QKr-88 = (500 mrem /yr.)(RF)(SF) (17) sX/Q)y(IE6 pCi/pci)(KKr-88) where:
QKr-88 = the maximum releare rate,_ based on Kr-88, allowed to'give a limiting total body do;'
rate _of 500 mrem /yr in pei/sec; and f K 0 = the total body dose factor due to'Kr-88
- ~
in units of mrem /yr per pCi/m 3 (Attachment 6.4).
All other terms-are as previously_ defined. I!
-The monitor-setpoint(can be calculated as:
SN = QKr88 (18)-
F max =
and all terms are previously-defined i
l l
2 61
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd) 5.49 Dose Projection due to Gaseous Effluents 5.4.9.1 Specification 5.4.4 requires that appropriats subsystems of the Gaseous Radwaste Treatment, System he used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a 31-day period, any of the following:
0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC.
5.4.9.2 The following calculational method is provided for-performing _this dose projection.
At lease once every 31 days 1the gamma _ air dose, beta air dose and the maximum organ dose for the month-to--
quarter will be divided by-the number of_ days into l~ the quarter and multiplied by;31. -If these-projected-l- doses exceed any;of the~ values listed above and the Gaseous Waste Management System has-not been operating, it shall be' operated to reduce radioactivity levels prior to release. (This is performed in accordance with the ' Surveillance Requirements of Specification 5.4.4.
e
.62
l UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.4 GASE0US EFFLUENTS (cont'd) 5.4.10 Ganeous Effluent Bases
- a. DOSE RATE (Section 5.4.1)
This specification is provided to ensure that the dose at any time at and beyond the SITE BOURDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in a UNRESTRICTED AREA, either within or outside the SITE BOUNDARY, to annual average concentrations ,
exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, _
the occupancy of that MEMBER OF THE PUBLIC will urually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE B0UNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond the SITE BOUNDARY to less than or equal to 500 mrem / year to the skin. These release rate l limits also restrict, at all times, the corresponding thyroid dose rate above background to a child via the inhalation pathway to less than or equal to 1500 I
mrem / year.
63
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd)
The required detection capabilities for radioactive materials in gaseous vaste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of tb e LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to 1:adio-chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell,-
J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report
-ARH-SA-215 (June 1975).
- b. DOSE - NOBLE GASES (Section 5.4.2)
The Specification is provided to implement the requirements of Sections II.B, III. A and IV. A of Appendix I,10 CFR-
-Part 50. It implements the guides set forth in.Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section'IV.A of Appendix I'to~ assure that the releases of radioactive material in gaseous effluents to assure that the releases 'of radio-active material in gaseous effluents to. UNRESTRICTED-
' AREAS will be kept "as-low as is reasonably achievable."
-The Surveillance Requirements implement the' requirements-in Section III.A of Appendix I- that conformance with the.
- guides .of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of=
a.NEMBER OF THE PUBLIC through appropriate _ pathways is unlikely_to be substantially underestimated. The dose 64
l UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.4 GASEOUS EFFLUENTS (cont'd) calculation methodology and parameters established for calculating the doses due to the actual celease rates of radioactive noble gases in gaseous ef fluent s are consintent with the methodology provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating -
Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.
Sections 5.4.'i and 5.4.3 equat ions provided for detennining the air doses at and beyond the SITE BOUNDARY are based #
upon the historical average aunospheric conditions.
Grab sampling of effluents from the main condenser evacuation and turbine gland sealing system is not _
required when this source has been continuously dis-charging to the plant stack over the past 30 days. If no primary to secondary leakage in the steam generator exists, then there should be no radioactive release from the main condenser evacuation and turbine gland sealing system and the gross beta or gamma monitoring for noble gases will be sufficient to determine if any radioactivity is present in the release. If a primary to secondary leak exists, then tne release from the main condenser evacuation and turbine gland sealing systems will be sampled and analyzed in accordance with Table 5.4-1.
65
l Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.4 GASEOUS EFFLUENTS (cont'd)
- c. IODINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN -PARTICULATE FORM (Section 5.4.3)
This specification is provided to implement the raquire-ments of Sections ll.C, III.A and IV.A of Appendix I, 10 CFR Part 50. The Specifications are the guidea set --
forth in Section II.C of Appendix I. The ACTION state-ments provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
The calculational methods specified in the Surv. 11ance Requirements implement the requirements in Section III.A of Appendix 1 that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBElt CF THE PUBLIC through appropriate pathways is unlikely La be substantially underestimated. The calculational m thodo-logy and parameters for calculating the doses due to the actual release rates of the subject materials are con-sistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Pegulatory Guide 1,111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Vater-Cooled Reactors,' Revision 1, July 1977. These equations also provide for detenaining the actual doses based upon the historical average atmospheric conditions.
66
m_._ . . _ , . - - . 4 m _ _ . _ . . . . . .~ . _ . _ . . _ . _ . _ _ . _ _
l l
-Administrative Procedure UNT-005-014 l i
~ Offsite Dose Calculation Manual Revision 1 l l
l l
l 5.4 GASEOUS EFFLUENTS (cont'd) ;
i The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the exirting radionuclide pathways to inan in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy arean where milk animals and meat producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
- d. GASEOUS RADWASTE TREATMENT (Section 5.4.4)
The OPERABILITY of the WASTE GAS 110LDUP SYSTEM and the VENTILATION EX11AUST TREATMENT SYSTEM ensures that the ,
systems will1be available for use whenever gaseous effluents-require-treatment prior to release to the environment. The discharge from the main condenser evacuation and turbine-gland scaling system shall be required;to be directed to the-plant stack when the
' release race of 1-131 from this source isL1 2 x 10 4 pCi/s. The requirement that the appropriate portions of ,
these systems be_used, when-specified, provides reasonable I
assurance that the. releases of radioactive materials in gaseous effluents will be kept "as low as-is reasonab]y achievable". This; specification implements the require-- -
ments of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to110 CFR Part 50 and the' design objectives- ,
given in Section II.D of Appendix.1-to 10-CFR Part 50. The specified' limits governing'the use of appropriate portions of the systems were specified.as a suitable: fraction of the dose design objectives set forth in Section II.B and II.C of Appendix =1, 10 CFR Part 50, for gaseous effluents.
67
UNT-005-014 Administrative Procedure
-Offsite Dose Calculation Manual Revision 1 5.5- TOTAL DOSE l l
5.5.1 TOTAL DOSE SPECIFICATION l
The annual (calander year) dose or dose commitment to any-MEMBER OF THE PUBLIC due to release of radioactivity and to radiation from uranium fuel cycle sources shall be limited to i less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. l APPLICABILITY: At all times.
ACTIO_: N
~
With the calculated doses'from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of . Specification 5.3.2.a 5.3.2.b, 5.4.2.a. 5.4.2 b, 5,4.3.a, or 5.4.3.b calculations-shall be made including direct radiation contributions from the reactor units and from outside storage tanks to deternine whether the above
< limits of Specification 5;5.1.have been exceeded. .This:
= evaluation should be done-in'accordance with guidancesin Section 5.5.2. If such'is the case, prepare and submit to
'the Commission within 30 days, pursurnt to Technical Specifi-!
cationJ6.9.2, a Special-Report that-defines the corrective Jaction to be taken to reduce subsequent releases to prevent recurrence of. exceeding the-above limits and includes the f- _
schedule for ach'ieving conformance with the above limitsi Tbis.Special Report,.as definedEin 10 CFR 20.405c, shall
- include an. analysis that estimates the radiation exposure
.(dose) to'a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar-year that includes the release (s). covered by.. .
thia report. It shall also describe 11evels of radiation and 68
Adtninistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.5 TOTAL DOSE 5.5.1 TOTAL DOSE SPECIFICATION (cont'd) concentration of radioactive mat erial involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provinions of 40 CFR Part 190.
Submittal of the report is considered a timely request, and a variance is granted until staff action on the request ir, complete, ,
SURVEILLANCE REQUIREKENTS:
- a. Cumulative dose contributions frem liquid and gaseous effluents shall be determined in accordance with Specifi-cation 5.3.2, 5.4.2, and 5,4.3 and in accordance with the methodology and parameters in the ODCM.
- b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be delarmined in accordance with the methodology and parameters in the ODCM. This requirements is applicabic only under condition set forth in Specification 5.5.1.
l 69 i
UNT-005-014 LAdministrat.ive Procedure offsite Dose Calculation Manual Revision .
7 5.5 TOTAL DOSE (cont'd) 5.5.2 40 CFR 90 DOSE EVALUATION This section demonstrates compliance with Specification 5.5.1 Surveillance Requirements, Specifically, the dose or dose connitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and raalation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited .
to ler.s than or equal to 75 mrem) over 12 consecutive months.
Dose evaluations to demonstrate compliance with the above dose limits need to be performed only if quarterly doses exceed: -
(1) 3 mrem to the total body (liquid releases).
(2) 10 mrem to any organ (liquid releases).
-(3) 15 mrem to the thyroid or any organ from radiciodines and particulates (gaseous releases).
^ otherwise no evaluations are required. .
For'the evaluation of doses to'real individuals from liquid
. releases, the same. calculational methods as employed in Section 5;3.4 will; be used. However, more encompassing and realistic. assumptions will be made concerning the dilution and ingestion of radionuclides by. individuals who live _and fish in
+
the Waterford,3 area. The results of the Radiological Environ-
- mental Monitoring Program willL be used in. determining- the; crealistic dose based on actual measured radionuclide concentra-s 70
Administrative Procedure UNT-005-014 iJ Offsite-Dose Calculation Manual Revir.fon 1 i
l I
5,5 TOTA!, DOSE (cont'd) l tions. For the evaluation of-doses to real individuals from gaseous releases, the same calculational methods as employed
,L in sections 5.4.6 and 5.4.7 111 be used. The total body dose l factor should be substituted for the gamma ait dose factor
'(Mg ) to determine the total body dose. Otherwise, the same calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, .
the-meteorological conditions, and the consumption of food.
Data obtained from the latest land use census should be used to-determine locations for evaluating doses. The results of t.he. Radiological Environmental Honitoring Program will be included in determining more realistic doses based on a_.ual ,
. measured radionuclide concentrat ions. .
' Cumulative dose-contributions-from direct radiation, from the
. reactor unit, and from Radwaste Storage Tanks shall be deter-mined utilizing .the result s of' routine plant perimeter surveys, TLD data,- or a combination 'of both when neccarary.
s 9
9 71 ,
,'i , -.. , . . - . . - - . . . . , . . , , , . . . -
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.5 TOTAL DCSE (cont'd) 5.5.3 Total Dose Bancs The specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report whenever the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives if Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small.
The Special Report will describe a course of action that should result in the limitation of the annual dose to a MEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits.
For the purposes of the Special Report, it may be assumed that
- the dose coannitaent to the- NEMBER OF TifE PUBLIC f rom other uranium fuel cycle sources is negligible, with the exception l that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of 8 km must
-be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to-exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditionr. resulting in violation of 40 CFR.Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed.
72
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases The variance only relates to the limits of 40 CFR Part 190, and does not apply in any way to the other requirements for dose limitation of 10 CFR Part 20, as addressed in Specifications -
5.3.1 and 5.4.1. An individual is not cour'.dered a MEMBER OF THE PUBLIC during in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
A d
_ II
UNT-005-01'4 Administrative Procedure
- Offsite Dose Calculation Manual Revision 1 5.6 INSTRUMENTATION 5.6.1 Radioactive Liguid Effluent Monitorinj Instrumentation Speci f i ca tiot.
The radioactive liquid ef fluent monit oring instrumentation channels shown in Table 5.6-1 shall be OPERABLE wit.h their alarm / trip setpoints set to ensure that the limits of Specification 5.3.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section
5.3.5. APPLICABILITi'
At all times.
1 ACTION:
- a. With radioactive liquid effluent monitoring instrumentation channel-alarm / trip setpoint less conservative than required by the above Specification, inanediately suspend the release of radioactive liquid effluents monitored by the. ,
affected channel, or' declare thel channel inoperable.
- b. With less than the minimum number of radioactive liquid >
effluent monitoring-instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-1. Restore:the inoper-able instrumentation to OPERABLE status.within':30 days or, if unsuccessful, explain >1n-the next! Semiannual Radioactive Effluent Release Report, . pursuant to Technical Specifica :
Lion'6.9.1.8, why this inoperability was not corrected-
~
within the time specified. Releases need not'be terminated-after130 days provided the specified ACTIONS are continued.
i 74
L UNT-005-014 l-Administrative Procedure l Offuite Dose Calculation Manual Revision 1 l 5.6 INSTRUMENTATION (Cont'd)
SURVEILLANCE REQUIREMENT Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE. CHICK, CHANNEL CALIBRATION and CHAlNEL FUNCTIONAL TEST operations at the frequencies shown in Table t 5.6-2.
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UNT-005-014 Surveillance; Procedure .
-Revision 1 Offsite Dose Calculation Manuni'
. TABLE 5.6-1 RADI0 ACTIVE LIQUID EFFLUENT' MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE ACTION INSTRUMENT i
- 1. RADIDACTIVITY MONITORS PROVIDING ALARM AND
- AUTOMATIC TERilINATION OF RELEASE 1 28
- a. Boric Acid. Condensate Discharge 28 ;
1
- b. Waste, Vaste Condensate and Laundry Discharge 29 1/ sump
- c. Dry Cooling Tower Sumps 29
- d. Turbine Building Industrial Waste Sump 1
- e. CirculatingWaterDischarge(BloadownHeatExphanger 1 29 and Auxiliary Component Cooling Water Pumps).
- 2. CONTINUOUS COMPOSITE. SAMPLERS 1 29 Steam: Generator Blowdown Effluent'Line
- a. ~1
- 3. FLOW RATE MEASUREMENT DEVICES 1 30 :
- a. Boric Acid Condensate Discharge 1 30
- b. Waste, Waste Condensate and Laundry Discharge N.A.
Turbine Building Industrial Waste Sump
- N.A.
- c. ~
N.A. N.A.
- d. Dry Cooling Tower Sumps *
- e. Circulating Water Discharge * (Blowdown and Blowdown Heat l Exchanger and Auxiliary Component Cooling Water Pumps) N.A. N.A. ,
f I
- Automatic termination of bIcwdown discharge only i
76
Administrative Procedure UNT-005-014
- Offsite-Dose Calculation Manual Revision 1 TABLE 5.6-1 (Continued)
TABLE, NOTATIONS
- Pump performance curves generated in place shall be used to estimate flow.
ACTION STATEMENTS ACTION 28 - With the number of channels OPERABLE less than required by the Minimtun Channels OPERABLE requirement, ef fluent releases via this pathway may continue provided best efforts are made to repair the instrument and that prior to initiating a release:
a.- At=least two independent samples are analysed in accordance with Specification 5.3.1, and
-b. At least two technically qualified members of the-
= Facility Staff independently verify the release rate calculations and discharge line' valving; ACTION.29:- With the number of channels-OPERABLE lesr. than required by the Minimum Channels OPERABLE requirement,' effluent _ releases-via.this pathway may_ continue provided-best efforts are made uto-repair the instrument and that grab: samples are analyzed -
for radionet'vity at a. lower: limit of detection of-at least 10-7 microcurie /ml- ,
- a. At=Icast'once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.when-the specific activity.of-the L secondary coolant is greater than 0.01~ microcurie / gram -
-l-DOSE EQUIVALENT.I-131, ur
- b. At_least:once per 24 hourcLwhen the_ specific' activity of?
'the secondary coolant is:less than or{ equal to 0.01
= microcurie / gram DOSE EQUIVALENT 1-131.
ACTION 30 -'With-the number of channels OPERABLE less than required,by.the-
. Minimum Channels OPERABLE requirement, effluent releases ^via-
_-_this pathway may continue-provided best efforts are made to repairtthe-instrument and that the flow rate is estimated'at least once per-4'hoursLduring actual releases. Pump performance curves generated in-place may be used to estimate
_ flow, e
- 77 l
UNT-005-014L Surveillance Procedure- ' Revision 1 Offsite' Dose Calculation Menus 1
-TABLE 5.6-2 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CliANNEL CHANNEL SOURCE CHANh1L FUNCTIONAL INSTRUMENTJ CHECK CHECK CALIBRATION - TG f
- 1. RADI0 ACTIVITY MONITORS PROVIDING ALARMS AND AUTOMATIC TEPJfINATION' 0F RELEASE
- a. -Boric Acid Condensate Discharge P P R(3) Q(1)
- b. Vaster Waste'. Condensate and Laundry P- P R(3) Q(1)
Discharge
- c. Dry Cooling' Tower Surnps D M R(3) Q(5)
- d. Turbine Building-Industrial Vaste Sump D M R(3) Q(5)
- e. Circulating Water Discharge (Blowdown lleat Exchangerj . _. .D M R(3) Q(5)
Auxiliary Component Cooling Water Pumps) g
- 2. : CONTINUOUS COMPOSITE SAMPLERS a.
~
Steam Generator Blowdown Effluent Line D(6) N.A. R Q
- 3. FLOW RATE' MEASUREMENT DEVICES
- a. Boric Acid Condensate Discharge D(4) N.A. h Q
- b. Waste, Vaste Condensate'and Laundry D(4) N.A. R Q Discharge Turbine Building Industrial Vaste Sump N.A. N.A. N.A. N.A.
c.
Dry Cooling Tower Sumps- N.A. N.A. N.A. N.A.
d.
- e. Circulating Water Discharge (Blowdown and Blowdown Heat Exchangers and Auxiliary Component--Cooling Water Pumps) N.A. N.A. N.A. N.A.
- Automatic:terminaticn.of: Blowdown; discharge-only-78
UNT-005-014
' Administrative Procedure l Offuite Dose Calculation Manual Revision 1 1
1 3BLE 5.6-2 (Cont.inued)
TABLE NOTATION
-1. 'The CllANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists. ,
l'. Instrument indicates measured levels above the alarm / trip setpoint.
12 . Circuit failure
- 3. Instrument indicates a downscale failure.
-2. The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. The initial CllANNEL CALIBRATION shall be performed using one or more of the' reference standards certified by the National-Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement' assurance accivities with NBS. These standards shall perm 1L calibrating the system for overiits intended range of energy and measurement range.. For subsequent-CIIANNEL CALIBRATION, sources 1that have-been related_to the initial calibration'shall be used.-
- 4. CHANKEL CliECK shall _ consist of verifying = indication _ of flow during periods of release.- TCllANNEL CIIECK shall be made at _least once per 24. hours on
- 1 days on which continuous,-periodic, or batch' releases _are made.
- 5. -The CllANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway: occurs if the-instrument indicates measured levels above the alarm / trip setpoint and.that_ control room alarm
' annunciation' occurs if~any of.the__following conditions exists: ,
- 1. .. Instrument indicates measured levels:above the alarm set.
- 2. Circuit failure.
3.- Instrument controls not~ set in. operate mode.
- 6. CllANNEL CHECK shall.be made at least once per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-on days _on which L continuous releases are made to-the_ Circulating Water System or Waterford.
3 waste pond.
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UNT-005-014 Administrative Procedure Offsite Dose Calculation rianual Revision 1 l
l 5.6 INSTRUMENTATION (cont'd) 5.6.2 Radicactive Gaseous Ef fluent tionitorint nstrumentation I Specifications The radioactive gaseous effluent monitoring instrumentation channels shown in Table 5.6.3 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of --
Spec.fication i 5.4.1 are not cxceeded. The alarm / trip setpoints of thece channels shall be determined and adjusted in accordance with the methodology and parameters in Section
5.4.8. APPLICABILITY
As shown in Table 5.6-3 ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above Specification, -
immediately suspend the releane of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative,
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-3. Restore the inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Eifluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.
80
UNT-005-014 Administrative Procedure Revision 1 Offsite Dose Calculation Manual 5.6 INSTRUMENTATION (cont'd)
SURVEILLAKCE REQUIREMEh"lS:
Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated CPERABLE by performance of the CHANNEL CIECK, SOURCE CIECK, CilANNEL CALIBRATICN, and CilMTNEL FUNCTIONAL TEST operations at the irequencies shown in Table 5,6-4.
81
1 cSurveillance Procedure UNT-005-014-
' Revision 1:-
I'Offolte Dose Calculation Manual-TABLE 5.6-3 RAD 10 ACTIVE GASEGUS EFFLUEN1 MONITORING INSTRLHEhTATION MINIMUM CHANNELS.
OPERABLE APPLICABILITY ACTION INSTRUMENT
- 1. BASTE GAS HOLDUP. SYSTEM:
- a. N'oble Gas Activity Monitor'-
Providing Alarm and.' Automatic? **
, -Termination of-Release 1. - 35:
. b;, . . Effluent System Flow Rate- **
1 Measuring Device 1 36
- 2. MAIN CONDENSER EVACUATION AND TLTBINE GLAND SEALING SYSTEM' 1
- "~* 37
- a.
Noble Gas Activity Monitor I
- 39
' b.. Iodine Sampler #'
- - 39 Particulate Sampler Y' I c.
- 36
- d. . Sampler. Flow' Rate Monitor 1
- #If a primary to secondary leak exists or.if the noble gas monitors in the main condenser evacuation and turbine gland sealing. system or if the. steam generator blowdown monitor indicates .the presence of radioactivity in the secondary system, the flow from this release point shall be diverted imediately to the plant stack. These instruments are in
'the plantistack and sampling for radiciodines and particulates shall occur at the plant vent when this occurs.
1 s
e i
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UNT-005-014 Revision 1 Surveillance Procedure Offsite Dose Calculation Manual 1 TAELE 5.6-3 (Continued)
RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMLH CHANNELS ACTION OPERABLE APPLICABILITY INSTRUMENT
- 4. REACTOR AUXILIARY BUILDING VENTILATION SYSTEM (PLANT STACK)
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
- 37 1
Termination of Release #
- 39 l
1
- b. Iodine Sampler
- 35 I
c Particulate Sampler ^ 36 1
- d. Flow Rate Monitor ~
36 1
- e. Sampler Flow Rate Monitor
- 5. FUEL IIANDLING BUILDING VENTILATION SYSTEM (NORMAL)
- 37 1
- a. Noble Gas Activity Monitor-
- 39 1
- b. Iodine Sampler
- 39 1
- c. Particulate Sampler
- 36 1
- d. Flow Rate Monitor
- 36 1
- e. Sampler Flow Rate Monitor
- Automatic termination of containment purge only.
83
- - - - O
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 TABLE 5.6-3 (Continued)
TABLE NOTATIONS
- At all times.
- During gas waste decay tank discharge.
- With irradiated fuel in the storage pool.
- When the main condenser is under a vacuum.
ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the-tank (s)_msy be released to the environment provided best efforts _are made to repair the instrument and that prior to initiating the release:
- a. At'least two independent samples of the tank's contents are analyzed, and
- b. At.least two technically qualified members of the facility staff independently verify the release rate calculations and discharge valve lineup; ACTION 36~- With the number of channels OPERABLE less than required by- I the Minimum Channels-OPERABLE requirement,-effluent releases via this rathway may continue provided best-efforts are made
-to repair thel instrument and that the flow rateLis estimated at least once per14 hours. For the waste ges holdup tank this action item is applicable only-.during periods of release. 'For the main condenser evacuation and turbine gland sealing systems, this action item applies-only during release-
'_via the discharge silencer and only during turbine gland sealing _ operations"and/or vacuum pump operation.
ACTION 37 - With the number of' channels OPERABLE less than--required by the Minimum Channels _0PERABLE_ requirement, effluent releases =
via this pathway may_ continue provided best efforts are made to repair the instrument and that grab samples are taken at
~
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and these samples are analyzed.for gross activity within-24 hours.-'However, containment purging of radioactive effluents must be immediately suspended during this condition for the plant-stack only.
~
84
.1 Administrative Procedure UNT-005-014 Offsite Dose calculation Manual Revision 1 TABLE 5.6-3 (Continued)
TABLE NOTATIONS ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue provided best efforts are made to repair the instrument and that samples are continuously collected with auxiliary sampling equipment as required in Table 5.4-1.
e n
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85
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. -- -.a
4 UNT-005-014
'St.rveillance Procedure Revision 1
'#0ffsite Dose Calculation Manus 1 TABLE 5.6-4 j RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CRAVEL MODES IN VHICH CHANNEL SOURCE CHANNEL FUNCTIONAL SL%'EILIANCE CHECK- CHECK CALIBRATION TEST IS FIQUIRED
. INSTRUMENT
' 1.' VASTE GAS HOLDUP SYSTEM a.- Noble Gas e,rtivity Monitor --
. Providing Marm and Automatic
- Terminatf<t of Release P P R(3) Q(I)
< .b. Effluent.. System Flow Rate-
- Measuring Device P N.A. R Q i
- 2. MAIN CONDENSER EVACUATION AND To"2BINE GLAND SEALING SYSTEM l
-a. Noble Gas Activity Monitor D M R(3) Q(2) 1 a-Iodine Sampler W N.A. N.A. N.A.
l b.
)
- Particulate Sampler W N.A. N.A. N.A.
I c.
i *
-d Sampler Flow Rate Monitor D N.A. R Q i
i I
i i
i
- 16
.UNT-005-014 Surveillance Procedure Revision 1
.Offsite Dose Calculation Manual
-e
' TABIE 5.6-4 (Continued) ;
I RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SITEILLANCE REQUIREMENTS l i
' CHANNEL % DES I4 VHICH j SURVEILLANCE CHANNEL SOURCE CHANNEL FUNCTIONAL t CECK CHECK CALIBRATION TEST IS REQUIRED INSTRUMENT l f
I 4. REACTOR AUXILIARY BUILDING i VENTILATION SYSTEM !
(PLANT STACK) L
- a. Noble Gas' Activity Monitor -
' l Providing Alarm and Automatic
- Tensination of Release D M R(3) Q(6)
N.A. *
- b. Iodine' Sampler- W N.A. N.A. f I
N.A. *
- c. Particulate Sampler W N.A. N.A. l L
- d. Flow Rate Monitor D N.A. R Q.
- e. Sampler Flow Rate Monitor 'D N. A. - R Q i
- 5. FUEL HANDLING BUILDING f
VENTILATION SYSTEM (NORMAL) i i
1*
- a. Noble Gas.' Activity Monitor D M R(3) Q(2)
I W N.A. N.A. N.A. ***
- b. . Iodine Sampler N.A. ***
.c. Particulate Sampler- W N.A. N.A.
J N.A. R Q *** i
- d. Flow Rate Monitor D I'
N.A. R Q *** . ,
- c. Sampler Flow Rate Monitor D .
i t
'# Automatic termination of containment. purge only. i I
t i
87
[
Administrative Procedure UNT-005-014 Offsite Dose Calculatisn Manual Revision 1 TABLE 5.6-4 (Continued)
TABLE NOTATIONS
- At all times.
- When irradiated fuel in in the spent fuel pool.
- 1. The CilANNEL FUNCTIONAL TES1 shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
2.- Circuit failure.
- 3. Instrument indicates a downscale failure. i
- 2. The CllANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. The initial CilANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CFANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
6.- The CilANNEL FUNCTION TEST shall also demonstrate that' automatic isolation 1 of this pathway occurs if the instranent indicates measured levels above the- alarm / trip setpoint and that control room alarm annunciation occurs-if any of the;following conditions exists: ,
~1; Instrument indicates measured levels above the alarm set.
2, Circuit failure.
- 3. Justrument cont.rols not set in operate mode, i
6 88
UNT-005 014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.6 INSTRUMENTATION (Cont'd) 5.6.3 Instrumentation bases _
- a. RADIOACTIVE LIQUID EFFLUENT HONITORING INSTRUMENTATION (S.6.1)
The radioactive liquid effluent. Instrumentation is provided to monitor and control, as applicabic, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents.
The alarm / trip setpoints f or these instrument s shall he calculated and adjusted in accordance with the methodology and parameters in Section 5.3.5 to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumenta-tion is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
- b. RADIOACTIVE GASEOUS EFFLUENT HONITORING INSTRUMENTATION (5.6.3)
The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or pstential releases of gaseous ef fluents.
The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and_ parameters in Section 5.4.8 to ensure that the alarm / trip will occur prior to' exceeding the limits of 10 CFR part'20. This instrumentation also include provisions for monitoring (and cont.alling) the concen-trations of potentially explosive gas mixtures in the WASTE GAS Il0LDUP SYSTEM. The OPERABILITY and use of this instrumentation is consistent with the requirements of General _ Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
89
UNT-005-014 Administrative Procedure Revision 1 l Offsite Dose Calculation Manual 1 l
5.7 LIQUID AND CASE 0VS RADWASTE PROCESSES The block flow diagrams of the radwaste systems are shown in I
Attachments 6.11 and 6.12. In order to obtain a more detailed description, see the appropriate i.ections of the PSAR, T
?
i
~
i I
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\
90 J
"-+e-
- e-.- , , , , , , , _ , , , ,
UNT-005-014 Administrative Procedure Revision 1 OfIsite Dose Calculation Manual 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIREMENTS 5.8.1 R_adjplagical Environmental Program Specification The radiological environmental toonitoring program shall be conducted as specified in Table 5.8-1.
APPLICABILITY: At all times.
ACTION:
- a. With the radiological environmental monitoring program not being conducted as specified in Table 5,8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.7, a description of t.he reasons for not conducting the program as required and the plans for preventing a r-currence.
- b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a speci-fled location exceeding the reporting levels of Table 5.8-2 when averaged over any calendar quarter, pre-" ire and submit to the Conmiission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annua). dose
- to a MEMBER OF TllE PUBLIC is less than the calendar year limits of Specifications 5.3.2, 5.4.2, and 5.4.3. When more than one of the radionuclides in Table 5.8-2 are detected in the sampling medium, this report shall be submitted if:
_ concentration (Il , concentration (2) ,
... > 1,0 reporting level (1) reporting level (2)
- The methodology and parameters used to estimate the potential annual dose to A MEMBER OF THE PUBLIC shall be indicated in this report.
91
- - - - - - - -..---- - -. - _.- - . - -. ~ ..- .. --
i Administrative Procedure UNT-005 014 :
Offsite Dose Calculation Manual Revision 1 5.6 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRW PIQUIPINEH1S (Cont'd) l When radionuclides other than those in Table 5.8-2 are
. detected and are the result of plant effluents, this '
report shall be submitted if the potential annual dose l to A tiEMBER OF TIIE PUBLIC is equal to or greater than the calendar year limits of Specifications 5.3.2, 5.4.2, and 5.4.3. This report is not required if the measured level ;
of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological '
- Environmental Operating Report.
- c. With milk or fresh leafy vegetable samples unavailable i
from one or more of the sample locations required by Table 5.8-1, ide.itify locations for obtaining replacement samples and add them to the radiological environmental ,
monitoring program within 30 days.
The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.9.1.8, identify the cause of the unavailability of samples and &
identify the new location (s) for obtaining replacement samples in the next Semiannual Radioective Effluent-Release Report and also include in the report revisions of Attachments 6.13, 6.14, 6.16, 6.17 and 6.18 reflecting the new location (s).
92
=- . .- -.,--.- -.-.= -,- -. -- .- . - . . - .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 1 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REQUIRLME'<T5 (Cont'd)
Sl!RVEll.l.ANCE REQUlkEMENTS:
The radiological environniental monitoring samples ihail be collected pursuant to Table 5.8-1 irom the specific locations given in Attachnients 6.13 and 6.14, and shall be analyzed pursuant to the requirements of Table 5.8-1 and the detection capabilities required by Tabic 5.8-3.
I 93
UNT-005-014 Surveillance Procedure Revision i Offsite Dose. Calculation Maaual TABLE 5.8-1 RADIOLOGICAL EhTIRONMENTAL MONITORING FROGRAM*
NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQi~r3CT EXPOSUPI PATINAY SAMPLES AND OF ANALYSIS a OLLECTION FREQUENCY SAMPLE LOCATIONS AND/OR SAMPLE Quarterly Gaama dose quarterly.
31 routine monitoring stations
- 1. DIRECT RADIATION -
either with 2 or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows: l l
an inner ring of stations, one in each meteorological secter in the general area of the SITF BOUNDARY, an oater ring of stations, I in 10 of the meteorological sectors l
in the 6 - to 8-km range from the site; the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations This table presents an
- The number, media, f requency, and location of samples may vary f rom site Local to site.site characteristics acceptable minimum program for a site at which each entry is applicable.
must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included in the sampling program.
94 I ____ -
157-005-014 Surveillance Procedure Revision 1 Offsite Dese Calculation Manual TABLE 5.8-1 (Continued)
FADIOLOGICAL ENVIRONMENTAL MONITORING FROGP M NL?tBER OF REPRESENTATI'd SAMPLING AND TYPE A'O FREQW.NCY EXPOSURE PATHVAY SAMPLES ASTi OF ANALYSIS a COLLECTION FREQilENCY SAMPLE LOCATIONS AND/OR 2 AMPLE l
l
- 2. AIRBORNE Continuous sampler Radioiodine Canister f Radiciodine and Samples from 5 locaticns: operation with sample I-131 analysis weekly. j 1
Particulates collection weekly, or I 3 samples from close to the more frequently if 3 SITE E00NDARY locations, in Particulate Sampler: j different sectors, of the required by dust Grcss beta radioactivity j loading.
highest calculated annual average analy-is following l ground-ievel D/Q. filter change; c aeca isotopic analysis
- I saeple from the vicinity of a of composite (by comunity having the highes* In(ation) quarterly.
calculated annual average ground-level D/Q.
I sample froat a control location, as for exa g le 15-30 km distant and in the least prevalent vind direction.'
\
- 3. WATERPORNE isotopic analysis
- Camma Composite sagl,e over Composite for Surface 1 sample upstream I-month peried' menthly.
a.
1 sample downstream tritiumanalysisquarterlyf ane y Gm isot pic and tritium
- b. Ground Samples from I or 2 sources h analysis quarterly. t only if likely to be affected .
95 I
UNT-005-014 Surveillance Procedure Revision 1 I Offsite Dose Calculation Manual TRBLE 5.8-1 (Continued) ,
RADIOLOGICAL ENVIRONMEh7AL MONITORING PF0GRA!T*
. NUMBER OF REPRESENTATIVE i SAMPLES AND SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATINAY SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS AND/OR SAMPLE- i Composite sample- I-131 analysis on each
- c. Drinking 1 sample of each of I to 3 of .
the nearest water supplies that over 2-week period 8 composite when the dose could be affected by its when I-131 analysis calculated for the i discharge. is performed, monthly consumption of the water composite otherwise is greaterj than 1 mrem l per year. Composite for !
- i. gross beta and gamma
! isotopic analyses
- j-2 monthly. Composite for
' tritium analysis quarterly.
i
- 1. sample from downstream area Semiannually Gamma isotopic analysis'
) 'd. Sediment semiannually.
i from. with existing or potential h shoreline ' recreational value. t i
i i
- 4. INGESTION l Samples from milking animals Sesimonthly when Gamma isotopic
- and 1-131 .
"a. Milk in 3 locations within 5 km animals are on analysis seminenthly when I i distance having the highest pasture; monthly at animals are on pasture; j dose potential. If there are other times. monthly at other times. ;
y- none,-then, I sample froa milking I i
animals'in each of 3 areas between ~
5 to B km distrnt where doses are calculated,to be greater than i L
l' I mrem per vr.*
i i 1 sample from milking animals
- at a control location 15-30 km l l distant and in the least '
2 prevalent wind direction.C i r
I i
96 ,
t
.. . ,~- . . - - _ . _ . _. . . , . _ , . _. _ __ _ _ _ _ _ _ _ _ _ _
4 UNT-005-014 Surveillance Procedure Revision 1 Offsite Dose Calculstion' Manual TABLE 5;8-1-(Continued) 2 .
'RADIOIEGICAL ENVIRONMENTAL MONITORING PROGP M t
WUMBER OF
!' ' REPPISENTATIVE
. SAMPLES AND SAMPLING AND TYPE AND FREQUENCY
-EXPOSURE PAT!P4AY:
. SAMPLE LOCATIONS
- COLLECTION FPIQUENCY OF ANALYSIS AND'/OR SAMPLE 1 sample of each commercially Sample in season, or Gamma isotopic analysis
- lb. Fish and on edible portions.
Inverte- and recreational important' semiannually if they
, brates species.in vicinity of plant are not seasonal discharge. area.
I sample of same species in areas'not ir.fluenced by plant
., discharge.
1 sample of each principal class At time of harvest 5 Gamaa isotopic analysis'
! c. . Food on edible portion.
? Products of food products from any area that is irrigated by water in
- .w hich liquid plant wastes have.
I discharged.
4
-Samples of 1 to 3 different kinds Monthly when Gamma isotopic" and I-131 of broad leaf vegetation grown . available analysis.
nearest each of two different offsite locations of highest predicted annual average ground-1 level. D/Q if milk sampling is not perfo rmed.
1 I sample of cach of the similar. Monthly when Gamma isotopic" and I-131 l l'
' broad leaf vegetation grown available analysis.
!- 15-30 km distant in the least prevalent wind' direction if milk sampling is not performed.
4 97
UNT-005-014 Administrative Procedure .
Offsite Done Calculation Manual kevision 1 TABI.E 5.8-1 (Continued) 1ABLE NOTATIONS l
" Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample location in Attachments 6.14, 6.16, 6.17 and 6.18. !
Refer to NUREG-0133, "Pwaration of Radiological Ef fluent Technical Specifications for Nuc. > Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, kevision 1, November 1979. Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate teasons. If specimens are unobtainable >
due to sampling equipment malfunction, corrective action shall be completed prior to the end of the next sampling period. All deviations from the sampling t
schedule t. hall be documented in the Annual Radiological Environmental Operating i Report pursuant to Specification 6.9.1.1. It is recognized that, at times, it.
may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time, in these instances suitable alternative media and locations tusy be chosen f or the particular pathway in i question and appropriate substitutions made within 30 days in the radiological #
environmental monitoring pro), ram. Pursuant to Specification 6.9,1.8, identify
' the cause of the unavailability of samples for that pathway and identliy the .
new location (s) for obtaining replacement samples in the next Semiannual i
Radioactive Effluent Release Report and also include in the report a ravised figure (s) and table reflecting the new location (s).
bone or more instruments, such as a pressurized ion chamber, for measuring and {
recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoltuninescent ,
dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a _
packet are considered as two or more dosimeters. Film badges shall not be '
used as dosimeters for measuring direct radiation. The frequency of analysis or readout-for TLD systems will depend upon the characteristics of the specific. system used and should be selected to obtain optimtun dose information 1 with minima? fadingi The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted.
dAirborne particulate sample filters shall be analy. .1 for gross beta radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for random and thoron L
daughter decay. If gross bata activity .in air particulate samples is greater than 10' times the yearly mean of control samples, gamma isotopic analysis shall be performed on the' individual samples.
L
' Gamma-isotopic analysis = means the identlfication and quantification of L
gamma-emitting radionuclides that may be attributable to the effluents from the y facility.
98
_ _ _ _ _ _ _ _ . _ . __ . ____ _ _ . . . ._.,__.__,__%,_,. ~ _ _ . _ _ _ . -
Administrative procedure UNT-005 014 Offsite Dose Calculation Manual Revision 1 Continued)
TABLE 5.8-1 {kfIONS TAliUI~NOT I
The " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area
,- beyond but near the mixing tone. " Upstream" san >ples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational setivities.
EA composite sample is one in which the quantity (aliquot) of liquid sampled is l
. proportional to the quantify of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flov. In this program composite sample aliquots shall be c?llected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.
Groundwater -samplek shall be taken when this source is tappc<' for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.
I The dose shall be calculated f or the maximum organ and age group, using the methodology and parameters in this document.
d lf harvest occurs more than once a year, samp]Ing shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly. Attention shall he paid to including samples of tuberous and root food products.
L 1
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Administrative procedure UNT-005-014 offsite Dose Calculation Hanual Revision 1 j 5
TABLE 5.8-3 TAllLE NOTATIONS !
- This list does not mean that only these nuelldes ate to be considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
b Required detection capabilities for thermoluminescent dosimeters used for i environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13.
. The LLD is defined, for purposes of t.hese specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, ,
-above system background, that will be detected with 95% probability with only
, 5% probability of falsely concluding thst a blank observation represents a "real" signal.
For a parth.usar measurement system, which may include radiochemical separation:
. 4.66 s h LLD =
E . V . 2.22 x 106 . Y . exp(A AT7 Where:
LLD is the "a priori" 1,'wer limit of detection as defined above, as microcuries per unit mass or volume, 8b is the standard deviation of the background counting rate or of the {
counting rate of a blank sample as appropriate, as counts per rainute, E is the counting efficiency, as counts per disintegration, V is the sample size in units of ruass or volmne, ,
2.22 x 10 8 is the number of disintegrations per minute per microcurie. -
Y is the fractional radiochemical yield, when applicable.
A is the= radioactive decay constant for-the particular radionuclide,-and at for environmental samples is the elapsed time between sample -
collection,'or end of the sample collection period, and time of counting-
-Typical values-of E, V, Y and At should be used in the calculation.
102
_ . - . -__ __ __ .. . - _ _ . _ . - ~ _ ~ - _ . _ , _ _ ~ . - _ . . . , . _ . , , _ . -,_
- - -. - ._.-...~.
. . - - - - . - - - . . . . _ - - - - ~ - - . . - - ~ - . . -
- l B
)
Administrative Procedure UNT 005-014 <
s Offsite Dose Calculation lianual Revision 1 !
i 4
4 i
l TAllLE 5.8-3 JContinued) !
TAhli NOTATIONS
, i
, It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a menourement syr. tem and not as ati t a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved j- under routine conditions. Occasionally background fluctuations, unavoidable i small sampic sizes, the presence of interfering nuclides, or other i uncontrollable circumstances may render these LLDs unachievable. In such !
cases,'the contributing factors shall be identified and. described in the :
Annual Radiological Environmental Operating Report pursuant to Technical.
Specification 6,9,1,7.
d LLD for drinking water sampics. If no drinking water pathway exists, the LLD j of gamma isotopic analysis may be used, 4
L i
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103
- )
. . . . . - - _ . .___ _ _ . . . . ~ . . _ . _ . . _ . _ _ . . . . . _ _ . . _ _ . . . _ . _ . _ . . . _ . . _ _ . _. __ _ _ _ . _ _ _ _ . __
UNT-00$-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 1
1 1
5.8 RADIOLOGICAL ENVIRONMENTAL HONITORING (Cont'd) i 5.8.2 Interlaboratory Comparison Program Specification l Analyses shall be performed on all radioactive materials f supplied as part of an Interlaboratory Comparison Program that has been approved by the Conunission. ;
APPLICABILITY: At all times.
i ACTION: __ t
- a. With analyses not being performed as required above, report the corrective actions taken to prevent a i recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant. to Technical Specification 6.9.1.7. ;
i SURVEILLANCE REQUIREMENTS The Interlaboratory comparison Program shall ;r described in i
Section 5.8.5. A summary of the results obtained as part of j the.above required Interlaboratory Comparison Program shall .
be included in the Annual Radiological Envirotunental Operating Report pursuant to Technical Specification'6.9.1.7.
f i
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._._._.._.~...._a._..__... .._;.._._.-_.---._..__.._.,_-_...~..,_.,_______...._.__.._..u,__..,---
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd)
$.S.3 Land Ur.e Census Specification A lend use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden
- of greater than 50 m2 (500 ft2) producing broad leaf vegetation.
s APPLICABILITY; At all times.
ACTION:
- a. With a land use census identifying a location (s) that yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 5.4.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.
- b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (.via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 5.7.1, add the new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated 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.
Pursuant to Technical Specification 6.9.1.8 identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report p
revision of Attachments 6.13, 6.14, 6.16, 6.17, and 6.18 f reflecting the new locations (s).
105
i UNT-005-014 Administrative Procedure kevision 1 I Offsite Dose Calculation Hanual i
4 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) !'
s r
SURVEILLANCE REQUIREMENTS The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental ,
Operating Report pursuant to Technical Specification 6.9.1.7.
- Broad leaf vegetation sampling of dif ferent kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted 1 D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.8-1 Part 4.c. shall be followed, including analysis of contrcl samples.
r t
t 106
- .. . - . - , ~.- -, - , - . - . , - _ . . . - . . . - .
UNT-005-014 Administrative Procedure of fsite I)ose Calculation Manual Revision 1 5.8 kAD10 LOGICAL. ENVIRONMENTAL MONITORING (Cont'd) 5.8.4 Discription of the Radioloh cali Environmental Monitoring Program The Radiological Environmental Monitoring Program (REMP) is expounded on in Attachment 6.13, and the Sample Location Tabic, Attachment 6.14. Attachment 6.15 explains the sector and zone designations for the sample locations. Attachments 6.16, 6.17 and 6.18 show the sample locations within the 2,10, and 50 mile radius of Waterford 3.
l 1)eviations are permitted f rom the required sampling schedule j if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it nay not be possible or L
practical continue to obtain samples of the media of choice i
at the most desired location or time, in these instances, suitable alternative (nedia and locations may be chosen for the particular pathway in question and appropriate I substitut. ions made within 30 dayr. in the Radiological Environmental Monitoring Programs.
l l
l l
- s 107 l
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 1 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.5 Description of the interlaboratory Comparison program As described in Section 5.8.2 the quality assurance in radiological environmental sampling will be maintained through participation in the Envirotunental Protection Agency's Radiological Laboratory Quality Assurance Program.
The summary of results will be presented in tabular form and will include the type of analysis, the preparation (collection) date, the date the results are returned, the mean of the analyses (usually triplicate), the standard deviation, the date the values are released for information, the known value, the three standard deviation limit, and a two standard deviation /three standard deviation warning / action flag. If the sample analysis indicater results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report is submitted.
k' g 108
_ ~ - . . - - -
UNT-005-014 Adrainistrative Procedure Offsite Dose Calculation Manual Revision 1 5.8 RADIOLOGICAL DNIRONMENTAL MONITORING (Cont'd)
$.8.6 Dispersion Parameteri for Critical Locations As per Requirements $.8.3, the dispersion parameters f or the site boundary and where necessary, as identified by the Annual Land llse Census, are listed in Attachment 6.2. This table vill be subject to changes based on the Annual Land Use Census and historical data.
. )'
i a
a 109 1 m u im n g indsi l isi
l llNT-005-014 Administrative Procedure Revision 1 j
offsite Dose Calculation Manual 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORJNG (Cont'd)
$.8.7 Radiolojical Environmental Monitoring Banes
- n. INTERI.ABORATORY COMPARISON PROGRAM (Section 5.8.2)
The requirement for participation in an approved Inter-laboratory Compailson Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purpot.es of Section IV.B.2 of Appendix 1 to 10 CFR Part 50.
- b. LAND USE CENSUS (Section 5.8.3)
This spccification is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by ;
the results of this ceasus. The beat information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix T to 10 CFR Part 50. Restricting the census to gardens of greater than 50 m2 prevides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consa:nption by a child. To determine this minimum garden size , the following ast.umptions were made: (1) 20% of the garden was used for growing broad leat vegetation (i.e.,
similar to lettuce and cabbage), and (2) egetation yield of 2 kg/m2 .
110
_ . ~ . . _ . - _ . _ . . . . _ _ _ _ _ __ _ _ _ . . _ . _
Administrative procedure UNT-005 014 offsite Dose calculation Manual Revision 1 5.9 TECIINICAL SPECIFICATION CROSS-REFERENCES Changes to the Technical Specifications (TS) recom:nended by Generic 1.etter 89-01 (Reference 2.8) resulted in programmatic controls for radiological ef fluents, radiological enviromnental monitoring, and effluent radiation monitoring instrumentation being relocated t.o the Offsite Dose Calculation Manual. All referencer of the former version of the TS that are contained in current plant operating procedures shall be cross-referenced to specifications contained in (
the ODCM using Attachment 6.20. Relocated requirements set forth in the ODCM should be incorporated into current plant operating proce-dures as they undergo routine review and revision.
6.0 ATTAC (MENTS Refer to Table of Contents 111
SITE BOUNDARY TOR RADIDACTIVE GASEOUS AND LIQUID EFFLUENTS ,
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s UNT-005-014 Revision 1 Attachment 6,1 (1 of 1) 112
HISTORICAL AVERAGE DISPERSION ANI) DEPOSITION PAPMETERS FOR AREAS AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY NetAL AmWE ADEr:Mt3t1C DIsme.115 40 tt3XCmW 19JWC136 AM:3D G8 H181tR10.1. PE"11L5E1DGICG EAIn A@ C1859ff LA@ LEE CDEEE InFDA2 I/O IVQ ICIIP1tR '.'YIT DIRECf7CH A22*T3t N3 (ITAY (ger ,2)
FE M 6 TIE ItXA71CN FHM KHt:
(R 1DC3CICH (silms) (omtars) tKU A 0.80 1287 1.02-05 3 tt-08 Cnt It1 MARY N(s) tu 1.61-0S 3 41-00 tee (4) 5 0.60 0.60 9% 1.N 05 2.tE-08 HE(a) C D 0.60 DM 1.6E45 2 5t-08 DE(6) 6.91-06 1.31-08 6 E 0.90 1237 0.60 966 1.11 05 2 3E-08 F
ESE O 0.60 964 1.11 05 3.it-08 EE 6,3E-06 2.4E-08 SSE H 0.60 1297 2575 0.9E-07 2.7E-09
- 8 .7 1 60 7.9E-10 E 3.10 4989 3.0E-07 Ssk L 3.40 6472 3.3E-07 9.it 10 8W 4.9t-09 lEW M 1.60 3414 1.71-06 1.00 1509 2.31-06 7.11-09 W W 7.51-06 2.7E-09 tem F 0.80 1237 0.40 1237 1.0t-05 3.2E-08 W Q 9.41-06 2.41 00 19W R 0.90 1448 0,90 lost 7.St-ce 1.t!*08 F131tDE2 W' A 3.0E-06 5.81-09 DNE 9 1.30 2092 0.90 1448 6.3E-06 1.2E-08 NE C D 0,90 1448 6.ht-06 1.1E-00 EME 7.4t-07 1.0t 09 E E 3.20 3M1 3.10 4989 3.7E-07 4.8E 10 ENE F 4.00 6437 2.3E-07 3.6E-10 SE G 1 00 1609 2.3E-06 1.3E-09 W M 0.90 1448 S.6E-06 2.0E-OR j ' teet P 7,7E-06 3.3E-08 lef Q 0.90 1648 R 3.00 4426 7.71 07 1.3E 09 8088 0.90 1444 7.7E-06 2.3E-08 KI15 CDI IW(b) 0 4.1E-10 4.90 7646 2.6E-07
- Q 4
1.00 1609 S.3E46 8.2E-09 MI15 CEAT DE(b) D 3.9E-10 E 3.30 S311 3.62-07
'E(b) -
A 2.00 1609 6.1Ea06 1.4E-05 WrE!AKE CAMEEN N 5.8E-09 3 1.30 2091 3.0E-06 let 6.3E-06 1.2E-On IE C 0.90 1444 0.90 1444 6.82-06 1.1E-0s N D 7.4E-07 1.0E-09 E E 2.20 3S41 2.20 3641 7.OE-07 1.1E-09 ENE F ,
O 2.30 3701 6.2E-07 1.3E-09 '
SE 4.9E-Op l
team M 1.50 2414 1.7E-06 W 1.10 1770 19E-46 S.7E-09 W 2. 5 -08 0.90 1eet 6.6E-C6 tem /
7.7E-06 2.3E-Op lef Q 0.90 1448 R 3.00 6628 7.7E-06 1 3E-09 ,
leW S180 3.7E-07 4.2E-10 E I 3.30 3.6E-10 W27 CDf 3.50 5633 3.CE-07 ISE F 2.8E-10 G 4.60 7242 1.9E-07 RE 1931 2.7E-of 8.6E-09 trei M 1.20 2.0E 08 0.90 1448 S.6E-06 teed P 2.2E os 0.90 1648, 7.7E-06 IW Q 1.3E-06 2.4E 09 R 2.30 3701 peet Se location cunct to
- a. The sita inssiarv in this secter is icostm$ pier watar.
cxnguas courix6mly ter the life of tra plant.
- b. The animals et tids locatian do set prutom allk tw hamn criumptkn.
l l
UNT-005-014 Revision 1 Attaciunent 6,2 (1 of 1) 113
SITE RELATED LIQUID ING%TFON DOSE COMMITMENT FACTORS (Af ) TOR MDIVIDUAL NUCLIDES Att eeE Ps ADUL1 OllChAtit P0luis CitCULAtlNG nditt (ints altelsAlppi tlwr)
NUCLIDE ORGAN DC$i CONW8Alck FACTM8 peut LIWR f.00Cf tr2010 EIDeff LwG Cl LLI
- 3 0.0cJ+00 2.HE 01 2. W 01 2. HE 01 2. W 01 2.6M 01 2. w 01 C.14 3.1M+06 6.36t+03 6.NE +03 6.36t43 6.2M+03 6.2M+03 6.26t+03 mA 34 4.00t*02 4.00t*02 4.0st+08 4.00t+G2 4.0N42 4.Mt42 4.00t+02 P 32 4.6M+0F 2.07t+06 1.7MO6 0.00t*00 0.00t+00 0.00t+00 5.19t+06 relt 0.00t+00 0.00E+00 1.27te00 7.621 01 2.81E 01 1.69t+00 3.21t+02 e 54 0.3t +00 4.30t+03 8.35f+02 0.00E+ee 1.30t+03 0.00E+00 1.34t+04 .
4m 56 0.DeE+00 1.10t+02 1.9f4+01 0.00t+00 1.43t42 0.00:40 3.52t+03
- 7E 55 6.595 4 2 4.545*02 1.614+02 0.00t*00 0.00t+00 2.54t+02 2.61t+02 78 59 1.06845 ' 2.49443 9.* Jet +02 0.00t+00 0.00t+00 - 6.8M42 8.1H+03 CO 50 - 0.84+00 4.95E+01 2.01642 0.00E 00 0.00t+00 0.00t+00 '1.015 43 Co 60 0.988+00 2.57t+02 5.67t+02 0.000+00 0.00t+eo 0.03t+00 4.s3t43 e1 63 1.ta+46 2.14e45 1.05E+43 0.00t+00 0.00s+00 0. cot +00 4.51t42 al 45 - 1.27t42 1.e4841 7.514ee0 0.00t 4 0 0.00t+40 0.00t+00 4.17t+02 CU 64 0. set +00 1. set *01 4.70t+40 0.00t+00 2.5m+41 - 0. set +eo 8.53t+02 ,
M 45 7.A43+46 7.37t+06 3.330+06 0.seE+00 4.95t*06 0.00t+e0 4.044+M
..........~.....................................................................
D ee 4.eSt*et 9.43E41 - 6.5M+eo - 0.gu+40 4.13t*01. 8.ses+00 - 1.42E41
, M4 0.08t+00-0.selde 4.NE41 0. set +ec--0.seE+40 0.00E+00 5.8H+41 IW M 70.08E+00 0. set *te 5.368+81 8.08t+00 0.00E40 0.00E+00 4.11t
- M .
OR 4 0.85*e0 0.telM10
- 2.15E+00 ' 0.80$+00 0.00E+00 0.SeE+00 0.00E40 80 4 0.get+00 -1.01e+45 4.71E*e6 0.08E40 0.t0E+eo :0.00E40 1.NE*06 .
Re e 0.0N+00 2.9df 542 :1.54E+02 - 0.00E+00 O.get*e0 0.00t.00 4.est M se e ' 2 O.00t*40 1.95 42 1.35e+02 0.00E40 - 0.00t+4D 0.00E+00e 1.12E*11-
- OR 4 ~ 2.2R*e6 0.0m+e0 6.300+02 0.00t+00 0.00E*e0 - 0.CiW+00 -. 3.5W*e3 -
- et 90 ' . 5.47R+e5 0.ete*40 1.34E*e5 e.seE+40 0.0se+eo 0.00t+e0_ _1.58t+06 es 91 4.085+02 -' O.00t+40 1.000+41' 0.00t+40 0.00E+00 0.get+00 1.954*e5 80 02 1.550+02 0.085*e0 6.71G*e9 0.0N+00 0.00E*4D 0.geudo 3.0M*45 -
f.90- 5.79E 01 - 9.e5+00 1.5N 82 0.08E40. 0.eep.00 0.get+00 6.145*43-T.91st -5.475 55 0.00E+00 2.13E.06 0.em +00 0.00t+e0 0.00t+00 1.616 4 f.91 S.4M*00 0.80t+00 l 2.27t=01 0. gee +00 0.00t+00 0.00E+00 4.67t+03 f.02 ' . 5.est 82 0.00E40 1.4M 85 0.pM 0.00E+00 0.0st+40 8.91t+421 Caswersion facters are in units of aren/yf per dt/mL ,
e UNT-005-014 -Revision 1 Attachment 6.3 (1 of 6)
.114 v - _.
I GITE RF.I.ATED LIQUID INGESTION DOSE COMMITMENT 1 FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES 40s eMNPI As@,1 electionet PolWie CleoAAf tes wtge O we siteeleelept stier) autLIN eeGam 80em COWWilleu f 4CTf21 i
f.elst 18feele Efearf time 6 Cl LLI scia LIVEe d
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' TC 1M e.IM4 1.3M.st 1.388 01 e.ste*eb 2.388 01 6.Me 4 3.est.14 80 15 4.Sepee e. set Ge -1.ene ce e.888 4 4 1.Fa*01 e.sep ee 5.Be.et ap*15 3.798 01 e.emose 1.ast M e.see es 4.064.ee e.tenece t.acher 89 186 4. des *01 e.amate 0.444 00 4. set *eo 1.pspet e.segees 4.33p83 As*11em
- e.378.M 7.4e8 01 4.948 01 0.000.ee 1.tes ge p.ges*ee 3.13 03 Tetasil 2.97pel 9.35*W 3.44 tact F.7E*et 1.860 4 G. tee *80 1.00I.06 78 13'11 4.40pel 2.35*e5 7.eepet 1.eesees 3.aspe6 e.espen 3.17pe6 78 137 -
1.gepte 3.fereet 3.ne*01 7.01>01 4.3es*et e.gepee. 3.3epes fe*1Mel 1.teH46 4.11pe 1.Me*e 3.fe>W 4.depet e,sepes f.sepe6 78 19 3.81pM 1.1N*01 7.3es*ee 2.310*01 1.aes*ee e.aspes 2.7FN#1 70 13 5 1.4e>G e.tes*H 4.7954 1.M4 - e.21pel 8.sep40 e eee*e6 78 131 1.Gebet 7. W *ep 5.eassee 1.Sep et e.! m et e.en*ee 3.47 pee
.................. ........ .. ... ....1. m ................ .... .......
Fee d 1.Sehe6 e.sapee 7.380 06 78 13t 3 31p05 1.589*E5 1.4fe e I 13e 3.M041 8.81>01 3.iep et 4.ese d 1. asp et e.sekte 6.Tfeet l.131 1.Ste*W 3.108 4 1.314*Et 7. espe 6 3.Mpe e.sapee 5.feret t.13t - 7.37 pee .1.9 feet 6.espes 4. seed 3.14 pet l E.espee 3.7 epee t.135
.5.19e4e1 8.eepet I.7Ba#1 1.5meen 1.lebee e.espes e.086*01 3.m p es 1.W h et 3.Mpes 1.etpet 1.4epet e.sapee 3.118 4 f.134
......... ......... ~ . ~ ~........ ,
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m.136 -
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3.e5.es $.30pm 3 454 e.espee .1.77p8R 5. espe 6 1.Mee6 m.137 3.8444 3.7epet 2.3ee 4 m.13e f.edesee 5.33*W 2.50 pee e.espes- ,
en.13e 9.488 01 4.51 4 2.88 5 e.sep ee 4.43e
- 3.e 5 4 1 71p ee
............. ............ ..... . ~ . - ~ ~ ~ ~ ~ ...a ~ ... ~ . = ~
e ,w m en e.e. r. in mise et ereeryr per uct ml l'l-l.
1 Attachment 6.3 (2 of 6)
UNT-005-014--Revision 1 115
. ..~ - - , ~ ~ . . - - - . - . . - . - . . -+
- . - - - - - - . . - . . _ . - . _ ~ , . - ,- ~ ~--.
SITE RELATEL LIQUID INGESTION DOSE COMMITMENT FACTORS (A,) FOR INDIVIDUAL NUCLIDES 1
Af.t GRouh M1 Olstm4aet P0! tis Cl#CULAfibG W41th 11nto MI681641ppl Rived tP#.L10t DAGAd 0058 Couvitslam fAC10st tout Livte 1.50DY fuffol0 E10 EFT LuuG 01 LLI BA 140 2.02t*02 2.541 01 1.32t+01 0.00t+00 8.6M 02 1.45t=01 4.1M+02 6A 141 4.69t 01 3.541-M 1.5M 02 0.00t+00 3.29t M 2.018 M 2.21t 10 SA 142 2.121 01 2.18t N 1.2M 02 0.00t+00 1.844 M 1.2M M 2.99E*19 LA 140 1.511 01 7.59t 02 2.* i 02 0.00t+00 0.00t+00 0.0M+00 5.571*03 LA 142 7.718 03 3.51t 03 8.7M M 0.00t+00 0.00t+00 0.00t+00 2.56t>01 CE*141 2.59t 02 1.7M 02 1.99t 03 0.0W .00 8.1M 03 0.00t+00 6.71t+01 CE*i43 4.571 03 3.30t+00 3.741 M 0.00E+00 1.49t 03 0.00t+00 1.2M+02
- -Ct*144 1.35t+00 5.FA 01 7.2M 02 0.00t+00 3.3M 01 0.00t*00-4.57t+02 M
- 143 5.54 tid 1 2.22t 01 2.7H 02 0.00t+00
- 2st . 01. 0.00t+00 2.4M+03 M 144 1.81t 03 7.5M M 9.218 M 0.00t+00 4.2M M 0.00t+00 2.41t*10 ID 147 3.7M 01 4.3et 01 2.62t 02 0.00t+00 2.5M 01 0.00t>00 2.10t+03 W 187 2.9e8602-2.47t+02 8.6H +01' 0.00t+00 0.00t+00 0.00t+00 8.10E+04 NP*239 2.W8t 02. 2.58 05 1.57F 03 0.00t+00 8. set 03 0.00t+00 5.844+02 i.
' Cenwesten +eeface are in mitt of ures/yr per hl/et 6*
x Attachment 6,3 (3 of 6)
UNT-005-014. Revision 1 116
1 SITE RELATED LIQUID INGESTION DOSE COMMITMENT l FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES ,
AGE GROUP: ADUL1 OllChAAGE PolW1 ALL CtNEEl (into 40 Arpent Cane O MUCLIM CAGAN D0lt CmVEEllom f4CTOR$ ?
DONE LIVEE T.8 m fufR010 EtDeET LuuG Cl L'Lt N3 0.I'0E+00 8.Mt +00 8.ME+00 8.ME+00 8.90+00 8.ME+00 8.90E+00 C 14 3.15E+44 6.30E*03 6.30E+03 6.30E+03 6.30E +05 6.30E+03 6.30E *03 mA 24 5.4aE+02 5,4aE+02 5.4aE42 5.48E+02 5.44E42 5.48E +02 5.44E+02 P 32 4.62E+07 2.87t+06-1.7P .4 0.00E+00 0,00E +00 0.00E+00 5.2SE+04
.ca 51 0.00E +00 0.00E+00 1.4i *ao 8.M4 01 3.2M 01 1.9eE+00 3.7M+02 880 54 0.00E +00 4.7M45 9.0Ed+02 0.00E+00 1.42E + 03 0.00E+30 1.4M44 Ist 56 0.00E+00 1.20E42 2.12E *01 0.00E+00 1.52E+02 0.00E+00 3.82E +03
. FE+SS 8.87E42. 6.1k+02 1.43E+02 0.00E+00 0.00E+eo 3.42E42 3.52E+02 PE 59 1.40E43 3.29E45 1.3M+c3 0.00E+00 0.00E+00 9.19E+02- 1.10E+04 00 0.00E+00 1.51E 42 3.39t+02 0.00E+e0 0.00E+00 0.00E+00 3.0eE45 to 40 0.00E+00 4.34E*02 9.SW+02 0.0gE+00 0.00E+00 0.00E+00 8.1M +03 ul*65 4.1M +04 2.91E+05 1.41E*45 0.00E+00 0 OnE+40 0.00E+00 6.07t+02 NI45 1.7eE42 ; 2.21E*01 1.01E+01 0.00E+eo 0.00E+ee 0.0eE*e0 5.61E+02 EU44 0.00E+e0 1.40E+01 7.93E*00 0.00E+00 4.36541 0.00E40 1.44E+03 au 45 2.300+04 7.SeE+44'3.39E+44 0.0We00 ' S.02E+44. 0.00E+00 4.73E+04 au 49 S.OW+01 9.eW41 6.675+00 8.00000 6.34841 0.00E+00 1.44E41 W4l .0.8W+00 0.0N*e0 4.3541 n,ggago 0.te+ep 0.0W40 6.38E41 W 84 -- 0.0N+00 0.9E*00 S.Mt41. 0.85+00 0,85*e0 0.0N*e0 4.49E 04
-~
BR 4 0.0N+ee 0.0N+00 2.3N+00 0.885+es 0.00E+e0 0.e5+00 0. gee *e0 88 4 0.eW e 1.83E*W 4.Mt+44:0.45+e0 0.0m+e0 0.000,00 2.89E+44 AS 4 0.00E*e0 2.9eE*et 1.Ses* e .0.e85+40 0.00E+00 0.00E*e0 4.075 09-- "
- AS ep 8. FEE *eo .1.950*02 = 1.375+02 ~ P.00E+ee 0.00E+00 0.00E+00 1.13E 11.. '
OR et - 4.75+04 ' 8.seE40 1.379+e5 0.seE+es 0.seE+00'O.eW+00 7.edE45 SR 90 1.1M+e6 0.00E+00 2.88E+05 0.00E+00T 0.00E*e0 .0. gee +00 3.40E+04
= SR 91 8.NE*02 0.0N*e0 3.59E+01: 0.0m*e0 0.0N*00: 0.00E+00. 4.19E*e5 3R 92 ' 3.33E+02 0.88E*e0 - 1.44841 0.8EE+ee 0.80p+00 . 0. tee +ee . 4.488+05
'T 90 1.35 40 0.05+00 3.8054 0.08t*40 0.00B+40 0.tet*e0' 1.4ed*e4
-- T 91st - 1.38E 02 0.0m+00 5.04E 04 0.e5+e0 0.00E 00 0,seE+eo 3.saE.02 L T 91 - 2.85+ei 0.00E*eo - 5.398 01 ~ 0.0m*e0 0.00E+00 0.00E+eo- 1.11E+44.
> '.Y 92 '.1.21E 01 - 0.00E+40 s 3.354 - 0. tee +00 0.seE+00 0.eW+00 2.12E+45 Camersion facters oce in wilts of areWyr pse ucl/el UNT-005-014 Revision 1 Attachment 6.3-(4 of'6)-
h I17 l
- - . . - .- - - _ . . - - . ~ . - - - - . . . ~ - . - . - - - -
i i
SITE REI.ATED LIQUID INGESTION DOSE C0&f!TMENT FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES tee estW t 40 ULT DlK neast toists 4LL etates tinto 60 Arpent Caret)
WGAh east CcWYtell0m thC10R$
auC6tet LuuG Cl.LLI LitTe f.00ef TNY8010 Klesti Oest d v
i
- 0. tee.ap 1.est.et 0.ges.e6 0. cat.ee e net.c0 1.3 ape 6 T.95 3.est.01
- 0. tot 00 1.3e9+e0 0.0st+e0 3.53E.43 b. .,
38 45 3.fM+40 4.eE *e1 6.018 01 1.53t.01 3, set.et 1.418 02 0. esp 40 6.675.b2 0.00t+00 9.5M43 .y
- 38 47
......... ....g.g yog3y7;go ogno.ooo oo y,.f;p;o o.o o o o7.gg pf, ,
4.48t*Qt h480=e8 1.Me+et 0.eet.ee 344epet 0.tet+ee h44e.46 m 95 ND-ee .
t.eepte 4.6aR+42 8.7 West 0.005 4 1.eM*C 0.00E+00 1.e79.e3 TC.eus 3.Me.et 4.3N.at 1.0e6+40...........s...................8. tee +es 1.3ef+es 6.973 02 4.90541
............................................... 0. Late +0B 7.458 01 3.DE.et 1.314 13 TC*191 3.eu.et 4.3M.5 4.3541 Enetel 1.95 4) 0.04 00 't.M peo 0.88t440 7.57541 Soestate' 3.314 4 m>15 1.80440' O.eG*e8 6.55 01 0.085+40 3.1Neet 6.tet*e8 1.01t*5 0p.146 3l.Weest 9.sep ee 3.733 41 S.tetess 5.eeteet e.est 40 1.919 46 M.118 1.41041'1.38t*01 7.740*e0 B.eetees 3.544 01 0.085 00 5.33I.e5 .
it.13Bn 3.798 4 1.01e e5 3.74eest 8 Jet *e 1.13pe6 t.gepet 1.110.e6 i
p te. ith 7.055,45 3.5k+GB 4.Me d 1.eep el 3. ele +44 8.eu 40 3.Ms+e6
' Saepel 4.4dsee 3.see+es 9.mpel 1.14p e 4.11e*e1 3.6e41 TE.UF 8.tekee 6.eR4 .
t.354 4.47pe 1.est*El : 4.1t>EB 5.ethe6 11 13W 3.370sel 1.35 pet f.esteet - 3.51841 1.F1*4 8.sepee 3.4M41 ft.1W fe 131m 1.ege4 4.01 pet 7Je64 1.3spe . 3.g34 t.espee 3.1444 - .
TE*01
' k.0B041 8.97p et 4.47p et t.4e041 4.1W41 ; S.Espet 3.9epe5
........... 1.45 4 9.sapet B.EEpe6 15 13t 3.454 1.?W*5 1.9spe .1.WPS 4.19 pet 8.elp et 3.30 pet 1 138 9.01 pet 3.ethe 1.eBett.3JBe4 1 J Bee 8.elp es tostr et
- 4. esp =W 7.egeset 4.es> W 3.3RP G 5 131 . . . . . . . . . . . . . . . . . . . . . . . . . . .1.IN41 .................
3.43=e1 4.47 pet ' 3.ase41 : 3.aspe 1.Spe 4.sepet .
3 133 4.33*e6 5.13Het 8.seret 3. tee *eE -
1 135 1.eeteet - 3.94eest 8.fr>#1 3.985 4 1.3RN#1. 5.m>W 5Aepel. te. esp 40 L
' l.136 1.30041 3A341 ..................
................................ ........................0.110 4 3.35 4 8.espet 1.5dpet 2 135 5.MI41.1JBB*W 5.10041
- 3. Bee 7.3104 5.eING 6.espot 3.35pel 7.79pe6 1Jere6 .
es.134 es.136 1.1?>e6 1.358*G5 9.01p et s.ameet 4.Wre6 - 9. sere 1.43*e6
............................~.~.~.~~ao*...~..~.
'3.enkel SJ1pel 3Aspe8 7.espee 1.es>G 5.94*e6 3.3R4 1.WE*e6 88 137 -
m.135 3. espe SJte*W 3.epet e.espee 3.eSpa 3. Whets.es>GB 5.98E 4 3.Me 4 ga.13P 9.espes 4.4w.e 3.440 01 ~~~~..~~~*~~~"""
............~...~..........~.a.s samusesten feeters em in esdes of sruryr per d!Mi l
Attachaent 6.3 (5 of 6)
UNT-005-014' Revision 1 118-
SITE REl.ATED LIQUID INGESTION DOSE COMMITMENT FACTORS (Ag ) FOR INDIVIDUAL NUCl.lDES 451 Ca3JP ADULT DlltaAAGt Polu1 ALL 01stal tir4e 40 arpmt Genet)
WuCLIDE Car.Au Cost etwf;ttlom I AC1(St Sant Livtt 1.621 tuft 010 FIDbit LukG Gt LLI BA 140 1. tat +03 2.37t +00 1.23t*02 0.00t+00 6.0"t 01 1.35t*00 3.85t+03 M 141 4.3Ft+00 3.30t.03 1.4k 01 0.00t+00 3.0M 03 1'.471 03 2.064 09 4A 142 1.98t*00 2.038 03 1.241 01 0.00t+00 1.771 03 1.154 03 2.752 18 W 140 3.58E 01 1.80t 01 4.7M 02 0.00t+00 0.00t+00 0.00t+00 1.12t+04 LA 142 1.13t 02 0.334 03 2.071 03 0.00t+00 0.00t+00 0.00t*00 6.08t +01
l 141 8.018 01 S.421 01 6.114 02 0.00t+00 2.521 01 0.00t+00 2.07t +03 03 143 1.411 01 1.06t+02 1.1M 02 0.00t+00 4.@ 02 0.00t+00 3.90t+03 01 144 4.18t+01 1.3t*01 2.24t+00 0.00t+00 1.044+01 0.00t+00 1.41f+04 Pe 143 1.32t+00 S.281 01 6.52f 02 0.00t+00 3.058 01 0.00t +00 5.77t+03 PR 144 4.311 03 1.79t 03 2.19t 04 0.00t+00 1.011 03 0.00t+00 6.195 10 ar,147 9.00E 01 1.04t+00 6.221 02 0.00t+00 6.00E 01 0.00t+00 4.99t+03 W 187 3.04t+02 2.S$t+02 8.90t +01 0.00t+00 0.00t+00 0.00t+00 8.34t+04 me 239 1.28t:01 1.254 02 6.91t 03 0.00E+00 3.918 02 0.00t+00 2.57t+03 C==reten teetm ere in mite .# er svyr per u:t/ t UNT-005-014 Revision 1 Attactunent. 6.3 (6 of 6) 119
D_OSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE CASES Nuclide p-air *(Nj ) p-Skin **(Lf ) y-Afr* (M3 ) y-Body **(Kg )
Kr-83m 2.88E-04 --- 1.93E-05 7.56E-08 Kr-85m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 +
Kr-88 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 Kr-90 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Xe-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 ,
Xe-133- 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xc-135m -7.39E 7.11E-04 3.36E-03 3.12E-03
.Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 Xe-137 -1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xc-138 4.75E-03 4.13E-03 9.21E-03 8.83E-03 L Ar-41 3.28E 2.69E-03 9.30E-03 8.84E-03
- ' 3
-mrad-m
-pCi-yr-
- 3
-mrem-m -
pCi-yr l Extracted from Table _B-1 of Regulatory' Guide; 1.109, Revision 1,1977 ~
UNT-005-0141 -Revision-1 Attachment 6.4 (1 of 1)
l
(
l l IhTALATION PATIIWAY DOSES DUE TO RADIONUCLIDES OTTIER TilAN NOBLE GASES, R.
1 ALE Ca:UP: ADutt ( 1 Of 3 )
OtC&m DOSE CouvitS10h FACTOR $
NUCLlH 1.600Y tuYt010 11Datt tuu GI tu 5(*E Litti w.3 0.00E+00 1.2 6 03 1.2M +03 1.2d+03 1.2W+03 1.26t+03 1.2 m 03 C 14 1.82E*04 3.415+03 3.41t+03 1.41E+03 3.41E*03 3.41E*03 3.41E+03 1.02E +04 1.02E+ M 1.02t+04 mA.24 1.02t+06 1.021 4 1.02t+04 1.02t +M P.32 1.32t+M 7.71t+04 5.01t+04 0.00E*00 0.00t+00 0.00E+00 3.32E+03 8.Mt+M Ca 51 0.0M+00 0.00E +00 1.00E +02 5.95t +01 2.2aE+01 7.1.44 +M 74t +M see.54 0.00E+00 3.9d+04 6.33t+03 0.00E+00 9.84 +03 1.40E+06 Mm.56 0.00E +00 1.24t*00 1.53E-01 0.00t+00 1.30E+00 9.44E+03 2.02E+M ft.55 2.44E+M 1.70t+M 3.ME+03 0.00E+00 0.00E+00 7.21t+M 6.03E 43 Ft.39 1.1aE+M 2.fGE+M t .0M +04 0.00E*4) 0.00E+00 1.02t+06 1.8M*D5 CD 58 0.00E+00, 1.58E+03 2.075+03 0.00E +00 0.00E+00 9.2SE+05 1.04 +05 Co.60 0.00E +00 1.15t+M 1.48E+M 0.00E+00 0.00E40 3.97t+06 2.65845 51 43 4.32E+05 3.14E+04 1,45E+04 0.00E+00 0.00E+00 1.7mi+05 1.34t *M N1 65 1.54 +00 2.10E 01 - 9.12E.02 0.00E+00 0,00E+00 5.60E+03 1.23t44 CU-64 0.00E+00 1.46t+00 6.15E .0,1 0.00E+00 4.62E+00 6 fut+03 4.90E+04 2m 65 3.24E+04 1.03E+05 4.6eE+04 0.00E40 6.90E+M t.64t+05 5.34E+04 2m.69 3.4&E 02 6.51t.02 4.52E.03 0.00E+00 4.22E.M 9.20E*02 1.63E*01 ' I 54 83 0.00E+00 0.00E+00 2.41t+02 - 0.00E+0c 0.00EW 0.00E*00 2.42E+02 88-84 0.00E+00 0.00E+00 3.1N+02 0.00E+00 0.00E+00 0.00E+00 1.64 03 8#.85 0.00E 40 0.00E+00 1.20E+01 0.00E*00 0.00E*00 0.00E +00 0.00E 40 Re 86 0.00E+00 1.3SE*05 5.90E44 0.00E+00 0.00E+00 0.00E*00 1.644+0.
ke M 0.00E+00 3.87E42 1.93E+02 0.00E+00 0.00E+00 0.00E*00 3.341 09 R$.99 0.00e+00 2.56E42 1.70E42 0.00E+00 0.00E+00 0.00E+00 9.2eE.12
. sa.M 3.04445 0.00E+00 8.72t+03 0.00E+00 0.00E+00 1.40E46 3.50E *05 st.90 9.92E+07 0.00E+00 6.10E+06 0.00E+0C 0.00E+00 9.60E+06 T.22E+05 St.91 6.19E+01 0.00E+00 2.50E+00 0.00E+C0 0.00E+00 3.65E+04 1.9tt+05 58 92 6.74+00 0.00E*00 2.918 01 0.00E+00 0.00E+00 1.654+04 4,30E+M f.90 2.tM43 0.00E+00 5.61t+01 0.00E+00 0.00E+00 1.70t+05 5.06e+05 f.91n 2.613 01 0.00E+00 1.021 h2 0.00E+00 0.0ct+00 1.92E43 1.33E+00 Y.91 4.62E45 0.00E+00 1.24E+M 0.00E+00 0.00E+00 1.70E +06 3.85f+05 T-92 1.55e+01 0,00E40 3.02E.01 0.00E 40 0.00E+00- 1.57E*04 7.35E+04 Corwursisn facttre are in unite of ares /yr per uct/ceAlc inster.
UNT-005-014 Revision 1 Attachment 6.5 (1 of 12) l l
121
- --_ - _ _ _ _ _ - ~~- -------~ __
j
- INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTIIER THAN NOBLE GASES, R. )
i i l
l 40t catuh ADULT t 2 08 3 )
i d
WC4 f DE ORGAu 0051 Convittl0m f4Ctael a
1.napf Twit 010 flD#ti LUNG Gl'LLI samt Livlt T 93 9.44t+01 0.00t+00 2 61t+00 0.00E+00 0.00t.00 4.tSt+04 4.22t+05 In 95 1.0M+05 3.44t+04 2.33h04 0.00t+00 5.42t+04 1.7M46 1.50t +05
- 25 97 - 9.04t+01 1.16t+01 9.04t+00 0.00t+00 2.9M +01 7.8M +04 5.23445 me 95 1.41t+04 7.82t+03 4.21t+03 0.00t+00 7.74t*c32. 5.05t+05 m +05 1.04t +05
@M 0.0tM+00 1.21t+02 2.30E+01 0,00E+00 2.911 02 9.12t +M tc 994 1.03t 03 2.911 03 3.70t 02 0.00t+0c 4.425 02 F.64E+02 6.1M + 03 ft 101 4.181 05 6.021 05 5.90t M 0.00t+00 1.004 03 3.99t+02 1.t9t.11 40 103 1.53t+03 0.00t*00 6.54t+02 0.00t+00 5.85t+03 5.05t45 1.10t+D5 au 105 7.90t*01 0.00t+00 3.111-01 0.00t+00 1.02E+00 1.10C+04 4.5LE +M au-1M 4.91t +M 0.00t+00 8.72t*C3 0.00t+00 1.34t+05 9.3M+06 9.129 05
' 4G 11 tot i.00t+04 1 00t+06 5.Mt+03 0.00E+00 1.97t44 4.63p06 3.02t45
- 7t*125m 3.W43 1.54t43 4.67t42 1.05t+03 1.24444 3.14t+05 7.0M+04 TE 127m 1.2M46 5.7M+43 1.57t*07 3.29t43 4.54904 9.ect+05 1.50545 ff oll? ~ 1.4M+00 6.42t 01 3.108 01 1.0M+00 5.10t+00 6.51t43 5.74t44 1E 1PI8t 9.7M +03 4.6 m 03 1. Set 43 3.44t+03 '3.65t+04 1.1M +46 3.83: 4 5 It*129 4.90t 024.36841'2.90541 2.39t 02 1.2M 02 3.90s.02 1.87t 01 : 1.Mt+03 1.57t+02 5.54t+01 3.0ep02 1.4M+05 5.5M+05
-it*131u 6.99t+01 1.e4E+01 ft 131 1.11t41 5.95E 53 3.596+03 9.3eE43 4.37t 02 - 1.39t+G3
........................................................................e......, '
a TE 132 .2.40t*02~ 2.15t+02 1.42t42 1.9et+02 1.46t*03 2. set +03 5.10t+05
-1 130
.4.5M+03~1.36t+06 5.2H+03 1.14t+06 2.gep04 0.00t+00~7.68t+03 l*l31 2.53 46 3.5st+06 ' 2.M846 1.19t+07 6.13t+06 0.s0t+00 4.2e843 -
- .....................................................+..........................
1 132 1.14443 3.26243 1.14t*03 1.14E+05 5.14t*03 0.006+00 4.0M+02 -
'* .3 133 0.Ma*03 1.4et+06 4.52t+45 2.tSt+06 ' 2. Set +06 : 0.Nt40 8.a0603 1 134 4.44t+02 1.73t+0S 4.1W 42 .2.0st 44 2.75t41 0.Mt+00 1.016 00 1.11t+04 0.00t+00 5.25t+03 1 135 - 2.est+C 4.98t43 2.57t43 4.48t+05 2.ect+05 9.765 4 1.04t+04 Os 134 3.73t+05 - R.48t45 7.2et*05 0.00t+00 0s.136 3.90E 46 1.44905 1.10t+05 0.ast+00 B.54906 1.20446 1.17t 46 Os.137 4.75t+05l6.21t+05 4.2Af+s5. 0. toe4.4M +00a 2.22t+05
+01 1.066 03 7.53 4 t.4M*03 cs.138 - 3.31842 4.21d+02. 3.36842 - 0.00900 . 4.aot*02 BA.139 9.3M 41 6.6M4 2.748 02 0.00t*00 6.23 04 3.7M+03 3.96t+02
~
Camersion facters are in mits of aremryr per di/ cele setu.
UNT-005-014 Revision 1 Attachment 6.5 (2 of 12) 122
INHALATION PA'IHWAY DOSES DUE TO RADIONUCLIDES OTlfER THAN NOBLE GASES, R.
1 ACs GR.lUp: ADULT ( 3 Of 3 )
ORGAN 00:4 CCWvitlich FACTOR $
WUCLlet 1.tIET Trit 010 EIDeitY LUNG 01.tLi Ocut Liitt p.140 3.90f*D4 4.90i+01 2.57t+03 0.00t+00 1.67t+01 1.27t+06 2.18t+05 a4 141 1.00t 01 7.531-05 3.3M 03 0.00t+00 7.00E.05 1.94t+03 1.1M .07 ta.142 2.08 02 2.706-05 1.6M.03 0.00t+00 2.2'91 05 1.19t+03 1.571 16 4A.140 3.4At+02 1.74t+02 4.54t+01 0.00t+00 0.00t+00 1.3M +05 4.9t+05 LA.142 6.8M.01 3.10t.01 7.721 02 0.00t+00 0.00E+00 6.331+03 2.115 03 CE.141 1.99E+04 1.35t+06 1.534+03 0.00t+00 6.2M +03 3.62t+05 1.20t+M CI.143 1.8M+02 1.3M +02 1.53t+01 0.00E+00 6. cat +01 7.9et44 2.2M+05 Cf.144 3.'43t*06 1.43t+06 1.846 05. 0.00t+00 8.4aE+05 7.7st+06 8.1M+05 Pe.143 9.3M+03 3.7II+03 4.64t+02 0.00t+00 2.1M+03 2.81t+05 2.0tt+05 Pt.144 3.01t 02 1.25E.02 1.53E.03 0.00E+00 7.05t.03 1.02t+03 2.15t.08 mp.147 5.27t+03 6.10t+03 3.65t+02 0.00t+00 3.5M+03 2.21t+05 1.734+05 W.187 8.44t+00 7.08t+00 2.4M+00 0.00E+00 0.00t+00 2,90t+04 1.55t+05 NP.239 2.30E+02 2.2M+01 1.24E+01 0.00t+00 7.00t+01 3.7M44 1.19t+05 Corwersion 'f actors are in mits of prevyr per scl/csmic ester.
i l
l UNT-005-014 - Revision 1 Ar.tachment 6.5 (3 of 12) 123 l
INHALATION PATHWAY DOSES DUE TO RADIOllUCLIDES OTHER THAN NOBLE GASES, R.
1 Act Gaops fits ( 1 of 3 )
abCLlat (2G4m 0061 CDr48510m FAC10A1 Goat LIWit f.00DY tutt030 tIDatY LusG Cl LL1 n.3 0.00E *00 1.2M+C3 - 1.2M+03 1.27t+03 1.2M +03 1.27t+03 1.2M e03 C.14 2.40t +M 6.07t+036.07t+03 4.0M *01 4.0ft *03 4.84+03 6.0M +03 ma 24 1.30t+04 1.30E+04 1.30t aM 1.30t+06 1.30E +M 1.30f *M 1.3M *06
................... 4......... ............................................... . <
P 32 1.0eE+06 1.10E +05 7.1M *06 0.00t+00 0.00t+00 0.00E +00 9.20t+04 L Ce 51. 0.00E+00 0.00E+00 1.35E*02 7.50241 3.07t.01 2.10E+04 3.00E*03 ser 54 0.00t+00 5.11t+06 0.40E+03 0.00t+00 1.2M *06 1.90E+06 6.6Ac+06 8ed M 0.00E+00 1. M +90 2.53E 01 0.00t+00 1.79E+00 1.52M+06 5.74t +M Ft 55 3.34E +M 2. JOE +04 5.54443 0.00t+00.0.00E+00 1.24E+05 6.39E+03 f f 49 - 1.59t*01 3.70t +M 1.43E+M 0.00E+00 0.00E +00 1.53t+06 1.70e+05-Co 50 t.00t+00 2.07t43 2.70E-03 0.00t+00 0.00E+00 1.36E+06 9.52t+04~
Co-60 ' O.00E+00 1.11t+04 1,.90t +M 0.00E+00 0.lWE+00 0.72E+M 2.59t+05 NI 43 S.00E+05 4.34E+06 1.90t+06 0.00t+00 0.00t+00 3.07t+05 1.42E +06 -
.......................................................a............ ...........
51 45 2.10E+ee 2.93E.91 1.111 01 0.00E 600 ,0.00E*00 9.3M+03 3.6M +04 CU 44 - 0.00E+00 2.03E+00 A.40E 01 0.00N+00 4.41E*00 1.11E*06 4.14E+04
- 2N 48 - 3.04E+06 1.36E+05 4.36t+04 0.00t.90 0.he*06 1.34E+00-4.4eE+06 -
2w 40 - 4.0M 02 - 9.20E 02 4.44E4 0.00t+00 6.G2E 02: 1.5N +(13- 2.05E+02 Sa 03 0.00E+00 : 0.00t+00 ' 3.44E+02 0.00E+00 0.001 00 0.00C+00 0.00E+00 -
- OR4 0.0R*00 0.00E+00 ' 4.33E+02 0.00E+00 0.00E+00 0.00E+00 0.00E*00 00 4 - 0.llE+0D 0.00E+00 1.03E+41 0.00E*e6 0.00E*00 0.00E*00 0.00E+00 00 06 0.00E*00 1.90E 4 . 0.44E*06 0.00E+00 0.00E+ee 0.00E*00 ' 1.7FE*06 ~
00 00 ' O.00E*00 5.44E*1C - 2.75+02 0.08E+00. 0.00E+00 0.00E+00 2.03E*05 -
, -.00 00 - 0.00E*00 - 3.52E*02 2,332+02 '0.00E*00 0.00E+40-0.00E+00 3.301 07 On 00 ' 4.36E+05 0.00E*00 1.25E+44 1.00E*00 0.00E+40 2.63E+06-3.71E+05 ,
. .0R 90 - 1.ON+00'O.00E+40 4.40E+06 - 0.00E+40 0.00E*00 - 1.eSE47. 7.eSE+05 l On 91 ' O.00E41 0.0E+00 3.51E*W 0.00E*00 . 0.00E+00. 4.0M+06 2.39E+05 On 92 - 9.52E+00 0.00E+ee_ 4.04E 01' O.00E*00 0.00 tee 3 '2.74E+06 1.19E+05
.T 90_ _ 2.90E+45 0.00E+00 0.00E+01 0.00E*e0 0.00E+00 2.93E+05 5.59E+05 -
Y 914 ~ 3.70E 011 0.000+00 1.42E 4 0.00E+00 0.00E+00 -- 3.20t+03 - 3.03E+01 Y 91 ' : 6.41E+05 . 0.00E+00 1.7M+06 ' O.00E*00 L 0.00Ey00 2.94E+06 4.00E45 L T 921- -- 1.47E+01 - 0.00E+00 4.250 01 0.00E*e0? O.00E+00 2.40t+06-1.40E+05 M ................................................................................
Cumorsion facters ore.in mits of area /yr per utt/esic anter.
'UNT-005-014 Revision-I Attachment 6.5 (4 of 12)
- 124. .
+
.e- . - . - - e y
_ - _ _ _ _ _ __-_m .. __. . - - - - - . . . _. _ - - - _ _._--
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTlIER THAN N0llLE GASES, D.i Act G80W: fttu i 2 cf 3 ) .
munset ce?An Ocst couvtallom f acteas Tuftete ElDW T LumG El.Ltf sont ttvta 1.00c7 v.93- 1.35t+02 C. Jot +00 5.72t+00 0.00t+00 0.00t 40 4.32 4 5.7M *05 te 95 1.6at+05 4.5at+M 3.15t+M 0.00: 4 0 6.76t +06 2.m+M 1.6M+M te.97 1.38t+c2 2.728 41 1.2M*01 0.00t+0C 4.12641 1.30t+05 . 6.30t+M
................................................................................ 9. eat +M me 9S 1.66t +M % .03t +M 5.66t+C3 0.00E+00 1.00t*04 7.51t+05 -
Mo 94 0.00E+00 1.6*E+02 3.22441 0.00t+00 6.11442 1.54t+05 7.69t*05 / -
TC +99t . 1.34t 03. 3.tM OLI 4.99t 02 0.00E+00 5.744 02 1.15t+03 6.13f 43
............................................+...................................
TC 101 5.922 05 4.401 V5 8.24t.M 0.00E40 .1.5N 03 4.67t+02_ 8.721 07 W 103 2,1'A+03 0.00t*00 E.96t+C2 0.00t+C0 7.43443. 7.83t+05 1.oM+05 W 105- 1.125+00 0.00t+00 4.364 01 0.00t+06- 1.41t+00 1.82t+06 9.MDM W .106 9.86t+04 0.00t+00- 1.26t+04 0.00E+00 1.V.It45 1.61p07 9.60t+05 A4 110M 1.30Ee06 1.31t+M . 7.99t+03 0.00E+00 .2.50t+M 6.75t+06 2.7M+05 ff*125m 4. Ret +03 2.ME+03 6.67t42 1.40t+03 0.00t+00 5.NE45 7.50t+04 ft.127M 1.h0E +M 8.1M +03 1.781 4 4.5eE+03 6.$4t+06 .1.44t+06 1.5M*45 74 127 2.01t+00'9.1M*01 4.4R.01 1.42t+00-7.2EE*40 1.1M +06 8.00t+04 t
TI*129M -1.39t*04 6.58t+01 2.25443 4.5st+0315.19t*M 1.9et+46 6.05E+05-7t 129 ' 7.1M 02 3.300 02 1.744 02 5.18t 02 2.4d8 01 : 3.30903 1.62E+03-2
.TE*13SN 9.84441 6.01t+01 4.ON+01 7.25441 - - 4.39t+02 2.30t+05 6.21t+05 ft 131 1.54E 02 E.32E.85 5.NE 83 1.264 02 6.100 02~2.34t+03-1.51t+01
~
76 132 3.60$+02 2.90p42 - 2.19t+62 2.444*e2 1.95E+45 4.49t+05 4.43t+05
. I.130 6.M5 65 1.'79E*06' 7.111+65.' 1.60pe6 L 2.7M*06 . 0.00D00 9.1R+C3 ,
I 131 3.54t+es 4.91p e6 2.Me+46 - 1.44047 . 4.48p46 . 0.0e+00 - 6.69t+03 -
!=132:
1.595*05'4.30t*05 1.50t+el 1.51p05 6.9E*03.0.00t+00 1.27t+05 L--
t.133 - 1.23e*e6 2.05e+44 6.2N+0S- 2.9m+e6: 3.59906 0.80E*e0 -1.0bt+46 I.134 8.00p02 ' 2.32E*63. 4.44842 3.950+46-3.446*63 0.00pe0 2.mt41
- 0. ale 00 ' 4.95t+43 -
1 115 3.70t+45 l 9.44f +03 3.69t+43 : 4.21905 1.49t+M 1.i* Del =9.7M+01-CS 134 7 - 5.0M*05 1.1M*06 - 5.49t+05 0.00t+00 3.75905 ts 136 5.150 0611.968+45 1.37p05 0.00E+40 1.10t+05 1 *,et+M Mt.Det+06 ,
p ....................s ..........................................................
rC3*137?
6.70t+05 8.4aE 45 3.11t+05 ; 0.00p40 : 3.066+05 - 1.21t+05 - 8.40E+55 '-
' CS 138 - 4.44E+02 8.54t+02 4.64842 0.00E+00 6.ME+02 7.47t41 2.70E-01
' - BA.139- 1.34G+00 9.448 06 s 3.90E 02 C.00t+40 4.eN .M ..................
' 4.edE+43 4.4M+53-Caswrelen f acters are in mits of ar1m/yt por uti/seic seter.
UNT-005-034 Revisioti1- -
Att.achment 6.5 (5 of 12) r
-125
(
p
,. -. _ - . . ., .. - - . - , ...-. - - - . .- -..-.- - . - . - . ~ . . _ .
t INHALATION PATINAY DOSES DUE TO RADIONUCLIDES OTifER THAN NOBLE GASES, R.
1 AGE Cap s 1sts ( 3 00 3 )
auCLIN ' on448 0054 CD8vt#1108 f 4C121 poet 1.topt inveole EIDuti tunt Gi l tti tlwa SA.MO 5,47t+04 6.7tt+01 3.5M*03 0.00t+00 2.2st 41 2.0M+M 2.29t+05 sa.M1 1,42t.01 1.06t.04 4.744 03 0.00t+00 9.Mt.M 3.29t+03 7.*64 04 t e l42 3.70t.02 3.70E.M 2.!?f.03 0.0ct+00 3.14t .M 1.91t+03 4.79t.10 LA.140 4.79t+02 .2.3M +02 6.36t+01 0.00t*00 0.ont+00 2.14t+05 4.8?t+05 L4. %2 . 9.604 01 4.2M.01 1.hM .01 0.00t+00 0.00t 40 1.nN4 1.20t+04 CE.141 2.84t+04 1.90t 4 ' 2.17t+03 0.00t+00 8. cat +03 6.148 4 1.2M +M CE.143 2.ME*02-1.Mt+02 2.1M+01 0.00t+00 8.64t+01 1.30t+05 2.55t+05 CE.144 4.09t+06 2.0M+M 2.M+M 0.007 00 1.21t+06 1.34t+07 8.64t +M
. M 143 1.34t+*A ' 31t+03- 6. m +02 0.00t*00 3.00t*03 4.43t+M 2.14E+05
...... .......... ..... 6.......................................................
M *144 4.30t.02 1.7M.82 2.1M.03 0.000+00 1.018 02 1.75t+03 2.3H.E ND.147 ' 7.8M*03 8.544+41.5.13t+02'O.00t+00 3.0a+03 3.72t+05 1.828+05 W 187 1.20t+01 9.76t+00 3.tSt+00 0.00t+00 0.00t+00 4.74E+04 1.Tft+05 NP.2N _ 3.3M*02 3.19t+01. .i.772+01 0.00t+00 1.00t+02 6.49t+04 1.3Jr+M Coswersten factors are in witto et aren/yr Der WCl/cuble unter.
Y h .
^
._UNT-005-014L Revision 1 Attachment 6.5 (6 of 12) 126
- a. .- .
.- .. _. - -- - - --. - . . .- . . - . ._ .~ . . - ~ .
q INHALATION PATWAY DOSES DUE 70 RADIONUCLIDES OTHER TJLAN NOBLE GASES, R. i 1
AM GMurs Cultp t 107 31 NUC4IDt Wr.As cost trmwt4 ion f at1 cms f ,eces twr:0:0 stDatt tums 01.u t 80 4 Livte s
n3 0.00t+00 1.12T+03 1.12t+03 1.12903 1,12t.03 1.12t+03 1.128 03 Cela 3.5M+M 6.73903 6 fM C3 6.73d+B . 6.734 03 6.73843 4.73903 mA*24 1.615 +M 1.61t +M 1.61pH 1.61t +M 1.614 06 1.41t+06 1.61t4.... +04 2.40t+06 1.14t+05 9. set +M 0.00E *60 0.00t+03 0.00t*00 4.Z2t+M P.32 Cs 41 - 0.00E +0D 0.00t.00 1.4 902 4.55E+01 2.43E+01 1.7Df+M 1.00t+03 * >
ar 54 - 0.tN *03 4.29t+M 9.51t+03 0.00t*00 1.00: 4 6 1.5eE+06 2.79t +N
................................................................................ t mw 54 0.OM+ec 1.M4+00 3.12E-01 0,0st+40 1.67t+00 1.31906 t.ZH45 '
75 55 4.74t+M 2.52E+M 7. m 43 .0.tet+00 0.00t+00--1.11t+05 2.47t+03 78 59 ' 2.0M s46 3.M p 04J1.67t+06 0.0ut+00 0.00E40 1.2M+06 T.0M+M
- ........................=.........................,,............................ .
CD SS
.0.00p e0 1.m+03 3.16f 41 0.00E+00 0.00E+00 1.11906 3.44t+06 Co 60 0.00t+00 1.31t46.2.36E+04.0.00t+00 0.00D00 7.0M46 WRE46 88 63 ' 4.21E+05 4 m +04 2.00E46 0.000+00 0.00t+00- 2.75t+05 4.33t+03 al.65 2.99t+00- 2.966 01' 1.NE*01 0.90t*e0 0.00t+00 6.10E+03 0.40006
. CU46 0.seE+40 1.99t*40 1.0M +00; 0.90D 00 a.ast*eo 9.5eE+03 3.dM46 24 65 - 4.36t46 1.13t+05 7.03t+46 0.00t+00 7.14846 - 9.95 tac 5 1.m+04 -
2e*e# 6.70t.42. 9.Mt.82 6.908 83 - 0.00E*e4 S.054 02 - 1.m+03 ' 1.02906 -
5R 53 . 0,00p eo= 0.00t+40 4.744*02- 0.00t*00^4.00E*40 0.00E+00 0.00D00=
0.00g+00 MM 0.00peo 0.08p00 5.48t*02 0.0st+00 0.00E*00 0.00E+00:
- en.es : 0.00pec' O.00F.40 - 2.53841 0.00940 - 8.tet*e8 0.00000 0.00E+<3 .
0.seE*00 1.tepe5.1.14t*05 8.98p40 0.sepe0 ' O. cot *e0 - 7.9et+03 -
.e9 06.
80 08 0.0e840 S.24 ' 3.44p02 8.SeE*00 0.90p00-0.00f+00 1.73f41.
........................ ..................................................... 1.ept+40 -
.88891 0,e0840 ' 3.45e+et 2.90t*e2 ' O.seE+ee ' 0, sue +00 ~ 0.mt+03 M*e8 '5.98t 45' O.sepeo: 1.7m
- M 0.seE+e0=0.eeE*e8 2.ter+e6 1.47t45 08 +90 -
1.01e*e8 8.sepee 6.44t*e6' 0, set +40 0.sep40.1.44E47 3.43f+05 ,
W41 1.21962 - 0.00peo : 4.99 tee 0 = 0.eOE*40 0.00r*e0-5.33906 1.74905?
OR 92 1.318*01 .0.005 40 5.254 01 0.00900 0.eupee. 2.4eEeN 2.42E*05 -
7 00 -
4.11445 0.see+et 1.11t*e2 0.00p00 0.00t*e0 : 2.eaE+05=2.40005 *
- T41N :
5.FM .01 0.em*80 1.048-02 0.00d*e0 : 8.get*e9 ' 2.ste+03 .1.7343
~
~
9.14845
- 0. septo 2.46e46 0.00p00; 4.espoo.2. m +06 1.Me*e5
" - 1 91
- Y.92 2.064*41 = 8.8W+40 5.str.01 0.get+ee 0.00000 ' 2.39t*M - 2.39E+05 Comoralen factors are in etts of ergefyr 9me uCI/seis autor.
9
_-UNT-005LO14 Revision 1 Attachment 6.5.(7-of 12)-
-127 m _ _ _
INIIALATION PATINAY DOSES DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R.
1 attcaam Cults (2of35 _
uGAs Dost Comyttt10m F6CtW8 mucLIDI LUNO II'klI gag tgyge 1.3a01 1MR040 Klbutt 1 93 1.tM+02 f.00t+00 5.11t*0C 0.00t+.0 0.00t*00 2.231'04 6.11t+04 7.64t+04 3.89005 1.90t+05 4. lat +4 4 3.70t+04 0.000 00 5.96t +M 28 95 1.ast+02 2.72f*01 1.60t+0i 0.pM +00 3. ant 41 1.13t.M 3.51t+05 18 97
........................ ...................................~.................
me.95 2.35t*04 9.10t+03 6.11t43 0.00t @ 4.Mt+03 6.14t+05 3.70t+M mo.99 0.00t+00 1.72W+02 4.2M+01 0.00t+00 3.Y2t+C2 1.351 45 % .2M +05 ft.994 1.7st.03 3.44t-03 5.7M.02 0.00t+00 5.071 02 9.51t+02 4.81t+03
....................................v........................,.....
tc.101 8.10E45 8,115 05 1.46t.03 0.00t+00 1.451 03 3.85t+02 1.43t+01 Ru.103 2.79t43 0.00E+00 1.01143 0.00E+00 7.034+03 6.m @ 4.4M44 au.105 1.53t40 0.00t+00 5.554 01 0.00t+00 1.34440 1.59t +04 9.95t+r.4 t@iO6 1.34t+05 8.00t+00 1.69t *M 0.00t+00 1.Mf+35 1.434 47 4.29t+05 AG*11M 1.eSt+04 L14t+04 9.14t*G3 0 00t+00 2.12t+M 5.4at +06 1.10t*05 6.7N+41 2.33t+C3 9.14t+02 1. m +03 0.00E+00 4.7M +05 3.38t+M 15 125#
it.1TM 2.49t+M 4.5M43 3.02t+03 6.0M+03 6.3M+04 1.4aE+06 7.14E+04 ft.127 2.77t+00 9.518 01 6,111 01 1.9M+00 7.0M+00 1.00904 5.62t+06 ft.1294 1.M* W 6.35843 3.Mt43 6.3X+El 5.03444
.............. 1.768+06 1.82t+05
...............n..................................
ft.129 '9.7M.02 3.50t 02 2.3at 02 7.144 02 2.5Ft.01 2.9N+03 2.55t+M '
11 13181 1.342+02: 5.92t+01 5.0M +01 9.77t+01 4.00t+02 2.0M+05 3.DeE+05 TD 131 2.1M 02 8.448 03 6.396 03 1.79t.ftt 5. net C2 2.05t+03 1.33t+03 ft.132 4.81E+42 2.78 42 2 43E+02 3.tM +02 f.7M*03 3.7M+05 1.34t*05 l.130 -
8,M403 1.64t+04 8.W+GL 1.85t+06 2.4M*04 ' O 00E+00 5.11b03 '
1*131 4. bat +44 4.81E'+44 L7M+44 1. M +07 7.ast*04 0.00E*00 2.84t+03 lif32 2.1N45 4.071+03 1. ant +03 1.94t+05 6.2M*03 0.80600 3.20E+03 1 133 1.6dt+04 7.03t+04 7.7W+03 3.354+06 3.SeeM 0.0tt +00 5.48t+03 l.134 -1.1M +03 2. tee 43 9.1P5t+02 5.0M*04 3.30E+03 0.00H00 9.5M+02 l .
l 1 135 4.92t+03 8.73E+03 4.146 03 7. m +05 1.34b04 0.00t+00 4.444+03 L
' tb134 6.51E+05 1.016 04--2.25005 0.00E+00 3.30E+0$ 1.21t+05 3.aM +
0.00t+00~ 9.55t+04-1.4M +04 .4.18t*03 .
ts.136 a.51E+M 1.71t+05 ' 1.1M+05 9.OM+05 8.2M +05 1.25E6.22be2 W 0.0eE+00 2.82E+05 -1.M4+05 3. M @
Cl.137 6.81E+01 2.70E42 cs.136 4.334+02 8.40E+02 5.558 02 0.e0E+00 l az e4 179 1.84b 00 '9.e44 04 5.3M.02 0.00t+00 8.62t.04 ........... 5.7M+03 5.77t+04 L
ll
. term uon f actors are in unite of ares /yr per uct/cetc ester.-
l l
i.
j UNT-005-014 Revision 1 Att.achment 6.5 (8 of . 2) 1 l
128
INilALATION PATifWAY DOSES DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R j AGt GawPt cull 0 ( 3 of 3 )
ORGAs Dost Cmyttslom f4C10R1 outtIDE INYtolt KIDutY tmG GI LLI Dont Livtt 1.60DY 64 140 ~ - 7.40t+M 6.44t+01 4.33t+03 0.00t+00 2.11F+01 1.74t+06 1.c2t+05 sA.141 t.9M.01 1.0W .04 6.3M-03 0. m +00 9.4M 05 2.92t+03 2.nE+02 s4 142 5.00C.02 3 A t*05 2.79t.03 0.00t+00 2.918 05 1.64t+0) 2.74t+00 LA.140 6.44f+02 2.2R+02 7.55t+01 0.00t+00 0.00t+00 1.sM+05 2.26t*05 '
i' LA.142 1.30t+00 4.11t*01 1.294 01 0.00E +00 0.00t+00 s.70t*03 7.59t+04 Ct*141 3.92t+M 1.95t+04 2cMt+03 0.00t+00 8.55t+03 5.44t+05 5.6M +04 ca.143 3.6M+02 1.We+02 2.sM41 0.00t+00 8.3M+01 1.1M+05 1.2M+05 gg.144 -~ 6.7M+06 2.12t+M 3.611 05 0.00t+00 1.1M +06 9. M1.20t+07
+04 3. M +05 M.143 1.35*+04 5.5M+03 9.14t+02 0.00t+00 3.00643 6.3M+05 x.............
M 144 5.Mt.02 1.BM 02 3.00t 03 0.00t+00 9.7M.83 1.tM+03 1.9M +02 80 147 1.00t+M R.734+03 6.41t+02 0.00t+00 4.81E+03 3 IJr+05 8.21t +M W 187 1.63t+01' 9.6M +00 4.3M+00 0.00E+00 0.00t+00 4.11t+04 9.10t+06 uP 239 4.6et+02 3.344+01 2.3M+01 0,00t+00 9.73t+01 5.81t+04 6.40t +M Carwwsten factors are in witte of ares /yr per i.Cl/cels carter.
4
.j
- l. UNT-00.5-014 Revision 1 Att'achment 6.5 (9 of 12) 1 i- 129 l
l t
INHALATION PATINAY DOSES DUE TO RADIONUCLIDES OTIER THAN NOBLE GASES, R.
1 ACE Ct:L8' lufANT E 1 0F 3 )
i IEJCLICE Car.4m 0058 C3fvittlCm f4CTW t souf Livre f.scov tuvrolo KIDatt tuwG Cl Ltl
- 3 0.00E + 00 6.47E.02 6.4M +02 6.4?E+02 6.4M +02 6.4 M +02 6.4 M +02 C 14 2.65E +M 5,31E+03 5,31E+03 5.31t+03 5.31E+03 5.31t+03 5.31E+03 EA 24 1.0M *M 1.CM +04 1.06E +04 1.04 44 1.CM +04 1.06t+04 1.0M +04 P 32 2.05t+06 1.12t+05 7.74E+04 0.00E W 0.00E+00 0.00E 43 1.61E+04 Cs 51 0.00E+00 0.0x.90 8.95E+01 5.75E41 1.32101 1.2M +M 3.57E42 .
wa 54 0.00E +00 2.53E+04 4.98t+03 0.00E +00 4.14t+03 1.0ct+06 7.0M +03 MW 56 0.00E+00 1.54t+00 2.211 01 0.00E +0C 1.10E +00 1.25E+04 7.17t+M FE 55 1.97E *M 1.17E 04 3.33t+03 0.00E +00 0.00E+00 8.69E +M 1.09E +03 ft 59 1.3M +0+ 2.35E+M 9.48t+03 0.00E +00 0.00E+00 1.02t+06 2.48t +M CD-54 0.COE+00 1.22t+03 1.82143 0.00E +00 0.00E+00 7.77E+05 1.11E+04 Co 60 0.00E*00 8.02t+03 1.18E+04 0.00E+00 0.00E+00 4.51t +M 3.11t +M ul 63 3.39E+05 2.Mt44 1.1M *M 0.00E+00 0.00E+00 2.09E+05 2.42t+03 88 65 2.39E+00 2.84E 01 1.23E 01 0.00E+00 0.00040 8.12E+03 5.01E44 CU 64 0.00E+00 1.8eE +00 7.74E-01 0.00E+00 3.9eE+00 9.30E+03 1.50E+04 2m-65 1.1'3f +04 6.2M +04 3.11844 C.00E+00 3.25E*04 6.47t+05 5.14+04 2m-69 5.39E 02 9.f. % C2 7.1M 03 0.00E+00 4.02E 02 1.47143 1.322+M 82 03 0.00E+00 0.00E+00 3.81E+02 0.00E+00 0.00E +00 0.00E*00 0.00E+00 TM 0.0CE+00 0.02+00 4.00E*02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 34 85 0.00E+00 0.00E+00 2.04E+01 0.00E +00 0.00E +00 0.00E+00 0.00E+00 RS M 0.00E+00 1.90E+05 1.82E +04 0.00t+00 0.00E+00 0.00E+00 3.Ma+03 08 80 0.00E^00 S.57t+02 2.87E42 0.00E+00 0.00E+00 0.00E+00 3.39E+02 ks 89 0.00E*00 3.21E+02 2.0M*02 0.00E+00 0.02t+00 0.00E+00 6.82E +01 SE 89 3.98E+05 0. DOE +00 1.14444 0.00E+00 0.00E+00 2.034+06 6.40E+04 5R-90 4.09E+07 0.00E+00 2.59E+06 0.COE+00 0.00E*00 1.12E+07 1.31E+05 sat t) 9.5M+01 0.00E+00 3.4M+00 0.00E*00 0.00E+00 S.2M+M 7.34444 sa 92 1.05f+01 0.00E+00 3.91E-01 0.00E+00 0.00E+00 2.38E+04 1.40E+05 T 90 3.29t+03 0.00E+00 8.82E+01 0.00E +00 0.00E+00 ' 2.69E+05 1.ME+05 v.91m 4.07E 01 0.00E+00 1.39E 02 0.00E+00 0.00E+00 2.79E+03 2.343+C3 T 91 5.aaE45 0.00E+00 1.57t+M 0.00E+00 0.00E+00 2.45t+06 7.034 +M v.92 1.644+01 0.00E+00 4.61I 01 0.00E+00 0.00E+00 2.45444 1.27E45 Cannten voeten en in units of armer per uct/aste seter.
UNT-005-014 Revision 1 Attachment 6.5 (10 of 12) 130
4 INTIALATION PATlfWAY DOSES DUE TO RADIONUCLIDES OTIIER TilAN NOBLE GASES, R.
1 AGE GtCL* lufAmt t 2 07 3 )
suCLIDI DAGAN D061 Couvtallom f AC10R$
1.021 TNTt010 ElDut? LiasG Gl.Ltl tout Livtt 4.m. 0... 0.. . 7.64 06 i ..M . !
,.,, 1.,et . 0... l 28 95 0.15t+05 2.Mt +M 2.0M+M C.00t+00 3.118 44 1.75t+06 2.1M +06 /
29 97 1.50t+02 2.5ef+01 1.17t41 0.00t+00 2.59t+01 1.10t+05 1.40t*05 as.M - 1.57t+04 6.43443 357et+03 0.00t+00 4.72f+03 4.79t+05 1.2M+06 l 1
no-99 0.00t+00 1.656 02 3.23t+0i 0.00E+00 2.65t+02 1.35t+05 4.0 M + 06 '
fr 9eu 1.408 03 2. set.03 3.728 02 0.00t+00 3.118 02 8.11t+02 2.ON*03
................................................................................ I ft.101 6.51C 05 e.238 05 8.12t 06 0.00t+00 9.79t 04 5.6442 - 4.44t+02 .
- 00 103- 2.03E +03 0.00t+00 6.79t+02 0.00E+00 4.260 03 5.52e45 1.61t+06 I 1.5M*0+ 4.84(+04 av.105 1.22t+00 0.00t*00 6.10t+01 0.00E+00 e.99t 01 au.106 8.em *46 9. tee +a0 1.0st+06 0.00t+00 1.07t+05 1.14E +07 . 1.64t +05
. an.110m - 9.9e8+03 7.23s+05 5.00E+05 0.00t+00 1.09t+06 3.67t+06 3.30E*06 78 12Su 4.7e043 1.98043 6.5et+02 1.42E+03 0.00t+00 4.4M +05 1.78t+M TI.12M 1.6M+06 ~~ 6 .90e+0S 2.0M45 4.tM45 3.7M+06 1.31E+06 2.7M+06 71 127 2.23E+00 3.5M.01 4.est.01 h ut+00 4.ee6+00-1.03t+44 2.44t+04 15 139 1.41t+06 4.08t+c3 2.23e*c5 5.47t45 3.tet+04- 1.6e5. 4.sm+06
- 3. tee 45 2.63E+44 18 129 7.8EE.et 3.4M.82 1.em .02 6.750 02 '1.754-01
'7t.131m - 1.tfu.et 3.5er+01 -- 3.43e41 4.93t+01 2.eSe+02 1.98t+e5 1.19t+05 ft.131 1.748 02 - 3.23t. - 5.est 5 1.5et.et 3.996 82 ~ 2ME45 8.22E+05 78 132 - . 3.73+02 2.3M*et = 1.700+4R 2.Mt+et 1.5845 - 3.4ee+el : 4.41t+04 .
. I.fJIO 6.388+e5 1.30t+06 S.5M+e5 .1.485+e6 1.53e+44 0.00t+e0 1.995+05 3.NE+44 6.44t*e6 1.9es*e6 1.4et47 5.tet*% 0.see+00 1.ses*e5 1 1312
^
-I+132 1.e8t+85 3.544+05 1.36e45 ' 1.488+05 3,95e 45 0.00E+e0' 1.98t+45 -
-4 133 : 1.3M*06 1.W*06 5.48*e5 3.See+46 2.244406 0.cof+40 2.14e*e3 -
' l.134 : _ 9.21t+4R 1.eee+45 ' 4.45641 : 4.450+44 3 2.00 tee 5 0.00E+e0 - 1.29t+ss 1 135 3,86e45 7.40845 2.77t+03 6.900+05 '. 8.4M+e5 0.00e+40 ,1.83E+45 -
- 1. tee +05 7.97t+06- 1.33E 65 -
- 58 136 - - 3.90845 7.We+45 7.45e+06 0.00t+00 ts 136 - 4.e3s+06 ; 1.35e*e5 - $.29t+e6 0.80E40 5.Me+e4 1.188+e6 ^1.43E+e!'
CE*137- 5.4ee+05 -4.13e*05 4.35e+46 0.00t+00- 1.7N +05 7.13e406: 1.33e+G5' 88 13e
~ 5.85e*et 7.81t*42, 3.9ef+02 0.est*e9:4.1st*02.4.54Eest 8.Ne+et e4 139- 1.4N+00 9.06E.06 4.30E.02 0.00e+40-5.985 06 5.954 e5 - 5.10k+06 espuereien factors ses in talts of erentyr per dl/cels meter.
4 -
4
-.UNT-005-014 Revision;1 Attachment 6.5 _(11 of 12) 131
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER TIIAN NOBLE GASES, R g 4G4 Em(3JP1 lEFAdf ( 3 0F 3 1 mKLipt ceGAa IKnt convtellah f attoal fuf0010 flDutT LUuG Cl Ltl pont Livts 1.scDT t
94 140 5.60t+M 5.60t*01 2.90t+03 0.00t+00 1.34t+01 1.60t+06 3 64t+04 k 141 1.5M.01 1. cat k 4.94 03 0.00t+00 6.50E 05 2.9M+03 4.Mt +03
- 6. m +02 ha*142 3.985-Q2 3.30t=05 1.96t 03 0.00t+00 '1.Me 05 1.5%t+03 LA 140 - 5.0H+02 2.00t+02 5.15t+01 0.00t+00 0.00t+00 1.6et 05 8.4at +0i +
LA 142 1.0000 3.Tft 01 9.kt.02 0.00t+00 0.00t+00 s.22t+03 5.95t+04 CI 141 2.74+04 1.6M+04 1.99t+03 0.00t+00 5.25t+03 9.1M +05 2.1M+04
- tt*143 2.m+02 1. m *02 2.21t+01 0.00t+00 5.ht+01 1.1M +05 4.9M+M CE*144 3.19t+06 1.21t+06 1.7M +05 0.00t+00 5.38t+05 9 Mt+06 1.40E+05 -
Pe*143 1.40t+04 5.24t+03 6.99t+02 0.00t+00 1.9M+03 4.33t+05 3.72t+04
....................+...........................................................
4.79t.02 1.0H-02 2.418 03 0.00E+00 6.721 03 1.61t+03 4.28t+03
~
Pe.144 80 147 7.kt+03 8'.13t+03 5.00t+02 0.00t+00 3.15t+03 3.22f+05 3.12t+04 W-187 1.30t+01 9.02t+00 3.12t+0D 0.00t+00 0.00E+00 3 tet+04 3.5M +W F 2M 3.71tvJ2 3.32t+01 1.ser+01'O.00t+00 6.62t+01 S m*E 2.49t+04 2
Carwersten f actors ers in smits of areWyr per_ el/cels aeter. .
UNT-005-014 Revision-1 Attachment 6.5 (12 of 12) i 132
GROUND - PLANE DEPOSITION PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R.
1 Af.t GACLPt ALL i 1 Of 3 )
mxtiet Der.As Dost towvittlam FAC10R5
- 1. W1 Exit t3 0.00t 00 0.00t+00 t 14 0.00t*00 0.00t+00 mA.24 1.19t*07 1.39t+07 P 32 0.00t+00 0.00t+00 CR 51 4.66t +06 5.51t+06 nu 54 1.395+09 1.638+09 sem 56 9.034 4 1.07t*06 FI 55 0.00t+00 0.00E*00 ft.59 2.734 4 3.71t+06 Co 58 3.79t+06 4,44t+35 CD-60 2.15t+10 2.534+10 al.63 0.00t+00 0.00t +C4 s .........................................
st.65 2.97t+05 3.45t+05 tu 44 4.07t+05 6.84t+05 p 65 7.47t+06 8.59t+08 D -69 0.004+00 0.00t+00 te D 4.87t+03 7.00t+03
. ta 44 2.c3t+05 2.36t+05 34-85 0.00t+00 0.cnE+00 M 86 8.99t+06 1.03t+07 es te 3.31t+04 3.7st+04 .
as te 1.23t+0S 1.44t+05
, St.99 2.14t+04 2.31t+06 se.93 3.00f+00 0.00t+00 sa.91 2.154+05 2.51t+06 sa 92 7.77t+05 8.Ot+05 -
f.90 4.49t+03 S.31t+03 T.914 1.00t+05 1.14t+05 v.91 1.07t+06 1.21t+06 T 92 . 1.act+05 2.14t+05 terwrsion factors are in etts of equare noter.aren/yr per st/sec.
UNT-005-014 Revision 1 At.t.achment 6.6 (1 of 3) 133
. , - ~ - - - .. . ~= _-_ _, .. ~ . . .
CROUND - PLANE DEPOSITION PATINAY DOSE l I
FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R g
&Ist GA M I ALL ( 2 0F 3 3 MUCLIM 08GAW DOEt CO NEtlION FACf088
- 1. 8(DY SClN d 93 1.8M +M 2.51t+05 In 95 2.454+0g 2.kt+08 22 97 2.WM 3.44+06
............~............................
se 95 1.31t+08 1.6tt*0s MD 99 3.9M +06 4.6M+06 tC ten 1.84 +05 2.11f @
TC 101 2.04+04 2.Nt+M I
su 103 1.00t+0E 1.2M +08 au 105 6.WOS 7.21t+05 l
l RU 106 4.22t+08 5.0?t+08
' -A4 110N 3.64+W 4.01t+09 tt 12Sm 1.554+46 2.tM+06 ft 12M 9.1M +44 1.0At+05 ft.12' 2.9eE+05 3.20t41 ft 179u 1.988+07 2.31i+07 ft 129 2.62E+04 3.10t+44 ft.131M 8.63t+46 9.4M +46 ft.131- 2.92E+04 3.4M+07 78 132 6.2M+e6 4.9u+46 1 13e 5.51t+46 6.48t+e6
- +41 1.7N+07 2.0st+07 -
l.132 . ~1.25e+46 1.4eE+46
- I.135 2.4M+46 2.90t+e6 1 1M - 4.4M+05 S.30E+0S I.1M - 2.5M+46 - 2.9M+06
- Cs.1M 6.8H+49 8.eef+09 Cs 1M 1.518+0s 1.71t+0s .
Cs.137 1.03E+10 1.20t+10 -
CS 138 3.Mt+45 4.10t*e5 M 1M 1.0e8+45 1.19t+05 l __
'* Curwersion f acters ero in mits of somre aster.erevyt per gl/sec.
t UNT-005-014 Revision 1 Attachment 6.6 (2 of 3) 134 1
GROUND - PLANE DEPOSITION PATifWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R.
1 ,
AGE gat JPi att . 3 Of 3 )
uJCLIM CRCda 90lE Couvit5tok FACTOR $ .
- f. 8001 5814 ta.140 2.05t+0? 2.358*07 ba.141 4.17t*04 4.75C W t B4 142 4.49t+04 5.11t+04 LA.140 1.92t+07 2.1M+07 LA 142 7. cat *05 9.11t+05 f CE*141 1.37t*07 1.548 07 CE.143 - 2.31t+06 2.63t+06 *
!' tt.144 4.95t+07-4.04t47 pa.143 0.00E+0C 0.00t+40 Pa.144 1.85t +Q 2.11t+03 6s.147 8.39t+06 .1.01t*07 W.137- 2.I'A +46 2.738 06
. w.zst 1.71t*os - 1.9eE+os
. - canareten vect r. ee. in mise .e mm ter..ravyr p7. 4ti e. .
p _.
I . ._. ,
H; m.
t j.
.f co.
i I
- UNT-005-014 - Revision 1- Attaciunent 6.6 (3. of 3)
' '135
COW's MILE PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TllAN N0liLE GASES, R.1
(
MI 4 tars a u f ( ) DF 3 1 suckl0E onus Dost Cusvtation f actoss 1.a m 1seva0tp Elpett t uec st.LLI grut Livt e
- 0. cat +00 7.Mt+02 7.ut+02 7.Mt+02
- 7. Lit *02 7.ut+02 7.Ot+0t W3 C.14 2.63t+0e 5.27t+07 S.27t+07 5.271+07 S.271+07 5.2ft+07 1.271+*?
ma.24 2.64t*D6 2.44t +tm 2.A&t+06 2.648 46 2.66t+06 2.ut+06 2.64t*06
... .. ... .............................. ................+.. 4.......
p.12 1.71t+10 1.0M +09 6.61t+06 0.00t+00 0.00t+00 0.0M +00 1.92f+09
- 3. 798 +06 7.19t+06 ta 51 0.one+00 0.00t*00 2.5M +k 1.71t+M 6.30( 03 sw 54 0.uot =00 0.41t+M 1.6 tt+% 0. W +00 2.50t+06 0.t>0t*C0 2.58D07 sur$6 0.00E+00 4.15t 03 7.3M .% 0.00t+00 $.271 01 0.00E+00 1.321 01 Ft 55 2.51t+07 1.76t+07 4.05t+04 0.00t+00 0.0at+00 9.68t+06 9.95t+06 F1-19 2.97f.07 4.94t+07 2.6M+07 0.00t+00 0.00t*00 1.95t+07 2.35t+06 Co 58 0.00t+00 4.N+0a 1.0M+07 0.0ct+00 0.00t+00 0.00t+00 9.15f 47 CD 40 0.00f+00 1.u8 07 3.62t+07 0.00t+00 0. Cot +00 0.00t+00 3.0N+06 al O 4, M +09 4.ut +06 2.2M +08 0.00E*00 0.00E+00 0.0JE+00 9.73t+07
....................................................................r...........
kl.65 3.7tT.01 4.41t.02 2.19t.02 0.00t+00 0.00t*00 0.00t +00 1.221*00 CU-M 0.00t+00 2.340+04 1.12++04 ' O.00C+00 6.01t+04 0.00f 40 2.0M+06 2m+65 1.371 49 4.37t+09 1.97t+0* 0.00f+00 2.92t+09 0.00t*00 2.75t+09 Zu 69 2.89t.12 4.00t.12 2.78t.13 0.00t+00 2.60412 0.0ct@ A.018 11 St.43 0.00t+00 0.00t+00 1,172 02 0.00t+00 0.00t+00 4 00Ee00 1.684 02 SW 84 0.00f+00 0.00t+00 1.938 24 0.00t+00 0.003+00 0.00t+00 1.121 29 Da.83 - 0.00E+0D 0.00t+%1 0.00E+00 0.00E+00 0.00E+00 0.Cet+00 0.0mt+00 as 86 0.00t+00 2.5M +09 1.21449 0.00t +03 0.00t+00 0.00E+00 1.12t+08 R4 48 0.00$+00 0.00t+00 0.00t+00 0.00t+00 0.00t +00 0.00t+00 0.00t+00 88 99 0.00E+%) 0.0M+00 0.00t+00 0.00t 40 0.00t+00 0.00t+00 0.00E+00 St.99 1.45E+09 0.0nt+00 4.1M*07 0.0ut+00 0.00E+00 0.00t+00 2.33t+06 sa.90 4.68t+10 0.00t 40 1.1$4+10 0.00t+00 0.00t+00 0.00E+00 1.35t+09 sa 91 2.artt +04 0.00t+00 1.17t 43 0.00t+00 0.00E+00 0.00t+00 1.38t*05 sa 92 4.Wpt-01 0.00t*00 2.111 02 0.002+00 0.000+00 0.00t+00 9.6M +00 1 90 7.00t 41 0.00t+00 1.90t+00 0.00E+00 0.00t 40 0.00t+00 7.51t+05 t 91n $.9et.20 0.00t+00 2.321 21 0.00t+00 0.03D00 0.00t +00 1.768 19 f.91 8.59t+03 0.00E*00 2.30t+02 0.00t+00 0.00t+00 0.00t+00 4.734+M f.92 5. Sat.05 0.00t+00 1,08 06 0.00t+00 0.00t+00 0.00t+00 9.77t 31 Carwerelm f acters are in untas of some, seter. oram /ye per scliset for ett stat tdes ascept R.3 thith le in 4rtits of SFTSt/yf PGt LM$/CLtdC SS19f.
Att.achment 6.7 (1 of 12)
UNT-005-014 Revision 1 i l
136
(
t cob" s MILK PATINAY DOSE FACTORS DUE TO PADIONUCLIDES OTHER TRAN N0llLE GASES, R.
1 Mt %a mi ( 2 of 1 )
millet OR(.Aa Dott CENYttIIM IACTCat gout Ltytt f.tcot 1MYt310 E:Deff LLetG Gl.LLI 1 93 2.23t.01 0.00t+00 6.171 03 0.00t+00 0.coe m 0.00t+00 7.08& 4 3 it .M 9.43t+02 3.03t+02 2.054 01 0.00t+00 4.75t+02 0.00t+0C 9.59t+05
! 21 97 4.3M .01 8.741 02 4.004 02 0.00t+00 1.371 01 0.00t.00 2.71t+04
. ........................... ......................+.......... ................
se.95 8.264+04 4.59t +M 2.471+th 0.001 00 4 .54t +M 0.00t+00 2.79t+08 0 99 0.00(+00 2.69f*c7 4 J1t+06 0.00E+00 S.61t+07 0.tMt+00 . 74t+07 TC 9m 3.32140 9.3M+00 1.20t+02 0.00t+00 1.434+C2 4.4CD09 S.55t+03
- TC.101 0.u0L+03 0.00t+00 0.00t+0n 0.00t+00 0.90E+03 0.00E+00 0.00t+00 80 103 1.02t43 0.00t+00 4.37t+02 0.00t+00 3.m 43 0.0M
- 00 1.19t+05 eu.105 8.571 64 0.00t+00 3.3M.k C. W +00 1.111 02 0.00t+00 5.24t.01 tv.106 2.04t +M 0.0E+00 2. Set +03 0.00t+00 3.94t +4 0.0:#900 1.32f +M AG.110n $.823 07 $.39t+07 3.20te07 0.00t+00 1.064+08 0.00t+00 2.2(At +10 71 125M 1. W +07 5.90t+06 2.18t +M 4.90t+06 6.634 07 0.0W +00 4. Sot +07 ft.127W 4.54t+07 1.64t+07 5.5MW 1.17t+07 1,84d+08 0.00t+00 1.%t+08 ft.127 6.33t+02 2.34 +02 1.41t*02 4.84t+02 2.44t+03 0.00t+00 5.1H +04 T1 129m 6.02t+07 2.2H+07 9.51t +# ' 2.07t +07 2.51i+08 0.00t*00 3.03t+08 it.129 2.821 10 1.066 10 6.8At.11 2.171 10 1. M .09 0.00E*00 2.13t.10 f t.131st 3.61t+05 1.77t +05 1.,47t+05 2.00t 45 1.79t +M 0.00t+00 1.75E+07 ft.131 3.60t.33 1.511 33 1.144 33 2.964 33 1.58t.32 0.00t +00 1.tts.34 18 132 2 40t+M 1.sSt +M 1.4M+M 1.724 +% 1.50E47 0.00f+00 7.3M+07 1+150 4.29t+49 1.244 +M 4.99ty05 1.05t+08 1.9M +06 0.0dt+00 1.071+M -
l'131 2.964+N 4.De*06 2. W +0e 1.39t+11 7.26348 0.00t+00 1.12t+08 4132 1.shi=01 4.391 01 1.544 01 1.54 421 7.00c.01 0.00t+00 4.254 02 1 133. 3.E?t*M 6.732+M 2.05t+M 9.99t 48 1.17t+07 0.00t+00 4.0H+M t.134 2.028 12 S.48t.12 1.944 12 9.49E.11 8.714 12 0.00t+00 4.775 15 1 135 1.28t44 3.Mi*M 1.24t+04 2.22s+06 5.39t+M 0.00d+00 3. sot +M t.t.134 S.65t+09 1.35t+10 1.101+10 0.0C9+00 4.354+09 1.454+09 2.3M+C6 03 1 % 2.614 41 1.Mt+09 7.4N +08 0.00E+00 5.75t+05 7.9U47 1.1st+06 C1 137 7.38t+09 1.01t*10 6.61t+09 0.00E+00 3.43t+0) 1.144 49 1.FM+08 08 138 9.tMt.24 1.79t.23 8.854 24 0.00t @ 1.312 23 1.331 24 7.62t*29 5A.139 4.42144 3.15t.11 1.29t.09 0.00t+00 2.Mt.11 1.7+11 - 7.848 08 Caseroien factors are in 6mits si osaart entor.wtae pse W1/aec for all nurttees except t 3 elit is in unite of aree/yr ser diteelt enter.
UNT-005-016 Revision 1 Att.achment 6.7 (2 of 12) {
i 137
, . .- ~ - . - . . - - - - , -. . . ~ .. .- . - . - . - - - ~_- - . - . . - .- .
t COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBT.E CASES, R j
- AGE MCUP1 AOLA1 ( 3 Of 3 )
WCL1DI DRGAn Dont tl0MYttlluu FACY081 DOet Llyt t 1.38Df 1WT90;D titWett tumG cl.LLI i l
4 SA*140 2.69t+07 3.34t +M i .T64 +M 0.00t @ 1.151*06 1.914+04 5.53t+0?
SAa141 0.004*00 0.00t+00 0.00t+00 0.004+00 0.001+00 0.004+00 0.006+00
' 6A*142 0.00t+00 .0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.Ist+ao 0.00t+00 LA 140 4.51t*00 2.2?t+00 6.014 01 0.00t+00 0.00E+M - 0.00t+fA 1.67t+05 '
L A.14 1.848 11 8.450 12 2.106 12 0.00t+00 0.0M *00 0.00t+m) 6.17t*04 Ct.141 4.84t+03 3.2st+03 3.721+02 0.00t+co 1.52643 0.00(+00 1.25t+07
....................... ........................................................ s C3 143 4.1M+01 3.07t+06 3.40t+00 0.00t*00 1.35441 0.00t+00 1.15t+06 a .144 3.54E 45 1.50t+05 1.ftt+06 0.00E+00 8.87t*04 0.00t+00 1.21t+08 M 143 1.54E+02 6.33t+01 f.538+00 0.00t+00 3.4e4401 0.tJE+00 4.92t45
' PR 144 - 0.00E+00 0.00E *f0 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00t+00 le 147 9.42t41 1.096+02 4.51t+00 0.00t+00 6.3M+01 - 0.00E +00 5.221+05 4
Wait? - 6.51t+03 3.45t43 1.90E+03 0.00r+00 0.00t+00 0.00t+00 1.7st+ce
,e up.239 ~ 4.60t+01 4.52t+00 2.49t+00 0.00t *00 .1.41441 0.00t+00 f.27t*05
~
Oorwersten f acters are in mits of somere anter.areWyr per uti/see for ett metidos escort e 3 telch is in units of areWye per W1/snAsic mater.
b ,
s T
J UNT-005-014 Revision 1 Attachment 6.7 (3 of 12) ,
138
COW s MILK PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R.
3 Act OsaJP tite ( 1 Of 3 )
tuCLitt WGAs lost Cavtatna f actas TNYt0!O riOMT LumG Gl
- Li,1 hout L IV.E f .53)T h3 0.00t+00 9.94t+02 9.94t+32 9.W542 9.%4*02 9.ht+02 9.ht+02 C+14 4.ht*08 9.72t+07 9.72f 47 9.72t+0? 9.72147 9.72f+07 9.72t+07 mA 24 4.2M+M 4.2M406 4.2M +06 4.2M *06 4.2M+b 4.2M*06 4.2M+M
- 32 3.15t+10 1.95t+09 1.228+09 0.Mt+00 0.00t+00 0.00E+00 2.45t+09 co 51 0.00t+co 0.00t+00 4.99t+M 2.77t+M 1.09E+M 7.13444 f.,39t 44 hw 54 0.0M +00 1.40t+07 2.78t+M ' O.00t +00 4.18t+06 U.00t+00 2.87t+07 '
e 54 0.00E*00 7.3M 03 1.311 03 0.00E+tm 9.31t 03 0.00t+00 4.EE 01 ft 55 4.45t+47 3.1M 47 7.3M *06 0.00t+00 0.00t+00 2.00t+07 1.37t+07 Ff 59 5.19647 1.21t+08 4.67147 0.00t*03 0.00t+00 3.41847 2.0M+08 CO-54 0.00E*00 7.94t+06 1.83t*07 0.00t+00 0.?Ot+00 0.00t+00 1.09t+08 CO-40 0.00t40 2.7st+0? 4.2M+07 0.00E40 0. cot *c0 0.00t+00 3.621*00 ut.63 1.1k +10 8.35t*t5 4.01t +M 0.00t+00 0.onE+00 0.00t+00 1.Dt +08 ul 65 6.77t 01 8.454 02 3.944 42 0.00t+00 0.00t+00 0.00tNN 4.Ht+00 tu44 0.00t+00 4.25t+04 2. cot +04 0.0CE+00 1.07t+05 0.00E+00 3.29t+06 l 3 45 2.11t+09 7.37t+09 3.41t+09 0.00t+00 4.6aE+09 0.00t+00 3.10t+09 I ................................................................................
( zm 69 3.854 12 7.344 12 5.13t.13 0.00t+00 4.75t *12 0.0ct+00 - 1.354 11 84 4 0,00E+00 0.00E+00 2.155 02 0.f0E+00 0.00E+00 0.006+00 0,00f*00 ca 84 0.00t+00 0.00t+00 3.454 24 0.0M *00 0.00t+00 0.00t+00 0.00t+00 M@ 0.00t+00 0.00t+00 0.008+00 0.00t+00 0.00t+00 0.008+00 0.00E+00 as+86 0.00t*00 4.73249 2.2R+49 0.00t+C0 0.000+00 0.00E*00 F.00t+0e
- a4 48 0.00t*00 0.00t+0c 0.tet+00- 0.00E*00 0.00t*00 0.00E+00 0.tet+00 i
H49 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00t*c0 0.00t+00
$R 09 - 2.67t+M 0,00E+00 .7.NE+07 ' 0.00t+00 0.00t+00 0.00t+00 3.19t+00 se 90 - 6.61t+10 0.00t+00 1.63t+10 0.00t+00 0.00t+00 0.00t+00 1.tM+09 -
l- ................................................................................
se 91 5.31t M 0.00t+00 2.11t+03 0.00t+00 0.00t+00 0.00t+00 2.41t+05 as.92 4.94E.01 0.00t+00. 3.81842 0,00t+00 0.00840 0.00t+00 3.2at+01 T 90 1.30E+02 0.00t+00 3.51t+00 0.00h00 0.00teco 0.00t+00 1.07t+M v.oin 1.10E.19 0.00t+00 4.19E 21 0.00E+00-3.00E+00 0.00t+00 5.175 18 l T.91 1.50t+04 0.90t+00 4.244+02 0.00R+00 0.00t+00 0.00E+00 6.4aE+06 T 92 1.0M 04 0.00t+00 2.70t M 0.00t+00 0.008400 0.00E+00 2.8M *00 Oorwersten f acters are in mits of equere metee emvyr per .Ciftet far att mattees escept u 3 elch is in wits et erevyr per utt/cesc seter.
UNT-005-014- Revision 1 Attaciuneat 6.7 (4 of.12) 139-
COW's MILK PATHWAY DOSE TACTORS DUE TO RAD 10NUCL1 DES OTHER THAN NOBLE GASES, R.
1 .
AGt GR'JUPt titu ( 2 op 3 )
(EAa 0061 Cowytt$10N F ACTOR $
sfuCLik TNYR010 E!Dett tune Cl.4LI tsat Livtt 1.6:9Y Y.93 4.128 01 0.00t+00 1.134 02 0.00t+00 0.00t.00 0.00t+00 1.26a+04
- 1. tot +06 28 95 1.65t+03 5.20t+02 3.58t*02 0.00t+00 7.65t+02 0.00t+00 2A 97 7.8M 01 1.5M 01 7.19t 02 0.00t+00 2.3 4 01 0.00t+00 4.22t+04
.......~................................".""""".".""""*"."-""".
28 95 1.41t+05 7.818 4 4.30s.k 0.00E+00 7.57t+04 0.00t 40 3.34t+00 8eP99 0.00: 40 4.47t+07 Ir.53t+06 0.00t+00 1.02t+08 0.00t+00 8.0tt+07 ft.99u 5.7M +00 1.61t+01 2.08t+02 0.00t+00 2.39t.02 8.92t+00 1.05f+04
............................................~..".".."...""""""""".
ft.101 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00f +00 0.00t+00 av.103 1.81843 0.00t+00 7.74t+02 0.00t+00 6.3at+03 0.00E*00 1.51t+05 au.105 1.5M .03 0.00t+00 6.0M .04 0.00t+tc 1.m.02 0.00t+00 1.26t+00
- 1. sot +06 20 106 2.89t+04 0.00E+00 4.73t+03 0.00t+00 7.24t44 0.00400 ac.11tsi 9.63t47 9.11t+07 544847 0.00t+00 1.76t+0s 0.00E+00 2.5m.10 11 125e4 3.00t+07 1.08E47 4.02t+06 8.39t+06 0.00t+00 0.00t+00 8.8M+07 it.127m 8.44t+07 2.99t 47 1.00E+07 2.01t+07 3.42t+08 0.00t+00 2.1Ct+06 75 127 1.21E+03 4.29t+02 2.60t+02 8.35t47 4.90t+03 0.00E+00 9.34t44 ft.1291 1.10E+C8 4.09t+07 1.74E+07 3.55t47 4.41t+0c 0.00t+00 4.13t+08
..............................................".10 U 1M 5.20E 10 1.948 10 1.1M .10 3.71t 2.185 09 0.ote+00 2.848 09 ft.131M 6.57t+05 3.15t45 2 &3t+05 4.74845 3.29t+06 0.00t 40 2.511+07 n.131 6.58t.33 2.71t.D 2.044 33 5.0M *H 2.88t.32 0.005 00 5.40s.54 n.132 4.29t+46 2.T2t+06 2.5M e 2.87t+06 2 61t+0+ 0.00E40 8.6W+07 1 1?O 7.3at+05 2.14t+06 8.53t+05 1.74+08 3.2W+06 0.00t+00 1.44t+C6 1 131 5.3M+08 7.5tt+08 4.04t +08 2.1M+11 1.29t+M 0.00t+00 1.4M+c8 1 132 2.918 01 7.62E.01 2.74t .01 2.5M +01 1.20t+00 0.00t*00 3.33.M 3 133 7.6M+06 1.20t+07 3.6M +06 1.6M*09 2.10E 47 0.00t+00 9.0M +06 1 134 3. Sat.12 9.50s.t2 3.412 12 1.5M 10 1.5m.11 0.00t@ 1.252 13 3 135 2.7st+04 5.8M44 2. tat *04 3.7II+06 9.27444 0.00t+00 6.51844 Cs.134 9.82t+09 2.31t+10 1.677+10 0.00t+00 7.341+09 2.80t+09 2.8M+08 g.3 136 4,44t+08 1.1M+09 1.18t+00 0.00t+00 9.60t+08 1.51t+08 1.62t48 Cs.137 1.34f+10 1,75t+iG 6.20k+07 0.00t+00 6.0M+09 2.354*09 2.53t+08 Os.138 1.64 23 3.15t Z3 1.5M D 0.00E @ 2.338 D 2.71124 1.438 26
- 84 139 . 8.1M.00 5.758 11 2.Ma.09 0.00t+00 5.421 11 3.9M.11 7.298-07
...................................................+............................
Cawerstm f actors are in units of osare astee.orsm/yr per utt/see for ett fucildes except NG malem is le units of eree/yr pr ist/atic seter.
I UNT-005-014 Revision 1 Attachment 6.7 (5 of M) l 140
.. ,~ _ _ _-, . .. . _ - - _ _ . . - .. -
COW's MILK PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOllLE GASES, R j AGE GROUP: fttu i 3 0F 3 )
aucttDE (*LAs Dost Convittim PAttons 1.MeV 1pft010 EllHet t LuuG Gl.4LI tout L1958 4.00E+0; 7.484+07 SA.140 4.85t+07 5.95t +M 3.tM +06 0.0x+00 2.02t +M 6A.141 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00t+00 0.0X +00 CA.142 0.00E*00 0.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 LA.140 8.10t+00 3.tet+00 1.06t+00 0.00t+00 0.00E+00 0.00t+00 2.2M +05 LA.142 3.35t.11 1.4M.11 3.718 12 0.00t+00 0.00t+00 0.00t40 4.531 07 .
ct.141 8.88t+03 5.9M +03 6.81t+02 0.00t+00 2.79t+03 0.00t+00 1.7Dt+07 Ct.143 7.64t+01 5.5M44 6.215+00 0.00E+00 2.49t+01 0.00t+00 1.67t+06 CE.144 6.54t+0% 2.72t+M 3.54t+M 0.00E+00 1.63t+05 0.00t+00 1.6M + 08 M.143 2.00E 02 - 1.1M+02 1.44t+01 0.00E+00 6.73t+01 0.ca +00 9.14t+05 M.144 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00E+00 0.00t +00 0.00t+00 10 147 1.81t+02 1.97t42 1.18t+01 0.00t+00 1.1M42 0.00E+00 7.11t+05 W.187 1.19t +M 9.71t+03' 3.40t+03 0.00t+00 0.00t+00 0.00E+00 2.634*06
- .Z39 8.70t+01 8.20t+00 4.60t+00 1.00E+00 2.60t41 0.00t+00 1.33E+06 Comorelen f acters are in unite'ef someo meter. oram /yr por Nilees for all nucliese sacept m.3 shich le in mits of aren/yr per uti/cials ester.
+
p
.UNT-005-014 Revision 1 Attachment 6.7-(6 of 12) l i
141
l COW's MILL' PATHWAY DOSE TACTORS DUE TO l RAM ONUCLIDES OTHER THAN NOBLE GASES, R g )
I l
l Afd ta p e talLO ( t of 3 )
m eMcLlott on6An Gott cwriettom f attool l
60wt Livlt 1.60D1 t attotp stDatt two Glent 83 0.00t*00 1.lM+03 1.lM +03 1.lM+03 1.l ?l at'3 1.lM *03 1.17t*03 C+14 1.. M *09 3.39t+M I.3M*06 3.3M*00 2.3M*04 2.3M
- 06 2.3M +06 kA.24 8.tSt+06 4.tlE*07 8.63tw 6.95t*M 8.tSt*M 4. Bit @ 4.85t+06 P.32 7. Tat *1c 3.Mla09 3 ,0N +09 0.00t+00 0.00t.00 0.00t*00 2.15t+09 i 0.00s+00 0.00t+00 1.021 *M l .6lt +M 1.548 +M 1.01845 S.40t 4
, ce.51 sem 94 0.00t*00 2.1N +0F l.lat e 0.0N +00 $.aN+4 0.00t+00 1.76t*07
........................................"......="......."....""""""."
e le 0,00t+00 1.28t.02 2.90t.03 0.00P ~' i.158 02 0.00t+00 1.8M +00 ft ll 1.04+06 S.93t+07 1.Mt +a
- 0.00. . ' '.cnt @ 3.35t.07 1.1N +07 ft.19 1.20t*08 1.Mt+08 9.60t+0? 9.00E+00 0.00t+00 S.Mt+07 2.03t+06
...................................+...................................... .....
Co $8 0.0N+00 1.21147 h71647 0.000+00 0.00t+00 0.0N+00 7.0M +0 F Co H 0.tM *00 6.32t+07 1.2Ft+08 0.00t+00 0.00' +00 0.0N
- 00 2.3M +08 m).63 2.ht *10 1.lM *09 1.kt e 0.00t*00 0.00t+0D 0.00t.00 1.071+0a
..........................................................................+.....
si.65 1.Mt40 1.$64 01 9.ict.0? 0.00E+00 0.00E+00 0.00t+00 1J1t+01 tu.M 0.00t@ 7.66t +M 4. lit +M 0.00t+00 1.00E*05 0.00t+00 3.50t+06 In-63 4.1M 49 1.1N e 10 6.tSt+09 0.00t+00 6.%I+09 0.00t+00 1.93f+09 2s.69 9.475 13 1.37t*11 1.26t.12 0.00t+00 8.30s.it 0.000 40 8.621 10 be 83 0.00t 40 0.00t *00 l.20t.02 0.00t+00 0.00t+00 0.00t+00 0.00 +00
. str04 0.00t 40 0.00t+00 7.81t:34 0 eN+00 0.00t+00 0.00t+00 0.00t+00 pa.tl 0.00t+a0 0.00t*00 0.00t+0c 0.00t*00 0.00t+00 0.00t+00 0.00t +00 a?.M 0.00t*00 8.7M 49 5.39t49 0.00t+00 0.00t+00 0.00t+00 5.kt+0e es.88 0.000+00 0.00s*00 0.00s+00 0.00s+00 0.00t+00 0.0 0 00 0.0N+00
......................................".."."""~**"""*"""="""""
29 99 0.0N+00 0.00l+00 0.00t+00 0.000+e* t.00t+00 0.008+00 0.00t+00 W 99 6.62t+09 0.00r+00 1.99t +0B 0.1h1 N 0.008'00 0.00E*00 2.$44+08 88 90 1.1N *11 0.00t+00 2.8N +,10 0.00t.00 0.00t:JO 0.00t*06 1.11t+0e
[ 1.30t+05 0.00t+00 4.Mt43 0.00t+00 0.00E+00 0.00t+00 2.08t+05 98 91 De.92 2.19t+00 0.00t+00 8.7$8 02 0.00t+00 0.00t 40 0.00t+00 4,1M 41 f.90 3.22542 0.00t40 8.pt+00 0.00t 40 0.00t 40 0.00t40 9.1M +05
......................................++.................**.**.**...** ...**.***
1 914 2.6at.19 0.00t @ 9.76t.21 0.000+00 0.00t+00 0.00t+00 9.248 16 7 91 3.90t+M 0.00t+00 1.ht+03 0.00t+00 0.00t+00 0.00t+00 1.20t*06 1 92 2.lM.M 0.00E+00 7.248 06 0.00t+0n 0.00t+00 0.00t*00 7.31t+00 Cawersion f actors are in mits of esses meter.armWyr per utl/tec for att metimes except h.3 WhicA is in mits of areWyr per uti/cels ester, i
l l
(
i UNT-005-014 Revision 1 Attaciunent 6.7 (7 cf 12) 142 i
COW's Mll.K l'A*"l!WAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER THAN NOBII CASES, R g ord stoup talLD ( 2 08 3)
' AJCL10tl CaCM Dost (WWillow F4CW8 int 010 ElDart Lt24 Cl* Lit tout Livtt 1.topt
?.93 1.01t+00 0.00s+00 2. fat 02 0.00t+00 C. tot *00 0.00f 40 1. lit +04 21 95 3.u443 8.42 42 7.50642 0.00t+00 1.21t 43 0.00t+00 6.M 45 st.97 1.92t+00 2.T71 01 1.48 01 0.00t+00 3.964 01 0.000+00 4.20t
- se.95 3.1M+0% 1.24t 45 4.Ht+04 0.00t+00 1.1M *05 0.00t+00 2.29t+08 mo 99 0.0nt @ 8.14t 47 1.01147 0.00t+00 1.74t+08 0.00t + 00 6.73t'07 '
ft.99m 1.32141 2.59541 4.29t+02 0.00t+00 3.7M +02
- 32141 1.47t+04 it*101 0.00f+00 0.00s+00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 0.00s +00 99 103 4.2ft+03 0.00t 40 1.65143 0.00E 40 1.0M +M 0.00t+00 1.111 0$
sti.105 3.828 03 0.006 40 1.3Wt3 0.M 40 3.3M.02 0.0M
- 00 2.4M+00
.........................................................................=*.....
AV.106 9.24t*04 0. tot +00 1.1$4 44 0.00t+00 1. DI+05 0.00t+00 1.ht+06 A4 110N 2.098+04 1.41t+D8 1.13t46 0.00E+00 2.04+08 0.006*00 1.6M *10 f t. ipa 7.38t 47 2.00t+07 9.64t+06 2.07t 47 0.00t+00 0.00t+00 7.12547 TI.127W 3.CeE +08 S.60t+07 2.47t+07 4.97147 S.9M+M 0.00t+00 1.8.at *00 ft.127 2.98843 8.02t42 6.348+02 2.Dee03 8.47143 0.00s+00 1.1H 45 ft.129m 2.71tes 7.SaE47 4.21t+07 4.7H 47 7.fft+08 0.00t+00 3.31148 ft.129 1.IN.09 3. Sat.10 3.048 10 9.1M.10 3.7M tr i,00t@0 7.9er.04
- 15. e31m 1.60t*06 5.5M +05 1.Mt+05 1 144+06 l.35t+06 0.008 40 2.24t*07 ft.131 1.625 32 4.fM.33 4.s +33 1.248 32 4. sat.32 0.00t+00 4.495 32
......................................................~......-aa..".".".
rf 132 1.02t+07 4.$1446 l.4aE+06 6.6al @ 4.2it 07 0.00t 40 4.57t+07 1 130 1.73t+06 3.49t+06 1.40t+46 1.04t*00 5.IM +06 0.00t 40 1.LM +06 1 131 1.30f 49 1.31849 7.4H+08 e.3M *11 2.156 09 0.00E+00 1.17t+08
..............................+................................................*
1 132 6.Mt.01 1. m +00 5.82t.01 S.(?+01 1,944+00 0.00E+00 1.4M +00 1 133 1.7N 07 2.1M47 8.0M+46 3.944 09 3.544+07 0.00t @ 8. Set +0s 1 134 8.4at.12 f.".at 11 7.2M 12 3.62t.10 2.41t.11 0.00t+03 1.04t*11
........................................u...-..a...".-~.aa, *o"."".*"
1 135 S .4m +04 9.722+M 4.60s 4 4 8.610 +M 1.evt45 0.04 +00 7.40s+04 C*.1H 2.261+10 3.7M+10 7.M4+09 0,thit+00 1.1H+10 4.1M+M 2.00t+06 gg.1H 1.01149 2.4M 49 1.00t+09 0.00t+00 1.4a849 2.21t*06 9.77t47 cs.137 3.IM+10 3.09t*10 4.5M 49 0.00t+00 1.01t+10 3.62t44 1.fM +08
. cs.tse 3. pet.23 S.53t.23 3. tit.D 0.008*00 3.Mt .23 4.1M.24 2.5St.23 64 1M 2.01t 47 1.073 10 S.32E 49 0.0n:40 9.34t.11 6.305 11 1.1M *01 Carwersten feeters are in ells of equnre mete.aree/yr per uct/sec fee att ructione escept 64 melch to in mite of arearye pst ut1/ rett seter.
UNY-005-014 Revision 1 Attachment 6.7 (8 of 12) 143
COW's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R g J
AGE CatuP: CalLO ( 3 0# 3 )
auCLlH 8 car.As Dost trwvitsica tatttet 01.LLI !
ermt Livtt 1.0@ t 1Wthole Elbeit LumG p.140 1.171+00 1.0M *H 6.kt+06 0.00t+00 3.kt +p 6.12t+M l .tM +07 p.141 0.00t+00 0.00t*00 0.00t+00 0.00t+00 0.00t*00 0.00t*00 0.00t
- p.142 0.00t+00 0.00t+00 0.00t 00 0.00t*00- 0.00t*00 0.00t+00 0.0M+00 14 140 1.ht+01 6.70t+00 2.11t*00 4.00t*00 0.00t*00 0.00t+00 1.ME*M i LA 142 0.138 11 2.502 11 8.00t.12 f .0N*00 0.00t+00 0.00t 40 $.111 06 #
2.19t+04 1. Opt M 1.pt*03 0.0(8 40 4.70t *M 0.00t*00 1.3M*01 Ct.141 Lt.143 1.07t+02 1.0M +M *s.47t +01 3.00t+00 4.26t*01 0.00t+00 1.49t *W 1.*.2t+M l,0st+M 8.6M +0i 0.00t+00 2. cat +M 0.00t+00 1.3N+00 Ct.144 Pe.143 7.10t+02 2.iM+02 3.$M 41 0.00t+00 1.17t+02 0.00t+00 f.ftt +M Pt.164 0.00t*00 0.00t 40 0.00t+00 0.000+00 0.00t+00 0.0M+00 0.00t+00 e.147 4.4St+02 3.60E+02 2.79t*01 0.00E*00 1.90t+02 0.00t+00 S .70t +M
- e 181 2.Mt +04 1.Til+04 7.60E 43 0. gut +00 0.00s+00 0.00t+00 2.401 +H
.......................<.....................,s............................ ....
sp.IM 2.iM+02 1.lH 41 1.00E*01 0.00t*00 4.40t 41 0.00t40 1.1H+M Ce.werslen fetters are in mits of toaere sostee.aremryr per dt/sec for ett twellese sacept 0 3 dist le in ette of uren/yr per di/snels aster.
l l
l l
t l
l :-
i UNT-005-014- Revision 1 Attachment 6.7 (9 of 12) 144 ,
COW's MID: l'ATilVAY DOSE TACTORS DUE TO RADIONUCL1DESOTilERTilANN0!!LEGASES,Ig l
M.t f.ecup: 1past(1W3I suctipt onas to: Co ntesion f ut a l t
tett010 t10 mat ta6 64 4t1 00mg tme 1.0ces 03 0.00t+00 2.Mt+01 2. net.03 2.3at43 2.Mt 43 2.Mt+03 2.3m43 C*h 2.kt*09 1.00t*00 1.00t+00 9.00t+0S l.00t be $.00t*08 $ .00t+0e sia 24 1.54 47 1.kt47 1A4447 1.Mt47 1.$4847 1.$4t+0? i.54t+07
............................................., ................................. +
p.32 1.600+11 9.4M*M 6.2t(40 0.0pt*00 0.00t*00 0.00t+00 2.17849 Ce*ll 0.000+00 0.00t+00 1.61I 4 5 1.051+0S 2.306 de 2.05t+05 6.fotde 0.00t+00 0.64t +M 0.00t+03 1.4M*07 es k 0.00t+00 3.90t*07 0.kt +M em 56 0.00t 40 3.14 42 5.42t 03 0.00t.00 2. tot .tG 0.00t@ 2.05t
- 00 70 15 1.35t +M 0.TM 47 2.3M 4? 0.00t+00 0.00t*00 4.27147 1.116 4 7 ff*l9 2.kt+00 5.92t+08 1.Ht.00 0. Jot +00 0.000 40 1.iM*06 1.071 00 CO*H 0.00t 90 2.4M 47 6.0$t+07 0.00t+00 0.00t+00 0.00t+04 6.kt 47 to 60 0.00t+40 0 02t47 2.00s+44 0.00s+00 0.00t+00 0.00t+00 2 10e+08 el.63 3.setet0 2.16t +M 1.21B+09 0.00t+e0 0.toteto 0.00t+00 1.0ff*00 el45 3.$0t+00 3.m41 1.005 01 0.00t+00 0.01t40 0 00440 3 02841 CU M 0.00E*eo 1.06l+45 0.59E+44 0.tet+ep 31d*M 0,00t40 3 0tI+06 .
20 65 5.5M +49 1.90t+t0 0.F0t+ M 0.00t+00 9. kit +49 0.00l*e0 1.61t*10
.......................... .............................a......................
2049 2.03E.11 3.614 11 2.70t.12 0.00t*e0 1.$18 11 0.00t+00 2.964 *M M 03 ?.00t+00 0.00E+00 1.128 91 0.008+00 0.00s+00 0.008+00 0.00540 0.00t+00 0.00E 40 te M 0.000+00 0.00t+00 1.11,t 23 0.00r+00 0.00f 40 De M 0.00t+e0 0.00t+00 0.08t+40 0.0e8+00 0.0er*40 0.000+e0 0.00t*00 es 06 0,00040 2.23t*13 1.1R+10 0.00t+00 0.00540 0.005 40 4.08t*e0 08 06 0.00E*e0 0.00t*00 0.08t*e0 0.0N+00 0.00t+00 0.08t *80 0.00t+00
+ 00 M 0.0N+e0 0.00t40 0.00f40 0.00f*00 0.0C040 0.Sta+00 0.00t+00 to M 1.Mt*10 0.00t*e0 3.610+00 0.000 00 0.00t+eo 0.00I.00 ~ t.59848
- On 90 1.23t+11 0.tet+00 3.10t+10 0.08840 0.0st+00 0.0m+00 1.SN+M 9.03f+03 0.00t*e0 0.00t*00 0.0m+00 3.21t+05 90 91 2.72t+el 0.00t+00 0s 92 4.648+00 0.00E+00 1.708 01 0.00t*e0 0. tot *C0 - 0.00:40 5.00t+0) 1 90 6.0tt42 0.00t40 1.03t41 0.000*ep 0.00s+00 0.tkit40 9.61545 0.8meco 0.0st*40 0.er Ado 1.est.15 1 91R 5.67t*19 0.00f*e0 1.99t.20 T 91 F.33 tee 4 0.00t+eo 1.90t+83 0.00f.00 0.00840 0.f3E*40 5.29t+46 Y.92 $.302 N 0.00f+00 1.llia'It 0.00t+00 0.0er+40 0.At40 1.03E 41 Somersten f actors are in
- mite af swePo potee ereW Der giteet for 6Lt mactlene oncept 0 3 imish la la telte et smavyr per 41/sels enter.
l UNT-005-014 Revision 1 Attachment 6.7-(10 of 12) 145 L
- e .. - - , - . , _ - . . , _ , ,_
COW's HILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, }t i
Act f.83JP! let Amt t 2 tw 3 ) l wxt10l WCAa tott twvtafItu f R1ml 18tt0lb ElDWlf L48G Gl*Lkl scat tivt t 1.00DY 143 2.1M *00 0.00t+00 S.878 02 0.00t+00 0.00t+00 0.00t +00 1.70t +M 38*9% 6.80t*03 1.66t*03 1.1M+03 0.fot+00 1.79t+03 0.0M+00 8.2M 05 2347 4.0M +00 6.978 41 3.1M 01 0.00t+00 7.0M.01 0.00t+00 4.sst+04 he+91 S .9M
- 0$ 2.44t+0$ 1.41t+05 0.00s.00 1.75t+05 0.03t +00 2,bu+06 0 99 0.00t+00 2.0M +06 4.0M 47 0.00t+00 3.118 @ 0.03t+00 6.tSt47 f f *99e8 2.5t+01 5.671*01 7.3M*02 0.00t@ 6.10t+02...... 2.9M+01 1.65t+M ita101 0.00t+00 0.00t +00 0.00t+00 C.00t*00 0.00t+00 0.orJt +00 0.006 @
w 103
- 678+03 0.00t+00 2.90t 43 0.00t 40 1 tot +04 0.00t+00 1.058 45 W 105 8.0$t*03 0.00t+00 2.711 tt3 0.00t+00 l.921 02 0.00t+00 3.20t+03 0.00t+00 2.25t+05 0.00t*00 1.44t +M N.106 1.90t 45 0.00E+00 2.38t +M AG 110m 3.06t+0B 2.&M *06 1.5M +06 0.00t+00 4.0M *06 0.03t 40 1.4M *10 18 12588 1.11t+04 5.0M*07 2.04t+07 S.0M *07 0.00t+00 ... 0.00t+00 7.1M+07
+
Yt*127W
- 4. tit +08 1.608+08 5.10t47 1.22t+06 1.048+09 0.00E 40 1.?ptde 0.00t*00 1 3M *05 it.127 6.Ut+03 2.12t+03 1.36t43*l.14t+03 1.54t +M 18 121W l.$7t+04 1.91t+06 8.54t 4f 2.14f+06 1.3M *09 0.00t+00 3.3M+08 .
[ ...............................................................................
It 129 2.72E 09 9.3M.10 6.3M.10 2.2et.09 6.7M 09 0.00t+00 2.13 47 it 13th 3.30t+06 1.De+06 1.12t+M 2.?M+06 9.3M + M 0.0ce+03 2.29t47 11 131 3.4M .32 1.271 32 9.62t 33 3.0M 32 4.?M 32 0.00t+00 1.3at 30 78 132 2.11t+07 1.ht47 9.75446 1.54t+07 6.lM 47 0.00E 40 3.BM47 1*130 3.lM*M 7. tit +M 3.1M+06 8.nt+0e 5.$at+06 0.00t+00 1.6M+M l*131 2.72149 3.20049 1.41t+09 1.0M +12 3.74f+09 0,00t 40 1.14t+08 l*132 1.4M +00 2.90t+00 1.03t+00 1.3M 42 3.24t40 0.00t*00 2.35t 40 1 133 3.63t*07 5.28t+0F 1.lM+07 9.60E+09 6.21847 0.00t +00 3.9M+06 1 134 1.7M 11 3.60E.11 1.20t.11 8.40t.10 4.0M.11 0.00t+00 3.734*11 1.1M45 2.2M +05 8.144*04 2.00t+07 2.49E45 0.00t+00 8,00t44 l 1 135 l
' CS 134 3.6M+10 6.90t+10 6.8M +09 0.00t 00 1.M5*10 f.itt*09 1.8M +08 ts.1% 1.9et+09 1.ttt+09 2.1M49 0.00t40 2.32E+09 4.74f+08 8.82f+07
- 1. set +0s
+
cs.137 5.iM *10 6.ON+10 4.2M +99 0.00t+00 1.62E+10
- 6. tot.Z3 1.0M 23 2.10t 22 6.S$f*09 C8 136 8.3M 23 1.5M.22 6.618.D 0.0ct+00 1.725 10 2.718 05 i
ts.139 . 4.27t.07 2.EM 10 1.24000 0.00t+00 1.70s.10 Camsesten f acters are in mits of swore seter-erea/yf Pef dileec for ett euctiees except W 3 eAlch is in mits of eram/yt per diteste aster.
I .
l UNT-005-014 Revision 1 Attachment. 6.7 (11 of 12) 146
COW's lilLK l'ATHWAY DOSE FACTORS DUE To RAD 16UCLIDES OTilr.R TilAN N0llLE GASEG, R i sta teauri islast t 3 of 3 )
av:L104 cet.Aa Ocs: timvtt6tto eattcm5 187e010 titetY ttast &t.itt Eawl tivtt 1.t@ t 2.41t+00 2.41t*0$ 1.Itt*07 0.pJt+00 6./28*06 1.64E+0S l.92t+07 6A.140 0. m *00 6A.141 0.00t*00 0.Dut+00 0. cot *00 0.00t*00 0.00t+00 0.00t+00 6Aa162 0.00t*00 0. tot +tc 0.004+00 0.00t+00 0.00t+00 0.000+00 0.0W +00 LA.160 4.05t*01 1.60t*01 ,6.11t*00 0.00t+00 0.00t+00 0.00t @ 1.44t+0S LA.162 1.7.1t .10 e 24t.1% 1.695 11 0.00t+00 0.00t+00 0.00t+00 1.064 0$ ,
Ct.141 4.1+t
- 2.64t+06 3.11t+03 0.00t+00 8.tSt.43 0.00t+00 1.37t*07 Cf .141 3.97t+02 2 434+0$ 3.00t+01 0.00t+00 7.671*01 0.00t+00 1.$4t+06 Ct 144 2.3M *06 9.52t +M 1.30t+0$ 0.00t*00 3.05t+05 0.00t+00 1.3M W Pt.143 1.4M+03 5.15t+02 ?.344 +01 0.00t +00 2.06t+C2 0.00t *00 7.04t+0S Pt.144 0.00t @ 0.00s+00 0.0C4+00 0.00t*00 0.00s+00 0.00d+00 0 00t+00 2 14F 0.01t+02 9.056 +02 1.15t+01 0.00E+00 3.4 M +ct 0.006 @ 3.74t+0S W.187 6.08t+04 4.2M+06 1.44d+04 0.00r+00 0. tot *00 0.00t@ 2.688 06 me.239 4.57t+02 4.08t*41 2.3tt+01 0.00t+00 8.1$1+01 0.00t+01 1.18t+06 f.4mersion f actors are in etts of ewee aster.oren/yr per 'df/sec for ett re*Lldes eatopt D 3 elch le in mite tif eroe/yr per gif tets meter.
Uh'T 005-014 Revision 1 Attattunent 6.7 (12 of 12) 147
HEAT PATINAY DOSE FACTORS DUE TO RAD 10NUCL1 DES OTHER THAN NOBLE GASES, R g i
El t 80L* ADutt i 1 Of 3 )
estilet (seam 0058 tuntillos f A*ttal 1.6001 1918010 Elpett LumG Gl*Lil tant Livtl
.=w l
o.3 0.00t+00 3.2$t+0! 3.Ml+02 3.?Stei 1.25t42 3.2St+02 3.2St+02 C.to 2.61t*06 4.tJ4+9F 4.Ml+0F 4.834+Cf 6.tM +0F 4.831*0f 6.83t+0f mA.2d 1.ht. 03 1.ht r3 1.364 03 1.he*03 1.344 H 1.ht 03 1.ht 03
..... ............................................**.**.. *.. '*. ...*** ***= **
9 32 6. ut*09 2.90f+06 1.80t+08 0.00t+00 0.00t+03 0.00:40 %.26t+06 co 91 0.0(4 + 00 0.00:40 7.05t 43 4.21: 4 3 1.55843 9.35t+03 1.Tfl+06 mH 0.00t*00 9.1tf*M 1.75t*h 0.00t+00 2.7M+M 0.00t+00 2.81t+0F *
- M 0.00t+00 0.00t @ 0.00t+00 0.00E +00 0.00t+00 0.00t+00 0.DX 40 ft il 2.93t+06 2.Hf+04 4.721*01 0.00t+00 0.00t+00 1.13844 1 164*06 f1 59 2.64d+08 6.26t+08 2.39t+04 0.00t*00 0.00t+00 1.74t+08 2.088+09
';0 58 0.00t+00 1.82t +0F 4.09t +07 0.00t +00 0.0 t +00 0.03t+00 3.69t + 08 to 60 0.0te+00 7.$2X+07 1.444+08 0.but +00 0.00t+00 0.00t+00 1.411+0e 81 63 1.t9t*10 1.31t+09 6.3M +08 0.00t+00 0.0tOOO 0.00440 2 7M+04 81 65 0.00t+00 0.ttt e 0.00t+00 0.htv00 0.00t+00 0.00s+00 0. tot +00 CU 64 0.0E +00 2.T11 07 1.275 07 0.0M*00 6.844 07 0.00E40 2.318 05 ,
Zm 65 3.Mt+08 1.13t+09 1.125 06 0.0nt +00 7.lft*00 0.008 40 7.134*00 In H 0.0Jt+00 0.00t40 0.00t 40 0.00t+00 0.0Ft*U9 0.00t 4 0.00t +00 M 83 0.0m +00 0.00s+00 0.00t+00 0.on 40 0.004+00 0.008+00 0.00t+00 MM 0.00040 0.0th+00 0.004+00 0.004+00 0.0*It +00 0.00t+00 0.00t+00 se 83 0.0W+00 0.00t +00 0.00t +00 0.00t+00 0.00f+00 0.00t+00 0.ON +00
- 8 14 0.00t+00 4.57t+08 2.27t+0B 0.00t+00 0.00E*00 0.00E+00 9.60t*07
- 94 00 0.00t+00 0.00t+00 0.00s+00 0.00s+00 0.00t+00 0.00t @ 0.0040
..................................................................o ............
ko 99 0.00t+00 0.00E *00 0.00E+00 0.00t+00 0.000+00 0.00t*00 0.30 +00 la.09 3.02t44 0.00t+00 8.H4+96 0.00t+00 0.00t*00 0.00t+00 6.kI47 na 90 1.244+10 0.0M+00 3.05449 0.00E+00 0.00t40 0.out+00 3.$9t+0s 3e 91 1.522 10 0.00t+00 6.168 12 0.00t*00 0.00t+00 0.00840 7.236 10 se.92 0.00E+00 0.00t+00 0.00040 0.00t+00 0.00t*00 0.00t+00 0.00t to T.90 1.00d*02 0.00E+00 2.08440 0.00t+00 0.00t*00 0.00t+00 1.14t+06 1 9ta 0.00t+00 0.00E*00 0.00t+03 0.00t+00 0.00t*00 0.00t.00 0.00t+00 1 91 1.134*06 0.00t+00 3.0M +04 0.00i(+00 0.00t+00 0.00t+00 6.ZM +04 1 92 0.00t+00 0.00240 0.00s+00 0.00s 40 0.00t 40 0.00t 40 0.00t40 Corwrslen f actere are in mits of owses seter. ares /yr per gl/sec for ett rucLtdee oncept e 3 telch le in mits of arse per WI/selt enter.
UNT-005-014 Revision 1 Attachment 6.8 (1 of 9) 148
e - &.-e a ++ * --.=m.. 4 4aAe.> -.- a 4a-- . - - - - . + . - . u a e - -~-.a4 h* _e ..- a_ m_4 au_a _paa MEAT PATHWAY DOSE I' ACTORS DUE TO RAD 10NUCL1 DES OTHER THAN N0DLC GASES, H j m Geotei amt a r De 3 :
- JCtlDi OPGAe 6058 Card ttlue tAff088 18980lD R IDkit LL*G &l.LLI
>>E tivtt 1.6:21
.W_.
v-91 4.6M .11 0.ttt @ 1.30s.13 0.00t+00 0.00t+00 0. tot +00 0.00t+00
- 1. m *09 1.4M.07 18 9% 1.8Pt+06 6.01t +M 4.071+05 0.00t+00 9.42t +M 29 9F
- .071 M 4.171 06 1.918.M 0.0 4 *00 6,34t @ 0,00E+03 1.298 00
........................................................................4..e..
1.rM 4 6 g?tgl 0.03t @ 1.2M +06 0.00t w 7.?M *09 we.95 2.30E *M 1,90s*06 0.00t*00 t .16445 0.00t+00 t.3?t+0S Mo.99 0.00t*00 1.00t +M tt 99u 4.458 71 1.!M 20 1.601 19 0.00t+00 1.918 19 E .1M . 21 7.444 18 fC.101 0.00640 0.00t 00 0.00t+00 0.00t+00 0.00t*'c 0.00t 4 0.006+00 au it) 1.054 4 0.0N +00 4.11t+07 0.00t *00 4.01t+u6 0.0N +00 1.rH + 10 au 105 S .7N .28 0.00t+00 2.20Eete 0.00t+00 7.644 27 0.00t+00 3.$11 25 DV 1M 2.80t*09 0 00t+00 3.Mt.04 0.00t+00 S.ot+09 0.00f*D.I 1.01t*11 A0 11(M 6.6M+06 6.1M *W 3.67t +M 0.03t 40 1.27t *07 0.00t+00 f.lft+09 TI.1D# 3.59t+08 1.30t + M 6.81t+07 1.0N+04 1.4M +09 0.00t*00 1.4M +09 1I.177W i.139609 3.998+08 1.3M 4 2.05E+06 4.7 M *09 0.00t+00 3,74t+09 78 177 2.1N.10 7. 2 11 4.594 1% 1.171 10 4.Mt.10 0. tot +00 1.671 00 f t.1PM 1.13849 6.!M *04 79t @ 3.90t +M 4.73t+09 0.00t+00 9.71t
- 09
.................+............., ..............................................
tt.179 0.00t +00 0.008 @ 0.00t +00 0.00t40 0.004+00 0.00t 40 0.00t+00 ft 131e 6.511 42 2.21t+02 1.Mt42 3.49t*02 2.Dt+03 0.91t+00 3.19t+04 H.131 0.00t+00 0.00E+00 0.0W +00 0.00t+00 0.00t 40 0.Dat.00 9.00t+00 18 132 1. m +06 9.10845 8.62s+0S 1.01t +M 8 M4+06 0.00E+00 6.34t +07 1 130 2.118 @ 6.22t @ 2.4H.M l.I7t.M 9.714 @ 0.00t +00 $.!H @
1 131 1.0Pv4F 1.Mt-07 8.00t+06 5.0M *09 2.6M 4 r 0.aut+00 4.0H 4 1 132 0.00t+00 0.00t*00 0.001 40 0.00t+00 0.00t+00 0.00t+00 0.00t+00 1 1D 3.6M.01 6.3M.01 1.Mt .01 9.34t+01 1.11t+00 0.00t+00 $.71141 letM 0.00t+00 0.00t+00 0.00t+00 0.00E*00 0.00t+00 0.00t+00 0.0nu+00 I.135 4.4M .17 1.168 16 6.28t.17 7.Mt.15 1.tM.16 0.00t+00 1.311 14 Cs.tk 6.54t+08 1.Mt +09 1.20t 49 0.00t+00 5.Mt*M 1.6M'*M 2.7+4 4F cs.136 1,21t+07 6.7M 47 3.6M*07 0.0N +00 2.45447 3.4M 4 5.41t @
Ct.137 8.72t+08 1.19t +09 F,litt+M o.00t+00 4.05t+08 1.3H 48 2.31t+0T Cs.08 0.00t*00 0.00t+00 0.00t90 0.00840 0.00t+00 0.out.00 0.00t ata SA.139 0.0at+00 0.008+00 0.00t+00 0.00t*00 0.00t+00 0.00t*00 0.00t+00 Carwerelen f actere are in unite of agee enter. ares /yr per gl/ses ter all smstidos esespt k.3 nelsh te in units of ersevy per gt/staalt enter.
UNT-005-014 Revision 1 Attachment 6.8 (2 of 9) 149
. _ . _ _ . _ ._ _ .. _ ._ .._ _ _ _ ... _ . _ _ -- . _ . _ _ _ _ _ - - ~._
MEAT PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN N011LE GASES, R. .
1 Afst G8:LF AfsAt i 3 Of 3 )
sur.t:0g gas test 00WVillica f actons tut 0010 LW1 tumG 41 441 Dont tivts f . Dest
{
SA.140 2.8 Pl +0F
- 61t+04 1.00t +M 0.00t+00 1.2M.M 2.nrt+M l.02t+0F 0.00t+00 0.0ct+00 0,00E+00 0.00t+00 0.00l+00 0.00t+00 0.00t+00 64 141 6A*142 0.00t+00 0.00s+00 0.00s+00 0.006*00 0.00t+00 0.00 +00 0.00 +00 3.118 02 1,87t=02 6.06t.03 0. cat +00 0.00t+00 0.00t+00 1.!?t+03 u 140
- LA.142 0.00t+00 0.00t+00 0.00t+00 0.00t 40 0.00t 40 0.00t+00 0.00t*00 (1 141 1.60t+06 0.10t+03 1.00f+03 0.00t*00 4.4tt+03 0.0(E 40 3.6M+0F (4 943 2.018 10 1.40t 41 1.Mt.03 0.00t+00 6.l M .03 0.00t 40 $.llt*02 cf.144 1.4e446 6.00t+05 7. flit.M 0.00t+00 3.61t+05 0.0nt.00 4.VM *08 M 143 2.10t +M 0.41t+03 1.06443 0.00t+00 4.05t+03 0.00s 00 0.1M +0?
Ps.144 0,008 +0LI 0.00E+00 0.000+00 0.00t+00 0.00t*00 0.00E+00 0.00t*00 7.0M 43 8.17t43 6. set +02 0,00t+00 4.70E 43 0.00t*03 3.9M+0F no.1&F W iff 2.075 02 .1.73t.02 6.Mt.03 0.00t+00 0.00t+00 0.00ty00 $.66t*00 se.231 6.5M42 6.42E41 3.54441 0.00t*00 2.000 +02 0.00t+00 1.32E4F t.amerslen f actere ore in ette of somre meter.oreWye per Wl/see for ett tastia) Datert 0 3 dish is in mits of areWyr per Wl/tnelt setet.
I
- +
UNT-005-014 Revision 1 At tachinent 6.8 (3 of 9) 150
_ ~ -- __ _ - - -. - _ . _- .. - - - - - - - _ - - _ _ .
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i
AGE Gass tits ( i far 3 )
(AtAs post tarvttila.s f atical aut(tSt poet tivtt 1. EDT 1879010 tt0st? LUWG Cl*Ltl e
p.3 0.0te.00 1.ht42 1.ht +02 1.ht et 1.Mt+02 1.Mt +0J 1.Mt+02
. c.16 2.06t+08 4.0ef+07 4.Mt+07 4.tel+07 4.0N +07 4.00t*07 6.06t+07 an.34 1.oet.03 1.0N 4*J3 1.ON.03 1.088 43 1.0N.03 1.06t.03 1.0H .03 p.32 3.93t+09 2.ut +08 1.lM*04 0.00t+00 0.0M +00 0.00t+00 3.31t +M ca.ll 0.00t+00 0.00t+00 f.6tt 43 3.13t+03 1.26t+03 0.05t*C3 9.67t*05 ew $4 0.00t+00 7.00t+06 1.392 06 0.00t+00 2.09t *M 0.00E+00 1.ut 47 ,
em44 0.00E+00 0.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t @
f8 55 2.3N 4 1.69848 1.ht 47 0.00t40 0.00t+00 1.0M +08 7.31f 47 7e 59 2.12f+08 4.958+08 1.91t+08 0.004 +00 0.0ce+00 1.SN
- 08 1.14+09 CD 54 0.0CE+00 i.411+07 3.24147 0.0x +00 0.00t*00 0.00 40 1.%t+08 CD.40 0.00t40 $.KM 47 1.31t+08 0.00400 0.00t+00 0.00t*00 7.60t+08 Cl.63 1.57t +10 1.07t+09 5.13t+08 0.00t+00 0.00t+00 0.00t+00 1.71148 Bl.6l 0.00E+00 0.00t+00 0.00t+00 0.00t+00 0.00t 40 0.00t+00 0.00t 40 tu 64 0.00t+00 2.218 07 1.06847 0.00t+00 5.60E 47 0.00t+00 1.7N.05 2m.65 2.$0t+08 8.6et+08 4.0H+08 '0.00t+00 S. Set +08 0.00t+00 3.6ae48 2n 69 0.00t+00 0.00t*00 0.00E*00 0.00t+C0 0.00t+00 0.00t+00 0.00t+00 M 83 0.00r 40 0.00t+00 0. cat +00 0.00t+00 0.00t+00 0.00E+00 0.004 40 08
- H 0.00t+00 0.00t+00 0.00E*00 0.00t40 0.00t+00 0.00t+00 0.00t+00 94 05 0.10t+00 0.00t+0C 0.00E+00 0.00t+00 0.00t+00 0.00t 40 0.00t 40 as.M 0.00t+00 6.07t *04 1.91t+08 0.00t+00 0.00t40 0.00t*00 6.02t+07 ~
0.00t+00 0.00t+00 0.00t*00 0. set *00 0.00t+00 0.00t+00 0.00E+00 09 88
+.......................... 4...................................................
80 09 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00t40 0.00t+0D 0.00f*00
.SR 09 2.SH+08 0.00E+00 7.19t+46 0.00t40 0.00t+00 0.00t+00 3.0M*07 8A.00 8.0$t49 0.00t+00 1.998 4 0.00t+00 0.00t+00 0.00t*00 2.26E+0C es.91 1.28t.10 0.00t+00 5. pet.12 0.00t+00 0.00t+00 0.00t+00 5.796 10 38 92 0.0C4+00 0.00E 40 0.00t+00 0.001 40 0.00t+00 0.00t+00 0.00t+00 t 90 9.0M +01 0.00t+00 2.444+00 0.008+00 0.005+00 0.00t+00 7.47145 Y.91st 0.00t+00 0.00E*60 0.00t40 0.00t+00 0.00t 40 0.00t+00 3.00t*00 1 91 9.54t+05 0.00t+00 2.54446 0.0cs+00 0.00t+00 0.0tt+00 3.91t+08 f.92 0.00t+00 0.00840 0.00t+00 0.00E 40 0.00t+00 0.00t+00 0.00t*00 Carwersion factors are in etts of se6re ester-sreWit per uct/sec for ELL ruellene sacept p.3 elch is in unite of areWyt per WCl/cthic meter.
UNT-005-014 Revision 1 Attachment 6.8 (4 of 9) 151
MEAT PATINAY DOST l' ACTORS DLT TO RADIONUCLIDES OTHER TilAN N0llLE GASES, R g A&E Ga p s litt t t ot 3 3
>xtibt ter.As cost Convtallta f actual te18010 t10sti tune Cl*LLt Imt Livte 1.tatt f 93 3.9et .12 0.00t @ 1.09t.13 0.00t+00 0.00t 40 0.00t*00 1.219 07 iA.f$ 1.50t+06 4.738+0$ 3.25445 0.008*te 6.954+0% 0.008+00 1.09t+09 19 97 1.721 01 3.418 4 1.17t .4 0.00t 40 S.171 06 0.00t+00 9.234 01 nFM 1.796 06 9.95845 1.441+0S 0.008+00 9.65t+05 0.00t+00 4.264+09 mo 99 0.00t +00 8.27t46 1.$ht +M 0.00t+00 1.89t*C$ 0.00t+00 1.46t+0%
t t.Mn 3.5?t.21 9.464 21 1.28t*19 0.00t*00 1.471 19 $.475 21 6.47t.14
- tt.101 0.000 00 0.00t+00 0.00t 40 0.00t+00'0.00t+00 0.00t+00 0.00t+00 W.103 8.57t47 0.00t+00 3.664+07 0.00t @ 3.02D04 0.00t*00 7.tM+09 4u.105 4.4M.28 0.flut +00 1.871 20 0.00t+00 6.09t 27 0.00t*00 3.908 21 W.106 1.421*09 0.00t+00 2.97t +08 0.00t @ 4.llt+09 0.00t+00 1.1M*11 A4 110n $ 0M+06 4.79t +06 2.91t *M 0.00t+00 9.1M+06 0.00t+00 1.34t +09 ft.1254 3.0M+08 1.0M *06 4.0$t47 8.47t+07 0.Ont+00 0.00t*0) 8.ht+0e Yt.127N 9.41948 3.344+08 1 .121 @ 2.241+08 3.528+09 0.00t+00 2.35f+09 ft.177 1.005 10 6.388 11 3.BN.11 1.24 10 7.29t.10 0.00t 00 1.3M.08 f t .129u 9.50t *06 3.tu+08 1.59t+44 3.07t+08 3.971*09 0.00f+00 3.17t+09 It.1M 0.0lt +00 0.00t+00 0.00t+00 0.00t 40 0.00t+00 0.00t+00 0.00t*00 fI.131m 3.7M +02 1.not+c2 1.lat+02 2.718 out 1.tet+03 0.00E+00 1.4St+M 11 131 0.80t40 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.000+00
............. 4.................................................................
Ii*132 1.1M @ 7.3M *05 6.925+05 7.?M 45 7.ME +M 0.00t @ f.33t+07 1 130 1.7M.M 4.91EW 1.9EM 4.00t.04 7.5M 4 0.00t+00 3.TM.06 '
1 131 8.92t+06 1.2M 47 6.71G+06 3.6H +09 2.1M +0F 0.00t+00 2.47t+06 1 132 0.00t+00 0.tWE40 0.tnI40 0.00f 40 0.tet40 0.00t 40 0.00t 40 1 133 3.eH.01 1.1st.01 l. Sat.01 7.2M41 9.09t.01 0.00t+00 3.92E.01 1 134 0.00t*00 0.00t+00 0.00f*00 0.00t @ 0.00t+00 0.00t*00 0.00t+00 1 131 3.60t.17 ?.271 1T 3.ut.17 1.9M.15 14M u 0.00t+00 1.0M.16 Cs.134 S.23t+08 1.23t+09 1.71t+08 0. cat +00 3. tit +08 1.49t*08 1.13t47 C5 13e 9.40t+06 3.70t+07 2.4at47 0.0tt+00 2.01847 3.17t+M 2.9et+06 ca.137 7.2M*08 9.LM+00 3. Set *u8 0.00t+co 3.24t.08 1.771+08 1.37t+07 c8*134 0.0Jt+00 0.03t+00 0.00t+00 0.00t+00 0.1% M 0.00E*00 0.00t+C0 BA 1)# 0.00t+00 0.0Ce+00 0.00t+00 0.00t+00 0.61 4 0.00E40 0.00f+00 es nien v.n.n en in unite of n mte mem/ve w ucts e te ett auctneses sacept n.3 which is tri units of erss/yf w uct/cels smeter.
UNT-005-014 Revision 1 Attachment 6.8 (5 caf 9) 152
MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCI.lDES OTl[ER TilAN NOBII GASES, R .
1 AGI LA0tet fttu ( ) of 3 3 wJCLlDE tsua 00st tarvtalita f aticas ,
tout Livta 1.eT V tuttotD tt0mit tuuG Ct.LLt M
- 140 2.3M+07 2.91t *M 1.llt +M 0.00t*00 9.8Pl+03 1.ht+M 3.H4*07 M.tAl 0.00t+00 0.00t @ C .00t @ 0.00t+00 0. M +00 0.00t+00 0.00t*00 M.142 0.00t+00 0.00t
- 00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 LA.isc 3.05t.02 * *0t.02 3.998 03 0.00E+00 0.00t*00 0.pnt+00 8.61t+C2 LA.142 0.00t+00 0.00t+00 0.00t+00 0.00t @ 0.00t+00 0.00t+00 0.00t +00 ,
Cf*161 1.iM m 7.87t+03 9.Mt+02 0.00t et4 3.71t+01 0.00t+ea 2.Mt+07 ft.1&1 1.49t.02 1.234 41 1.371 03 0.00t+00 5.511 01 0.006 00 3.6et+02 cf.14 1.Z3t +M l .0st +M 6.60t +M 0.00t+00 3.Mt+C1 0.00t +00 3.0M+M Pt.143 1.7M +M 7.Mt+t!1 8.73842 0.00t+00 4.0M +03 0.00t+00 5.00t+07 Pe.tu ti.00t*00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+M 0.00t+00 e.147 4.ZM+03 6.77t+03 6.0N 42 0,00t+00 3.9W+03 0,00t*00 2.ut +07
. W.187 1.TM ut 1.41E.J2 4.958 03 0.00:40 0.00t+00 0.00t+m 3.m+00 8.4H +M up.Z39 S.7Dt+02 5.3at41 2.99t41 0.0La+00 1.64+02 0.00t +M Carwortlen f acters are in W11ts of somre outer.oreWyt per di/sec for ell ~ '
tarttees emcept N.J eith it in unite of areWyr per WCt/s*(a unter.
I r
i i
- UNT-005-014 Revision 1 Attachment 6.8 (6 of 9)^
153
. . - . - - ._ - - _. - -. _ -- . - . _ - ~ _ - - - - . _ - . . _ _ -
l I
MEAT PATHWAY DOSE TACTORS Dl!E TO RADIONUCLIDES i I
OTHER THAN NOBLE GASES, R.
1 AM f.A*Uh (site i 1 of 3 )
auttIbtI at.Am tat cowvteitou u.ctOns trTeotD tibuti LLasG Gl LLI post Livil 1.Wt s3 0.00t+00 2.34t+02 2.Mt +t.2 2.kt+02 3.M442 2.16: 4 2 2.ht+0!
C 16 3.83t+08 7.671 +( 7 7.671+07 f.671+07 7.67147 7.675 +0F F.67t+0F mA.24 1. Tit-03 1.778 02 1.728 03 1.T28 03 1.72143 1.77t 43 1.nt 03 P 32 7.42t 49 3.671+0s 2.tM+06 0.00t+00 0.00t+00 0.006*00 2.0$t+06 Co.ll 0.00l*00 0.00t+00 8.79ter3 4.dt+03 1.33843 8.911 43 6.6M +CS 8ee $4 9.M 40 8.018 46 2.13t 46 0.M40 2.258+06 0.00t+00 6.T?t 46 l ................................................................................ 0. M +00 l tw Se 0.03t +00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 ft $5 6.37t+0e 2.62t+08 7.11t+07 0.00t+00 0. M +00 1.37t+08 6.49t 47 Ft49 3.76t<06 6.09t+06 3.034+08 0.0m*00 0.txt +00 f.Trl+08 6.Mt+os CD 58 * - J+00 1.kt+07 1.02147 0.00t40 ' 0.00140 0.00t+00 9.SN 4T +
CD 60 0,00t+00 6.nt+07 2.0&t 48 0.0tt*00 0.00t40 0.00t+00 3.ki+08 al.63 2.91t+10 1.SM 49 1.02f 49 0.00t+03 0.00t+00 0.00t+00 1.0M +0C al.65 0.00t+00 0.00t+00 0.ttd 40 0.00t40 0.03F 40 0.00t+00 0.00t*00 CU 64 0.00t+00 2.971 07 1.00t.0? 0.00t @ 7.19t CT 0.00t 40 f .4W .05 3.75t+00 1.00t+09 6.22f +M 0.00t+00 6.30t+08 0.00t+00 1.TM 48
' 2n 65 7s 69 0,00t 40 0.00t*00 0.00t+00 0.00E*40 0.00t+00 0.00E+03 0.00t+00
. N 83 0,00s+00 0.00t+00 0.00t+00 0.000 +00 0.00t+00 0.00t40 0.00s+00 Mak 0.00t+00 0.00t+00 0.00t+00 0.00t 40 0.00t*00 0.00t+00 0.00t+00 DA 05 0.00f+00 0.0t4 +00 0.00t 40 0.00E*00 0.00t+00 0.0ct+00 0.00t+00 l
ka M 0.00t+00 $.TFt 4 3.SH +46 0.00140 0.00t+00 0.00t+00 3.F1t+07 H 08 0.00t+00 0.00t+00 0.00E+00 0.80t+00 0 0ut+00 0.00t*00 0.0H+00 as 00 0.00s+00 0.00t+00 0.00E+00 0.008+00 0.008 +00 0.00t+00 0.00t 40 f 3t 09 6.82f+08 0.00t+00 1.30f +07 0.00t*00 0.00f+00 0.00t+00 1.87547 M 00 1.Mt*10 0.00t+00 2.644+09 0.00t.00 0.00t 40 0.00t+00 1.40f+08 58 91 2.608 10 0.63t+00 9.0H .12 0.00t+00 0.00t+00 6.00t40 S.29t.10 se.92 0,00540 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t 40 0.00t 40 t 99 1.T1842 0.00f*00 6.99t+00 0.00t40 0.00t*00 0.00f*00 6.est+05 v.tta 0.00f+00 0.00t+00 0.Wat+00 0.00t+00 0.00t+00 0.0tt40 0.00t+00 I. 7 91 1.0Ct44 0.00t+00 6.82E+06 0.00t+00 0. hot +00 0.00f+00 2.40t+00 t.,2 0.00f400 0.0ct+eo 0.00t+00 0.00t+00 0.0m+00 0.p00 0.0M +00 l
cen..nien teet.rs we in ette of een meter.or /yr p c eu e tw ett
. matless tactpt 9 3 tAlth is in mits of area /yf pef dl/C@(C meter.
UNT-005-014 Revision ) Attachment 6.8 (7 of 9) 154
HEAT PAT}NAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R.
1 608 082)P CulLD ( 2 08 3 )
MJCLIDE5 08GAN 004f CM VVt$1(m iAC1088 tout Livtt f.KtY tettolD tiputy Lung Gl LLI f.t3 7.64t.12 J.00t+00 2.06t.13 0.00f+00 0.0(4+00 0. tot.00 1.118 07 la.95 2.6M +M ).85t+05 l.21t+D5 0.00t+00 8.38t+05 0.00t+00 6.11t
- 24 97 3.218 05 4.6H .06 2.7H.06 0.0 0 00 6.65t M 0.00f+00 7.021 01 es.95 3.106 4 1.21646 8.62t+05 0.00E+00 1.11t +M 0.00t+00 2.2M
- 09 no.99 0.00t+00 1.1H +f) 2.44t+04 0.00L*00 2.46t*05 0.00t+00 9.51t + 04 tC 99m 6.2tt .21 1.221 20 2.010 19 0.00f*00 1.UI.19 6.178 21 4.91t.16 tt.101 0.008 4 0.006 @ 0.006 @ 0.006+00 0.00C+00 0.00t*00 0.out +00 RV.103 1.1$1+0p 0.0 @ 00 1.9M
- 07 0.00t 40 3.90t+05 0.00f+00 4.01t+0a 2u.105 9.021 28 0.00t+00 3.271 28 0.00t+00 7.9M.7f 0. M +00 1.8vt.25
. .............................................................................. p 29 1 % 4.64t+09 0.00t+00 5.56t48 0.00t+00 5.99t aM 0.00T+00 6.V0t+10 60 110N 8.39t +M 5.67t +M 4.53e +M 0.00t @ 1.06t 47 0.00t+00 6.76t+06 14 122 S.69t+08 1.54t*01 7.19t 47 1.vit +06 0.0]t+00 0. tot +00 5.49t+06 l it.12?u 1.77t+09 4.78t+06 2.11146 4.244 @ 6 S.0M+M 0.00t+00 1.64t+09 11 127 3.39t.10 9.13t.11 7.2M 11 2.346 10 9.638 11 0.0Cd+00 1.321.M ft.129H 1.79t+09 5.00t+08 2.78t*08 5.7Ft+06 S.2M+09 0.00t+00 2.18t+09 1t*129 0.00t40 0. N +00 0.00R+00 0.00t+00 0.00t+00 0. tot +90 0.00t+00 ft.131n 7.00f+02 2.42t*62 2.5M+02 4.94t+02 2.Mt+03 0.00t*00 9.8Jt+03 0.00t+00 0.00t+00 0.00t+40 0.00t+00 0.00t40 0.00E+00 0.00t +00
' 'TE.131 71 132 2.122+M 9.18t*05 1.1M46 1.37t+06 8.711 4 0.00t+00 9.4H +M l.130 3.Mie 6.13t.M 3.1M.06 6.764 04 9.171.M 0.00t+00 2.875 4 i
1 131 1.6M +07 1.6M47 9.4M+M 5.50s+09 2.73847 0.00t+00 1.486+06 l*132 0.03240 0.00t40 0. W 00 0.01b00 0.00E*00 0.00t+00 0.00tt00 1 133 5.671 01 7.02t.01 2.6M.01 1.30s+02 1.17 faco 0.00t+00 2.83t-01 l*134 0.00t+00 0.00t+00 0.00t40 0.00t+00 0.00t 40 0.00t+00 0.00t+00 1*135 4.521 17 1.175 16 5.$M.17 1.Mt.14 1. Pot.16 0.00t+00 8.96t.17 Ct.1M 9.22t 48 1.51t+09 3.19t +06 0.00t 40 6.69e 06 1. W oe 8.1M 4 C,1M 1.62t+07 4.5M+0? 2.8At+07 0.00t+00 2.37t47 3.54f+M 1.5N +06 C8 137 1.13t+09 1.2ht 49 1.SaE+08 0.00E40 4.1M +06 1.50t+04 7.99t+06 Cs.138 0.00t+00 0.0K +00 0.00t*00 0.00s+ M 0.00s+00 0.00t 40 0. mat +00 SA.139 0.00t+00 0.00t+00 0.0CE+00 0.00t+00 0.008 40 0.00t+00 0.00t 40 Comeston f actors are m mits of somre suter.oren/yr per dt/s.se for ett nucthtes except u.3 Witch is in mits of areW1T per dt/cWie seter.
l UNT-005-014 Revision 1 Attactunent 6.8 (8 of 9) l 155 -
I J
l MEAT PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES I OTHER THAN NOBLE GASES, R.
2 i
4 Act saatri (*l2 ( 3 of 3 ) ,
muttibil Cor.As Mit Corytelica f atiml a
a DOMt Litti 1.WT fuit0!D tibet f tuht 01.LLI 5
44*140 4.36t*07 3.ht
- 04 2.We+06 0.00t +N 1.25t*04 2.29f*04 2.27t*07 6A.141 0.00t*00 0.00t*00 0. tot *00 0.00t 00 0.00t+00 0.00t*00 0.00t*00 SA let 0.00t*00 0. 03t
- 00 0.00t @ 0.000+b0 0.00t+00 0.00t+00 0.004*00 LA.140 S'.lM 02 1.951 02 6,0st 03 0.00D 00 0.00f*00 0.00E*00 5.44(*02 LA 142 0.00t+00 6.M4 +0h 0.00t+00 0.00t+00 0.00t*00 0.00t*00 0.00t+00 CE*141 2.22t+04 1.11844 1.kl+03 0,00t+00 4.aM *04 0.00t+00 1.14b0f Ct.i43 3.171 02 1.T2t+01 2.49t 03 0.00t*00 7.211 41 0.00t @ 2.$2t*02 .
ti 144 2.3?t+06 T.2M *05 1.24t*05 0.W4 % 4.02605 0.00t*00 1.0M*08 Pt.143 3.34t*04 1.00t+04 1.Ma*03 0.00E+00 S.43t+03 0.00t+00 3.MA*07
+
Pe*144 0 unt+00 0.00t @ 0.Wi +00 0.00t*00 0.00t+C9 0.00t +00 0.00t+00 MD 147 1.17t+M 9.47t+03 7.3M+02 0.00t*00 5,15d+03 0.00t+00 1.m+c7 '
, W 187 3.218 02 1.90t 02 8.5M Oi 0.00F +00 0.00t+00 0.00t*00 2.47t*00 W 237 1.07t+03 7.71t+01 S.42f+01 0.00t*00 2.23d+02 0.00E+00 5.70t+06 Catwersten f at. tere are in intte of somre seter erodyr per Wl/sec for ett $
ts.clidee emusrt e 3 editch le in mits of area /yr per di/cels meter.
4 P
I t
1.
l l
l l
UNT-005-014 Revision 1 Attactusent 6.8 (9 of 9)
I 156 i=
- - - _ _ _ - _ _ _ _ _ _ _ _ - - _ _ _ _ . - - . _ . . - ~ . . , . - , , - , , - . , . . _ - _ _ . , , , , _ , , -
LE/WY VEGETABLE PATWAY DOSE FACTORS DUE TO l RADIONUCLIDES OTilER Tl!AN NOBLE CASES, R.
1 AGt (ALP At%f C 108 3 1 l
. l wettot ost.u cost corvtorom #4ctort 1,tTt favs010 tit.att tuuG Gl.tti sakt t avle W.3 0.00t @ 2.2M *03 2.2 Met! 2.2M *01 2.24t+03 2 rM+03 2.26t *03 C.14 2.?St W 4.15t47 4.15t*07 4.55147 4.15t+07 4.55407 4.S$t47 p.24 2,Ht + M 2.69t+M 2.69t+05 2.6M+M 2.69t 41 2.69145 2.69E *M P 32 1.4M 09 0.71447 5.434+07 0.00E*00 0.0M+00 0 00t @ 1.$ $t +06 (J .51 0,00t40 0.00t*00 4.ut W 2.76t
- 1.02t h 6.1M *04 1.t?t=07 k 54 0.00t+00 3.13t+M 5.971+07 0.00t 40 9.31147 0.0M +00 9.59t @
2.0.+1* 01 0.00t @ $,07t+02 mm.56 0.0rt + 00 1.59t +0i - 2.82t+00 0.00t 40 fl.S$ 2.1M+tt 1.6448 3.3M+07 0.00t*00 0.00f @ 8.0M47 8.11t+07 88 99 1.26t+D8 2.96t+08 1.14t+00 0.00t40 0.00t+00 8.26t +07 5.8M 42 20 58 0.00d+00 3.071+07 6.39t+07 0.0M +00 0.00t+00 0.00t+00 6.2M +06 CD 60 0.00t+00 1.671*06 3.6M *06 0.00t+b0 0.00t+00 0.00t+00 3.14t+09 al.63 1.04t*10 f.21846 3.49t+06 0.00t+00 0.00t @ 0.00t+00 1.50t+08
- 0. W *00 0.00F+00 0.00E M 2.03g 42
- s!.6% 6.15441 7.99t 40 3.64t+00 C& 64 0.00t+00 9.2ct+c3 4.321*03 0.00+00 2.32t+04 0.04 40 f.64t+0$
i 2n45 3.17t @ 1.Dit+09 4.SM+06 0.00t+00 6.75t+06 0.00t *00 6.3M 46
.. ......... 4...................................................+..............
- 1. Sat @
22 69 5.49t @ 1.05t.05 7.311 07 0.00F00 6.83t.M 0.00t+00 sa 13 0.00t+00 0.Due+00 3.11t*00 0.00t40 0.0M+00 0.00t+00 6.471+00 ga.84 0.00t+00 0.00t*00 2.44t.11 0.00E+00 0.00t+00 0.00t+00 1.941 16 De.05 0.00t+00 0.00t+00 0. M +00 0.00t40 0.001 40 0.00s+00 0.out @
88 86 0.00t+M 2.19t+M 1.02t+06 0.00t+00 0.0((+00 0.00t+00 4.33t+07 ks 88 0.00E+00 3.43t.22 1.6JE+22 0.00l!*00 0.00t+00 0.00t+00 4.748 33 I
.............. ............+....................................................
l as 99 0.00t 40 3.99t.26 2.734 26 0.00t40 0.00t+00 0.00t40 0.00t*00 te 89 9.97t+09 0.006 00 2.0M+08 0.00t+00 0.00r40 0.00t+00 1.60t+09 48 90 6.Mt +11 0.00(+00 1.48t+11 0.00t+00 C.00it @ 0.00t+00 1.75d+10
.......................................................+.............
pa.91 3.0$t+0$ 0.00t+00 1.ZM+04 0.00t+00 0.00t+00 0.04t+00 1.45t46 4.J7t+02 0.0tt 40 1.854*01 0. tot +00 0.00t*00 0.00t+00 s.45t+c3 ss.F2 Y40 1.3M +04 0.00t+00 3.571 42 0.006+00 0.03E+00 0.00t40 1.41:+0s v.9tm 5.221-09 0. tnt +00 2.024 10 0.00t+00 0.00r,+ 00 0.00t+00 1.5N.08 f.91 3.11544 0.0t4+00 1.37t45 . 0.00E+0c 0.00t40 0.00t+00 2.tu+09
! 7 62 9.131 01 0.00t +00 2. tat.02 0.00640 L.00t40 0. N +00 1.60r+04 terwerste tectors are in mite of ersJars ester.uren/yr per WCt/sec fee ett fixttses euept s 3 iAtem to in mite et esserr per gt/aetc ester.
UNT-005-0M Revision.1 Att.achment. 6.9 (1 of 9) 157
LEATY VEGETABLE PATHVAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R.
2 i
Et ha5JPs A M T ( 2 Of 1 )
4 ctg 4a Dott CONVlallum E ACtott ,
auG104 1NYt0lp ElDuff LUW4 41441 Mht LIVit 1.60D7 1
7 93 1.7DE+02 0.00t+00 4.Mt+00 0. tot +00 0.008+00 0.004+00 n.34t 4 28 95 1.171+06 3.T7t+05 2.$5t45 0.00t 40 l,91t+05 0.00t+00 1.19t*09 3.3M 42 6.81841 1.111 01 0.00t+co 1.0M+02 0.00t+00 2.11t+07 28 97 W9 95 1.42t+05 7.9?t+04 4.24t+04 0.00t+00 7.83t+04 0.00t+00 4.81t+08 e 99 0.00f+00 6.15t*06 ' 1.1MW 0.00t+00 1.39t 47 0.00t+00 1.45t 47 .
fC+99M 3. tdt +00 8.7M40 1.12142 0.00t 40 1.3M*02 4.30t*00 S.19 +03 i TC.101 8.2H.31 1.18t.30 1.iM.29 0.00t*00 2.1M.29 6.05t.31 0.00t+00 W.103 4,77t+06 0.00t+00 2.06t+06 0.00t 4 0 1.821 07 0.00t+00 5.17t+00 av.105 1.39t+01 0.00t 40 2.13f 41 0.00t+00 f .%t* 02 0.00t*00 3.29t 46 ,
l W.106 1.9M *08 0.00t do 2.44t 47 0.00t+00 3.72t48 0.008 40 1.25t+10 A4 110M i.05t+07 9.75t+06 5.79t*06 0.00t+00 1.92t+07 0.00t+00 3.9st.09 l
. TI.125# 9.664+07 3.508+07 1.29647 2.90t 47 3.9M+08 0.00k+00 3.6M
- 08 4 ................................................................................
it.127N 3.49t+0B 1.2H +08 4.N447 8.9N+07 1.LN49 0.00t 40 1.17t 49 f ft.127 5.66t*03 2.0M43 1.tN*03 4.19t+03 2.314 4 0.00t+00 4.4M45 i
f t.12W 2.11t48 9.38t*07 3.9K+07 8.6M+07 1.05E+09 0.00t+00 1.27A49 78 129 7.62t.04 2.875 04 1.8M .04 5.058. k 5.808 03 0.00E+00 5.75t.04.
ff.131n 9.12t 41 4.46t+05 3.7N +05 7.0M+05 4.lM+06 0.00E+00 4.4M47 11 131 1.50t.15 6.2M 16 4.744 16 1.2M.15 6.5M.11 0.00t+30 2.1M.16 l
7I.132 4.30E+M 2.7M+# .2.61t+M 3.0M+06 2.60t47 0.00t+00 1.32t*08 3.93t6c5 1. 46 t+M 4'.5M45 9.81t47 1.81446 - 0.tvit+00 9. M +05
! 3 130 .
1*131 8.08f47 1.14+48 4.62t47 3.79t+10 1,98t*06 0.00( 00 3.0M47 i
1 132 S.7M *01 .1.54t+02 S.30e 4 1 $.398+03 2.45t42 0.00E+00 2.MM1 l
(- 1 133 2.09t+06 3.63t46 1.116+06 5.33t OS 6.33t*06 0.00t+00 3.7.M + #
l ').134 9.6W.05 2.628 44 9.38105 6.ht45 4.175.k 0.00t+00 2.2W47 1 135 3.904 04 1.025 05 3.TM*04 6.75t+06 1.64t+05 0.0.W+00 1.1H+05 C5 1M 4.6M +09 1.11t+10 9.0er*09 0.00t+00 3.94 +09 1.14 49 1.9M+48 Cs.136 4.2M +07 1.6at+48 1.21t+08 0.00t+40 9.3at 67 1.29547 1.91t+07
. C5 137 6.ME*09 8.70E*09 5.70t*09 0.00t+00 2.9H+p9 9.81t+08 .1.68t+08 C4 138 3.918 11 7.TM.11 3.8M 11 0.00t+00 !.68t.11 5.41f.12:3.30t.16 34 139 2.N4 02 2.0*0 05 4.3M.04 0.00t+00 1.90t.05 1.1 H.05-5.0M 02 Cwwerulen lectors are in mits of were arter.oreatyr per W1/sec fee att rmalless escept N.3 iAle is in mits et premfyt twe Wl/ celt ester.
i UNT-005-014 Revis4on 1 Attactuaent 6.9 (2 of 9) ,
158 ,
.I
- L ~ . _ . . - . . . . _ . _ _ . _ _ . . . - . - - . , . . . r . , . .m , , - . _ ,-._.,_.-,,-.M.r c-mm , #,y_._ y
l LEAFY VEGETABLE PATlIWAY DOSE FACTORS DUE TO RAD 10NUCLlDES OTi[ER TilAN N0llLE GASES, it ACA C&mp t ANAT ( 3 Of 3 )
mJCLlt'l (af.As tott ComWtiltu f AC1084 best Livtt 1.bTT tettC.+ IIDuff LUuG ClaLL1 SA i&O 1.28t+06 1.61t*05 8.42t+06 0.00t+00 5.4M W 9.24t
- 2.6$t+08 RA 141 1.151 21 8.714 25 3.995 23 0.00t+00 8.tM 25 4.ht . 25 9.418 3%
6A 142 0.0(4*00 0.00t+00 0.00t @ 0.rK4 +00 0.00t+00 0.00t*00 0.00t+00 L4 160 1.96t*D1 9.97t+02 2.Of*02 0.00t+00 0.00t*00 0.00t+00 7.32t+07 LA.142 2.C21. M 9.19t 05 2.294 05 0.00t*00 0.00t*00 0.00t+00 6.711 01
- C8 161 1.97t+05 1.31t+05 1.51t +M 0.00t*00 6.19t+ M 0.00t+00 S.10t+08 Ct.143 9,96t*02 F.3N 05 t.1H +01 0.00t+00 3.25t+02 0.0C4 +00 2.7M*07 ct 144 3.29t+07 1.Saa+07 1.771* M 0.00t*00 t,1H+M 0.00t*00 t,til+10 Pt.143 6.244 +M W.51t+06 3.114 +03 0.00t*D0 1.45t +M 0.00t400 2.76t +06 Pt.164 3.09t.26 1.2M.26 1.5?t.27 0.00t+00 7.25t 27 0.00t+00 4.64t.13 ao.147 3.11t +M 3.tSt
- 2.31t+C3 0.00t*00 2.25t
- 0.00t*00 1.05t*ce w il? 3.80t+04 3.18t
- 1.11t
- 0.00t+00 0.00t*00 0.00t+00 1.04t+07 kP 239 9.54t+04 9.3M +03 S.17t+03 0. W *C0 2.91t+06 0.0;*+00 1.92t+09 Cervrerstm f actors are in mits of emere mete. stamhy pr u:l/sec for att axtlers eatept h 3 elch is in mite ti eWp per u:t/ ethic poter.
UNT-005-014 Revision 1 Attachment 6.9 (3 of 9) 159
)
IIATY VEGETAlil1 PATINAY DOSE FACTORS DUE '!O RADIONUCLIDES OTHER THAN N0!!LE GASES, R,1 Ar.t ta0LP: ttis t i of 3 )
WutL101 ter.Aa cost couvtastcn paticas 1stt010 t it,sti Luka st qtt 6*t Livtt t.Sapt e3 0.00t+00 2.$9t*03 2.59t+03 2.59t+03 2.$9t+03 2.$9s+03 2.19t*03
. c.14 3.69t *06 7.36t+07 7.36t+0? 7.38t+07 7.ut+07 7.38t+07 7.18t +07 ma.24 2.39 +0S 2.39t+0$ 2.39t*0$ 2.391+05 2.395+05 2.391 4 2.39%+05 P 32 1.611+09 9.97 +07 6.248+07 0.00t+00 0.0%+00 0.00s*00 1.35t+08 1.04t+07 c3 51 0.0/t*00 0.00t + 00 6.17t+04 3.4M+M 1.35t+04 8.81t +M ew.$4 0.00t+00 4.$41+08 9.01t+07 0.00t+00 1.36t+08 0.004 @ 9.32t + 08 mu 16 0.00t*00 1.4M+01 2.55t*00 0.00t*00 1.81t+01 0.00t+00 9.44t +(,2 ft 55 3.264 4 2.31t+08 5.39t
- 07 0.00t*00 0.00t +00 1.47t*08 1.0x+08 ft.19 1.?vt+08 4.19t+08 1.62t+08 0.00t+00 0.00t+00 1.3Zt+08 9.90t.p 0> $8 0.00t+00 6.34t$ 07 1.00t+08 0.00t+00 0.0M+00 0.00t+00 6.01t 06 to 60 0.00t+00 2.49t+08 5.60t*08 0.00t*00 0.00t+00 0.00t+00 3.24t+09 81 63 1.61t+10 1.1M+09 S.4$t e 0.00t+00 0.00t*00 0.00t+00 1.81t @
- 1 65 $.72t+01 7.31t+00 3.33t+00 0.00t+00 0.00t+00 0.00t*00 3.97t+02 Cu 64 0.00t+00 6.34t+03 3.92t+03 0.00t+00 2.11t+04, 0.00E+00 6.47t+05 tu 65 4.24t @ 1.47t+09 6.87t+08 0.00t+00 9.42t@ 0.00t+00 6.ZM 08 Is.69 $.158 06 9.80t e 6.662 07 0.00E+00 '4.411 06 0.00t+00 1.811 05 ER 83 0.00E+00 0.00t*00 2.918+00 0.000+00 0.004+00 0.00t+00 0.00E+00 ba 64 0.00t+01 0.WJt+00 2.258 11 0.00t+00 0.00t +00 0.00t+00 0,00t*00 Sa.8) 0.00t+00 0.00s+00 0.00t+00 0.00f+00 0.00t+00 0.00t+00 0.00t+00
- 8 % 0400t+0D 2.741*00 1.29t+08 0.0tt+00 0.00t+0c 0.00t+00 4.05t+07 88 88 0.00t+00 3.171 22 1.69t.22 0.00t+00 0.00t+00 0.00t+00 2.718 29 88 89 0.00t+00 L $0t 4 2.47t.26 0.00t*C0 0.00E+00 0.00t+00 5.3M 35
- 1. tot +09
. SR @ 1.51t+10 0.0CE+00 4.341+C6 0.00t+00 0.00t*00 0.00t+00 54 90 7.51t*11 0.00t+00 1.8H+11 0.00t+00 0.00E+0C 0.00t+00 2.11E*10
................................................+...... .. ...................... '
58 91 2.85t*05 0.00t+00 1.1M +N O.00t@ 0.00t+00 0.00t+00 1.29t @
Sk.92 3.971+02 0.00t+00 1.69t+01 0.0064 Amt+00 0.00s*00 1.016+N 1 90 1.24t+M 0.00f+00 3.35t+02 0.00t*00 0.00t+00 0.00t @ 1.02t 4 f.91st 4.664 @ 0.00t+00 1.tM.10 0.00E+00 0.00E+00 0.00t+00 2.29t.U7 1 91 7.64t+06 0.00f*00 2.10t+0$ 0.0M+00 0.00t+00 0.00t+00 3.21t+09 f.92 6.60t '1 0.00t+00 2.496-02 0.8't*00 0.00t+00 0.00t+00 2.34f+04 terwerstm f actors em in mite of emere seter.oren/yr me Wl/sec for att ructicles sacept a 3 6Alts le in unita of weavyt per uct/sett ester.
UNT-005-014 Revision 1 Attachment 6.9 (4 of 9) 160
f i
IIAIT VEGETAB11 PATilWAY DOSE FACTORS DUE TO RADIONUCLIDES OTl!ER TilAN NOBII GASES, R g I
48 680LP ttis t I 07 3 )
p.CLIDE tufa Dost tovettsl0m #Attoes tint t!vit f .k:01 taitolD t!batt ttaiG &l tti l
1*93 1.59t+02 0.00t+00 4.3M + 0C 0.00E+00 0.00t+0C 0.03t @ 4.6u .D6 26 95 1.72t +W 5.4 M *0f 3.73t*05 0.00t+00 7.968 45 0.000+uu 1.25t+09 28 97 3.128*02 6.1M 41 2.til41 0.03t +00 9.371+01 0.00s+00 1.67:+0?
W8 95 1.9?t*05 1.07t+05 5.87t +M 0.00t+00 1.03t+05 0.00t+00 4.5M+0e 80 99 0.00t+00 5.65t+06 .1, cat +06 0.00t*00 1. M *C7 0.00t+00 1.01t 47 ft 994 2.74t+00 7.63t+00 9.99t*01 0.00t+00 1.14t+02 4.266+00 5.01: 4 3 l ft 101 7.Ht 31 1.09t 30 1.071 29 0.00f+00 1.971 29 6.621 31 0.00t+00
' RV 103 6.82t+06 0.00t+03 2.9?t +06 0.00t+00 2.40t 47 0.00t +00 5.7Dt+08 a0 105 5.00t+01 0.00t+00 1.kf*01 0.00t*00 6.31642 0.00t @ 4.06t *M l ................................................................................
RV 106 2.342+0e 0.00t+00 3.90t*07 0.00t+00 5.97t+08 0.00t+00 1.6M*10 A4 11W 1.52t+07 1.43447 8.72f+M C.00t+00 2.74t*07 0.00t+0C 4.03 49
. ff*125m 1.648 0e 5.36t+07 1.9er47 4.14t+07 0.00t+00 0.00t+00 4.37t+0e tt irfu 5.518+0a 1.9M*0e 6.568+07 1.318+06 2.248+09 0.00s+00 1.371 +09 )
11 127 5.36t+03 1.99t+03 1.15t+C1 3.6at+03 2.1M *04 0.00t+00 6.12t+05 18 12*M 3.62:+0e 1.Mt+0e 5.7M +07 1.1?f+08 1.51t+09 0.00s @ 1.361+09 ff*179 7.141 M 2.6M M 1.59t M 5.10E M 3.ont.03 0.00t+00 3.90E.03 iI.131m 8.648+05 4.05t+05 3.3at*05 6.096+05 4.22 46 0.00t 40 3.25847 11 131 1.39t.15-5.7H 16 4.365 16 1.07t 15 6.1'* 15 0.00t+00 1.14t 16
- ft 132 3.91t+06 2.47t+M 2.3M+06 2.61t+06 2.37147 0.00t+00 7.kt+07 1 130 3.51t+05 1.01t+06 6.05t*05 8.20t+07 1.54t+06 0.00t+00 7. tot +05 1 131 7.69t47 1.0st+0e 5.?tt+07 3.164+10 1.85t+06 0.00t+00 2.1M+07
............................+...................................................
1 132 5.19t 41 1.3M+02 4. set +01 4. Set +03 2.14t 42 0.00t*00 5.92t+01 ,
1 133 1.96t+06 3.29t+M 1.00t+06 4.59t*CJ 5.76t+06 0.00t43 2.49t+M I 134 4.7M .05 2.315 04 8.31t 05 3.85t 03 3.65f*04 0.00t+00 3.058 M I 1 135 3.52E+04 9.07t+04 3.3M+04 5.83t*06 1.4M*05 0.00t+00 1.00t+05 C8 134 7.1M +09 1.67t+10 7.75t*09 0.00t+00 5.31t+t9 2.0M +09 2. cat +0e C5 136 4.37147 1.721+0e 1.1M +08 0.00t+00 9.373+07 1.&at47 1.3M+07 C4 13f 1.01t*10 1.35t+10 4.69849 0.00t+00 4.59t49 1.7Br+09 1.92t+0e CS 138 3.618 11 6.9M
- 11 3.47E 11 0.00t+00 5.12t 11 5.968 12 3.154 14 SA 139 2.69t*02 1.99t 05 7.EX 04 0.00t+00 1.78t*05 1.308 05 2.60f*01 Conversten factors are in mits of equare seter sromfrr P*r Wl/Dec for all tuclidee escept u 3 shich le in mits of aree/yt per dt/csbic meter.
UhT 005-014 Revision 1 Attachment 6.9 (5 of 9) 161
l i
LTAFY VEGETABLE PATl!VAY DOSE FACTORS DUF, TO f
RAI;10NUCLIDES OTifER THAN NOBLE GASES, H j i
l t
' AGE GACUP: 18th ( ) Of 3 )
I I
tutitbl (sf.Aa tott trsMillem f acit*l l
1.DTV 1pftelD EIDutt Lthe $1 441
>:st LlWt 3.4 160 1.3N *00 1.69t*05 8.90t*b6 0.M *.10 S.76t*04 1.14t*0$ !.13t
- 03 p.141 1.00E.21 0.061 fl 3.19t U 0.0M*00 7.4M . t$ l.$0t.Z$ t.79 terr p.162 0 00t+00 0.00t+00 0.00t+00 0.00t+00 0.00E*00 0.00f *00 4.00t.00
............. ..................................................+..............
La.140 1.011 03 8.let+02 2.36t+02 0.00t*00 0.0M+00 0.0M*p3 1.1M
- 0F LA.142 1.tSt 04 8.Dt .0$ t.0$t .13 0.00t*00 0.00t*00 0.00t+00 2.51t*00 t!.141 2.83t+05 1.99t*01 2.17t+04 0.00E *00 8.99t+N 0.00t+00 $ .60t eW ' i Ct .10 9.33t+02 6.79t*05 7.5tt*01 0.004 +00 3.Mt*02 0.00t+00 f.Mt*07 C1 164 5.27t*07 2.19t*07 2.831*M 0.00t+00 1.30l*07 0.00t*03 1.33t*l0 j Pt.143 7.00t*N 2.80t *M 3.49t*03 0.00t*00 1.63t+04 0.00t*03 2.3M+0a Pt.144 f.5M .26 1.18t te 1.47t*!? 0.00t+00 6.60E.27 0.00t+00 3.19f.29 ND.147 3.62t+N 3.ht+M 2.3M *03 0.00E+00 2.31t*04 0.00f*00 1.4?!+08 W 187 3.54t +M 2. tat *04 1.01t+06 0.00t*00 0.00t*00 0.00t+00 7.82+M me.ZM 1.60E+0S 1. lit +M t.38t(43 0.00t+00 4.74t+N 0.00t+00 2.43t+09 Carwersten f acters are in mits of equsre seter.oree6tyr per et/sec for alt ruslides sacept D 3 telch is in mits of eram/yr per ucl/csels meter.
f 1
I r
l l
I UNT-005-014 Revision 1 Attachment 6.9 (6 of 9) 162
1 LEAIT VEGETADLE PATWAY DOSE TACTORS DDE TO RAMONUCLIDES OTHER THAN NOBLE GASES, R r
AGE G8CLPt Cult 01 108 3 )
l NJCllttl ORLas tost tamvtelloh #Af10F8 l
6 Cat ilVtt f.Wr:1 trit 010 tibuti LUNG 81+t48 I
i i W3 0.00t @ 4.01t+03 4.011 43 4.01t 43 4.018*03 4.01t*03 4.01t+03
+
C 14 4.09t
- 1.70f+08 1.70f*00 1.70448 1. 706 +08 1.70t*06 1.7N W eA*P4 3.fM *M 3.fM
- 06 3.7M 4$ 3.fM +05 3.TM
- 05 3.7M*0$ 3.fM +0$
Pa32 3.3TI+09 1. Set +08 1.30t*06 0.00t+00 0.00t 40 0.00t+00 9.311+07 tt+11 0.00E+00 0.00t+0J 1.171 05 6,$0E * .& 1. 7N +04 1.19e+05 6.21t*06 ese 14 0.00t+00 6.658 08 1.T7t+C8 0.00L+00 1.06t 48 0.00t+00 $ .5N +08 *
.........................s......................................................
Mu 56 0.000 40 1.00t41 4.26840 0.00t
- 2.2M 41 0.00t40 2.728+03 ft 51 7.Mie 4.2St+08 1.32t+08 0.00t+00 0.00t*00 2.40t48 7.87t+07 ft 69 3.90t 46 6.4M 08 3.20:48 S.14 40 0.00l+00 1.0M 00 6.70t+08 CD $$ 0.Mt +00 6.44t+07 1. 9M +08 0.00t+00 0.00t+00 0. tot *00 3.76t+08 20*jo 0.00t*00 3.70t+08 1.12E 49 0.00t+00 0.00t*00 0.tME*00 2.10t+09 ul 63 3.95t+10 2.111*09 1.30E+09 0.00t+00 0.00t+00 0.00t+00 1.42t+08 01,65 1.0H42 9.59t+00 S.TM+00 0.00t 40 0.00t+00 0.00t+00 1.21t+03 MM 0.00t+30 1.10t +04 6.Mt*03 0.00t+00 2.Mt+04 0.00E*00 5.1N *0$
24 65 8.1M +08 2.1M.09 1.3M *09 0.001 00 1.34t+09 0.00t+00 1.00t+08
...................+.............................................................
2m.69 9.49t 4 1.3M4 1.2M 4 0.00t+00 8.32t
- 0.00t+00 8.6H .04 Se.03 0.00t 00 0.00t+00 S.375+00 0.00E40 0.00f+00 0.00640 0.00t+00 MM 0.00E+00 0.00E*00 3.02t 11 0.00E+00 0.00E*00 0.00t43 0.00t+00
....................................... ...................................+....
Sa 4 0.00t+00'O.00t40 0.00s*00 0.00t+00 0.tet+00 0.00s+00 0.0t000 H 06 0.00t+00 4.$N+0B 2.70t+48 0.00t+00 0.00t+00 0.00E*00 2.91t+0F
- M4 0.144 40 4.3 M 22 3.064 22 0.00t +00 0.00t+00 0.00E+00 2.1H 23 00 09 0.00t+00 4.618 4 4.198 4 0.uet+00 0.00t+00 0.00E+00 4.0M.28 l
> ta*09 3.60t+10 0.00t*00 1.0M +M 0.00t*00 0.00t+00 0.00E *00 1.Mt+M f te.90 1.248+12 0.00f 40 3.1M*11 0.00s+00 0.00t *'to U.00t+00 1.675+10 l
' N.91 $ 26t+05 0.00t+00 1.90t+04 0.00t+00 0.00t 43 0.00t+00 1.16t+06 te 92 ' 7.20t+02 0.00t+00 2.9N41 0.00E+00 0.00t+00 0.00E+00 1.30t+04 f.90 2.31t+06 0.00t40 6.1 D 02 0.00t+00 0.00t+00 0.00t*00 6.57t 47 t.91t.09 0.00E+00 3.248 10 0.00t+00 0.00t+00 6.00E40 1.764 4 f41a l
Y41 1.0M+07 0.00t+00 4.99t+0S 0.00t+00 0.00t*00 0.00E*00 2.60t+09 f.92 1.50E+00 0.00t+00 4.$M
- 02 0.00t+00 0.00E*00 0.00t+00 4.50t+04 f
Cammsten f actors are in mits of er.are metee.oren/yr per uC1/ pet for et(
i ewellese encept 2 3 nelsh is in mits of aren/yr per (Cl/ celt ester.
l UNT-005-014 Revision 1 Attachuent 6.9 (7 of 9)
L 163 I
i l
1 ISAFY VEGETABI.E PATHWAY DOSE FACTORS DUE 70 RADIONUCLICES OTHER THAN N0!!I.E GASES, H j i
4M t. nows talte t t 09 3 5 4
auctiDI8 ts(An 004 tratvttiiou f 4ttca6
- 1. set 1stt019 Elpett tuhG $1.tti Dcust Livts f.93 2.9M*02 0.00f*00 8 Mt*00 0.00t @ 0.00t+00 0.00t+00 4.3MW l 3.Ma *M 8.44t*05 7.llt +M 0.00t+00 1.21t+06 0.00t
- 4 tit +M l 28 95 28 91 S.70t
- 02 8.24t+01 4.Mt+01 0.00t *00 1.1M +0! 0.00t+00 1.25847 !
i 0.00t+00 1.50t *0$ l'.00t+00 2.96t+08 f
me 95 4.1M
- 0$ 1.6N*M 1,14t *M 80 99 0.00t*00 7.71t+06 1.91t+06 0.00t +00 1.6H47 0.00t+00 6.34t
- M '
1C.9W 4.71t+00 9.244 00 1.$M +0! 0.00t*00 1.34t*02 4.69E*00 $.26t*03
...........................................................+....................
18 101 1.411 00 1.4?t.30 1.sn .29 0.00t+06't.11f.If 7.78t.31 4.6M 40 1 49 103 1.134*P7 0.00t+00 l.9M*M 0.00t+00 3. Pet +07 0.0M +00 3.9M
- 08 l kV.105 9.1M+01 0.00t 00 3.32941 0.00t+00 8.05142 0.00t*00 $.9et +M
' 40 1 % 7,4St+08 0.00t*00 9.30t+07 0.00t+00 1.01t+09 0.00t*00 1.1M + 10 44 1 tom 3.21t+07 2.1M *07 1.7M*07 0.00t+00 4.Mt 47 0.00t*00 2.$Mm iI.1254 3.518+08 9.50447 4.675+07 9.kI+07 0.00t 40 0.0w +00 3.5M 40 18 127t1 1.325*09 3.5M +08 1.57t+08 3.16t+M 3.7M49 l'.00t*00 1.0M
- 09 Ik.12T 9.bH43 2.65t+03 2.11t+03 6.stt+03 2. pot +M 0.00te00 3.tif *05 ft.1294 B.41t+08 2.35t+08 1.310 08 2.71t+08 2.47t49 0.00t+00 1.0M49 11 129 1.3M 03 3.6*t .M 3.144 M 9.4M M 3.87t.03 0.00t+00 8.tM.02
?!*131# 1.544*M l.33t+05 S.64t+05 1.itt +M $ .1M +06 0.00t+00 2.1M+07 ft *1M 2.$75 15 7.RM .16 7.M,t.16 1.97t.15 7.7M.15 0.00t+00 1.3M 14 i- ................................................................................ v 18 132 7.00t+M 3.10t+06 3.74t+# 4. lit +M t. net 47 0.0nt+00 3.1M*07 f 0,1M+05 1.24t+06 6.41t+M 1.37t+0s 1.tM+06 0.00t+00 5.8N+05
- l 1 130 l*131 1.Ot+08 1.444+0B 8.17t47 4.7M+10 2.SW+08 0.00E+00 1.fM47 l l.112 9.22t+0! 1.40t+0! 7.79441 7.84 43 2.99t42 0.00t+00 1.9R*02 8 133 3.5M4 4.3?t+M 1.6M +06 8.11t+# 7.20f 4 0.00e+00 1.fet+06
[
1 134 1.5M.M t.get M 1,32E .M 6.628 4 4.44t.M 0.00t+00 1.918.M
................................................................................ s 1 135 4.2M +04 1.1M+0S 5.3M44 9.tn+46 1.73445 0.00840 8.lat+M C3 134 1.60t+10 2.6M *10 S.SSt 41 0.eut+00 s.1M49 2.9M49 1.42E+08 l
cs.136 8.24t+07 2.3M+04 ' 1.4it+04 0.00t+00 1.21t+08 1.90t+07 7.9M *06 l ................................................................................
Cs.137 2.39t*10 2.29t*10 3.3et+09 0.00t+00 7.4M+09 2.6st 09 1.4Me es.1M 6.57t.11 9.1M.11 5.79t*11 0.00t+00 6.4M.11 6.91t.12 4.Itt.11 M l>9 4.9't.02 2.Mt.05 1.444 03 0.00t+00 2.31E 05 1.5M.05 2.tM+00 Carwereien f actors are in mitt of meance ester.wsWye per df/eee for all raillaes oncept u.3 elsh le in mits of eroWyr per Wl/sels ester.
l I UNT-005-014 Revision I Attachment 6.9 (8 of 9) 164
- ~ ~_ _ _ _ ._ _ _ . _ ._ .-
LEAFY VEGETABLE PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAh NOBLE GASES, R g At.t G83#1 CNILO ( ) Of 3 )
tutt IDIt on6Au 005I tmytattom fMtDa3 00pt Livt t 1.02 f 1pftSt0 410mit LumG &l.LLI M 160 2.77t+00 2.42f +M 1.61t+0F 0.006 00 7.Det+M 1.45t*05 1.60t+06 64+141 1.99t 21 1.11t 26 6.471 23 0.00t+00 9.62t 25 6.lM
- 24 1.1M 21 M 1&2 0.00s+00 0.00t+00 0 . 006
- 0. cot *00 0.00t+00 0.00t+03 0.00s+00 LA*140 3.2St+03 1.1M*03 3.lM+02 0.00t @ 0.00t+00 0.00t+00 3.1M+01 LA 162 3.3M M 1.0/t M 3.35t 05 0.00t @ 0.00t+00 0.00r*00 2.12t*01 s Ct *141 - 6.SM+0S 3.2M+0$ 4.tM *M 0.00t+00 1.4M *M 0.00t+00 4.0N +M
. Ct.143 1.72t +03 9.311+05 1.3St+02 0.00t+00 3.91t+02 0.00t + 00 1.3M+07 Cf 144 1.2M+08 3.90t+07 6.70t*06 0.00t+00 2.21t*07 0.00t @ 1.Mt+10 P0 143 1.46t+M 4.37t +M 7.23t+03 0.00t+00 2.3M+M 0.00t+00 1.l?t*00 P0 144 S.3M.H 1.66t
- N 2.7W 2F 0.00t+00 8.79t*27 0.00t+00 3.Sm.23 e*147 T.16t+M $.79t+M 4.60f*03 0,00t+00 3.18t +M 0.00t @ 9.1TI+0?
W 18F 6.4M +04 3.01t+04 1.71t +06 0.00L.00 0.00t+0A 0.00t+00 $.3$t+06 .
No 239 3.0M+05 2.?M+M 1.95t+04 0.00t+00 8.01t +M 0.00t+00 2.0H+09 .
twwesim f actere are in mits of emere mter.areWyr per utt/sec for ett nuctione ensept 0 3 dish is in'mits of araWyr por utt/sels ester. .
b l .
1
- l -
l .
l l
4 i +-
?
-.UNT-005-014 Revision 1 Attactunent 6.9 (9 J 9) 165
GOAT's Milk l'ATilWAY DOSE FACTORS DLI TO RADIONUCLIDES OTiiER THAN NOBLE GASES, R.
1 M.! t.80JP ADUL1 t 1 08 3 )
tutilDt Cat.Ae br+t Cuwvittlot f4Ct0R4 rat tivtu 1 get tuva010 EtDatt tuwG G M LI h3 0.00t 40 1.56743 1.SM*03 1.SM 43 1.56t 43 1.$M 43 1.5M +03 0 16 2.63448 5.2 /t 47 5.27147 1.2M 47 S.27t+0? 1.27147 1.77t*07 s& 24 2.93t 45 2.9h *05 2.93t 45 2.93t *M 2.93t @ 2.73tec) 2,93t+05 P 32 2.0$t+10 1.28t+09 7.93F.08 0.00t+00 0.00t*00 0.00t+00 2.31t 49 te.11 0.00t+03 0.00t+00 1.43t+03 2.05t 43 7.15t+02 4.15t.03 8.621*05 su $4 0.00t+00 1.01t W 1.931*05 0. tot +00 3.00t*05 0.006+00 3.00t+06
........................................................s.......................
Mw S6 0.00( 4 0 4.96t M 6.844 05 0.00t+00 6.3rt M 0.00t+00 1.59t.02 ft 15 3.2M *05 2.2M*05 5.2M+04 0.00t*00 0.001 00 1.2M+05 1.291 45 ft 59 3,8M
- 05 9.07t+c5 3.48t
- 05 0.00t+00 0.0x 40 2.54t 45 3.021W 00 58 0.00t+00 1.66845 1.2nW 0 00t+00 0.00t+00 0.00t @ 1.15t+0F Co 60 0.00E+00 1.9M+06 4.34t*06 c.cCt +00 0.00t+00 0.00t+00 3.70t+07 el43 8.07t+0B $.60t*07 2.71t*C7 0.0te +00 0,00t*00 0.00t+0c 1.17t+0?
5845 4.448 02 $.771 03 2.638 03 0. tot @ 0. tot *00 . 0.00t +00 1.468 01 CU 64 0.03t +00 2.6M +03 1.25t43 0.00t+00 6.70t+03 0.00t+00 2.2M 05 1s.65 1.6St*06 S.24t+00 2.3M+08 0.00t+00 3.5M+08 0.00t40 3.30t+08 Ja 69 2.51t.13 4.80E 13 3.34t 14 0.00t 40 3.122 13 0.00E 40 7.21t*14 64 83 0.00E*00 0.00t*00 1.40t 03 0.006 40 0.00t @ 0,00t*00 2.021 03 p E4 0.00E+00 0.006 @ 2.325 FS 0.00E+00 0.00t+00 0.000+00 1.8?! 30 De 85 0. tot +00 C. W +00 0.0]t*00 0.00t @ 0.00E+00 0.u%40 0.0x +00 88 84 0.0M*00 3.11t+08 1.45t+08 0.00t+00 0.00t+00 0.00t+00 6.14t+0?
49 h8 0.03t+00 0.03E*00 0.00t+00 0.00t+00 0.00t+00 0.00t 40 0.00t+00 RS 99 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00L*00 6A 89 3.05449 0.00t+00 8.75t*07 0.00t+00 0.00t+00 0.00f+00 4.996+08 sa.90 9.R3t+10 0.00t+00 2.41t+10 0.00E+00 0.00t+00 0.00t+00 2.64t49 sa 91 6.071+04 0.00t*00 2.45t*C3 0.00: 40 0.00t+00 0.0Je+00 2.tvt+05 54 92 1.03t+00 0.00E40 4.44E 02 0.00t40 0.00t 00 0. tot @ 2.03441 f.90 8.50t+00 0.00E+00 2.20t.01 0.00t+00 0.00t+00 040t+00 9.01t44 1 91m 7.184 21 0.00t+00 2.7tE 22 0.00t+00 0.00t*00 0.006 40 2. lit 20 141 1.03E+03 0.00t @ 2.7M +01 0.00E JD 0.00t+00 0.00E 00 5.67t+05 Y 92 6.695 06 0.00t+00 1.96t 07 0.03t +00 0.00t*00 f.00t+00 1.1M 01
......................................... ....................+............... -
towerelen f actere ers in mits of equere enter eree/rr ser uCl/eet for ett rurtloes except e 3 iAlm is in mits of eroWye per LCl/ctelt setef.
UNT-005-014 Revision 1 AttachrDent 6.10 (1 of 12) 166
COAT's Hil.K PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER 1HAN NOBLE GASES, R f
Af.E Gt0LO ADULT i 2 08 3 )
er.xt it4 DecAr tat Convitstou FACital Sout 61470 f.8001 18Y2010 Elbatt *uuG
. Gl t(t 1 98 2.688 02 0.00t+00 7.408 N 0.00t+00 0.00t+00 0.00t + 00 8.50t*02 13 95 1.1L .+02 3.638 41 2.6N 41 0.00t+00 $.70t 41 0.00t+00 1.158+01 te 9/ l.20t*02 1.051 02 4.006 03 0.00t+00 1.5N 02 0.00t+00 3.25t43 t8 95 9.915+03 5.$1t+03 2.9M*03 0.00t+00 5.45t+03 0.00r *00 3.34t +07 MD 99 0.00t+00 2.9M +06 $ .Mt +05 0.00t+00 6.73846 0.00t+00 6.89t+06 1C +19 3.904 01 1.131*00 1.43t+01 0.00t @0 1.71t+01 $.%2t+01 6.66t+02
.................................................r..............................
TC 101 0.00t+00 0.00t+00 1,.00t+00 0.00t+00 0.00t+00 0.00E+00 0.00r +'Jo 2u 103 1.22: 4 2 0.00t @ 5. 2M *01 0.00t+00 4,66t +02 0.00t+00 1.43t +M au 105 1.031 04 0.00t*00 4.061 05 0.00f+00 1.3M 03 0.00E+00 6.29t 02 9u 106 2.45t+03 0.00t +' 00 3.10902 0.00F+00 4.73t+03 0.00t+00 1.$M+05 A4 110M 6.99t46 6.4H +06 3.kt+M 0.00E+00 1.!?I+07 0.0nt+00 2.Me
- 09 ft*125M 1.95t+06 7.00t+05 2.62t+05 S.4At*05 7.95t+06 0.00t+00 7.80F 4 fI 127N 5.414+06 1.968 +W 6.6M 45 1.4W +06 2.23t 47 0.00t+00 1.kI+07 ft 127 7.8M+01 2. tit 41 1.7W41 5. tot 41 3.1Df+02 0.00t @ 6.18t+03 .
ff 129M T.'4224 2.64+06 1.141+06 2.4tE+06 3.02t47 0.00t40 3.H147 It 129 3.39t.11 1.27t 11 8.25t 12 2.60t.11 1.421 10 0.00t+00 2.56t.11 ft 131M 4.33f+04 2.12t +M t.77t +N 3.3M +M 2.15t+05 0.00e+00 2.101 4 ft 131 4.3H 34 1.81t
- H 1.3M 84 3.$M H 1.99t 33 0.00t+00 6.121 3%
i 1t 132 2.tet+06 1.ht+05 1.75t+05 2.0M+05 1.80t +06 0.00t 40 8.82t +M I !*130 S.Mt+05 1.4M 4 $ .84 +05 1.3M +08 2.32t+06 0.00t+00 1.20t+06 .
l.131 3.15t+08 5. tee +C8 2.91t+0B 1.6M+11 8.71t+08 0.00t+00 1.34t+08 1*132 1.fM*01 S.27t 01 1. Nt 04 1.84t+01 8.4M 01 0.00t+00 9.906 02 1*133 4.ut+06 8.00t+06 2.46t +M 1.1M49 1.41147 0.00t+00 7.2M+06
, ' l .1M 2.&28*12 6.571*12 2.357 12 1.144 10 1.051+11 0.00t+C0 S.7M.15 t
l I
1 13$ 1.54144 4.03t+04 1.4M44 2.6M +06 6.47t+04 0.00t+00 4.56t+M l CE*1M 1.7DE*10 4.06t+10 3.30t*10 0.00t+00 1.31t+10 4.34t+09 7.0M+06 C5 136 7.90E+08 3.128 49 2.24t49 0.0ct+00 1.73t+07 2.34t+08 3.54E+08
\
( CS 137 2.21t+10 3.03t+10 1.98t+10 0.00t+00 1.03t+10 3.42t+09 5.864 4 l Cs 138 2.711+23 $.3M.23 2.658 23 0.00t40 3.Mt 23 3.998 24 2.295 28 l BA 1?>9 5.30E 09 3.78t 12 1.555 10 0.00E+(0 3.53t 12 2.14t 12 9.40t 09 Csaersian f actere are in mits of esses meter ereWyr per utt/sec ter all tweildes except a 3 Which le in mite of areWyv per scl/cselc meter.
l I UNT-005-014 Revision 1 Attaciunent 6.10 (2 of 12) 167
GOAT's MILK PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTER THAN NOBLE GASES, R.1
&GI C40JP ADUL1 ( ) 08 3 )
uJCLIDI WLAs bott CtwAttIm f att0*8 1stt010 t!0ett luuG St.LLI sont Livtt 1.e001 6A.140 3.23t +M 4.0$t+01 2.11t*05 0.00t+00 1.3M *03 2.12t+C3 6.44t+06 SA lal 0.00t+00 0.00t*00 0.00t+00 0.0M +00 0 M+00 0.0M@ 0.03t+00
&A.142 0.0N +00 0.0CE*00 0.00t+00 0.00E+00 0.00t+00 0.00L+00 0.00t+00 LA 140 S.41t 01 2.738 01 7.215 02 0.00t+00 0.00t*00 0.00t+00 2.0M+04 LA.142 2.23t.12 1.011 17 2.53t 13 0.00t @ 0.00t+00 0.00t+00 7.40t.09 ,
- 0. tot +00 1.%0t +M C8 141 1.01t+02 3.93E+02 6.6M +01 0.03t+00 1.83t+02 C3 143 6.99t+00 3.69t+03 4.08t.01 0.00t+00 1.621*00 0.00t+00 1.3M +05
- Ct.144 4.?'t +% 1.79t+M 2.30t+03 0.00t+00 1.0M +04 0.00t+00 1.45t*07 Pt.143 1.99t+01 7.60t+0c 9.395 01 0.00t +00 4.39t +00 0.0M + 00 0.30t+04 Pt 144 0.00t+00 0.00t+00 0.00t +00 0.00t+00 0.00t+00 0.00t*00 0.00t+00 ND.147 1.13t+01 1.31t+01 7.ttt 01 0.00t *00 7.Ot+00 0.00t+00 6.ZTt +M W.il? 7.82t+02 6.53t+02 2.28t+02 0. tot +00 0.00t+00 0.00t+00 2.16t*05 WP Z39 5.52t+00 5.(St.01 2.99t 01 0.00t+00 1.69t+00 0.00t+00 1.11t+0$ .
Lerwerslen f 6cters are in mits of pr* setet.oreWyt por utt/sec for ett rucLtdes oncept p 3 which is in mitt, of areWyt per uti/cels meter.
UNT-005-014 Revision 1 At.tachment 6.10 (.3 of 12) 168
GOAT's M11.K PA'DNAY DOSE TACTORS DUE TO HADIONUCLIDES OTHER THAN NOBLE GASES, H g ACA Lt0# tile t t ot 3 3 l
uucklot car.As tat COW /ttilow #4:foss 64mt Livt e 1.txt fattele r1 butt tuer. $1 441 e.) 0. 00t
- 00 2.03t*03 2.03t+03 2.0M +03 2.0M +03 2.031*03 2.03t*D3 C.14 4.46t*06 9.72t+07 9.T2t+07 9.72t+07 9.72t*0? 9.7tt+07 9.72t*07 mA.24 S.11t*05 S.11t*05 1.11t+05 5.11t *M l.111 4 1.11t +H 5.11t*05 P 32 3.78t+10 2.34t+09 1.671 09 0.00t+00 0.00t+00 0.00t+00 3,*h!*09 l
Co $1 0.00t+00 0.00t+00 ' l .99t *C3 3.33t*03 1.31t+03 8 llt*03 1.01t*06 l
- w .54 0.00t*00 1.68t+06 3.54t+f/5 0.00t+00 5.02t*05 0.00t @ 3.45t*06 l
t seela 0.00t @ 8.08 0s Ll?t 04 0.00t*00 1.121 03 0.0M +00 5.81t 02 7I.55 $.79t+05 4.111+05 9.571+04 0.00t+00 0.00t @ 2.40E+0; 1.781*05 ft.59 6.76t+05 1.5 7t +06 A.07t*05 0.00t @ 0.00t+00 4.96t+05 3.72t+06 CD 58 0.00t+00 9.523+0$ !.t95+06 0.00s+00 0.00t @ 0.00t +00 1.31t 47 00 60 0.00t+00 3.54t @ 7.$2t+04 0.00t*00 0.Dut+00 0.00t+00 4.31847 81 63 1.4?f+09 1.00t+M 4.81t*07 0.00t+00 0.00t+00 0.00t+00 1.59t*07 al.65 8.121 02 1.06t.02 4.7M .03 0.00t+00 0.00t+00 0.00t 40 5.631 01 Cu 64 0. M *00 4.7M+03 2.23t+03 0.00t +.10 1.20t*06 0.tet+00 3.67t*05 p.6$ 2.5M48 8.7st+08 4.10t*06 0.00t+00 S.62t+08 0.00t+00 3.72t+08
! IW.69 4.621 13 8.80t.13 4.iM .14 0. tot +C0 5.75t.13 0.00t+00 1.621 12 M 83 0.00f+00 0.00t+00 2.50t 43 0.00t+00 0.0(440 0.00t*00 0.00t*00 N 64 0.00t+00 0.00E+00 4.14t.25 0.00t+03 0.00t+0S 0.0nt *00 0.004+00 M .t$ 0.00t+00 0.0t4 *00 0.00t+00 0.00t40 0.00f+00 0 Ont40 0.00t+00 00 @ 0,00t+00 5.67D 06 2.671+08 0.00840 0.00t*00 0.00f+00 8.et+07 f6 88 0.00t+00 0.00t 40 0.00t+00 0.0tt+00 0.00t.40 0.8K4+00 0.00D00 R8 99 0.00E+00 0.00t+00 0.00t 40 0 'J0E+00 0.00t+00 6.00t+00 0.00t+00 38 99 S.625+09 0.00t+00 1.61E+08 0.00r40 0.00t40 0.00t+00 e.69t +06 38 90 1.390+11 0.00t+00 3.43610 0.00t+00 0.00t+00 0.00f*00 3.90909 ga 91 1.12t+0$ 0.00t*00 4.44f+03 0.00t+00 0.00t+00 0.00t*00 5.0M +05 M42 1.tet+00 0.00t+00 8.00t.02 0.000 00 0.00t+00 0.00E+00 4.7N41 T.90 1.56t*01 0.00t+00 4.218 01 0.00t+00 0.00E+00 0.00t @ 1.79t+05 l
l ................................................................................
19m 1.311 20 0.00t+00 5.025 22 0.00t+00 0.Mt+00 0.00D00 6.21t.19 Y.91 1.90t+03 0.00t+00 5.04t 41 0.00900 0.00t @ 0.00E+C0 7.T7I@
v42 1.248 05 0.00Lf00 3.50847 0.00t40 0.00f*00 0.00E+00 3.39t.01 Camerslen f actors are in mits of assers seter-area /yr per uti/sec for ett ruellees except W 3 which la it. ette of areWyr per dl/cels meter.
UNT-005-014 Revision 1- Attachment 6.10 (4 of 12) 169
_ _ _ _ _ _ _ _ _ _ _ __ -- -~ __ . _ _ _
GOAT's MILK PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES, R.
1 I
)
~
Act CA37111tu ( 2 0F 3 )
_. c ECLIM DeCAs Dutt Cow W tlich FACT 081 r ,
.~ 4 .
y E.F T LWG 41 sLi tlytt 1.BCCY 15T2010 BOWE y
w
- w Qft 4
T 93 4.941 02 0.00t+00 1.36t 03 0.00E*00 0.00t+00 0.0? 10 1.51t+03 4 tR 95 1.98E+02 6.25t+01 4.30t+01 0.00t+00 9.184+01 C. st+00 1.ut+05 9.4M 02 1.871 02 8.62t*03 0.00E+00 2.84t 02 0.00t +00 5.075+D3 1*
W /7 as*95
- 69t+04 9.3it+03 5.16t +03 0.00t+00 9.Qu+03 0.00t+00 4.01t47 sto 99 0.00t +00 % .37t +M 1.02t+06 0.00t+00 1.23t+07 0.00E 4 9 #t46 ft 99u 6.91t 01 1.9M +00 2.50E +01 0.00E+00 2.8M+01 1.0TE+00 1.27t+03 "4I 1C 101 0.00E *00 0.00t +00 0.00t+00 0.00E+00 0.005 00 0.00t+00 0.00t+00 tu 103 2.17t +02 0.00t+40 9.29t+01 9.00E +00 7.66t+02 0.00E+00 1.81&+04 tu 105 1.6M 06 0.00t+00 7.2W 05 0.00E +00 2.37E 03 0.0%+00 1.521 01
................................................................................ e 20 106 3.475 03 0.00E+00 5.67t+02 0.00E+00 8.60E+03 0.00t+00 2.16E+05 4
- P110M 1.1M47 1.09t+07 6.45t+M 0.00E+00 2.08E+07 0.00t+00 3.07t+09 Il 125M 3.60E+ce 4.3tt+06 4.82t+05 1.01t+0S 0.00t+00 0.00E+00 1.06E+07 15 12Mt 1.01E+07 3.59E+M 1.20f+06 2.41E+M 4.10C 47 0.00t+00 2.52f 47 1r 127 1.45t+02 5.15t+01 3.12t+01 1.00t+02 5.8&t+02 0.00t+00 1.12t+04 ft.129M 1.32547 4.90E+06 2.09t+06 4.268+M 5.53f+07 0.00E+00 4,9M+07 11 129 6.24t.11 2.33E 11 1.39 11 4.44E 11 2.621 10 0.00E+00 3.41t.10 72 131R 7.88E+04 3.79E+04 3.15t+04 5.69t+04 3.Mt+05 0.00E+00 3.0Ma06 Yt 131 7.90E 34 3.2M.34 2.475 34 6.09E.34 3.45E 33 0.00!+00 6.49E 33 11 132 - 5.tSE405 3.26E+05 3.0M+05 3.44t+05 3.tu+06 0.00E+00 1.03t+07 1 130 8.8M+05 2.56E4e 1.02t+06 2.09t+D8 3.95t+M 0.00E+00 1.97t+M .
l.13e 6.4M+08 9.0M+08 4.85t+08 2.63E+11 1.55E+09 0.00E+00 1.79E+08
+...............................................................................
1 112 3.50E 01 9.1M 01 3.2sE 01 3.0eE+01 1.444 40 0.00E40 3. vet-01
,1 133 8.4aE+06 1.444+C7 4.39E+06 2.011 49 2.52547 0.00E+00 1.09t+07 l.134 4.30E 12 1.14E 11 4.09t.12 1.90E.10 1.20E.11 0.00E+00 1.50E.13 3 135 2.74E+04 7.04E+04 2.41144 4.5M+06 1.11t+05 0.00E+00 7.815 44 08 134 2.94t+10 6.9M+10 3.22f+10 0.00E*00 2.20E+10 8.41E+09 8.f3 +0S 05 136 1.34DC9 5.29t+W 3.35E+09 0.00E+0c 2.88E*09 4.544+08 4.2M +06 03 137 4.62f + 10 5.34t+10 1.6M +10 0.00t+00 1.82t+10 7.0M49 7.60E+08 Cs 138 4.922 23 9.454 2*, 4.772 23 0,00E+00 6.982 23 8.125 24 4.29E 26 4A* l39 9.415 09 6.90E*12 1.864 10 0. tat +00 '4.50E 12 4.7M.12 8.75E-08 Corwersten f actors are in mire of equaev astee.eewyf Mf u0l/mec for all nuctions except h.3 iAlch is in mits of stun /st per df/ce'.c meter.
UNT-005-014 stevision 1 Attachment 6.10 (5 of 12) 170
- - - - - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ __ _ - - - - - - - ~ _ _ _ _ _ __ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _
i GOAT's MILK PATINAY DOSE FACTORS DUE TO RADIONUCLIDES OTllER TllAN NOBLE GASES, R.
1 Act e.amm ?tts ( 3 07 3 )
aOCLIDE CeGAn bolt CCWVittl0N FAC10RS 1.t@T 18T8010 Kl!WEY LUNS Cl*LLI tout Livts sA 140 5.82t+0e 7.13E+03 3.75E+M 0.00E+00 2.42t+c3 4.6cA +03 a.9st +06 SA 141 0.00E*00 0.00E+00 0.00E+00 0.00E*00 0.00E +00 0.bOE+00 0.00E*00 EA.142 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E +00 0.00Ee00
- .******* .*. 0.00E+00 LA 140 9.725 01 4.7st 01 1.271 01 0.00E.00 0 M +00 0.00E*00 2.74E+N LAa142 4.02E.12 1.79E*12 4 A5E*13 0.00E+00 0.00E+00 E.OnE+00 5.44E 04 Ct.141 1.07t +03 7.12t+02 L17t*01 0.00E*00 1."5f*02 0.00E*00 - . * . . > *2.04f+06 9.171+00 6.67t+03 7.45E-01 0.00E+00 2,99t+00 0.M +00 2.00E*05 Ct.143
- CE.144 7.90E+04 3.271+04 4.24t+03 0.00E+00 1.95E+04 0,00E+00 1.Wt+07 PA.143 3.48E*01 1.39E+01 1.73E+00 0.00E*00 8.08E+00 0.00F+00 1.15t+05
.........................t..... ................................ -.. .. ...**..
Pe.144 0.00E+00 0.00E +00 0.00E+00 0.00E+00 ' O.00E-00 0.00E*00 0.00t+00 NO-147 2.17t+01 ?.36E+01 1.42E+00 0.03E+00 1.39E+01 0.00E+00 8.53E+04 W-187 1.43t+03' 1.17t+03 4.06E+02 0.00E*00 0.00E+00 0.00E+00 3.15E*M l ...............'.............................................-..........
we.239' i.Os.+01 9.93t 01 5.521 01 0.00E+00 3.12t+00 0.00E+00 1.60E +05 Corwersion tectors are in units of somre meter eree/yr per gl/see for all mztless sumpt e-3 which is to mits of areatyr per xt/ cele seter.
?
UNT-005-014' Revision 1 Attaclunent 6.10 (6 of 12) 171-
. . ~ - - .- -- -- . . . - . - . - -- - - . ~
GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONtlCLIDES OTl[ER TliAN NOBLE GASES, R.
1 AGE Gaoups tulL01 1 of 5 )
muCLICE S CaGAa DoEE CouvEnssou #Acf 0st 40NE LIVER T .3(EY INYt010 EIDeET LUNG Gl*LLI N3 0.00E+00 3.20E+03 3.20E+03 3.20E+03 3.20E
- 03 3 20E4J 3.20E+03 C+14 1.1M+09 2.39E +08 2.39E +08 2.5M +06 2.39E*06 2.39E+08 2.39E+04 RA 24 1.0M *06 1.06E 47 1. NE +06 1.%E46 1.0M +M 1.06E +06 1.0M *06 P 32 9.33E+10 4.'3M+09 3.60E +09 0.00E +00 0.00E+00 0.00E+00 2.54E*09 Ca 51 0.00E*00 0.00E+0d 1.27E 44 6.7N+03 1.85E +03 1.24k+04 6.4aE +05 uu 54 0.00E+00 2.!M+06 6.7DE+05 0.00E40 7.0M+05 0.00E +00 2.11E W .
mm 56 0.00E 40 1.54E.03 3.4N 04 0.00E*00 1.8M 03 0.00E+00 2.23E 01
' FE 55 1.39t+06 7.71E+05 2.39E+05 0.00E+00 0.00E+00 4.3M +05 1.43E+05 Ff*59 1.5M + 3 2.53E+06 1.2M46 0.00E +00 0.00E *00 7.33E+05 2.63E+06 Co-58 0.00E+C0 1.45E.06 . 4.45E +06 0.00E
- 00 0.00E+00 0.C0E+M 8.49E+r4 Co-60' O.00E+00 5.18E+06 1.53f+C7 0.00E *00 0.00E+00 0.00E+00 2.87E +07 ul*63 3.5H+09 1.90E*0ft 1.2&E*06 0.00f+00-0.00E+00 0.00E+00 1.20E*07 al45 1.9M.01 1.5M 02 1.09E 02 0.0x+00 0.00E+00. 0.00E+00 2.29E+00 CW-64 0.00E+00 4.32E+03 5.ON+03 0.fAE+00 2.01E44 0.00E+00
- 90E+05 .
Zu-45 4.96E+08 1.3N+09 8.22E+08 0.00E+00-8.33E+06 0.00E +00 2.32E+06
~25 69 1.14E 12 1.64E.12 1.5 N.13 0.00E*00 9.9M 13 0.00E+00 1.03E.10 52 @ 0.00E+00 0.00E+00 6.34E-03 0.00E+00 0.00E+00 0.00E+00 0.00E*00
' M 84 - 0.00E+00 ~0 .00E+00 9.3M 25 0.00E+00 0.00E*00 0.SOE40 0.00E 40 OR*85 0.00E*00 0.00E 40 0.00E*90 0.00E+00 0.00E 4 0' O.00E 40 0.00E+00 at 46 0.00E+00 1.05E+09 '6.47t+0e 9.UDE+00 - 0.00E+00 - 0.00E*00 6.7M+07 . i R0 04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 .0.00E 4 0 0.0M+00 R8 99 0.00E+00 0.00E+00 0.00E*00 0,00E+00-0.00E+00 0.00E+00 0.00E+00 -
SR 09 1.39E*10 0.00E+00 3.9M+08 0.00E+00 0.00E+00 0.00E+00 5.3AE+06 58-90 2.3SE+11 0.00E+00 5.95E+10 0.00E+00 0.00E+00 - 0.00E+01 3.1f O
.......................... ................................................* m .
sa-91_ 2.74E+05 0.00E+00 1.0M +04 0.00E*00 0.00E *00 0.00E+00 6.04E+05 l1 sa.92 ' 4.50E+00 0.00E+00 1.04E 01. 0.00E+00 0.00E+00 0.00E40 ' 8.40E+01 T.90 3.$M+01 0.00E+00 1.03E*00 0.00E+00 0.00E+00 0.00E *00 1.10E+05 L
1- -Y 91A 3.21E 20 0.00E+00 1.17E.21 0.00E +00 0.00E+00 0.00E+00 4.29E 17
! T.91 4.40E+03 0.00E+00 1.25E+02 0.00E+00 0.00E+00 0.00E+00 6.24 toc 5 T 92 3.04E-05 0.00E+00 E.40E-07 0.00E+00 ' O.00E+00 0.00E+00, 8.7M 01
- l. Corwersion factors are in mits of 6.ance meter.aren/yr per uCl/see for att l
i~
mellous except 5-3 shich is in mite of ersmtyr per utt/seic meter.
UNT-005-014 Revision l' Attachment 6.10 (7 of 12)-
l 172 L
GOAT's MILK PATINAY DOSE FACTORF DUE TO RADIONUCLIDES OTIIER TIIAN NOBLE GASES, R.
1 AGE GROUPS ChlLD I 2 Of 3 )
MuttIDES caGAs Dost conviaston nctons DOLE LIVit 1.DCDV TNY2010 ElDetf LuuG Cl Ltl V.93 1.215 01 0.00E+00 3.33E.03 0.00t+00 0.00E+00 0.00t+00 1.81t+03 28 95 4.60E+02 1.01t 02 9.00E+01 0.0M+00 1.45t+02 0.00t+00 1.05t+05
+
It.97 2.30t.01 3.33t.02 1.96t.02 0.00t+00 4.78t-02 0.00t+00 5.04t+03 me 95 3.81E+M 1.49t+04 1.06t
- 0.00E+00 1.40t+04 0.00t+00 2.75E47 mo-99 0.00t+00 9.76t+06 2.42f+06 0.00E+00 2.09t+07 0.00E+00 8.08t +M TC.f9m 1.59t +00 3.11t+00 5,15t41 0.00t+00 4.52t+01 1.58t+00 1.77t+03 it.101 0.00E + 00 0.00E+00 0.00t+00 0.00t+00 0.00E+00 0.00t + 00 0.00t+00 tu.103 5.14t+02 0.00t+00 1.96t+02 0.00t+00 1.29t+03.0.00t*00 1.33t+04 RU 105 4.585 04 0.00t+00 1.6M .04 0.00t+00 4.034 03 0.00t+00 2.99t.01 RU.106 1.111+04 0.00t+00 1.38t+03 0.LDE+00 1.50t+04 0.00E+00 1.72t+05 4G.110m 2.51847 1.65f+07 1.35t47 0.00E+00 3.15t47 0.f4E+00 2.01t+0?
Yt.125m 8.85t+06 2.40t+06 1.18e+06 2.4st+06 0.00t+0C 0.Ont+00 8.54t+06 ft.127W 2.50t+07 6.721*06 2.96t+06 5.97t+06 7.12t+07 0.00t+00 2.02f+07 ft.127 3.57E+02 9.63t+01 7.66E41 2.47t+02 1,02t+03 0.000C9 1.40t44 1E 129m 3.2M +07 9.09t+06 5.0M +G , 1.05447 9.5M +07 0.00E+00 3.97t+07 ft.129 1.54t.10 4.304 11 2.6M.11 1.10E.10 4.50t.10 0,,00E+00 9.58E.09 ft.131m 1.92t+05 4.64t+04 7.0M44 . 1.3M +05 . 42E+05 0.00E+00 2.69t*06 7E.131 1.94t.33 5.915 34 5.TTE.34 1.488 33 5.86E.33 0.00t+00 1.02E 32
........................+.......-..................................... ..........
7E.132 1.23E+06 5.44t+05 6.5M45 7.93t+05 5.05E+06 0.00E+00 5.48t+06 1 130 2,07t+06 4.19546 2.1M+06 4.61t+08 6.26E+06 0.00E+0D 1.9M+06 1 131 1.5M+09 1.5M49 8.94t+06 5.20t+11 2.5at+09 0.00e+00 1.40t+05 l.132 8.271 01 1.5M+00 6.99E.01 7.05t+01 2.33E+00 0.00t+00 1.79t+00 1 133 2.064+07 2.5M +07 9.64E+06 4.73E+09 4.25E+07 0.00E+00 1.03E+07 i .. e 134 1.02t.11 1.99t.11 8.TUE.12 4.3M .10 2.9st.11 0.00E+00 1.255 11 I.135 6.40E+M 1.17t+05 5.52E+04 1.03E+07 1.79t+05 0.00E+00 8.3aE+0(
cs.134 6.79t+10 f.11t*11 2.3H +10 0.00E+00 3.4H+10 1.24t+10 4.01E+08 cs.136 3.03E+09 8.54t+09 5.40E+09 0.00t+00 4.44t+09 6.63E48 2.9M+08 cs-137 9.67t+10 9.26t+10 1.37t+10 0.00E40 3.02E+10 1.09t+10 5.SOE+06 C3 138 1.19E-22 1.64E.22 1.05E.22 0.00t+00 1.1M.22 1.26f.23 7.64E.23 BA.139 2.418 06 1.29E.11 6.90E.10 0.00E40 1.12E.11 7.571 12 1.39t.06 Conversten factors are in mits of emsre meter. ores 6fyr per di/see for att esstlers except u-3 which is in mits of arenryr per g l/ce lc swter.
UNT-005-014 Revision 1 Attaciunent 6.10 (8 of 12) 173
- - ~ ~ . _ ~ . - - . . . . .. - .- - .. . - ..- -. ~ . , - . ., ~
GOAT's MILE PATINAY DOSE FACTORS DUE TO RADIONUCLID'ES OTHER THAN NOBLE GASES, R.
1 AGE G437: CMILO ( 3 Of 3 )
tRJCLIDEs OsGAW DOER CCWYER$lCN FACTORS BONE LIVER 1.50DY fNfR0!D KIDNET- LUNG Gl.LLI sa.140 1.41E+07 1.2M +04 8.20E*D5 0.00E+00 4.01E+03 7.34E+03 7.12E +06 ga.141 0.00E+00 - 0.00E*00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 4A.142 0.00E+00 0.00E+0D 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E *00 LA.140: 2.33E+00 8.14E 01 2.54E.01 0.00E*00 0.00E+00 0.00E+00 2.27E*04 LA 142 9.7?E.12 -3.10E*12 9.70E.13 0.00E +00 0.00E+00 0.00E+00 6.14E.07
- CE.141 2.64:E+03 1.31E*03 1.94E+02 0.00E+00 5.74E+03 0.00E+00 1.6M +06 CE.143-- 2.25E+01 1.22E,04 1.77t+00 0.00E+00 5.12E+00 ' O.00E+00 - 1.79E+05
-CE.144 t."3E+05 6.11E+04 1.04E+06 0.00t+00 3.3eE+04 0.00E+00 1.59E+07 Pa.143 - 8.62E+01 2.59E*01 4.28E+00 0.00E+00 1.40E+01 0.00E+00 9.30E+44 Pt.144 0.00F+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00-0.00E*00 0.00E +00
., ae.147 5.33E+C? 4.32E+01 3.3M*00 0.00E+00 2.37t+01 0.00E+00 6.85E+04 W.187 3.47E+4I3 2.05E+03 9.21E+02 0.00E+03 0.00E+00 c.00E+00 2.8eE+05-WP.239 -2.59E+01 1. tee +00 1.31E+00 0.00E+00 5.3eE+00 0.00E+00 1.38E+05 Comsrelen factors are in mits 'of agere amter.oremfyr per 21/sec for ett I! twctidos escept M.3 unish is in writs of srem/yr per Wl/ cele enter.
5 x
UNT-005-014 Revision '! . Attachment 6.10 (9 of 12) 174
GOAT's MILK PATHWAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAM NOBLE GASES, R. .
1 ACE Catups Itf AE1 ( 1 08 3 )
butLIDE Cat.Am Dost ionvitttts f ACTOR 5 L IVt t 1.B(DY TWYtotD Elt4tf LIAG Gl LLI SONE n3 0.00E +00 4.66t+03 4.34 +03 4,W03 4.&6t+03 4.8M +03 4.6M +03 i
C 14 2.34t+05 5.00t+08 5.00E+08 5.00t @ 5.00E *08 5.00t*08 5.00E +08 '
hA 24 1.6)f+06 1.85t *M 1.85E +M i.85E+06 1.85t +M 1.85t+06 1.85t +M
......................... ,...................................................... 9 P 32 1.92t*11 1.134*10 7.4M
- 09 0.00t+00 0.00E +00 0.00t+00 2 40t +09 5.64t+05 ca 51 0.00t+0c 0.00E+00 1.96t+04 1.76t +M 2.7M +0J 2.46t +M MN+54 0.00E+00 4.68E+06 1.MI+M 0.00t+00 1.0LE+06 0.00E + 00 1.72t+06 4 ew 56 0.00t+00 3.771 03 6.50E 04 0.00E+60 3.24t*03 0,00t+00 3.431 01 71 55 1.76t+0/ 1.13t+06 3.23t+05 0.00E @ 0.00E +00 5.55E + 05 1.44E+05 .
ft.59 2.92t+06 5.10E+06 2.01t+06 0.00t+00 0.00E +00 1.51t+06 2.45E+06 00-18 0.00E+00 2.91t+06 7.2M +06 0.00E+D0 0.00E+00 0.00E d 7.25t+06 Co-60 0.CCE +00 1.0M +07 2.50E+07 0.00F.*00 0.00E+00 0.00E*00 7.52t+07 st.63 4.19t+09 2.59E +08 1.45f+08 0.00E+00 0.00E+00 0.00E+00 1.29E+07 Wi 65 4.215 01 4.764 02 2.17t 02 0.00F+00 0.00E+00 0.00E+00 3.62t+00 CU 64 0.00E+00 2.07t+04 9.57E+03 0.00E+00 3.50E+*4 0.00E +00 4 14t+05
!s 65 6.66E+08 2.2SE+09 1.05t+00 0.00E+00 1.11t+09 0.00i+00 1.93E+09 Zu 69 2.428 12 4.36t*12 3.24E-13 0.00t*00 1.814- C 0.00t+00 3.55E.10 3a 83 0.00E +00 0.00E+00 1.34E 02 0.00t+00 0.00E*00 0.00Es00 0.00t+00 Da 84 0.00E+00 0.00E*00 1.81E 24 0.00E+00 0.Dx +00 0,00E*00 0.00E*00 88 85 0.00E+00 0.00E+00 0.00E +00 0.00E+0C 0.00E*00 0.00E+00 0.90E+00 50 56 0.00E+00 2.67E+09' 1.32E*09 0.00E+00 0.00E+00 0.00E+00 6.83t+07 as-88 0.00E+00 0.00E+00 0.00E*00 0.00E*00 0.00t+00 0.00E+00 0.00E+C0 00 09 0.00F+00 0.00E+00 0.00E*00 0.00E+00 0.CCJ+00 0.00E*00 - 0.00t *00 08 84 2.64t+10 0.00E+00 7.SaE+00 0.00E+00 0.00E+M 0.00E 00 5.4M+C8 ta-90 2.55t+11 0.00P00 6.50E+10 0.00E+00 0.00E+00 0.00E+00 3.i m 09
...........................-~...................................................
sa 91 5.70E45 0.0M *11 2.Mt+04 0.00E+00 0.00E+00 0.00E*C0 6.75t+05 84 92 9.75t+00 0.00E+00 3.62t 01 0.00E+00 0.00E+00 0.00E+00 1.05t*L2 V40 a.17t+01 0.00E+00 2.19t+00 0.00E+00 0.00E+00 0.00t+00 1.13*+05 Y.914 6.8tE 20 0.00E+fl0 2.327 21 0.00E*00 0 00E+00 0.00E+00 2.270 16 TW1 8.79t+03 0.00E+00 2.344+02 0.00E+00 0.03E+00 0.00E+00 6.30E+05 f v42 6.45t 05 0.00E+00 1.818 06 0.00E+00 0.00E+60 0.00E+00 1.234+00 Carwersion f actors we in mits of somre meter.oren/yr per utt/see for all nwlldes except a 3 mtsich to in mits of arewyr per utt/ rete meter.
UNT-005-014 Revisitan 1 Attachment 6.10 (10 of 12) 175
GOAT's MILK PATHWAY EOSL FACTORS DUE TO RADIONUCL' DES OTIIER TilAN N011LE CASES, R.1 2 40t DMt lHast ( 2 04 3 )
h ..
suctird (*r.As Dost carvitston MCfWS 1.pt lutt019 twY LumG 01 LLI tout L t ytt i'
t 93 2.59E 01 0.00t+00 7.054 03 0.00t*00 0.00t+00 0.00t+00 2.04t+03 28 95 8.17t+02 1.99t +02 1.41t+02 0.00t*00 2.14t *02 0.00E+00 9.91t+04
$ 2a 97 4,t7t-01 8.371 02 3.E?t 02 0.00t+00 8.45t.02 0.00t +00 5.34t+03 P
mr .
I ks 95 7.121+M 2.93t+04 1.70E+04 0.00t.00 2.10t+04 0.00t+b0 2.4eA+07 0 99 0.00t+00 2.50t+07 4.871+06 0.0ct+00 1.73t+07 0.00t+00 8.22t+06 f 1c 994 3.30( 4 0 6.Ot+00 8 76t+01 0.00t+00 7.32t+0t 3.!44 +00 1.94 03 .
j -
0.00t+00 0.00t+00 0.00t+00 0.0Ct +00' O.00t+00 0.onE+00 0.00t+00 l
TC.101 p
RU.103 1.04E+03 0.00t+00 3.48t+02 0.00t+00 2.17t+03 0.00+ + 00 1.27t +M t
tv 105 9.66t.04 0.00t+0C 3.25t.04 0.00t+00 7.118 03 0.00E+00 3.64t 01 p-w e. 2.2u + m 0.0= = 2.85t.03 0.00t+00 2.m+a 0.0a = 1.7u.n P- Ab WM 4.634 07 3.3at+07 2.24t+07 0.00t+00 4.6At+0F 0.00t+00 1.75t+09
}
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it.1254 1.81E+07 6.05t+06 2.45t*06 4.09t+06 0.00E+00 0.00t+C0 8.62t+06 ft.127M 5.05t+07 1.681+07 6.12t+06 1.46t+07 1.24t+0S 0.00t+00 2.04E+07 it-127 7.58t+02 2.54t+02 1.63t+02 4.171+02 1.85t+03 0.00t+00 1.59t+04 ft.129M 6.69t+07 2.29t+0. 1.03t+01 2.57t+07 1.67t+06 0.00t+00 3.99t+07 11 129 3.24E.10 1.121 10 7.621 11 2.734 10' 4.128 10 0.00t+00 2.611.t2 TE.131M 4.05t+05 1.63t+05 .1.35t 95 3.31t+05 1.12t+06 0.00t+00 2.75t+06
, [
ft.13i 4 118 33 1.521 33 1.118 33 3.671 13 1.051 32 0.00t+00 1.46E 31 18 132 2.53a+06 1.25t+06 1.17t+06 1.tSt+06 7.84t +06 0.00t+00 4.44t+06 3 130 4.26t+06 9.37t+C6 3.76E*06 1.05t+09 1.034+07 0.00t+00 2.01E+06 -
l 131 3.244 09 3.85&+09 1.69t+09 1.2dd*12 4.49t+09 0.0Cd+00 1.371+06 l.132 1.72f+00 3.4at*00 1.244+00 1.63t+02 3.89t+00 0.00E+00 2.&2f+00 1 133 4.35t+07 6.34t+07 1.WA +07 1.15t+10 7.454+07 0.00t*00 1.07t+07 1 134 2.115 11 4.334 11 1.54t.11 1.018 09 4.54t.11 0.00t+00 4.471 11 3 135 1.35t+05 2.68t+05 9. Tit +04 2.40t +07 2.99t*05 0.00t+00 9.7Ct+04 .
CS 134 1.09t+11 2.04&+11 2.0dC+10 0.00t+00 5.25t+10 2.15t+10 5.54t+06 C$ 136 5.93E+09 1.74E+10 6.5tt+09 0.00t+00 6.95(+W 1.42t+09 2.65t+0s C3 137 1.$4f+11 1.81t*11 1.28t+10 0.00E+00 4.85t+10 1.96t+10 5.45t+08 Cs 13A 2.525 22 4.09f 22 1.9 tit.22 0.00t+00 2.04I.22 3.19E.23 6.54t-22 sa.139 5.13t.Os 3.40t.11 t.4st 0* 0.00t+00 2.044 11 2.0t2 11 3.25E.06
_ ' Camersten f actors are in mits of egare meter.ortantyr per utt/see for att t-
ructides except u-3 imich is in ette of eren/y* Per sti/ cubic seter, m
4 UNT-005-014 Revision 1 Attactunent 6.10 (11 of 12) i 176
=
a 55 k - - - - -_-- -_-_____-__ _ _ _ _ _ _ _ _ _ _ _
00AT's HILK PATHWAY DOSE FACTORS DUE TO RADIOliUCLIDES OTHER THAN NOBLE GASES, R.
1 Act saa Pt lutast ( 3 0F 3 ) e anK8.!DF ORGAM 0044 COINttll0W f ACTORS 1pvm3l0 (IDeff LUWG GI Let most LIVER 1. DIET BA*140 2.09t+07 2.99t+04 1.49t +06 0.00E+00 6.871 03 1.7st*04 7.10t+06 SA 141 0.00t*D0 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t+00 0.00t*00 SA.142 0.00t+00 0.00E+00 0.00t+00 0.00E+00 0.00t+00 0.00t+00 0.00t*00 l-LA.140 4.8M +00 . 1.92t +00 4.938 01 0.00E+00 0.00t+00 0.00E+00 2.25t+04 LA.142 2.068 11 7.49t*12 1.795 12 0.00E*00 0.00t+00 0.00t+00 1.271 06 e CE.141 5.20t+03 3.1M+03 3.74t+02 0.00t+00 9.79t+02 0.00t+00 1.64t+06 Ct.143 A.7W+01 3.1M*04 3.60t +M 0.00E+00 9.20E+00 0.00E+00 1.84t+05 CE.14A 2.79t+05 1.14t+05 1.56t+04 0.00t+00 4.62t+04 0.00t+00 1.60E+07 Pe 143 - 1.nE+02 6.67t+01 s.est+00 0.00t+00 2.48t+01 0.00t+00 9.41t*04 Pt.144 0.Cff*00 0.00t+00 0.00E+00 0.00E+00 0.00t+00 0.00t+00 0.00E+00 No.147 - 1.06t+02 1.09t+02 6.65t+00 0.00t+00 4.1M+01 0.00t+0C 6.00t+04 l
W.187- 7.30t+03 5.07t+03 1.75t+03 0.00t+00 0.tet+00 0.00t+00 2.98E 05 l- - .
WP.Z39 5.48t+01 4.90t+00 2.77t+00 0.00t*00 9.77t+00 0.00E*00 1.42E+05 Carwersten f actors are in units of saare seter.eren/yr per utt/see for ett -
fu:lldes except B 3 shish to L, .ntts of urem/yr per sti/ cubic ester.
l~
l 2 I
t UNT-005-014:- Revision 1 Attachment 6.10 (12-of 12)-
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J RADIOLOGICAL' ENVIRONMENT MONITORING PROGRAM ._
- Analysis
- Frequency Volume
'ISaCple' Type - Lc4.ation
- A-2, B-1, C-1,,.D-2,.E.1, - TLD" . Quarterly N/A
.TLD-F-2, G-2, H-2, J-2, K-1,
.: L-1, M-1, N-1, P-1, Qil, _. :
' R-1,'.A-5, B-4,.D-5, E-5' F-4, G-4~, H-6, P-6,-Q-5 R-6, F-9, G-9 E-15,'J E-30 285m3 /wk
. APP-1, APQ-1, APG-1, Gross beta, I-131 Weekiy Radioiodine and h Quaterly. compc, site 3700 r.3/qtr Particulates' 'APC-1 APE-30' y isotopic f y isotopic, H-3 QuarterJy 4 liters Ground Water GVJ-1 c d H-3 .Quarttriy composite Homogeneous i Drinking Water DWG-2, DWE-5 , LWP-7 Cross beta, y isotopic Monthly composite 4 liters I-131 E Semi-monthly composite
- d Quarterly composite Homogeneous Surface Water SWG-2,'SWE-5 , SWP-7 H-3 y isotopic ' Mon hly cocrposite 4 liters t
'y isotopic Semi-annually 2 kilograms
. Shoreline Sediment' SFWE-3, SHWJ-1 MKE-4, MKQ-5, MKQ-45, MKQ-1 .y isotopic, I-131 Semi-monthly / monthly 4 liters
.Hilk FH-1, FH y isotopic In season or g 500 grams I fish semi-annually
- y isotopic At harvest time 3 500 grams Food Products
~BLQ-1, BLB-1,.BLK-15 y iso *opic3 l I'- 131 Monthly 500 grams Broad-Leaf '< hen milk samples not collected
- Irrigated Food Pathway.does not exist. However, focd prodects grown within the site boundary are san: pled and analyzed.
UNT-005-014' Revision 1 Attachment 6.13 (1 of 2) 181 i
%W V ' re = w W g - '4 % W- 3 m._s" -w Mv - - - ' r-+
E f
~ RADIOLOGICAL'ENVIRONMENTAf, MONITORING PROGRAM (continued)
,fa. One or- more instrument, i nch as . a prassurizedL ion' chas;ber, ' for measuring. and recording . dose rate continuously may be used in-place oft or in-addition 1tonintegrating dosimetera. ALTLD is considered cne phosphor, two or l more phosphors in-a packat are considered two or more dosimeters. . Geographical limitations affect'sitingEof dosimeters.
j b. Airborne' particulate sample iilters shall;be, analyzed for gross beta' radioactivity 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after
- sampling to allow for radon and : thoron. daughter decay. If gross. beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopes analysis shall be' performed on the !
. individual samples. Gamma isotopic analysis means _the identification and quantification of gamma-emitting i radicnuclides:that may'be attributable to the effluents from the facility.
l
. Drinking Water and Surface. Water samples"are identical samples.
c.
- d. The downstream sample is beyond the mixing zone.
- e. A composite sample will containLaliquots of sample taken proportional to the quantity of flowing liquid that results in a specimen representative of the liquid flow.
- f. Ground water samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the: hydraulic gradient or recharge properties.are suitable for contamination.
This analysis will be performed when the dose calculated for the consumption of water is grester than 1 mrem .;
g.
per year as calculated for; maximum organ and age group.
-h. Milk will be collected semimonthly when animals are on pasture, monthly otherwise. If milk sampling is not performed,- broad leafy l vegetation will . b'e sampled. l Striped mullet, gizzard shad, freshwater drum,.and catfish will be collected. If they are not available,
.i.
substitute species will be collected and identified in reporting.
~
.j. One sample of each principal class of food products will be sampled in an area irrigated by water in which "
plant wastes have.been inadvertently discharged. If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If. harvesting occurs continuously, sampling shall be monthly.
Tuberous and root products will be sampled when available.
UMT-005-014- Revision 1 Attachment 6.13 (2 of 2) '
i 182
,w ,
. _ ~ _ - _ - - . . . . ~ . - . ~ . . . . - .... . _ .- . .~ - - . . . . . - . . - - . -
SAMPII LOCATION TABLE MILES FROM SECTOR LOCATION LOCAT10N DESCRIPTION PLANT DIRECTION NUMBER -
DIRECT-RADIATION (TLD)
A-2 (Eastbank) On fence enclosure surrounding 1.1 N water tower west of Little Gypsy opposite Etinenn St. Access from River Road (LA 628). The TLD's are located on the (5) fence opposite the entrance gate to the water tower.
B-1 (Eastbank) On fence enclosing the 0.8 NNE transmission tower 0.3 miles west (up-river) from Little Gyspy. . Access from River Road (LA 628). TLD's-are located at SW corner L of fence-enclosure.
-- C- l ' (Easthank) On fence enclosing the Little 0.B NE Gyspy Cooling Water Intake. Access is from River Road (LA 628) across from
.Little Gypsy Power Station entrance.
TLD's are on the south side (inside) of the Cooling Water Intake fence enclosure,
-directly opposite the entrance gate.
D '(Ea.ctbank) Located approximately 0.3 afles 1.1 ENE east. of Little Gypsy Power Station. Access from River Road'(LA 628) near the west end of the Bonne Carre Spillway. TLDs are on ,
the fence at the West entrance to the-spillway l(located on Icvee). ,
(Westbank)-Located on utility pole along 10.2- E-
~E-1 River Road (LA-18) approximately 0.3 miles "
east of W 'arford 3 plant entrance. Access
<from LA lu. TLD's are on the third. utility pole east of.the construction entrance road.
1.1- ESE LF-2 (Westbank) Located on fence enclosure surrounding the LP&L substation on LA 3142. Access from LA 3142 approximately
--0.2 miles souti. of LA 18. TLD's are on the southeast corner-of the lence enclosure.
. Attachment 6.14 (1 of 7)
- UNT-005-014 Revision 1 183
SAMPLE LOCATION TABLE (Continuedl MILES FROM SECTOR LOCATION LOCATION PLANT DIRECTION NUMBER DESCRIPTION-G-1 (Westbank) Located on utility pole on 1.2 SE East side of LA 3142 near Witco entrance gate (Next to Union Carbide Star Plant Gate 3). Access from LA 3142 approximately 0.2 miles corth of railroad overpass.
11 - 2 (Westbank) Located on fence enclosure 1.2 SSE l to shell road off of LA 3142, Access from LA 3142 sourth of railroad overpass on east side of LA 3142. TLD's are on the south side of the gate for shell road. (Just south.of Texaco pipeline station),
f-l J-2~ (Westbank) Located on northeast corner of 1.3 S fence enclosing Texaco valve station south of IA 3127. Access from IA 3127, approxmiately 0.6 miles west of LA 3127/3142 intersection.
E 1.0 SSW K-1 (Westbank) Located behind " Private Road"
-SIGN AT Gate 8 entrance off of LA 3127.
i- Access from LA.3127, approximately 1.3 L
miles' west of LA 3127/3142 intersecticn.
l~ (Gate'8 is the access to the Waterford 3 ,
l
-switchyard station and Training Center). l 1.0 SV
-L-1 (Westbank) Lccated behind~" Private Road" sign at LP&L Gate _9 entrance off of IA
-3127, approxistely 1.6 miles' west of L LA 3127/3142 intersection. (Gate 9 is E an access road for-Vaterford 3).
l .
0.7 WSW l
Mal (Westbank) Located on south gate;into
-ths Waterford l'and 2 fuel oil storage L
- tank enclosure. Access is either thru l~ LP&L Gate 8, Gate 9 off-of LA 3127, the l,
she11' access road froia!LA 18 between -
L Waterford 3,.or thru the Waterford'1 and:
l 2-access road, W
L 0.9 N-1, (Westbank) Located behind the "No L
Trespassing" sign off'on Short Street, in-Killona, just couth of the K111ona Elementa ry LSchool .
l-Attachment,6,14 (2 of 7)
UNT-005-014 Revision-1
_184
ma g = - e e v 9' 6 --+34- 4>--W4 >+MG3--a"6- J e ~L o-- &-suD-a4-ab Jsmoa & Lmam b+-a e :4 -A.---
a x A m-f SAMPLE LOCATION TABLE (Continued)_
LOCATION MILL 5 FROM SECTOR LOCATION DESCRIPTION PLANT DIRECTION N141BER
-P-1 (Westbank) Located on Short Street, TLD 0.8 WNW g
is inside fence at air sample r,tation APP ~
(Westbank) Locaced on fence enclosing air 0,F NW Q-1 sample station approximately 0.5 miles vest of Waterford 1 and 2 on River Road (LA 18).
R-1 (Westbank) Located on fence enclosure for 0.5 NNW Waterford I and 2 Cooling Water Intake Structure. Access is tram River Road (LA IS) opposite Waterford 1 and 2. TLD's are on the southwest corner of fence. ,
A-5 (Eastbank) Locaced on utility pole just 4.5 N east of the Shady Nook Trailer Park on Hwy 61 in Laplace. TLD's are on second 3 atility pole east of trailer park on north side of Hvy 61 (eastern end of Laplace).
B-4 :(Eastbank) Located on utility pole just 3.8 NNE ,
cast of shell access road to South Central Bell transmission tower on south side of Hwg 61. Transmission tower is just east of Weigh Station at_ St. John /St. Charles Parish line. ' TLD's are on_first utility 4
pole east of access road.
D-S (Eastbank) Located _on fence gate on shell 4.2 ENE access road _to Big 3 Chemical Plant.
Sht11 access road is approximately 0.1 miles west of Hwy 61/48 intersection (at black and yellow gate). TLD's are on fence' gate 0.1 miles north on shell access road'from Hwy 61.
E-5 -(Eastbank) Located on the Norco_ Substation - 4.2' E fence e'nclosure. Access from River Road (LA 48) onto Wesco St. (adjacent to Norco Shell Chemical Plant), take Wesco St. to -
the dead end. TLD's are . located on sixth fence post south of the north-substation gate.
LUNT-005-014' Revision 1 Attachment 6.14 (3 of 7) 185
SAMPLE LOCATION TABLE (Continued)
MILES FROM SECTOR LOCATION LOCATION PLANT DIRECTION NUMBER DESCRTSTION F-4 (Westbank) Located on utility pole behind 3.5 ESE blonde brick house on Aquarius St. In
. Hahnville. Access from River Road (LA 18) and turn onto Oak St. Follow Oak St. t.o Hickory St., turn right on Hickory St.
and follow to Aquarius St. and turn left.
Blonde brick house is second house on right (west) cade of Aquarius St. beading south.
G-4 (Westbank) Located on railroad cign 3.2 SE northwest side of LA 3160/ railroad t rack intersection. Access f rom either ?A 3127 or River Road (LA 18) onto LA 3160.
5.7 SSE H-6 (Westbank) Located on a road f sign on the Northwest side of the secotd canal bridge east of LA 3160 along LA 3127.
P-6 (Westbank) Located en utility pole at 5.5 WNW scuthvast corner of LA 640/ railroad track intersection. Utility pole is just went of LA 640 and east of radio L
transmission' tower.
(Westbank) Located on fence. post 5.0 NW
.Q-5 surrounding (green) river marker on levee just east of Edgard. Fence post'is located along River Road (LA
- 18) across from the Webre's house.
R-6 (Eastbnnk)' Located on' fence enclosing' 5.3 NNW LP&L Laydown Yard on LA 3223 in Laplace.
Access trom Hey 61 onto Elm St. (LA 3223),
take Elm St. to the-northeast corner of.
LA 3223/ railroad intersection. TLD's I are located at the' entrance of the fence enclosure.
(Eaotbank) Located on entrance gate 8.2 ESE F-9 to Destrehan Substation. Access from Piver Road (LA 48), approximate 1.5 miles. cast of Luling-Destrehan Bridge, onto Destrehan Road'(west of Bunge Corp. Grain Elevator), and proceed
-to substation gate.
Attachment 6.'14 (4 of 7)
_. UNT-005-014 Revision 1 186
______..i_.__.__.E______._._.__.______.__._.__.______ . _ _ _ ,-
I SAMPLE LOCATION TABLE (Continued)
~
MILES FROM SECTOR LOCATION LOCATION PLANT DIRECTION WUMBER DESCRIPTION _-
G-9 (Westbank) Located on back fence of 8.1 SE LP&L District Office in Luling. Access via Ellirwton St. from either River Road (LA 18); or Second or Third S.
from Paul Mallard Rd. (LA 52) to Ellington St.
E-15 (Eastbank) Located on Kenner Substation 11.8 E fence enclosure. Access from either ~
River Road (LA 48) or liwy 61, turn onto e
Alliaace Ave. TLD's are located at the entrance of the fence enclosure. l J-15 (Westbank) Located on fence enclosure 12.0 S surrounding LP&L switchyard at LA 631/llwg 90 intersection in Des Alleraands.
TLD's are on the northwest corner of fence. Access from LA 631 via shell road.
E-30* (Westbank) Located at LP&L General 27.0 E Office or Delaronde St. in Algiers.
TLD's are on a tree in the courtyard at the south en', m ee to the building.
Airborne APP-1 (Westbank) Located in soybean field 0.8 W at northwest corner of Short St. in Killona.
APQ-1 (Westbank) Located at northwest corner 0.8 NW oi soybean field cu east side of Killona.
Access f rcm River Road (LA 18) approxim-ately 0.6 miles east of LA 18/3141
' intersection.
APG-1 (Westbank) Located at the north side 0.5 SE of the Secondary Meterological Tower.
APC-1' (Easthank) located inside the Little Gypsy 0.8 NE Cooling Water Intake Structure fence enclosure.
UNT-005-014 Revision 1 Attachment 6.14 ($ of 7) 187
SAMPLE LOCATION TABLE (Continued)
MIL': 3 FROM SECTOR LOCATION LOCATION PLANT DIRECTION NUMBER DESCRIPTION APE-30* (Westbanh) Located on the roof of the 27.0 E LP&L General Office building on Delaronde St. in Algiers..
Food Products FPP-1 (Wstbank Located in field on eastern edge 0.8 WNW of Killona, between air sample stations APP-1 and APQ-1. The crops grown alternate s
between soybeans at.d sugar cane.
FPG-1 (Westbank) Located in field east of Water- 0.4 SE ford 3 near the Back-up Meteorological Tower and air sample station AFS-1. The crops grown alternate between soybeans and sugar-t cane.
w Broad Leaf (Westbank) Located between LA 18 and 0.8 NW BLQ-1 soybean field on eastern edge Killona, near air sample station APQ-1.
BLB-1 !Eastbank) Located at wooded area at *.he 0.8 NNE southwestern corner of the LP&L Little Gypsy plat:t along River Road.
15.0 SSW BLK-15* (Westbank) Located 3.5 miles SSW of _
Des Allemands on Hwy. 90.
1_nypstion Milk i (Westbank) Located at the Webre's houst., 5.0 NV MKQ-5 just across LA 18 from river marker, at the eastern end of Edgard.
42 NW MKQ-45* (Eastbank) Located'off of I-12 in Denham Springs. Take LA 3002 south of LA 1034 then right to LA 1032. Turr. left and go to farm 1 mile on the right.
1.0 NW MKQ-1 (Westbank) 1.0 miles west of Waterford-3 at the corner of River Road and Post Street in Killona.
Attachment 6.14 (6 of 7)
UNT-005-014 Revision 1 186
. ~. . - . . . ~ - - _ _ - _._-._ - .- . - _ . . _ - . _ _ . . - . ~.-. _ _ ---
SAMPLE LOCATION TABLE (Continued)
LOCATION MILES FROM SECTOR
~ LOCATION DESCRIPTION PLANT DIRECTION ,
NUMBER Fish F FH-1* Upstream of the plant intake structure. N/A N/A FH-2 Downstream of the plant intake structure. N/A N/A
' Waterborne GWK-1 (Westbank) Located at 40 Arpent Canal 0.5 SSW south of the plant. Access from LA 3127 through LP&L Gate 8 which is at the Waterford-3 Training Center. The canal is northwest of the shell access road /
railroad track intersection.
2,0 SE l l:' DWG-2 (Westbank) Located at the Union Carbide l SWG-2 drinking water canal. Access from LA L 3142 through Gate 28.
l-SINE-3 (Westbank) Located at the Foot Ferry 3.0 E Landing off of LA 18 in Taft. .
SINK-1 (Westbank) Located at,40 arpent canal 0.5 SSW l
- south of plant. Access thru LP&L gate 8 i off of LA 3127.
DVE-5 (Eastb'ank) Located at.the St. Charles 4.5 E ll SWE-5 Parisii Waterworks off of River Road
- (LA 48)- near New Sarpy.
ll DWP-7*E .(Westbank)' Located at the St. John Parish- 6.5 WNW l SWP-7* 1 Waterworks off of LA-18 in Edgard.
- DENOTES CONTROL LOCATIONS
- N/Al Not Applicable for this: sampling. location.
~
1 I
LUNT-005-014 Revision l' Attachment 6.14 (7 of 7)
L 189-
SECTOR AND ZONE DESIGNATORS FOR RADIOLOGICAL SAMPLING' I AND MONITORING POINTS
! SECTOR NOMENCLATURE ZONE NOMENCLATLTE' l2 CENTERLINE OF. SECTOR
- IN DEGREES TRUE NORTH 22 -
. MILES FROM SECTOR FACILITY ZONE FROM FACILITY l
.0 & 360 *A N. 0-1 1 1-2 2 22 B ..NNE C NE 2-3 3
'45 4 L
D ENE 3-4 1
67\ 4-5 5 ,
90 ,
E E ESE- 5-6 6 112\ F 6-7, 7 1 135 G- SE-7-8 8 157 H or SSE
~J S 8-9 9 180- 10 202 K .SSW 9-10 10-15 15
.225 L SW-M WSW- 15-20 20 247\ 20-25 25 270- N W P. WNW 25-30 30 292 35 315 -Q NW 30-35 R. NNW 35-40 40 337\ 40-45 45 45-50 50 L
AREA SEGMENT - An area is identified by a Sector'and Zone designator. Thus, area N-1 is that area which lies between 348 3/4 and lik degrees true north from the facility out to a radius of 1 mile. Area r G-4 would be that area between 123 3/4 to'146 k degrees and the 3- and 4-mile arcs from the facility.
For Airborne, Ingestion (milk), and Food Products pathways, the sector designator will be preceded by; acronyms AP, MK, and FP, respectively.
- The letters I and 0 have been omitted from these sector designators 'so as to eliminate possible re::iusion between letters and numbers.
l Attachment 6.15 (1 of 1)
'UNT-005-014 Revision 1 190
REMP SAMPLING LOCATIONS WITHIN 2 MILES OF WATERFORD 3.
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Attachment 6.16 (1 of 1)
UNT-005-014 Revision 1 191
REMP SAMPLING LOCATIONS WITHIN 10 MILES OF WATERFORD 3 I So 2 0' 90 30' A I f j -
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Attachment 6.17 (1 of 1)
UNT-005-014 Revision 1 192
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SPECIFICATION CROSS liEFERENCE TABLE Methodology Specification Requirement Section Section 5.3.1 Liquid Etfluent Concentration 5.3.5 & 5.3.6 5.3.2 Dose due to Liquid Effluents 5.3.4 5.3.3 Dose Projections for I.iquid Releases 5.3.7 5.4.1 Dose Rate Due to Noble Gases 5.4.5 & 5.4.8 -
5.4.1 Dose Rate Due to Iodine, Tritum 5.4.5 & 5.4.8 And Particulates with Half Lives Greater than Eight Days 5.4.2 Air Doses due to Noble Gases 5.4.6 5.4.3 Doses Due to Iodines, Tritium 5.4.7 and Farticulstes with Half-Lives Greater than Eight Days.
5.4.4 Dose Projer.tions for Gaseour Releases 5.4.9 5.5.1 Total Dose 5.5.2
-5.6.1 Radioactive Liquid Effluent Monitoring 5.3.5 Channels Alarm / Trip Setpoints 5.6.2 Radioactive Gaseous Effluent 5.4.8 Monitoring-Channels Alarm / Trip Setpoints Radiological Environmental 5.E.4 5.8.1 Monitoring Program Interlaboratory Comparison Program 5.8.5 5.8.2 Land Use census 5.8.3 5.8.3 UNT-005-014 Revision 1 Attachment 6.19 (1 of 1) 194
+
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TEClINICAL SPECIFICATION CROSS REFERENCE TABLE Specification.
Technical Specification Section Requi remer4 Seetion Liquid Effluent Concentration 3.11.1.1, 5.3.1 4.41.1.1.1, 4.11.1.1.2 5.3.2 Dose due to Liquid Eifluent s 3.11.1.2 &
4.11.1.2 Dose Projections for Liquid Releases 3.11.1.3, 5.3.3 4.11.1.3.1 &
4.11.1.3.2 Dose Rate Due to Noble Gases 3.11.2.1, 5.4.1 4.11.2.1.1, 4.11.2.1.2 &
4.11.2.1.3 Dose Rate Due to Iodine, Tritum 3.11.2.1, 5.4.1 And Particulates with Half Lives 4.11.2.1.1, Greater than Eight Days 4.11.2.1.2 &
4.11.2.1.3
-5.4.2 Air Doses due to hoble Gasri 3.11.2.2 &
4.11.2.2 5.4.3 Deses Due to lodines, Tritium 3.11.2.3 &
and Particulates with Half-Lives 4.11.2.3 Greater than Eight Days.
Dose Projections for Gaseous Releases 3.11.2.4, 5.4.4 4.11.2.4.1 &
4.11.2.4.2 Attachment 6.20 (1 of 2)
UNT-005-014 Revision 1 195
TECHNICAL SPECIFICATION CROSS REFERENCE TABl.E (cout'd) l Technical Specification Specification Requirement Section
_ Section 3.11.4, 4.11.4.1 &
5.5.1 Total Dose 4.11.4.2 5.8.1 Rad'.ological Environmental 3.12.1 & 4.12.1 Monitoring Program e 5.8.2 Interlaboratory Comparison Program 3.12.3 & 4.12.3 5.8.3 Land Use Census 3.12.2 & 4.12.2 5.6.1 Radioactive Liquid Effluent Monitoring 3.3.3.10 &
Channels Alarm / Trip Setpoints 4.3.3.10 Radio.ctive Gaseous Effluent 3.3.3.11 &
5.6.2 ,
Monitoring Channels Alarm / Trip 4.3.3.11 .
Setpoints Attachment 6.20 (2 of 2)
UNT-005-014 Revision 1 196
r .
SPECIFIC FACTORS USED TO DETERMINEg A and R3VALUES FOR THE OFFSITE DOSE CALCULATION MANUAL
-Values for A and g
R were-calculated g
as per.NUREG-0133. Recommended values for various factors in the calculations were as specified in NUREG-0133. The location of most of the recommended factors are coatained in Regulatory Guide 1.109. All-factors used in Waterford-3 SES's calculations are for the maximum individual and are not site specific. The various factors are discussed below.
Stable element transfer coefficients for vegetation, cow's milk, and meat were obtained from Regulatory Guide 1.109 Table E-1.
Stable element transfer coefficients for goat's milk were obtained f rom Regulatory Guide 1.109 Table E-2. t Animal consumption rates were obtained from Regulatory Guide 1.109 Table E-3.
Usage or consumption rates for adult, teen, child, and infant age groups were obtained from I.egulatory Guide 1.109 Table E-5. These values art for the maximum j exposed individual.
External dose factors for standing on contaminated ground were obtained from 5
- Regulatory Guide 1.109 Table E-6.
Inhalation tnd ingestion dose factors for adult, teen, child, and infant age groups were obtaine d f r,m Regulatory Guide 1.109 Tables E-7 through E-14.
Other factorn used were obtained from Regulatory Guide 1.109 Table E-15=for various parameters.
Bioaccumulation factors for freshwater and saltwater vertebrates'and invertebrates are listed on the following page.
UNT-005-014 Revision 1 Attachment 6.21 (1 of 2) 197 6 -l
l h ...
B10ACQMJLA110N f ACTORS FOR VAtlGJS ELEMENTS IN AN AQUATIC Ewy1ROMMENT ELEMENT FRESN Fl5H FRESN lWV EALT FISM 1 ALT *lWV N 9.00e 1 9.00e 1 9.00e 1 9.30e 1 C 4.60e+3 9.10e+3 1.80c3 1.40e+3 he 1.00e+2 2.00e+2 6.70e 2 1.90e 1 P 1.00e+5 2.00e+4 2.90e+4 3.00e+4 Cr 2.00c2 2.00e+3 4.00e2 2.00e3 nn 4.00e2 9.00e+4 5.50e+2 4.00e+2 Fe 1.00e+2 3.20e+3 3.00c3 2.00c4 to 5.00e1 2.00c2 1.00e2 1.00e3 Ni 1.00e2 1.00e+2 1.00e2 2.50c 2 Cu 5.00e1 4.00e2 6.70e*2 1.70e3 2n 2.00e3 1.00c4 2.00e+3 5.00e4 tr 4.20e2 3.30e2 1.50e 2 3.10c0 f ab 2.00e3 1.00e+3 8.30e0 1.70e+1 $
3.00e1 1.00c 2 2.00cc 2.00e1 Sr Y 2.50e1 1.00c3 2.50c1 1.00e3 )-
2r 3 g30e+0 6.70e+0 2.00e2 8.00e1 ub h00c4 4
1.00e+2 3.00e+4 1.00c2 I[>
Mo 1.Coet 1.00e1 1.00e+1 1.00e1 Tc 1.50e+1 E.00e+0 1.00e1 5.00e*1 2u 1.00c1 3.00e2 3.00e+0 1.00e3 As 2.00e+0 8.00e2 3.00c3 3.00c3 Te 4.00c 2 6.10e+3 1.00e1 1.00c 2 1 1.50e1 5.00e4 1.00e1 5.00e1 Ca 2.00e3 1.00e3 4.00c1 2.50e+1 34 4.00e0 2.00e+2 1.00e1 1.00e2 La 2.50e 1 1.00e+3 2.50e+1 1.00c!
Ce 1.00e0 1.00c3 1.00c1 6.00e 2 Pr 2.50e1 1.00e3 2.50e1 1.00e+3 Nd 2.50e+1 1.00c3 2.50e1 1.00s>3 W 1.20e3 1.00e+1 3.00e1 3.00c1 up 1.00e1 4.00c2 1.00e1 1.00e+1 Data obtained f rcen Regulatory Guide 1.109 f ebte A 1 for f att elements except Silver (Ag) which 16 frcen *Models and Parameters f or Envirarsmental tediological .'ssessmente" .- -
fnf (DCE/ TIC 11448) and utrbluen(ne) which to frem the (
Interectional Atcenic Energy Agency (IAEA) Safety Series ho. 57, Generic Models and Parameters f or Assessing the 3{
Environmental Transfer of sodionuclides f rain Routine teleases, Exposure 1 of Critical Grotos.
Attachment 6.21 (2 of 2)
UNT-005-014 Revision 1 10R
\
PORC/PORC-- t -
m
.U UNT-005-014 REVISION O EFTECTIVE DATE :
s SAFETY-RELATED 1
ADMINISTRATIVE PROCEDURE Offsite Dose Calculation Manual
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R' G?DS y .:. 22NT eg e -4 ,p >< e-
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UNT-001-002 Revision 12 Attachment 6.3 (1 of 2) 41.
- PORC AND-PORE---S/E REVIEW AND APPROVAL SHEET PORC 5:
REVIEW OF: UNT-005-014 - Offsite Dose Calculation Manual (Rev. 0) PORC - S/C O The PORC or PORC S/C has reviewed this item and determined that a Safety /
Commitment Review was performed, (if applicable) that a Safety Evaluation was performed (if applicable), that an unreviewed safety question does not exist and that nuclear safety is/was not adversely affected.
^ DATE PORC MEMBER SIGNATURE YES NO MEMBER Maintenance ,
Superintendent I ig g 4 t / kl@b u r dent h Radiation Protection Superintendent ( g/ [ .
~6
]
Operations Quality /
J Assurance Manager V
, f' I- 0.
Plant Er.gineering //
Superin'.endent Assistant Plant Manager PORC-S/C Member -
PORC-5/C Member PORC-S/C Member PORC-S/C Chairman g PORC Chairman ,] / f[hi p
. Meeting No.90-067 Item No. VIII-B Date: 8/2/90 This item is recommended for approval? E YES O NO This item requires SRC/NRC review prior to implementation? O YES E NO If yes, ensure documentation supporting review is attached.
PIANT MANAGER-NUCLEAR APPROVAL Comments: _f
O f. / ,hi h / /1 Appr ed by man % lh Da e f[Jhd Pla'at Mdnager-Nucb6ar //
LWT-001-004 ev sion 12 Attachment 6.1 (1 of 1)
L_ .- _ __.______ - _ _ _
WAIERFORD 3 SES PLANT OPERATING MANUAL Check Block Below NEV PROCEDURE REQUEST l@PORCl((PORC-S'/C l
[] O PROCEDURE TYPE in A i "' * ""
PROCEDURE NO.UNT-005-014 REV. NO.
TITLE Of f nite Done Calculation Manual Sys . N et EFFECTIVE DATE 7 te n *D-c?(II APPLICABLE)
AUTHOR Iiernadette a. Lee T IRATION DATE (IT APPLICABLE)
DESCRIPTION OF PROCEDURE ~ncorporate kaatological Erfluent Tech speen (nETn) and The Radiolocical Environmental Monitoring Program (R!MP) into existing Offsite Dose Calculation Manual ( llP-001 -2 3 0 ) and make into an UNT procedure, s
REASON FOR PROCEDURE US 20 Genoric Lc ter, o';ed January 31, 1935, allowed f or the RETS and 'U.:MP to be incorport w n:o the Offsite Doce Calculation Manual. Once thic oraenaurr- ;; enoc;ve. m; ;he URC, these po;-tiann of the Toch Soecs will be deleted, v
// ? ,i> I (n AUTHORI ED BY M / m.on M t w .,.I [ DATE 4/.7 MlIbtManager-Nuclear (POM) / /
/ J SAFETY StRrD ENG/ EVALUATION L8u 9-J3-96 Signature, Author Date
/
x/7/ J,i 4d<2-#A
~ 7 -J' r - 1D IECHNICAL REVIEW ~ /
Date N Gituature.
i Techns. cal Reviewer GROUP HEAD REVIEW-r- b /.J lT ( A /d. k '//hi[9c
'Date j/ / ' Signat:1re, Group Head Applicable Conditions (Temporary Procedures Only):
UNT-001-003 Revision 12. Attach =wmt 6.4 (1 of 1) 30 I- - - - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _________ _ _ _ _ _____
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UhT-005-014 l
-Administrative Procedure ,
Offsite Dose-Calculation Manual Revision 0-TABLE OF CONTENTS 1.0 PURPOSE ,
2.0 REFERENCES
3.0 DEFINITIONS 4.0 RESPONSIBILITIES
. -5.0 PROCEDURE 3 5.1 Site Characteristics 5.2 ' Specifications and Surveillance Requirements 5.3 ' Liquid Ef flut ats 5.4 Gaseous Effluents 5.5 Total Dose
'5.6 Instrumentation .
- 5. 7- Liquid and Gaseous Radwaste Processes 5.8 Radiological Environmential Monitoring Program Requirements .
5.9 Technical Specification Cross-References 6i ATTACHMENTS 6.1 Site Boundary for Radioactive Gaseous and Liquid Effluents 6.2' Historical Average Dispersion and Deposition Parameters for Areas at or Beyond the Unrestricted Area Boundary -
6.3 : Site Related Liquid Ingestion-Dose Commitment Factors (Ag ) for Individual'Nuclides 6.4 Dose Factors for Exposure to_a Semi-Infinite Cloud of Noble Gases 6.5- Inhalation Pathway Doses Due to-Radionuclides Other Than Noble Gases, R g 6.6 Ground Plane Deposition Pathway Dose Factors Due-to Radionuclides-
-Other Than Noble Gases, Rg .
6.7 Cow's Milk Pathway Dose Factors Due to Radionuclides Other Than p Noble Geses,'R g 1
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
6.8 Meat Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R g 6.9 Leaf Vegetable Pathway Doce Factors Due to Rndionuclides Other Than Noble Gases, R g 6.10 Goat's Milk Pathway Dose Factors Due to Radionuclides Other Than Noble Gases, R g 6.11 Liquid Vaste Management System Effluent Sources and Release Pathways and Points 6.12 Gaseous Effluent Sources, Gaseous Waste Management Systems Effluent Sources ano Exhaust Release Points !
6.13 Radiological Environmental Monitoring Program 6.14 Sample Location Table 6.15 Sector and Zone Designators for Radiological Sampling and Monitoring Peints 6.16 REMP Sampling Locations Within 2 Miles of Waterford 3 6 17 REMP Sampling Locations Within 10 Miles of Waterford 3 6.18 REtiP Sampling, Locations Within 50 Miles of Waterford 3 6.19 Specifications Cross-Reference Table 6.20 Technical Specification Cross-Reference Table LIST OF EFFECTIVE PAGES Title Revision 0 1-196 Revision 0 0
2
y UNT-005-014 Administrative Procedure Offsite Dose Calculation Manua'l~. -
Revision 0-Q 1.0 PURPOSE 1.1 The offsite Dose Calculation Manual (ODCM) is a supporting document of the Waterford 3 Technical Specifications. This document provides (1) The Radiological Effluent Specifications and Radiological Environ-mental Monitoring Program required by Technical Speciffcation 6.8.3; (2) the general characteristics of the Waterford 3 site; (3) the detailed Radiological Environmental Monitoring Program (REMP); (4) the description of the Radiological Environmental Monitoring Inter-laboratory Comparison Program; (5) the liquid and gaseous radwaste block flow diagram; (6) the Radioact'ive Liquid and Gaseous Waste Sampling and Analysis Programa; (7) the general methodology to be
, used to calculate dose to individuals due to releases of radioactive gaseous and liquid effluents from the Waterford 3 site; (8) the general methodology to the used to calculate effluent monitor setpoints O and allowable release rates to ensure compliance with the Radiological Effluent Controls, 10CFR20, and 10CFR50 criteria; (9) the methodology to be used to ensure representative sampling of liquids; and (10) the methodology to be used to comply with 40CFR190 criteria.
1.2 The Offsite Dose Calculation Manual (ODCM) follows the general models suggested by NUREG 0133 and Regulatory Guide 1.109. However, alternate calculatico methods from those presented may be used provided the overall methodology is acceptable and consistent with regulation or.
provided the alternate methodology is conservative. In addition, the most up-to-date dose conversion factors and bioaccumulation factors may be substituted in lieu of Regulatory Guise 1.109 values.
1.3 Actual step-by-step dose calculation will be performed by in-plant procedures which are consistent with the methodology presented in this document.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O
2.0 REFERENCES
2.1 Waterford 3 SES Technical Specifications, Chapter 16 of Waterford 3 FSAR.
2.1.1 Technical Specification 6.14.1 2.1.2 Technical Specification 6.14.2 2.2 USNRC Regulatory Guide 1.111, Pethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases for Gaseous-Effluents from Light-Water-Cooled Reactors, July 1977.
2.3 USNRC Regulatory Guise 1.113, Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I, April 1977.
O 2.4 USNRC Regulatory Guide 1.109, Calculation of Annual Doses to Man .
from Routine Releases of Reactor Ef fluents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix 1, Revision 1, October, 1977.
2.5 USNRC NUREG 0133, Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, October 1978.
l 2.6 Code of Federal Regulations.. Title 10, Parts 20, 40, 50 and 100, 1987; Title 40, Part 190.
2.7 HP-001-215, NRC and EPA Ra.iological Reporting Requirements l
2.8 USNRC Generic Letter 89-01, Implementation of Programmatic Controls l
for Radiological Effluents Technical Specifications in the Administra-l l tive Controls Section of the Technical Specification and the Reloca-tion of Procedural Details for RETS to the Offsite Dose Calculation lh Manual or to the Process Control Program.
2.9 .UNT-006-010, Event Notification and Reporting 4
' Administrative Procedure UNT-005-014 Offsite' Dose Calculation Manual Revision O l 0
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- 3. 0 DEFINITIONS.
3.1 ' ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions.
3.2 CHANNEL CAllBRATION shall be the adjustment, as necessary, of th e channel output such that it responds with the necessary range and accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel including the sensor and alarm and/or trip functions, and shall include the
. CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by i any series of sequential, overlapping, and total channel steps such that the entire channel is calibrated.
3,3 A CHANNEL CHECK shall be the qualitative assessment of channel O' behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter. ,
3.4 A CHANNEL FUNCTIONAL' TEST shall'be:
- a. Analog channels - the injection of a simulated signal into channel.as close to the sensor as practicable to verify-OPERABILITY including alarm and/or trip functions.
b.. Bistable channels - the injection of a_ simulated signal-into the sensor to verify OPERABILITY including alarm and/or trip functions.
- c. Digits 1 computer channels - the exercising of the digital.
computer hardware using diagnostic programs and the injection of simulated process data into the channel to verify OPERABILITY including alarm-and/or trip function.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 G 1 3.0 DEFINITIONS (cont'd) 3.5 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the following intervals. 1 i
i NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
W At least once per 7 days.
M At least once per 31 days.
P Completed prior to each release.
i Q At lesst once per 92 days SA At least once per 184 days.
R At least once per 18 months.
S/U Prior to each reactor startup.
N.A. Not applicable.
l 3.6 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the licensee, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or make deliveries. This category does include persons who l
use portions of the site for recreational, occupational, or other purposes not associated with the plant.
3.7 A system, subsystem, train, componer.t, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, electrical power, required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support function (s).
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Administrative Procedure- UNT-005-014 Offsite Dose Calculation Manual Revision-0 O
3.0 DEFINIT]ONS (cont'd).
3.8 An OPERATIONAL MODE (i.e. MODE) shall correspond to any one inclusive combinatio'n of core reactivity condition, power level and averaSe reactor coolant temperature as specified. ,
i REACTIVITY % OF RA'ID _ AVERAGE COOLANT OPERATIONAL MODE CONDITION, K THERMAL POWER
- TEMPERATURE ff
- 1. POWER OPERATION > 0.99 > 5% 2 350*F
- 2. STARTUP > 0.99- 15% 1 350'F
- 3. HOT STANDBY < 0,99 0 > 350'F
- 4. HOT SHUTDOWN < 0.99 0 350'F) T,yg>200*F i
'5. -COLD SHUTDOWN < 0.99 0 1 200'F
- 6. REFUELING ** 5 0.95 0 5 140*F h-l
- Excluding decay heat.
l.
- Fuel in the reactor vessel with the vessel head closure bolts less than
_ fully tensioned or with the head removed.
3.9 PURGE or' PURGING shall be the controlled process of discharging air or gas from-a confinement to maintain temperature, pressure, l-humidity, concentration or other operating condition, in such a l
manner _that'~ replacement air or gas is-required to purify tb-confinement.
3.10 The SITE BOUNDARY shall be that line__beyond which the land is neither.
I- owned, nor leased,-nor otherwise controlled by the licensee.
3.11 A' SOURCE CHECK shall be-the qualitative' assessment of channel response when the channel sensor is exposed to a source of increased radioactivity.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 3.0 DEFINITIONS (cout'd) 3.12 An UNRESTRICTED ARE/. shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreation purposes. j l
3.13 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radiciodine or radioactive material in particulate form in effluents by passing ventilaticn or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment.. such a system is not considered to have any effect on noble gas effluents.
Engineered Safety Feature (ESF)( atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
3.14 VENTING shall be the controlleo process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.
Vent, used in system names, does not imply a VENTING process.
3.15 A WASTE GAS HOLDLTP SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 4
4.0 RESPONSIBILITIES -
4.1 Nuclear Plant Operations Manager has lead responsibility for insuring implementation of the Radiological Effluent Specifications and Radiological Environmetal Monitoring Program as required by Technical Specificat2on 6.8.3 and as set forth in this procedure. I l
4.2 The Radiation Protection Superintendent is responsible for ensuring Radiological Effluent Specifications and the Radiological Effluent Monitoring Program are performed as required according to procedures and methodologies established by the document. He is also responsible for inauring the Land Use Census and Semi-Annual Effluent Release Report are performed and issued as required.
4.3 Nuclear Operations Support and Assessment - Manager is responsible
- for the issuance and submittal of the Annual Environmental Report as required by this document. He is-also responsible for the negotiation and mainenance of vendor contracts to supply Sample Analyses and Reports as required by the. Radiological Environmental Monitoring Program.
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UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 0
- n PROCEDURE 5.1 SITE CHARACTERISTICS Waterford 3 SES is located on the west (right descending) bank of the Mississippi River at River Mile 129.6 between Baton Rouge, Louisiana, and New Orleans, Louisiana. The site is in the north-western section of St. Charles Parish, Louisiana, near the towns of Killona and Taft.
The geographic coordinates for the Waterford 3 reactor are Latitude 29' 59' 42" North, and Longitude 90* 28' 16" West. Based on the UTM (Universal Transverse Mercator) Zone 15, the UTM cooroinates are Northing 3,320,743 meters and Easting 743,962 meters.
The Mississippi River is the closest prominent oatural feature to Waterford 3, while other important nature features include Lac des Allemands, about 5.5 miles southwest of the cite, and Lake Pontchar-train, about 7 miles northeast of the site. The land slopes gently from its high points near the Mississippi (10-15 ft. above mean sea level) to extensive wetlands located 1.5 to 2.5 miles inland from the river.
Most of the man-made features are located on the narrow strip of dry land between the Mississippi River and the wetlands. Near the Waterford 3 site are several large industrial facilities, including Waterford 1 and 2 (0.4 miles northwest of the site), Little Gypsy -
Steam Electric Station (0.8 miles northeast of the site, acron the river from Waterford 3), Agrico, a fertilizer manufacturer b '
miles east-southeast), Occidental Chemical Company (0.8 miles east-southeast), and Union Carbide, a chemical manufacturer (1.2 miles east-southeast). Louisiana Power & Light Company (LP&L) owns and operates the above-mentioned steam electric stations.
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Administrative ?rocedure UNT-005-014-I Offsite Dose Calculation Manual Revision 0 O
5.1 SITE CHARACTERISTICS (cont'd) ;
Attachment 6.1 provides a uap of the UNRESTRICTED AREA and SITE l BOUNDARY for radioactive effluents. LP&L will have full control of all activities conducted within the exclusion area boundary of the Waterf'rd 3 site. All of the property within the designated exclusion area is owned by LP&L with the exception of the bottom lands below mean low water of the Mississippi River.
LP&L owns, in title, all surface rights within the exclusion area boundary of the plant. There is presently no intention to allow exploration for subsurface minerals from points on the surface of the exclusion area.
The Mississippi River, Louisiana Highway 18, the Missouri Pacific O Railroad right-of-way, and the west (right descending) bank levee of the Mississippi River constitute traversals of the site exclusion area as allowed by 10CFR100.3 (a). Refer to the Waterford 3 Emergency Plan Implementing Document for the arrangements which have been made to give LP&L authority and control over these traversals.
(Note that Louisiana Highway 3127 does traverse the SITE BOUNDARY but not the-exclusioncarea, However, LP&L does have'the authority to control this traversal in accordance with the Waterford 3 Emergency Plan-Implementing Document.)-
In addition to Waterford 3, there are two fossil-fueled units, Waterford SES Units 1 and 2, which are owned by LP&L and which are within the site exclusion area. The plant staff for these two units consists of about 60 people. Since this includes workers assigned to shifts,'it is a conservative estimate of the maximum number of fossil plant personnel that would be within the exclusion area at any given time. Evacuation procedures for Waterford SES Units 1 and.
2 are described in the Waterford 3 Emergency Plant Implementing Document.
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UNT-005-014 Administrative Procedure Revision 0 Offsite Dose .alculation C Manual 0
5.1- SITE CHARACTERISTICS (cont'd)
A portion of the land within the SITE BOUNDARY is utilized for agricultural activities. Farmers presently work the land but can be expected to actually be in the field less than 10 percent of the time.
Fishing in the Mississippi River from the batture is a rare practice in the Waterford area. An estimated maximum of 2 people may be expected to be engaged in this activity for a period less than 10 percent of the time within the exclusion area.
Texaco maintains a gas valve station east-southeast of the Waterford 3 SES island structure just within the radius of the exclusion area. This valve station is automated and requires only periodic monthly maintenance involving, typically, two persons. Evacuation procedures for these maintenance workers are described in the Waterford 3 Emergency Plan Implementing. Document.
The Waterford property is shown in Figure 5.1-3 of the STS and includes 3,561.3 acres. The plant area is about 48 acres and is defined as including the fenced area immediately adjacent to Waterford 3. The site area is shown in Figure 5.1-3 of the STS along with principal station structures and nearby features. The site includes only station structures and does not include any residential, recreational, or other industrial structures. There is a visitor center and adjacent recreational area approximately 1.0 mile SSW of the plant.
The SITE BOUNDARIES for establishing effluent release limits along with radioactive effluent release points are given in Attachment 6.1. The nearest distances to the boundary line are shown in Attachment 6.2 of this procedure. The release point elevations for gaseous effluents are provided in Attachment 6.1.
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- Administrative Procedure 1 Revision 0 -j Offsite Dose Calculation Manual - !
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- 5.1 SITE CHARACTERISTICS (cont'd)
The restricted area, defined for the purpose of controlling ingress into and egress from the site, coincide with the plant area which is enclosed by the plant perimeter fence.
For the purpose of establishing effluent release limits in accordance l with 10CFR20 and Appendix 1 to 10CFR50, the concept of the restricted area, -as defined above for the purpose of ingress and egress control, is not applicable. The effluent release limits are established in order to ensure that: (1) the concentrations of the radionuclides in gaseous effluents discharged from the plant stack and exhaust systems do not result in exceeding .he limits outside the site boundary set forth in Table II, Column 1 of Appendix B to 10CFR20; (2) the concen-tration of radionuclides in liquid effluent at the unrestricted area O, boundary does not exceed the iimits set forth in Table II, Column 2 of Appendix B to 10CFR20; and (3) the cumulative liquid and gaseous radionuclide releases do not result in exposures to individuals outside the UNRESTRICTED AREA or SITE BOUNDARY in excess of the limits set-forth in Appendix I to 10CFR50, 1980 population by annular sectors within 5 miles or Waterford 3 can be found in the En.rironmental Report. Population waa estimated for 1977 and projected for 1980. The methodology for estimating and projecting population is described in detail in section 6.1.4.2 of the Environmental Report. The closest town to Waterford 3 is Killona, 0.9 miles west-northwest. Other towns near the plant include Forco 2.5 miles east; Hahnville, 3.7 miles east-southeast; and Laplace, 4.7
-miles north. There are also smaller-settlements and homes along both banks of'the river, the nearest such place to Waterford 3 being Montz, 1.0 mile northeast.
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UNT-005-014 Administretive Procedure Offsite Dose Calculation Manual Revision 0, O
5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.1 Compliance with the SPECIFICATIONS contained in the succeeding sections is required during the OPERATIONAL MODES or other conditions specified therein; except that failure to meet the SPECIFICATIONS requires that the associated ACTION requiremer.ts shall be met.
5.2.2 Noncompliance with this procedure shall exist when the require- ,
1 ments of the SPECIFICATION and/or associated ACr70N requirements ;
i are not met within the specified time intervals. If the l SPECIFICATION is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.
5.2.3 Surveillance Requirements shall be applicabic during all OPERATIONAL MODES or other conditions specified for individual systems unless otherwise stated in an individual Surveillance Requirement.
5.2.4 Each Surveillance R'equirement shall be performed within the specified time ' interval with:
5.1.4.1 A maximum allowable extension not to exceed 45% of the surveillance inte.rval.
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.5.2 SPECIFICATIONS AND SURVEILLANCE REQUIREMENTS 5.2.5 Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet j the OPERABILITY requirements for a Specific System for Operation. Exceptions to these requirements are stated in
.the individual specifications. Surveillance Requirements do not have to be performed on inoperable equipment. ,
5.2.6 . Failure to comply with the compensatory ACTION requirements or failure to-complete the surveillance requirements within
- the specified time shall be documented and evaluated in accordance with Reference 2.9.
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Administrative Procedure UNT-005-014 0'ffsite Dose Calculation Manual Revision 0 0i 5.3 LIQUID EFFLUENTS 5.3.1 Concentration Specification The concentration of radioactive material released in liquid effluents to UNKESTRICTED AREAS (see Attachment 6.1) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or !
entrained noble gases, the concentration shall be limited to 2 x 10 microcurie /ml total activity.
APPLICABILITY: At all times ACTION:
O With the concentration of rad 4oactive material released in i
liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, and describe the events leading to this condi-tion in the next Semiannual Radioactive Effluent Release Report.
SURVEILLANCL REQUIREMENTS l
l a. Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 5.3-1.
- b. The results of the radioactivity analyses shall be used in accordance wit 5 the methodology and parameters in section 5.3.5 to assure that the concentrations at the polat of release are maintained within the limits of l Specification 5.3.1.
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Administrative Procedure UNT-005-014 Offsite Dose. Calculation' Manual- Revision 0 O
TABLE 5.3-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYfils PROGRAM LOWIR LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a -
TYPE- FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
A. Batch Waste P P Each Batch Each Batch Principa(Gamma 5x10 7 Releasg,f,g,h,i Emitters Tanks I-131 1x10 6
- 1. Boric Acid Condensate P M Dissolved and 1x10 5 Entrained Gases
- 2. Waste One Batch /M (Gamma Emitters)
Condensate P M H-3 1x10 6 d
Each Batch Composite
- 3. .Laund ry Gross Alpha 1x10 7 Waste P Q Sr-89, Sr-90 Sx10 "
d -
- 4. . Turbine Each Batch Composite
-Building ,
Industrial Waste Fe-55 1x10 6 Sumps *
- 5. Dry Cooling Tower Sumps
- 1 and #2*
- 6. Regenerative Waste
. 7. Filter Flush
- 8. Vaste O *When release from this source is batch in nature.
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UNT-005-014 Administrative Procedure Revision 0 l Offsite Dose Calculation Manual 9
TABLE 5.3-1 (Continued)
LOWER LIMIT MINIMUM OF DETECTION SAMPLING ANALYSIS TYPE OF ACTIVITY (LLD)a LIQUID RELEASE (pCi/mL)
TYPE FREQUENCY FREQUENCY ANALYSIS B. W W Continuoug 5x10 7 Release #' Grab Sample PrincipagGamma Emitters 1-131 1x10 6
- 1. Turbine Building Industrial Waste Sumps **
M M Dissolved and 1x10 b
- 2. Dry Cooling Grab Sample Entrained Gases Tower .
(Gamma Emicters)
Sump #1***
W M H-3 1x10 6 d
- 3. Dry Cooling Grab Sample Composite Tower Samp #2**i Gross Alpha 1x10 7 F Q Sr-89, Sr 90 5x10 "
d
- 4. Circulating *. Grab Sample Composite -
Wat,er Discharge- Fe-55 1x10 6 Steam Gene-rator Blnw-down HX--
- 5. Auxiliary Component Cooling Water g Pumps
- When release from this source is continuous in nature.
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Administrative Procedure UNT-005-014 Offcite Dose Calculation Manual Revision 0 O
TABLE 5.3-1 (Continued)
LOWER LIMIT MINIMUM OF DETECTION LIQUID RELEASE SAMPLING ANALYSIS TYPE OF ACTIVITY (Lil))a TYPE FREQUENCY FREQUENCY ANALYSIS (pCi/mL)
-B. W W PrincipagGama Continuoug k d 2 Release *' Continuous Composite Emitters 5x10 7
- 6. Steam Generator 1-131 1x10 6' Blowdown .
Discharge3 '
M M Dissolved and 1x10 b Grab Sample Entrained Gases (Gamma Emitters)
W M H- 1x10 b d
Continuous Composite Gross Alpha 1x10 7 W 9 Sr-89, Sr-90 5x10 6 k d Continuous Composite Fe-55 1x10 6 m
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Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
TABLE 5.3-1 (Continued)
TABLE NOTATION
'The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system backgrcund, that will be detected with 95% probability with only 5% probability of falsely concluding tbst a blank observation represents a "real" Signal.
1 For a particular measurement system, which may include radiochemical ]
separation: )
LLD e 4.66 s b E . V . 2.22 x 10' . Y . exp (-Aat)
Where:
LLD is the "a priori" lower limit of detection as defined above, as microcuries per unit mass or volume, sg is the standard deviation of the background counting rate or of the c5unting 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 fraction radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.
Typical values of E, V, Y, and At should be used in the calculation.
It should be recognized that the LLD is defined as an a priori (before the fact) limit representing th c. , Uility of a measurement system and not as an a posteriori (after the fart 'lmit for a particular measurement.
b A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in Section 5.3.6 to assure re.presen-tative sampling.
O 20
i Athinistrative Procedure '
UNT-005-014 .
l Offsite Dose Calculation Manual Revision 0 1 RELE 5.3-1 (Continued [
'lahtE NOTATIONS The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54, re-$9, Co-58, Co-60, Zu-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Specification 6.9.1.8.
A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the <
met. hod of sampling employed results in a specimen that is representative of ;
the liquids released.
'A continuous release is the discharge of liquid wastes cf a nondiscrete volume t.g., from a volume of a system that has an input flov during the continuous release.
I Prior to analyses, all samples taken for the composite shall be thoroughlf mixed in order for the composite sample to be representative of the effluent O release.
81f the contents of the filter flush tank or the regenerative waste tank contain detectable radioactivity, no discharges from these tanks shall be made to the UNRESTRICTED AREA and the contents of these tanks shall be directed to'the liquid radwaste treatment system, h
Turbine Building Industrial Vaste Sump (TBIWS)
ThF TBIWS shall be required to be sampled and analyzed in accordance with this '
table if any of the following conditions exist:
i (1) Primary to secondary leakage is occurring; or, (2) Activity is present in the secondary system as indicated by either the SGB monitors or secondary sampling and analysis; or, (3) Activity was present in the TBIWS during the previous 4 weeks. .
l- If none of th . cove situations exists, then the sampling and analysis of this' stream need r' be performed.
I Sampling and analysis of the dry cooling tower sumps and the auxiliary l
component cooling water pump discharge will be required only when detectable activity exists in tne CCW.
l Sampling and analysis of the circulating water discharge-steam generator blowdown heat exchanter discharge (CWD-SGB) will be required only when i detectable activity exists in the secondary system.
l 21
Administrative Procedure UNT-005-014 Sifsite Dose Calculation Manual Revision 0 O
TABLE 5.3-1 (Continued)
TABLE NOTATIONS dSampling and analysis of the steam generator blowdown will be required only when the blowdown is directed to the circulating water system or Wrterford 3 waste pond.
Steam generator blowdown to the Waterford 3 waste pond vill be limited to situations requiring secondary chemistry cot.6rol where the Circulating Water System is not available or the secondary chemistry is outside the requirements for Circulating Water System discharge. Blowdown to the waste pond will tse terminate upon direction of sample & activity greater than the LLD levels of Table 5.3-1.
F To be representative of the quar.tities and concentration of radioactive materials in liquid effluents, samples shall be collected continuously in proportion to the rate of flow of the effluent stream.
1 Steam generator blowdown discharge to the waste pond is not available unless radiation monitoring and automatic isolation capabilities are added to the vaste pond discharge path.
O O
C 1
22
UNT*005-014 Administrative Procedure Offsite Lose, Calculation Manual Revision 0 O
5.3 LIQUID EFFLUENTS (cont'd) 5.3.2 Dose Specification The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released to UNRESTRICTED AREAS (see Attachment 6.1) shall be limited:
- s. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to ess than or equal to 5 mrems to any organ, and
- b. During any calendar year to less than or equal to 3 mrems '
to the total body and to less than or equal to 10 mrems to any organ. ,
APPLICABILITY: At all times.
ACTION:
- a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above
. limits, prepare and submit to-the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identified the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance vfth the above limits. This Special Report shall-also include (1) the results of radiological analyses of the drinking water source and (2) the radio-logical impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141.
23
_ - _ - . - - . - - - - ~ . . . . - - . ._. - . - - - . _
d J .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O
5.3 LIQUID EfTLUENTS (cont'd)
SURVEILLANCE REQUIREMENTS:
i i a. Cumulative dose contributions from liquid effluents for j the current calendar quarter and the current calendar .
I' year shall be determined in accordance with methodology and parameters in Section 5.3.7 at least once per 31 days.
'l 1
0' ,
I l
l l
l 4
O' 24
1 Administrative procedure UNT-005-014 Offtite Dose Calculation Manual Revision 0, O
5.3 LIQUID ETpLUENTS (cont'd) 5.3.3 Liquid Radvaste Treatment System Specification The liquid radvaste treatment system shall be OPERABLE and appropriate portions of the sy, tem shall be used to reduce ,
releases of radioactivity when the projected doses due to the liquid effluent to UNRESTRICTED AREAS (see Attachment 6.1) would exceed 0.06* mrem to the total body or 0.2 mrem to any f organ in a 31 day period.
APPLICABILITY - At all tines.
ACTION: i
.a. With radioactive liquid vaste being discharged without treatment and in excess of the above limits and any.
portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission within 30 days pursuant to Technical Specification 6.9.2 a Special Report that ine'ludes the following'information.
- 1. Explanation of why-liquid radwaste was-being discharged f without treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability, t
- 2. Action (s) taken to restore the inoperable equipmet.t to OpEpABLE status, and >
i
- 3. Summary description of action (s) taken to prevent a
. recurrence.-
i 25
A hein4 sEr - tve Procedure UNT-005-014
- t ,4tu N 3 Calculation Manual Revision 0
- G I
5.3 LIQUID EFFLUENTS (cont'd)
SURVEILLANCE REQUl?IMENTS
- a. Doses due to liquid releases to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in Section 5.3.7.
- b. The installed Liquid Radwaste Treatment System shall be demonstrated OPERABLE by meeting Specifications 5.3.1 and j 5.3.2.
O 9
i l
O 26
Adsinirtrative Procedure UNT-005-014 0'ffsite Dose Calculation Pfanual Revision 0
. O 5.3 L1 QUID ETTI,UENTS (cont'd) 1 5.3.4 Liquid Effluent Dose Calculation l 5.3.4.1 The dose commitment to an individal from radioactive l materials in liquid effluents released to unrestricted areas are calculated for the purpose of implementing Section 5.3.2 using the following expressions l n
Dtf = at Fg f IE A1 itC jg (3) m Ut *Ab'Dtg [y) ;
k'he re :
O- i Dg= the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for each liquid release in mrem during time period (f) t = the cumulative dose commitment to the total body or any organ (t) from the liquid effluents for all (f) time periods Ot time period over which t= the length of the f the release is made, in hours Cgg = the concentration of radionuclide (i) in undiluted liquid effluent during time-period 4tffrom any liquid release, in pCi/ml LO
.27
_ . _ _ _ . _ . - . . ~ _ . _ . . _ - _ _ _ . . . - . . _ . . . . _ -_ _-
Administrative Procedure 11NT-005-014 Offsite Dose Calculation Manual Revision 0 O
5.3 LIQUID EFFLUENTS (cont'd) l I
A = the site-related liquid ingestion dose gt commitment factor to the total body or any organ (t) .er each identified nuclide (i) in mrem-ml/hr-pC1 (Attachment 6.3) i Fp : the near field average dilution factor for C
gg during any liquid effluent release.
Defined as the ratio of the undiluted liquid waste flow during release to the average flow from the site discharge structure to site boundary receiving waters.
= liquid radioactive waste flow F' discharge structure exit flow The liquid radioactive waste flow is the maximum flow from the effluent release. The discharge structure exit flow is the flow during disposal from the discharge structure release point into the receiving water body. For radionuclides.not determined in each batch or weekly composite, the dose contribu-tion to the current calendar quarter cumulative summation may be approximated by using a ratio of concentrations based on the previous monthly or quart erly composite analyses.
O 28
Aduinistrative procedure LNT 005-014 Revision 0 Offsite Dose Calculativ.a Hanual .
O 5.3 1.IQUID ETTI.UENTS (cont'd) 5.3.4.2 Equation (1) above for calculating the dose contribu-tions required the use of a dose factor, An' I '
each nuclide (1) which embodies the dose factors and dilution factors for the points of pathway origin.
The adult total body dose factor and the adult organ dose factor for each radionuclide vill be used from Table E-11 of Eegulatory Guide 1.109; thus the list contains critical organ dose factors for various organs. The dose l actor is written:
Ag
= 1:0( W UW* f i) "i t (}
where O U = 730 1/yr adult water consumption, D, = Dilution factor from near. field area to potable water intake, _
= 220 for discharges from the circulaticg water discharge into the Mississippi River (based on the ratio of the average Mist issippi River flow to the maximum discharge flow),
=1 for discharges into the 40 Arpent Canal (based on the assumption that dilution from the near field area to a potable water intake is ,
negligible),
A gt = Composite dose parameter for the total body or O critical organ (t) of an adult for nuclide
.(i) for all appropriate pathways (mrem-ml/hr-pC1),
29
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
5.3 LIQUID ErflUENTS (cont'd)
K = Unit conversion factor, 9
Ug = 21 kg/yr, adult fish consumption, lir g= Iticaccumulation factor for nuclide (1) in fish (pci/kg per pCi/1) from Table A-1 of Regulatory Guide 1.109, DCF3 (
= Dose conversion factor for nuclide (1) and organ (L) for adults (mrem /pC1). Values are from Table E 11 of Regulatory Guide 1.109, NOTE For other liquid pathways, the appropriate dose f actors will be utilized.
!. 9 l
t 30
Administrative procedure UNT-005-014 Offolte Dose Calculation Manual Revision 0 0
5.3 LIQUID EITLUENTS (cont'd) 5.3.5 Liquid Effluent Monitor Setpoint Calculation Methodology Specifications 5.3.1 and 5.6.1 require that the liquid effluent monitoring instrumentation alarm / trip setpoints be set so that the concentration of radioactive material released from the site is limited to 10CTk20, Appendix B. Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases.
(For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pC1/ml total activity). This sc; tion presents the method to be used for detennining setpoints in accordance with Surveillance Requirements 5.3.1 and 5.6.1.
5.3.5.1 The calculated setpoints for the liquid effluent O monitors satisfy the following equation:
n e= (SF)(E)(T+f)g[3g C (4)
TriPC (f )
where; n
gj)Cf a the 1:ndiluted ef fluent gamma concentration pCi/ml for all radionuclides (1). The value will be derived from radionnalysis of liquid effluent to be released. This-value will be i
supplied for each liquid release.
c = the setpoint, in pCi/ml, of the liquid effluent monitor measuring the radioactivity concentra-l tion in the effluent line prior to dilution-and subsequent release. This setpoint repre-sents a value which, if exceeded would result O in concentrations exceeding the limits of 10CTR20, Appendix B Table II.- Column 2, to an UNRESTRICTED AREA.
31 l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
5.3 LIQUID EFFLUENTS (cont'd) f a the liquid effluents flow as measured at the liquid effluent monitor location in gpm.
F = the dilution water flow as determined via pump curves or other appropriate measures that determine correct plant operating configuration in gpm.
NOTE IF F is large compared to f then F + f a F.
SF = Safety factor to ensure that the effluent limit is not exceeded. Actual value is set by procedure (in the range 0.5 - 0.9).
RF = Release fraction allocated to this release (to be used only in situations of .
simultaneous or concurrent release).
n m TMPC = gCg , y3 C 3
=
} the. undiluted nongamma MPC) fraction for all nongamma emitting radionuclides (j)
MPC)
C g
= undiluted gamma MPC g fraction for all gamma SI;C g
emitting radionuclides (1)
Maximum Permissible Concentration for the MPC) e applicable nongamma-emitting isotope (j) f rom 10CFR20, Appendix B, Table II, Column 2.
MPCg= Maximum Pennissible Concentration for the applicable gamma-emitting isotope (i) from 10CFR20, Appendix B, Table 11, Column 2.
32
UNT-005-014 Administrative Procedure Revision 0 l Offsite Dose Calculation Manual l 5,3 LIQUID EFFLUENTS (cont'd) l l 5.3.5.2 The values of C 3 andCpwillbemeasuredforeach release as appropriate and the parameters for f and F will be supplied based on current plant operating configurations. The setpoint will be calculated in f
i terms of pCi/ml and the liquid effluent monitor will be adjusted as necessary to ensure that 11guld i- releases are secured prior to e.~.ceeding limits q
4 specified in 10CFR20, Appendix B Table ll, Column 2 l-to an UNRESTRICTED AREA.
l i-1 t
1 I_ . _ _ l 1
I. .i 1
+
1 L
+
( -
i k
33-
Adainistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
5.3 LIQUID EFTLUENTS (cont'd) 5.3.6 Representative Liquid Sampling l
Prior to grab sampling liquid waste tanks, methods should be used to guarantee representative sampling. Large volunes of liquid waste should be mixed in as short a time as possible and uniformly distributed prior to sampling. To determine the minimum mixing time for tanks from which releases are made, the following tests were performed prior to initial use for release purposes,
- a. The tank was filled to a known volume.
- b. A specific quantity of a selected chemical and/or sediments was added to the tank.
- c. Recirculation was initiated through the normal path,
- d. Periodic samples were taken until equilibrium is reached.
- e. The time observed to completely mix the tank is used as a minimum recirculation time prior to effluent sampling.
Records of the test will be maintained.
O 34
UNT-005-014 Administrative Procedure '
Revision 0 Offsite Dose Calculation Manual ~
0 5.3 LIQUID EFFLUENTS (cont'd) 5.3.7 Dose Projection for Liquid Effluents Specification 5.3.3 requires that appropriate subsystems of the liquid radwaste treatment system be used to reduce releases of radioactivity when the projected doces due to the liquid effluent from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem total body or 0.2 mrem to any organ in a 31-day period. The following calculational method is provided for performing this dose projection.
At least once every 31 days, the total dose from all liquid releases for the quarter-to-date will be divided by the number of days into the quarter and multiplied by 31. If this projected dose exceeds 0.06 mrem total body or 0.2 mrem any organ, and the Liquid Waste Management System has not been operattag, it shall be operated, if operation would reduce the monthly projected doses below 0.06 mrem total body or 0.2 mrem any organ. (This is preformed in accordance with tb Surveil-
" lance Requirements of 5.3.3.)
O 35 l-
Administrative Procedure UNT-005-014 Offaite Dose Calculation Manual Revision 0 0
5.3 LIQUID EFFLUENTS (cont'd) 5.3.8 Liquid Effluent Bases
- a. CONCENTRATION (Section 5.3.1)
This specification is provided to ensure that the concen-tration of radioactive materials released in liquid vaste effluents to UNRESTRICTED AREAS will be less than the concentration levels specified in 10 CFR Part 20, Appendix B. Table II, Column 2. This limitation provides additional assutance that the levels of radioactive materials in bodies of water in UNPISTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR Part 50, to a MEMBER OF Tile PUBLIC and (2) the limits of 10 CFR Part 20.106(e) to the population.
The concentration limit for dissolved or entrained noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration is water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
The sampling and analysis of the contents of thy regenera-tive waste tank and the filter flush tank is performed if primary to secondary leakage occurs in a steam generator.
The contents of these tanks cannot be discharged to the UNRESTRICTED AREA if any radioactivity is detected in these tanks since the discharge from these tanks is unmonitored. When radioactivity is detected in these tanks, the contents from these tanks must be discharged to the liquid radwaste system where the contents may then be monitored upon discharge, i
i l
36 l .-
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Hevision 0 O
5.3 LIQUID EFI'LUENTS (cont'd)
The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discus- l slon of the LLD, and other detection limits can be found in llASL Procedures Manual, llASL 300 (revised annually), ;
l Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," l Anal. Chem. 40, $86-93-(1968), and lia rtwell, J.l'. .
" Detection Limits for Radioanalytical Counting Techniques,"
Atlantic Richfield llandford Company Report AR}i-SA-215 (June 1975).
- b. DOSE (Section 5.3.2)
This specification is provided to implement the requirem<ats of Sections II.A, III.A and IV.A of Appendix 1, 10 CFR Part 50. The Limiting Condition for Operation implements the e,atdes set forth in Section II.A of Appendix 1. The ACTION statement.s provide the required operating flexibi- ,
lity and at the same time implement the guides set forth in S'ection IV.A of Appendix I to assure that the releases >
of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable."
Also, for fresh water sites with drinking water supplies that can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility,will not result in radionuclide concentrations in the finished drinkinc. water that are in excess of the requirements of 40 CFR Part 141.
O 37
____ _ . _ . _ . _ _ _ _ _ _ _ _ ~ _ . _ _ _ _ . . _ . - . . . _ _ _ _ _ . _ _ . _ . .
Ad;ninist rative Procedare UNT-005-014 I Offsite Dose Calculation Manual Revision 0 9'
5.3 LIQUID EFFLUENTS (cont'd)
- b. DOSE (Section 5.3.2) (cont'd)
The dose calculation methodology and parameters iroplement the requirement in Section Ill.A of Appendix 1 that confor-mance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated.
The equations specified for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculatdon of Annual Doses to Man f rom Routine Releases or Reactor Effluents for the purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1,"
Revision 1, October 1977 and Regulatory Guide 1.113,
" Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implement-ing Appendi.x I," April 1977.
- c. LIQUID RADWASTE TREATMENT SYSTEM (Section 5.3.3)
The OPERABILITY of the liquid radwaste treatment system ensures that this system will be available ter use whenever liquid effluents require treatment prior to release to the envi ronmer't . The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid efflu~
ents will be kept "as low as is reasonably achievable." This -
specification isglements the requirements of 10CTR Part 50.36a, General Design Celterion 60 of Appendi*. A 10 CFR Part 50 and the design objective given in 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 dose design objectives set forth in Section II.A of Appendix I, 10 CFR Part 50, for liquid effluents.
38
Administrative Procedure UNT 005 014 Of fsite lose Calculation Manual Revision 0 O
5.4 GASEOUS EFFLUENTS 4
5.4.1 Dose Rate Specification The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY (see Attachment 6.1) shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and
- b. For iodine-131, iodine-133, for tritium, and for all radionuclides in particulate form with half lives greater O- than 8 dayst Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times ACTION: .
With the dose rate (s) exceeding the above limits, immediately restore the release rate to within the above limit (s), and describe the events leading to this condition in the next L
Semiannual Radioactive Effluent Release Report.
l i.
I O
39
_ ._ . - - _ . . _ . . _ _. . . _ _ . _ . . __ - . _ _ _ . _ _ _ - .a
UNT-005-014 l Administrative Procedure Offsite Dose Calculation Manual Revision 0 9
5.4 GASEOUS LITLUENTS (cont'd)
SURVEILLANCE 11QUIREMENTS:
- a. The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in Section 5.4.5.
- b. Representative samples and analysis of gaseous effluents shall be obtained in accordance with the sampling and analyses program specified in Table 5.4-1.
- c. Based upon the sampling and analysis performed in Table 5.4-1 the dose rate due to I-131, 1-133, H-3, and all other radionuclides in particulate form with half-lives greater than 8 days shall be determined to be within the above limits in accordance with the methodology and parameters in Section 5.4.5.
G 40
-.S. I edure UNTOOl6 I
- Surveillance Revi b 0 i
,0ffsite Dose Calculation Manual
- i J
I TABLE 5.4-1 .
t i
RADIO. ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM !
{ __
MINIMUM UJWER LIMIT OF i ANALYSIS TYPE OF DETECTINO (LLD)* l J -SAMPLING (pCi/mL)
' FREQUENCY FREQUENCY-- ACTIVITY ANALYSIS i lGASEOUSRELEASETYPE i I P P Each Tank Principal'Gaussa Emitters 1xlO * .
j A .- Waste Gas Ifoldup Each Tank !
'- Tanks Grab Sample _
P P I
Each PURGE Principal Gamens Emitters Ix10 * ,
B. Containment PURGE Each PURGE (Plant Stack). Grab Sample ,
i 1
C 'I Principal N ble Gas Gassea Ix10
- C.I Plant Stack M' b Grab Sample M ' Emitters ,
9 j
H-3 1 x 10 , [
4 1
Principal Nb ble Gas Ganwna 1x10
- l' C.2 Fuel.andling H M3 Grab Sample M Emitters t Building Ven-tilation '
i H-3 1x10
- j (Normal) j Exhaust t 4 l l
i i
9 4 5 e
i t
41 l
l
, . . - , . , - , - -. , , ~ ,,.n+
?
,- - - - , , . . , , , . , - , . -- - - . . - - - . . ~ , ,- .--
UNT-005-014 Surveillence Procedure Revision 0 Offaite Doce Csiculstio.1 M:nual TABLE 5.4-1 (Centinued)
RADIOACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM MINIMUM LOWER LIMIT OF ANALYSIS TYPE OF DETECTINO (LLD)*
SAMPLING ACTIVITY ANALYSIS (pCi/mL)
GASEOUS RELEASE TYPE FREQUENCY FPIQUENCY 1x10 12 D.1 All Release Types ContinuousI ' 'l W8 I-131 as listed in Charcoal Sample I-133 1x10 3 B., C.1, and C.2 above
' 'l W8 Principag Particulate Gama 1x10 33 D.2 Main Condenser Continuous Evacuation and Particulate Emitters Turbine Gland Sample Sealing System Continuous
' 'l in Gross Alpha 1x10 t1 Composite ,
Particulate Sample Continuous * 'l Q Sr-89, Sr-90 Ix10 33 Composite Particulate Sample Continuous
' 'l Noble Gas Noble Gases 1x10 6 Monitor Gross Beta or Gamma G e2e g
. _ _ _ _ - - - _ . _ . . _ . - . _ . . . _ - . . _ . - _ _ . . -- . _ _ _. _ . _ _ _ m. -
l Administrative Procedure UNT-005-014 Offsite Dohe Calculation Manual Revision 0 ,
5.4-1 (Continued) !
- IAB11 NOTATION
- The LLD is defined, for purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only
-d Q robability of falsely concluding that a blank observation represents a "realt signal.
L
- For a particular measurement system, which may include radiochemical !
separation:
LLp =
4.66 s b E . V . 2.22 x 10C. Y , exp (-Aot)
Where
-LLD is the "a priori" lower limit of detection as defined above, as f microcuries per unit mass'or volume, [
s is the standard deviation of the background counting rate or of the c unting rate of a blank sample as appropriate, as counts per minute.
E is the counting efficiency, as counts per disintegration, 9
V is the sample size in units of mass or' volume, 2.22 x 108 is the number of disintegrations per minute per microcurie, ,
Y is the fractional radiochemical yield, then applicable, .
A is the. radioactive decay constant for the particular radionuclide, and At for plant effluents is the elapsed time between the midpoint of sample eclieetion and the time of counting.
Typical values of E, V, Y, and at should be used in the calculation.
It should be recognized that the LLD is defined as an a, priori (before the fact) limit representing the capability of-a measurement system and not as an a,posteriori (after the fact) limit for a particular measurement.
O 43
UNT-005-014 Administrative Pro:edure Offsite Dose Calculation Manual Revision 0 O
b4-1 (Continued)
TABLE NOTATIONS bThe principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xc-135, and Xe-138 in noble gas releases and Mn-54, Pe-59, co-58, Co-60, 2n-6$, Mo-99, 1-131, 1-133 Cs-134, Cs-137, Cr 141, and Ce-144 in iodine and particulate releases. This list does not mean that only these nuclides are to be conside' red. Otbre gamma peaks that are identifiable, together with those of the above nuclides, shall alto be analyzed and reported in the Semiannual Radioactive Effluent Release Report pursuant to Technical Specification 6.9.1.8.
cSampling shall also be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following shutdown, startup, or a TIEPJ1AL PokTR change exceeding 15% of RATED TIERMAL P0kTR within a 1-hour period. Analysis for principle gamma emitters as defined in (b) above shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of sampling.
d Tritium grab samples shall be taken at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling canal is flooded.
- Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool.
I The ratio of the sample, flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Section 5.4.1, 5.4.2, and 5.4.3.
8Saaples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
Sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each shutdown, startup or TIERMAL P0kTR change exceeding 15% of RATED THERMAL P0kTR in I hour and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing, k' hen samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are analyzed, the corresponding LLDs may be increased by a factor of 10. This requirement does not apply if (1) analysis shows that the DOSE EQUIVALENT I-131 concentration ,
in the primary coolant has not increased more than a f actor of 3; and (2) the noble gas monitor shows that effluent activity has not increased more than a factor of 3.
If no primary to secondary leakage exists, then only the gross beta or gamma noble gases analysis need be performed for the main condenser evacuation and turbine gland sealing system. If a primary to secondary leak exists and the release from the main condenser evacuation and turbine gland sealing system has not been released via the plant stack, then the sampling and analysis must be performed.
I Note (c) above is not applicable for the plant stack unless the noble gas monitor shows that effluent activity has increased by a factor of 3.
dFuel llandling Building sampling is required whenever irradiated fuel is in the storage pool.
44
UNT-005-014 Administrative Procedure Offsite Dose calculation Manual Revision 0 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.2 Dose-Noble Gas Specification The air dose due to noble gases released in gaseous effluents to areas at and beyond the SITE BOUNDARY (see Attachment 6.1) sha.1 be limited to the following:
- a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or , qual to 10 mrads for beta radiation and,
- b. During any calendar _ year: Less than or equal to 10 mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.
O APpLICABII.1TY: At all times.
ACTION:
With the. calculated air dore from radioactive noble gases-in
)
gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for' exceeding the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken ,
to assure that subsequent releases will be in compliance with the above limits.
SURVEILI.ANCE REQUIREMENTS:
() Cumulative dose contributions for the current c61endar quarter and current calendar year for noble gases shall be determined in accordance with the methodology and parameters in Section 5.4.6 at:1 east once per 31 days.
45 1
i Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0
5.4 GASEOUS EFFLUENTS (cont'd) 5.4.3 Dose - lodi:;e-131, lodine-133, Tritium tand Radionuclides in Particulate Form Specification The dose to MEMBER OF Tile PUBLIC f rom iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives grear than 8 days in gaseous effitents released to areas at and peyond the SITE BOUNDARY (see Attachment 6.1) shall be limited to the following:
- a. During any calendar quarter: Less than or equal to 7.5 torems to any organ and,
- b. During any calendar year: Less than or equal to 15 mrems to any organ.
APPLICABILI17: At all times ACTION:
With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate f orm with half-lives gieater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
46
UNT-005-014 Administrative Procedure Revision 0 Offsite Dose Calculation flanual .
O 5.4 GASEOUS EFFLUENTS { cont'd)
SURVEILLANCE REQUIREMENTS:
Cumulative dose contributions for the current calendar quarter and current calendar year for iodine-131, fodine+133, tritium, and u dionuclides in particulate form with half-lives greater than 8 days shall be determined in
' .secordance with_the methodology and parameters in Section 5.4.7 at least once per 31 days, f d
i 4
b
)
a M
O .
47.
Administrative Proccoure UNT-00$-014 Offsite Dost Calculation Manual Revision 0 O
5.4 GASEOUS EFFLUENTS (cont'd) 5.4.4 Gaseous Radwaste Treatment Specification The VENTILATION EKilAUST TREATMENT SYSTEM and the VASTI' GAS 110LDUP SYSTEM shall be OPERAllLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases to areas at and beyond the SITE BOUNDARY (see Attachment 6.4} would exceed either:
- a. 0.2 sarad to air f rom gamma radiation, or
- b. 0.4 mrad to air from beta radiation, or
- c. 0.3 mrem to any organ of a KEMBER OF THE PUBLIC.
APPLICABILITY: At all times.
ACTION:
With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technicai Specification 6.9.2, a Special Report that includes 'he following information:
- a. 16catification of any inoperable equipment or subsystems, and the reason for the inoperability,
- b. Action (s) taken to restore the inoperable equipment to OPERABLE status, and
- c. Summary description of action (s) taken to prevent a recurrence.
48
UNT-005-014 Administrative Procedure
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- Offaite Dose Calculation Manual 5.4 ' GASEOUS EFFLUENTS'(tont'd)
SURVEILLANCE REQUIREMENTS:
- a. Doses due to gaseous releases to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 ;
days in accordance with the methodology and parameters in Section 5.4.9.
- b. The installed Gases Raivaste Treatment System shall be demonstrated operable by meeting Specifications 544.1, 5.4.2 or 5.4.3.
i v
A f
4 4
0
. 49
UNT-005-014 Administtative F:ocedure Offsite Dose Calculation Manual Revision 0 O
5.4 GASEOUS EFFLUENTS (cont'd) 5.4.5 Calculational Methodology for Gaseous Effluent Dose Rate This section presents the calculational methods used for calculating gaseous effluent doses in fulfillment of Specification 5.4.1.
5.4.5.1 The dose rate due the radioactive materials released in gaseous effluents from the site to areac at and beyond the SITE BOUNDARY shall be limited to the following values and expressions:
Release rate limit for noble gases:
K' (X/Q)y g{3 K Qgy $500 mrem /yr. total body (5) O n
K' (X/Q)y g{) (Lj + 1.1M )g Qgy $3000 mrem /yr. skin (6)
Release rate limit for Iodine-131, Iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days:
n Q 1y 11500 mrem /yr any organ (7)
(X/Q)y ib1 P g Where:
K' = a constant of unit conversion, lE6pCi/pci.
Kg = the total body dose factor due to gamma emissions for each identified radionuclide (i) in units or mrem /yr per pCi/m 3 (Attachment 6.4).
50
.- - . - - . . . ~ - . - . . - - . . _ . . . . - . . - . . . -. .
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Administrative Procedure Offsite Dose Calculation Manual Revision 0
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5.4-- GASEOUS EFFLUENTS (cont'd)
Lj = the skin dose factor due to beta emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m 3 (Attachment 6.4).
Mg = the air dose factor due to gamma emissions for each identified radionuclide (i) in units of mrad /yr per pCi/m3 (Attachment 6.4).
The constant 1.1 converts air dose to skin dose.
P = the thyroid dose parameter for Iodine-131, it Iodine-133, tritium, and radionuclides in particulate form with half-lives greater O than 8 days (i) for the inhalation pathway only, in mrem'/yr per pCi/m 3 (Same as R g values for the .aild receptor listed in Attachment 6.5). The doce factor is base on the-most restrictive age group (child) and most restrictive organ (thyroid) at the SITE BOUNDARY.
P = (child breathing rate of 3700 m y yr)(DFAg )
, it (K')~where DFA g is the inhalation dose l factor for each radionuclide from Table E-9, Reference 2.4 i
i I -= summation-for all identified radionuclides j .- i=1.
O
! 51
= . ._
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O
5.4 GASEOUS EFFLUENTS (cont'd)
Q gy = the average release rate of radionuclides (i) (either noble gas or Iodine-131, Iodine-133, tritium, and radionuclides in the particulate form with half-lives greater than 8 days, as appropriate) during the time of release from all vent releases (v).
Value is averaged over one hour and is in units of pCi/sec.
3 (X/Q)y = 1.1E-5 sec/m in the ESE sector at 0.6 mile for all vent releases (v) (the highest calculated annual average dispersion factor at the SITE BOUNDARY based on historical data). The actual X/Q for the time of release may be determined and used under certain circumstances.
NOTE All radiciodines are assumed to be released in elemental form.
9 O
52
. - - . . - . . = . . . . . - _ _ - - - - - . . - ~ . - . - .
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5.4 -GASEOUS EFFLUENTS (cont'd)
-5.4.6 Calculational Methodology for Noble Gas Doses This section presents the calculational methods used for calculating noble gas effluent dose in air in accordance with Surveillance Requirement 5.4.2.
5.4.6.1 The air. dose due to noble gases released in gaseous effluents to areas at or beyond the SITE BOUNDARY will be determined by the following expressions:
- a. During any calendar quarter, for gamma radiation:
n m O, D = (1.14E2) (X/Q)y g[3(M)){)
g (6t)) (Q gy ) (8) and for' beta radiation:
n m D
g = (1.14E2) (X/Q)y gf3(N)){3 g (atj) (Q g)y ) (9)
- b. During any calendar year, for gamma radiation:
n m D =-(1.14E2) (X/Q)y{,jM}I,j(at](Q gjy) (10) and for beta radiat!on:
a m D
p = (1.14E2) (X/Q)y{g(N,3(at](Q g)y) (11)
-Where:
D = the total gamma (y) air dose from gaseous effluents for the total time period and not to exceed 5 mrad quarterly and 10 mrad yearly.
'53
Administrative Procedure UNT-005-014 Offsite Dose. Calculation Manual Revision 0 0 5.4 GASEOUS EFFLUENTS (cont'd) D : the total beta ( ) air dose from gaseous p effluents for the total time period and not to exceed 10 mrad quarter 1j and 20 mrad yearly. Q gy = the average release rate of radionuclides (i) in gaseous effluent from all vent releases (v) in pCi/sec during the time period 4t. J-( }v = 1.1E-5 sec/m 3 in the ESE sector at 0.6 mile for all vent releases (v). The actual X/Q for the time of release may be determined and used under certain circumstances. 4t = the length of the j time period over j which Q are accumulated for all gaseous y releases in hours. Mg and Ng = the gamma and beta air dose factors (respectively) for a uniform semi-infinite cloud of radionuclide (i) in mrad /yr per pCi/m3 (Attachment 6.4). l O 54
.. . - - _ _ ~ - . . - . ..- . .
. Administrative-Procedure -UNI-005-014 i Offsite Dose Calculation Manual Revision 0
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5.4 GASEOUS EFFLUENTS (cont'd) , 5.4.7 Calculational Methodology for Doses Due to Radioiodines, Tritium, and Radioactive Materials in Particulate Form This section presents the calculational methods used for . calculating doses due to Iodine-131, Iodine-133, tritium, and radionuclides in particulate-form in accordance with Surveil-lance Requirement. 5.4.7.1 The dose to an individual from Iodine-131, Iodine-133, tritium, and radionuclides an particulate form with half-lives greater than 8 days 17. gaseous effluents released to areas at and beyond the SITE BOUNDARY will be determined by the following expressions: , l O-During any calendar quarter: n Dj , = 1.14E-4 At I , R f, Wy Q h ,. (12)
. x=1 During any calendar year:
n
= 1.14E-4 at I R WvQ.
av (13) D.ta I ggy ita 1 n 55
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (cont'd) Where: 1.14E.4 = a onstant of units conversion
= lyr/8760 hr D g, =. the cumulative dose to an organ (t), age group (a), due to radionuclides (i) in gaseous ef fluents; not to exceed 7.5 n. rem l quarterly or 15 mrem yearly.
Wy = the dispersion parameter for estimating the dose to an individual at the controlling lacation for long term vent releases (v). Wy = (X/Q)y for the inhalation pathway from vent releases (v) in sec/m 3 , from historical data, at the location of the critical receptor (Attachment 6.2).
=
Wy (D/Q)y for the food and ground plane pathways from vent releases (v) in m 2 , from historical data at the location of the critical receptor (Attachment 6.2). O 56
UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 5.4 GASEOUS EFFLUENTS (cont'd) Rg = the dose factor from each identified radio-nuclide (i), for each applicable organ (t), and age group (a), in mrem /yr per uCi/m 3 for the inhalation pathway (Attachment 6.5) and in mrem /yr per uCi/m2 -see for che food and ground plane pathways ( At ta ciunent s 6.6, 6.7, 6.8, 6.9, and 6.10). For set tors with real pathways wit.hin 5 miles of the plant, the values of R areg used based on these real pathways; for sectors with no real pathways within 5 miles from the plant, Rg is used assuming that the cow-grass-milk pathway exists at the 5-mile distance. (Rg 's were calculated using the methodology found in Reference 2.5, pages 31-36.) . Q gy = the average release rate of radionuclides (i) in gaseous effluent from all vent _ releases (v) in pCi/sec. At = the time required for the release in hours for all releases per quarter or per year. O 57
UMT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.8 Gaseous Effluent Monitor Setpoint Calculational Methodology 5.4.8.1 Specification 5.6.2 requires that the radioactive gaseous effluent monitoring instrumentation alarm / trip setpoints be set to ensure the limits of Specification 5.4.1 are not exceeded. 5.4.8.2 The calculated high alarm / flow termination setpoint is the maximum value for that particular release. For conservation, an administrative safety factor (SF) of usually 10% will be utilized in tne setpoint calculation. To allow for simultaneous releases from common or different release points a Release Fraction (RF) may be used to allocate percentages of the total allowable release. 5.4.8.3 Since the noble gas dose rates are more limiting than the radiciodine dose rate, gaseous setpoints will be based on noble gas dose rates (less than or equal to 500 mrem /yr total body, and less than or equal to 3000 mrem /yr skin). Specifically, gaseous setpoints will be based on the most limiting of the following equati ons : a, Total body (Qg):
, (500 mrem /vr.)(RF)(SF) (14) 9 (X/Q)y(IE6 pCi/pCi) n i Oiv i=1 n
I 9 iv t=1 58
.__.m.___. _ _ _
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (coat'd) Where: n I i=1 = summation of all nuclides considered. Qg = maximum release rate allowed to give a limiting total body dose rate of 500 mrem /yr in pCi/sec. Kg = the total body dose factor due to gamma emissions for each identified radionuclide (i) in units of mrem /yr per pCi/m 3 . (Attaciunent 6.4) . Q iy = average release rate of isotope (1) from the release point (v) in pCi/sec. RF = release fraction allotted-to release point
-in consideration.
(X/Q)y = -1.1E-5 sec/m3 (in the ESE sector at 0.6 mile). The sector with highest value_of annual average atmospheric dispersion factor at the site boundary for the release point (v) in question. SF '= administrative safety factor to account for-uncontrollable variables (sampling, monitoring l (i errors, etc.). Usually, the SF takes on a value of 0.9. 59
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (cont'd)
- b. For Skin (Q skin):
Q skin = (3000 mrem /yr.)(16)(SF) (15) (X/Q)y(IE6 pCi/pCi) n 1 (L.1 + 1.1M.)Q. 2 2v i=1 n O iv i=1 where all terms are as defined above except: Q skin = maximum release rate allowed to give a limiting skin dose of 3000 mrem /yr in pCi/sec. Lj = skin dose factor due to beta emissions for each identified radionuclide (i) in units , 3 of mrem /yr per pCi/m (Attachment 6.4) 1.1 = conversion factor to convert from air to skin dose. Mg = air dose factor due to gamma emissions for identified noble gas isotope (i) in units of mrad /yr per pCi/m3 (Attachment 6.4). 5.4.8.4 The monitor setpoint is calculated is the following manner: SN = Q (16) F,,x e 60
.-. - _ - .~ .. .. - - - _ .
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Administrative Procedure Revision 0
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- 5. 4- GASEOUS EFFLUENTS (cont'd)
Where: SN = maximum monitor setpoint in pCi/cm 3 3 F,,, = maximum effluent flow rate (cm /sec) Q = Minimum value of Q th #O skin 5.4.8.5 Since Kr-88 is the noble gas with the highest dose rate conversion factors, for conservation, the preceeding calculations may be computed using Kr-88 only. Total' body dose bc omes'more limiting than skin and the release limit is: QKr-88 = (500 mrem /yr.)(RF)(SF) -(17)
- (X/Q),(IE6 pCi/pci)(KKr-88) where:
_Q Kr-88 = the maximum release rate, based on Kr-88, allowed to give a limiting total body dose rate .of 500 mrem /yr in pei/sec. kr-88=thetotalbodydosefactorduetoKr 3 in units of_ mrem /yr per pCi/m (Attachment 6.4), All other terms are previously defined.
~
The monitor setpoint can be calculated as: SN = Q Kr88 (18) . F max and all terms are previously defined 4 61 - .~ - - - .-,
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (cont'd) 5.4.9 Dose Projection due to Gaseous Effluents 5.4.9.1 Specification 5.4.4 requires that appropriate subsystems of the Gaseous Radwaste Treatment System be used to reduce releases of radioactivity when the projected doses due to the gaseous effluent to areas at and beyond the SITE BOUNDARY would exceed, in a 31-day period, any of the following: 0.2 mrad to air from gamma radiation; or 0.4 mrad to air from beta radiation; or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC. 5.4.9.2 The following calculational method is provided for performing this dose projection. At lease once every 31 days the gamma air dose, beta air dose and the maximum organ dose for the month-to-quarter will be divided by the number of days into the quarter and multiplied by 31. If these projected doses exceed any of the values listed above and the Gaseous Waste Management System has not been operating, it shall be operated to reduce radioactivity levels prior to release. (This is performed in accordance with the Surveillance Requirements of Specification 5.4.4. O 62
ITNT-005-014 - Administrative Procedure Offsite Dose Calculation Manual Revision 0
- l l(M d.
5.4 GASEOUS EFFLUENTS (cont'd) 5.4,10 Gaseous Effluent Bases
- a. DOSE RATE (Section 5.4.1)
This specification is provided to' ensure that the dose at any time at and beyond the SITE BOUNDARY from gaseous effluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 to UNRESTRICTED AREAS. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20, Appendix B, Table II, Column 1. These limits provide reasonable-assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC in a UNRESTRICTED AREA, either within or ( outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For MEMBERS OF THE PUBLIC who may at times be within the SITE BOUNDARY, the occupancy of that MIMBER OF THE PUBLIC will usually - be sufficiently-low to compensate for any increate in the atmospharie diffusion factor above that frr the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM. The specified release rate limits restrict, at all times,.the corresponding gamma- - and beta dose rates above' background to a MEMBER OF THE PUBLIC at or beyond the SITE B0UNDARY to less than or equal to 500 mrems/ year to the skin. These release rate limits also restrict,-at all-times, the corresponding
- thyroid dose rate above background to a child via the
("' inhalation pathway to less than or equal to 1500 l ' \~ - i mrems/ year. 63
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5.4 GASEOUS EFFLUENTS (cont'd) The required detection capabilities for radioactive materials in gaseous waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD, and other detection limits can be found in HASL Procedures Manual, HASL-300 (revised annually), Currie, L.A., " Limits for Qualitative Detection and Quantitative Determination - Application to Radio-chemistry," Anal. Chem. 40, 586-93 (1968), and Hartwell, J.K., " Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
- b. DOSE - NOBLE GASES (Section 5.4.2),
The Specification is provided to implement the requirements O of Sections II.B,-III.A and IV.A of Appendix I, 10 CFR Part 50. It implements the guides set forth in Section II.B of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appandix I to assure that the releasas of radioactive material in gaseous effluents to assure that the releases of radio-active material in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III. A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is l unlikely to be substantially underestimated. The dose ( 64
q Administrative Procedure UNT-005-014
.0ffsite Dose Calculation Manual Revision 0 O .
5.4 GASEOUS EFFLUENTS (cont'd) calculation methodology and parameters established for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology'provided in Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October'1977 and Regulatory Guide 1.111. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine-Releases from Light-Water Cooled Reactors," Revision 1, July 1977.
Sections 5.4.2 and 5.4.3 equations provided for determining 1 the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions. l Grab sampling of_ effluents from the main condenser evacuation and turbine gland sealing system is not required when this source has been continuously dis-charging'to the plant stack over the past 30 days. If no I primary to secondary leakage in-the steam generator exists, then there should be no radioactive release from the main condenser evacuation and turbine gland sealing i 1 system and-the gross beta or gamma monitoringfor noble j; gases will be sufficient'to determine if any radioactivity is present in the release. If a primary to secondary leak exists, then the release from the main condenser evacuation _and turbine gland sealing systems will be L sampled and analyzed in accordance with Table 5.4-1.
- - 65
~
Ad;.tinistrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 O 5,4 GASEOUS EFFLUENTS (cont'd)
- c. 10 DINE-131, 10 DINE-133, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM (Section 5.4.3)
This specification is provided to implement the require-ments of Sections II.C, III.A and IV.A of Appandix I, 10 CFR Part 50. The Specifications are the guides set forth in Section II.C of Appendix I. The ACTION state-ments provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable." The calculational methods specified in the Surveillance Requirements implement the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate patbways is unlikely to be substantially underestimated. The calculational methodo-logy and parameters for calculating the doses due to the actual release rates of the subject materials are con-sistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977 and Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors,' Revision 1, July 1977. These equations t also provide for determining the actual doses based upon the historical average atmospheric conditions. l l 66 i l
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0-O 5.4 GASEOUS EFFLUENTS (cont'd) The release rate specifications for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half-lives greater than 8 days are dependent upon the existing radionuclide pathways to man in the areas at and beyond the SITE BOUNDARY. The pathways that were examined in the development'of these calculations were: (1) individual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) deposition onto grassy areas where milk animals and meat-producing animals graze with consumption of the milk and meat by man, and (4) deposition on the ground wi' $ subsequent exposure of man.
'd. GASEOUS RADWASTE TREATMENT (Section 5.4.4)
The OPERABILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EX11AUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The discharge from the main condenser evacuation and turbine gland sealing system shall be required to be directed to the plant stack when the release rate of I-131 from this source is > 2 x 10 4 pCi/s. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as is reasonably achievable". This specification implements the: require-ments of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and the design objectives given in Section II.D of Appendix I to 10 CFR Part 50. The-specified limits governing the use of appropriate portions of the systems were specified as a suitable fraction of the dose design objectives set forth in Section II.B.and II.C of Appendix I, 10 CFR Ptrt 50, for gaseous effluents. ( 67 c - _- 1
UNT-005-014 Administrative Procedure
- Revision 0 Offsite Dose Calculation Manual .
O 5.5 TOTAL DOSE 5.5.1 TOTAL DOSE SPECIFICATl;N The annual (calander year) dose or dose commitment to any MEMBER OF THE PUBLIC due to release of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except'the thyroid, which ahall be limited to less than or equal tp 75 mrems. APPLICABILITY: At all times. ACTION: With the calculated doses from the release of radioactive materials in liquid or gaseous' effluents exceeding twice the limits of Specification 5.3.2.a. 5.3.2.b, 5.' 2.a. 5.4.2.b, 5.4.3.a. or 5.4.3.b calculations shall be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 5.5.1 have been exceeded. This evaluation should be done in accordance with guidance in Section 5.5.2. If such is the case, prepare and submit to the Commission within 30 days, pursuant to Technical Specifi-cation 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF T1IE PUBLIC from uranium fuel cycle sources, includrog all effluent pathways and direct radiation, for the caleadar year that includes the release (s) covered by this report. It shall also describe levels of radiation and 68 1
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 (v 5.5 TOTAL DOSE 5.5.1 TOTAL DOSE SPECIFICATION (cont'd) concentration of radioactive material involved, and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the above limits, and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete,
- p. SURVEILLANCE REQUIREMENTS:
- a. C'unulative dose contributions f rom liquid and gaseous effluents shall be determined in accordt*ce with Specifi-cation 5.3.2, 5.4.2, and 5.4.3 and in accordance with the methodology and parameters in the 0DCM.
- b. Cumulative dose contributions from direct radiation from the reactor units and from radwaste storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirements is applicable -
only under_ condition set forth in Specification 5.5.1'. b l g
-69
UNT-005-014 Administrative Procedure Revision 0 Offsite Dose Cal.ulation Manual . O 5.5 TOTAL DOSE (cont'd) 5.5.2 40 CFR 90 DOSE EVALUATION This section demonstrates compliance with Specification 5.5.1 Surveillance Requirements. Specifically, the dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and radiation from uranium fuel cycle sources shall be limited.to less than or equal to 25 mrem to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrem) over 12 consecutive months. Dose evaluations to demonstrate compliance with the above dose limits need to be performed only if quarterly doses exceed: (1) 3 mrem to the total body (liquid releases). (2) 1.0 mrem to any organ (liquid releases). (3) 15 mrem to the thyroid or any organ from radioiodines and particulates (gaseous releases), otherwise no evaluations are required. For the evaluation of doses to real individuals from liquid releases, the same calculational methods as employed in Section 5.3.4 will be used. However, more encompassing and realistic assumptions will be made concerning the dilution and ingestion of radionuclides by individuals who live and fish in the Waterford 3 area. The results of the Radiological Environ-mental Monitoring Program will be used in determining the realistic dose based on actual measured radionuclide concentra-O 70
_ _ . - __ . ~ , _ _ _ _ . _ _ _ _ _ _ _ _ . _ . - . _ _ _ _ _ _ _ _ _ . _ . . _ . . . . . UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 -l i
-5.5 ~ TOTAL DOSE (cont't) tions. For the evaluation of doses to real individuals from gaseous releases, the same calculational methods as employed I
-in sections 5.4.6 and 5.4.7 will be used. The total body dose !
factor should be substituted for the gamma air dose factor (M ) to determine the total body dose. Otherwise, the same f calculational sequence applies. More realistic assumptions will be made concerning the actual location of real individuals, the meteorological conditions, and the consumption of food. Data obtained from the latest land use census should be used
- to determine locations for evaluating doses. The results of the Radiological Environmental Monitoring Program will be included in determining more realistic doses based on actual
- f-sg measured radionuclide concentrations.
U CumulatAve dose contributions from direct radiation, from the . reactor unit, and from Radwaste Storage Tanks shall be deter-mined utilizing the results of routine plant perimeter surveys, TLD data, or a combination of both when necessary. l: 'L(' i 71
UNT-005-014 l Administrative Procedure Revision 0 0'ffsite Dose Calculation Manual . O 5.5 TOTAL DOSE (cont'd) 5.5.3 Total Dose Bases The specification is provided to meet the dose limitations of 40 CFR Part 190 that have been incorporated into 10 CFR Part 20 by 46 FR 18525. The specification requires the preparation and submittal of a Special Report wh-never the calculated doses from plant generated radioactive effluents and direct radiation exceed 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems. For sites containing up to four reactors, it is highly unlikely that the resultant dose to a MEMBER OF THE PUBLIC will exceed the dote limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives if Appendix I, and if direct radiation doses from the reactor units and outside storage tanks are kept small. The Special Report will describe a course of action that should result in the limitation of the annual dose to a KEMBER OF THE PUBLIC to within the 40 CFR Part 190 limits. For the purposes of the Special Report, it may be assumed that the dose commitment to the MEMBER OF TIIE PUBLIC from other uranium feel cycle sources is negligible, with the exception that dose contributions ' rom other nuclear fuel cycle facilities at the same site or within a radius of 8 km must be considered. If the dose to any MEMBER OF THE PUBLIC is estimated to exceed the requirements of 40 CFR Part 190, the Special Report with a request for a variance (provided the release conditions resulting in violation of 40 CFR Part 190 have not already been corrected), in accordance with the provisions of 40 CFR 190.11 and 10 CFR 20.405c, is considered to be a timely request and fulfills the requirements of 40 CFR Part 190 until NRC staff action is completed. 4 i l 72
UNT-005-014 rAdministrative Procedure ,
-Offsite Dose Calculation Manual Revision O' ,
o
- 5.5 TOTAL DOSE (cont'd)
- 5.5.3 Total Dose Bases
.he variance only relates to the Ifmits of 40 CFR Part 190, and does not apply in any way to the other requ.rements for dose limitation of 10 CFR Part 20, as addressed in Specifications 5.3.1 and 5.4.1. An individual is not considered a MEMBER OF
' THE PUBLIC during in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
s Y il l l g u
.- __ 73
UNT-005-014 Adainistrative Procedurc Offsite Dose Calculation Manual Revision 0 O 5.6 INSTRUMENTATION 5.6.1 Radioactive Liquid Effluent Monitoring Instrumentation Specification The radioactive liquid effluent monitoring instrumentation
. channels shown in Table 5.6-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 5.3.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section
5.3.5. APPLICABILITY
At all times. ACTION: l a. With radioactive liquid e~ffluent monitoring instrumentation channel alarni/ trip setpoint less conservative than required by the above Specification, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel inoperable.
- b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 5.6-1. Restore the inoper-able instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Technical Specifica-tion 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the specified ACTIONS are continued.
O 74
_ . ~ - - . . - . . . ~ . _ . - . . - = .
.- . . - . _ . - . . . . - - . - . . . . . . - - . . - . ~ . . .
UNT-005-014 LAdministraAive Procedure
. Revision 0 Offsite Dose Calculation Manual O
5.6- INSTRUMENTATION-(Cont'd) SURVEILLANCE REQUIREMENT Each radioactive liquid. effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 5.6-2. t O e-h
-75
UNT-005-014 Surveillance Procedure IOffsite Dose Calculation M nual ' Revision 0 TABLE 5.6-1 RADIOACTIVE LIQUID EFFLUENT MONITGRING INSTRUMENTATION MINIMUM CllANNELS INSTRUMENT OPERABLE ACTION
- 1. RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE Boric Acid Condensate Discharge 1 28 a.
Waste, Waste Condensate and Laundry Discharge 1 28 b. 1/ sump 29
- c. Dry Cooling Tower Sumps Turbine Building Industrial Waste Sump 1 29 d.
- e. Circulating Water Discharge (Blowdown lleat Exghanger 1 29 and Auxiliary Component Cooling Water Pumps)
- 2. CONTINUOUS COMPOSITE SAMPLERS 29
- a. Steam Generator Blowdown Effinent Line 1
- 3. FLOW RATE MEASUREMENT DEVICES Boric Acid Condensate Discharge 1 30 a.
Waate, Waste Condensate and Laundry Discharge 1 30 b.
- c. Turbine Building Industrial Waste Sump
- N.A. N.A.
- d. Dry Cooling Tower Sumps
- N.A. N.A.
- e. Circulating Water Discharge * (Blowdown and Blowdown lleat Exchanger and Auxiliary Component Cooling Water Pumps) N.A. N.A.
# Automatic termination of blowdown discharge only G 76e e
UNT-005 014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 : TABLE 5.6-1(Continued) TABl.E NOTATIONS i
- Pump performance curves generated in place shall be used to estimate flow. .
t ACTION STATEMENTS ACTION 28 - With the number of channels OPERABII less than required by the Minimum Channels OPERAB11 requirement, effluent releases , via this pathway may continue provided best efforts are made ' to repair the instrument and that prior to initiating a releases
- a. At leart two independent samples are analysed in accordance with Specification 5.3.1, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and discharge line valving; i ACTION 29 - With the number of channela OPERABLE less than required by the.Hinimum Channels OPERAB1I requirement, effluent releases via this pathway may continue provided best efforts are made to rep' air the instrument and that grab samples are analyzed
- for radioactivity at a lower limit of detection of at least 10*7 microcurie /ml.
- a. At least once per 12 hours when the specific activity of
-the secondary coolant is grater than 0.01 microcurie / gram
- DOSE EQU1VAIINT 1-131, or
- b. At_least once per 24 hours when the specific activity of the secondary coolant is less than or equal to 0.01 ,
microcurie / gram DOSE EQU1 VALENT 1-131. ,- ACTION 30 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releasy, via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per 4 hours during actual releases. Pump l Q performance curves generated in place may be used to estimate !b l-flow. 77
t%T-005-014 Surveillsnce Procedure ' Ferision 0 Offolte Dose Calculetion .1=u21 TABLE 5.6-2 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRITMENTATION SURVEILLANCE REQUIREMEhTS CHAN7EL CliANNEL It'NCTIONAT. CHANNEL SOURCE CALIBRATION TEST CHECK CHECK INSTRUMENT
- 1. RADIDACTIVITT MONITORS PROVIDING ALARMS AND AUTOMATIC TERMINATION OF RELEASE P R(3) Q(1)
P
- a. Boric Acid Condensate Discharge P R(3) Q(1)
P
- b. Vaste, Waste Condensate and Laundry Discharge M R(3) Q(5)
D
- c. Dry Cooling Tower Sumps M R(3) Q(5)
D
- d. Turbine Building Industrial Waste Sump
- e. Circulating Water Discharge Q(5)
(Blowdown Heat Exchanger D M R(3) _ Auxiliary Component Cooling Water Pumps)
- 2. CONTINUOUS COMPOSITE SAMPLERS N.A. R Q D(6)
- a. Steam Generator Blowdown Effluent Line
- 3. FLOW RATE MEASUREMENT DEVICES N.A. R Q Boric Acid Condensate Discharge D(4) Q
- a. N.A. R Waste, Waste Condensate and Laundry D(4) b.
Discharge N.A. N.A. N.A. N.A.
- c. Turbine Building Industrial Vaste Sump N.A. N.A. N.A. N.A.
- d. Dry Cooling Tower Sumps
- e. Circulating Water Discharge (Blowdown and Blevdown Heat Exchangers and Auxiliary N.A. N.A. N.A. N.A.
Component Cooling Water Pumps)
# Automatic termination of Blowdown discharge only 9 18e e l
Administrative procedure UNT-005-014 offsite Done. Calculation Manual Revision 0 j cO l TABLE 5.6 Q (Continuedl TABLE NOTATION
- 1. The CilANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exists.
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
2.- Circuit failure
- 3. Instrument indicates a downscale failure.
l
- 2. The CilANNEL FUNCTIONAL TEST shall also demonstrate thei control room alarm annunciation occurs if any of the following conditions exists: ,
- 1. Instrument. Indicates measured levels above the_ alarm setpoint.
- 2. Circuit failure.
- 3. The initial CilANNEL CAtlBRATION shall be performed using one or m9re of the reference standards certified by t.he National Bureau of Standards or using standards that have been obtained from supplierm that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system for over its intended range of energy and measurement range. For subsequent CllANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
- 4. CilANNEL CIIECK shall consist of verifying indication of flow during periods of release. CllANNEL;ClIECK shall be made_at least once per 24 hours on days on which continuous, periodic, or batch releases ire made.
- 5. The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm / trip setpoint and that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm set. l
- 2. Circuit failure.
- 3. Instrument controls not_ set in operate mode.
6.: CIIANNEL CIIECK shall be made at least once per 24 hours on days on which , ,g - continuous releases are made to the Circulating Water System or Waterford f lg 3 waste pond. 79 l - . -- -- . - _ ~ _ . . . , - , - , _ -____ _
UNT-005-014 Administrative Procedure itevision 0 Offsite Dose Calculation Manual - 9 5.6 INSTRUMENTATION (cont'd) 5.6.2 kadioactive_ _ Gaseous Ef fluent Monitorudst rumentation Specifications The radioactive gaseous effluent monitoring instrumentation channels shown in Table $.6.3 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 5.4.1 are not exceeded. The alarm / trip setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in Section
- w.3.
APPLICAhlLITY: As shown in Table 5.6-3 ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentatt w channel alarm / trip setpoint less conservative than required by the above Specification, inraediet cly suspend the release of radioactive gaseous effluents monitored by the affected channel, or declare the channel inoperable, or change the setpoint so it is acceptably conservative.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, .
take the ACTION shown in Table 5.6-3. Restore the
' inoperable instrumentation to OPERABLE status within 30 days or, if unsuccessful, explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Technical Specification 6.9.1.8, why this inoperability was not corrected within the time specified. Releases need not be terminated after 30 days provided the l specified ACTIONS are continued.
80
l 4 Administrative Precedure UNT 005-014 Offsite Dore Calculdtion Mancal Revision 0 O-5.6 INSTRUllENTATION (cont'd) f Sl'RVEILLANCE REQUIREMENTS: 1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERAllLE by performance of the Cl!ANNEL CIIECK, SOURCE C)[ECK, CilANNEL CALIBRATION, and CilANNEL FUNCTIONAL TEST operations at the frequencies shown in i Tabic 5.6-4. . , p F f a 4 F 1 k
- V
- k J
F i [ l 81
...u.x,, , , , , , . . . , - - _ . . , . . , . , . . . . . . , , , _ - . . . . _ ..,...,.-,%..,.,...- . . _ , , . , . , - , . . . - ,,.....-..c..,~.r.... , . -
TABLE 5.6-3 RADICACTIVE GASEOUS EFFLUENT MONITORING INSTRLMENTATION MINIMUM CHANhTLS OPERABLE APFLICABILITY ACTI(W 1NSTRUMENT .I. WASTE GAS HOLDUP SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
- 35 Termination of Releaw I
- b. Ef fluent System Thw Rate
- 36 Measuring Device I
'2. MAIN CONDFNSER EVACUATION AND TURBIhI GLAND SEALING SYSTEM
- 37
- a. Noble Gas Activity Monitor I I
- b. Iodine Sampler
- c. Particulate Sarepler
- 26
- d. Sampler Flow Rate Monitor I
#If a primary to secondary leak exists or if th: .:Sie gas monitors in the main condenser evacuation and turbine gland sealing system or if the steam generator blowdown monitor indicates the presence of radioactivity in the secc.ndary system, the flow from this release point shall be diverted immediately to the pla.it stack. These instruments are in the plant stack and sampling for radiciodines and particulates shall occur at the plant vent when this occurs.
9 eze e
TABLE 5.6-3 (Cu2nued) RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATIOR' . 9 MINIMUM CHANNELS OPERABLE 'AFPLICABILITY ACTION INSTRUMENT. 4 i 4. REACTOR AUXILIARY BUILDING i VENTILATIOC SYSTEM l . (PLANT STACK)
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
- 37 Termination.of Releasef-I I
- 39
- b. -Iodine Sampler I i
- 39 i
c Particulate Sampler I I 36 [ d. Flow Rate Monitor i
- 36
- Sampler Flow Rate Monitor I j e.
i l 5. i FUEL HANDLING BUILDING 1 VENTILATION SYSTEM (NORMAL) 4 a 1
*** 37
- a. Noble Gas Activity Monitor I *** 39
- b. Iodine Sampler I *** 39
- c. Particulate Sampler i *** 36 j d. Flow Rate Monitor I I i+2 36 l e. Sampler Flow Rate Monitor 1
i
; # Automatic termination of containment purge only. -
i I l . 4 3 83 ^ i
, , - - - , , _ . .,_r.- . ..,-,..-v -
-. . - - - , - , _ --m _ _-- - _ _ - _ __ _ _ _--------_b
UNT-005-014 j Arbinistrative Procedure Revision 0 Offsite Dose Calculation Manual . I O TABLE 5.6-3 (Continued) TAllLE NOTATIONS sat all times.
*+During WASTF GAS HOLDUP SYSTEM operation.
***With irradiated f uel in the storage pool .
ACTION STATEMENTS ACTION 35 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents of the tank (s) may be released to the environment provided best efforts are made to repair the instrument and the prior to initiating the release:
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of the f acility staff independently verify the release rate calculat.fons and discharge valve lineup; ACTION 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that the flow rate is estimated at least once per 4 hours. For the vaste gas holdup tank this action item is applicable only during periods of release. For the main condenser evacuation and turbine gland sealing systems, this action item applies only during release via the discharge silcocer and only during turbine gland sealing operations and/or vacuum pump operation.
ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided best efforts are made to repair the instrument and that grab samples are taken at least once per 12 hours and these sampics are analyzed for gross activity within 24 hours. However, containment purging of radioactive effluents must be immediately suspended during this condition for the plant stack only. O 84
l I UNT-005-014 Administrat.ive Procedure Revision Offsite Dose Calculation Manual [$ i I TAllLE $.6-3_(Continuedj - l p T_Allll NOTATIONS ACTION 39 - With the number of channels OPERAllLE less than required by j' the Minimum Channels OPERAllLE requirement, effluent releases j via the affected pathway may continue provided best efforts i are made to repair the instrument and that samples are tontinuously collected with auxiliary sampling equipment as
- required in Table $.4-1.
l
- I l l 1 i I i
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-I
. i I
l- r L { t I e
-i
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i
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i t 1 I I 1 ; 85 i i +.G-. _ _ . - . ~ , . _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ . - d
TABLE 5.6-4 . RADIOACTIVE GASEOb EFFLUENT MONITORING INSTRUMENTATION SURVEILL%NCE REQUIFIMENTS CHANNEL MODES IN *-HIOT CHANNEL SOURCE CIIANNEL FUNCTIONAL SURVEILTANCE INSTRUMENT CHECK CIIECK CALIBRATION TEST IS REQUIRED __
- 1. VASTE GAS IIOLDUP SYSTEM
- a. Noble Gas Activity Monitor -
Providing Alarm and Automatic
- Teonination of Release P P R(3) Q(1)
- b. Effluent System Flow Rate Measuring Device P N.A. R Q
- 2. MAIN CONDENSER EVACUATION AND TURBINE GLAND SEALING SYSTEM
- a. Noble Gas Activity Monitor D M R(3) Q(2)
V N.A. N.A. N.A. *
- b. Iodine Sampler W N.A. N.A. N.A. *
- c. Particulate Sampler Q *
- d. Sampler Flow Rate Monitor D N.A. R 4
e "e -- - e
e i TABLE 5.6-4 (Continued) t i RADIOACTIVE GASEOUS EFFLUENT MONIT08 TING INSTRUMENTATION SURVEILLANCE REQUIREnf.nid q ' CHANNEL MODES IN WHICH i i CHANNEL SOURCE. CHANNEL FUNCTIONAL SUR\TILLANCE ! . INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED j
- i. i I
' 4. REACTOR AUXILIARY BUILDING l
! VENTILATION SYSTEM ! ! (PLANT STACK) 7 r Noble Gas Activity Monitor -
.j a.
j . Providing Alarm and Automatic
- i Termination of Release D M R(3) Q(6) l t
N.A. N.A. * !
- b. Iodine Sampler W ~N.A.
N.A. *
- c. Particulate l Sampler W N.A. N.A.
} i N.A. R Q *
- l
- d. Flow 1*. ate Monitor- D R * -
- e. Sampler Flow Rate Monitor D N.A. Q [
a i i . l 5. FUEL HANDLING EUILDING t
- l. VENTILATION SYSTEM (NORMAL) 7
. i l- Q(2) *** j
- j. a. Noble Gas Activity Monitor' D M R(3) t f W N.A. N.A. N.A. *** t
- i. b. Iodine Sampler.
I $ W N.A. N.A. N.A. *** c., Particulate Sampler ) l J D N.A. R Q *** . j d. Flow Rate Monitor i 4 fL A . R Q ***
- e. Sampler Flow Rate Monitor D 7 i
~ -i # Automatic termination of containment purge only. . l R
l i ! l 87 ! i i
l UNT-005 014 Administrative procedure f Revision 0 Offsite Dose Calculation Manual 9 TABLE 5.6-4 (Continued) T ABLE NOTATIONS
*At all times.
**%' hen irradiated fuel is in the spent f uel pool.
- 1. The CilANNEL TUNCTIONAL TEST t. hall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm / trip setpoint.
- 2. Circuit failure.
- 3. Instrument indicates a downscale failure.
- 2. The CllANNEL TUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm setpoint.
- 2. Circuit failure.
- 3. The initial CllANNEL CAllBRAT103 shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have Men obtained f rom suppliers that participate in measurement assurance activities with NBS. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CllANNEL CAllBRATION, sources.that have been related to the initial calibration shall be used.
- 6. The CllANNEL TUNCTION TEST shall also demonstrate that automatic isolation of this pathway occurs if the instrument indicates measured levels above the alarm /. trip setpoint and that control room alarm '.nnunciation occurs if any of the following conditions exists:
- 1. Instrument indicates measured levels above the alarm set.
- 2. Circuit failure.
- 3. Instrument controls not set in operate mode.
O 88
UNT-005-014 4dministrative Procedure Revision 0 Jffsite Dose Calculation Manual O 5.6 INSTRUMENTATION (Cont'd) 5.6.3 Instrumentation Bones
- a. RADIDACTIVE L10UID ErrLUENT MONITORING t INSTRlTHENTATION (5.6.1)
The radioactive liquid effluent instrumentation is l provided to monitor and control, as applicable, the relerses of radioactive materials in liquid elfluents
- during actual or n tential releases of liquid effluents. ,
The alarm / trip setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in Section 5.3.5 to ensure that the alarm / trip will occur prior to exceeding the limits _of 10 l CFR Part 20. The OPERABILITY and use of this instrumenta- d tion is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50.
- b. RADIDACTIVF CASEOUS EFFLUENT MONITORING INSTRUMENTATION (5.6.2)
The radioactive gaseous effluent instrumentation is-provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.
' The alarm / trip setpoints for these instruments shall be calculated and adjurted in accordance with the methodology and parameters in Section 5.4.8 to ensure that the alarm / trip will occur _ prior to exceeding the limits of 10 CTR Part 20. This instrumentation also include provisions for monitoring- (and controlling) the concen-trations of potentially explosive gas mixtures in the WASTE CAS HOLDUP SYSTEM. The OPERABILITY and use of this '
instrumenta' tioni 's consistent with the requirements of General Design Criteria 60, 63, and 64 of-Appendix A to 10 CFR Part 50.
--. ~.. - _ - . . _ _ _ _ , . _.._89. _ . - . ~ _ _ . _ _ . . _ _ _ _ ,_
' UNT-005 014 Adctnistrative Procedure Offsite Dose Calculation Manual Revision 0
, - l I i j 5.7 1lQUID AND GASEOUS RADVASTE PROCESSES i l l The block flow diagrams of the radwaste systems are shown in ! i
/ttachments 6.11 and 6.12. In order to obtain a more detailed i description, t.ee the appropriate sections of the TSAR. ,
l [ 6 l i t ] l , I I L I I O: 90
Adminintrative procedure UNT-005-014 l Revision 0 , Offsite Dose Calculation Manual . O 5.8 RADIOLOGICAL ENVIRONtiENTAL HONITORING PROGRAM REQUIREriENTS , Radiological Environmental Program Speciffcation ; 5.8.1 The radiological environmental monitoring program shall be conducted as specified in Table 5.8-1. A At all times. _PPLICABILITY: ACTION:
- a. With the radiological environmental monitoring program not being conducted as specified in Table 5.8-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Technical Specification 6.9.1.7, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence, i O b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a speci- ,
fled location exceeding the reporting levelt of Table 5.8-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days, pursuant to
- Technical. Specification 6.9.2, a Special Report that
' identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce radioactive effluents so that the potential annual dose
- to a MEMBER OF THE PUBLIC is less than the calendar year limits of Specifications 5.3.2, 5.4.2, and 5.4.3. When more then one of the radionuclides in Table 5.8-2 are detected in the sampling medium, this report shall be submitted if concentration (1)_ , concentration (2)_ , . . . > l '. 0 reporting level (1) reporting, level (2)
*The methodology and parameters used to esticate the potential annual dose to A MEMBER OF THE-pUBLIC shall be indicated in this report.
91
UNT-005-014 M minit4trative Proceduse Di f s i t t. Lose Calculation ?!anual Revision 0 KAD101,0GICAl, EhTIRONMENTAE MON 110 RING PROGRAM REQUIREtiENTS (Cont 'd) O 5.8 When radionuclides other than those in Table 5.8-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose
- to A MEMitER Of Tile PUllEIC is equal to or greater than the calendar year limits of Specifications. 5.3.2, 5.4.2, and 5.4.3. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report,
- c. With milk or fresh leafy vegetabic samples unavailable from one or more of the sample locations required by Table 5.8-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days. 1 The specific locations from which samples ware unavailtble may then be deleted from the monitoring program. Pursuant to Technical Specification 6.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent j
Release Report and also include in the report revisions of Att.achments 6.13, 6.14, 6.16, 6.17 and 6.18 reflecting l the new location (s). O 92
UNT-005-014 Administrative Procedure Offsite Done Calculation Manual Revision 0 5.8 RADIOLOGICAL ENVIRONMENTAL MONIT0klNG PROGRAM REQUIREMENTS (Cont'd) SURVEILLANCE REQUIRDIENTS: The radiological envirottmental monitoring samples shall be collected pursuant to 'lable 5.8-1 from the specific locations given in Attachments 6.13 and 6.14, and shall be analyzed pursuant to the requi-ements of Table 5.8-1 and the detection capabilities require y Table 5.8-3. O 9 O 93
TABLE 5.8-I-RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF REPRESENTATIVE SA!!PLES AND SAMPLING AND TYPE AND FREQUENCY EXPOSURE PATINAY I
AND/OR SAMPLE SAMPLE LOCATIONS
- 31 routine monitoring stations Quarterly Gamma dose quarterly.
- 1. DIRECT RADIATION either with 2 or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:
an inner ring of stations, one in each meteorological sector in the general area of the SITE BOUNDART,
. an outer ring of stations, 1 in -
10 of the meteorological sectors in the 6 - to 8-km range frem the site; the balance of the stations to be placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations
*The number, media, frequency, and location of samples may vary from site to site. This table presents an acceptable minimum program for a site at which each entry is applicable. Local site characteristics must be examined to determine if pathways not covered by this table may significantly contribute to an individual's dose and should be included in the sampling program.
O "O e
l- TABLE 5.8-1 (W_snued) RADIOLOGICAL ENVIRONMENTAL Ff0NITORING PROGRAM
- 4 NIHfBER OF REPRESENTATIVE SAMPLES AND SAMPLING AND TYPE AND 5EEQUENCY jEXPOSUREPATTIWAY OF ANALTSIS a COLLECTION FREQUENCY
;'AND/OR SAMPLE SAMPLE LOCATIONS
- 2. - AIRBORNE l Radiciodine and Samples from 5 locatiens continuous sampler Radiciodine Canister
! Particulates operation with sample I-131 analysis weekly. L. 3 samples from close to the collection weekly, or i 3 SITE BOUNDARY locations, in more frequently if different sectors, of the required by dust Particulate Sampler: l Gross beta radioactivity i highest calculated annual average loading. j ground-level D/Q. analysis following ! filter change; 1 saeple from the vicinity of a Gamma isotopic analysis
- l comunity having the highest of composite (by calculated anr_aal average location) quarterly. ,
ground-level D/Q.. l I sample'from a control location, as for example 15-30 km i distant and in the least prevalent wind direction.' , i
- 3. WATERBORNE Surface' I sample upstream Composite samp"le over Gama isotopic analysis
- l f a.
1 sample downstream 1-month period monthly. Composite for i tritium analysis quarterly.
- i
! b. Ground Samples f rom 1 or 2 sources Quarterly Gama isotopic
- and tritirna h
only if.likely to be affected analysis quarterly. - l l } i
}
}
[ 95 i l- ,
TABLE 5.8-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
- NUMBER OF .
REPRESENTATIVE ' EXPOSURE PATINAY SAMPLES AND SAMPLING AND TYPE AND FREQUENCY SAMPLE LOCATIONS
- COI.LECTION FREQUENCT OF ANALYSIS AND/OR SAMPLE Drinking 1 sample of each of 1 to 3 of Composite sample I-131 analysis on each c.
the nearest water supplies that over 2-week period
- composite when the dose could be affected by its when I-131 analysis calculated for the discharge. is performed, monthly conrumption of the water composite otherwise is greaterg than I erem per year. Composite for gross twta and gamma isotopic analyses" monthly. Composite for tritiun analysis quarterly.
- d. Sediment 1 sample from downstream area Semiannually Gamma isotopic analysis -
from with existing or potential semiannually. shoreline recreational value.
- 6. INGESTION
- a. Milk Samples from milking animals Semimonthly when Gaimaa isotopic" and I-131 in 3 locations within 5 km animals are on analysis semimonthly when distance having the highest pasture; monthly at animals are on pasture; dose potential. If there are other times monthly at other times.
none, then, I sample from milking animals in each of 3 areas between 5 to 8 km distant where doses are calculated.to be greater than 1 mrem per yr.* 1 sample f rom milking animals at a control location 15-30 km Jistant and in the least - prevalent wind direction. G -
"O g
TABLE 5.8-1 (C a inued) ; i RADIOLOGICAL ENVIRONMENTAL ff0NITORING PROGRAM
- i t
1 NUMBER OF 1: i REPRESENTATIVE SAMPLES AND SAMPLING AND TYPE AND FREQUENCY '
' EXPOSURE PATHWAY l AND/OR SAMPLE SAMPLE LOCATIONS
- COLLECTION FREQUENCY OF ANALYSIS
~
1
' e >
- b. Fish and 1 sample of each comunercially Sample in season, or Gamma isctopic analysis and recreational important semiannually if they on edible portions. ;
l Inverte- '- brates species in vicinity of plant are not seasonal j discharge area.- 1 i- 1 sample of same species in ; ! areas not influenced by plant discharge. {
- c. -Food I sample of each principal class At time of harvest 5 Gamrna isotopic analysis' l
} Products of food products from any area on edibic portien. [ j - that is irrigated by water in , j j~ which liquid plant wastes have , j discharged.
- j i Samples.of.1 to 3 different kinds Monthly when Cacuna isotopic ~ and I-131 j l of broad leaf vegetatien grown available analysis.
- nearest each of two different [
I offsite locations of highest j' predicted annual average ground- , i level D/Q if milk sampling is not ! { performed. l 1 I sample of each of the- similar Monthly when Gamma isotopic" and I-131 f broad leaf vegetation grown available analysis. j o d 15-30 km distant in the least i prevalent wind direction'if milk [ sampling is not performed.
+
e 8 i [ l' i
" i i
i
TABl.E 5.b 1 iContinued) , TABU: NOTATIONS
. Specific parameters of distance and direction sector from the centerline of O
one reactor, and additional description where pertinent, shall be provided for each and every sample location in Attachments 6.14, 6.16, 6.17 and 6.18. Refer to NUREG-0133. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. Deviations are permit.ted f rom the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. 11 specimens are unobtainable due to sampling equipment malfunction, corrective action shall be completed prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time. In these instances suitable alternative media and locations may be chosen for the particular pathway in ' question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples for that pathway and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table reflecting the new location (s). bone or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as-two or more dosimeters. Tilm badges shall not be used as dosimeters for measuring direct radiation. The frequency of analysis or readout for TI.D systems will depend upon the characteristics of the specific system used and should be selected to obtain optimum dose information with minimal fading.
'The purpose of this sample is to obtain background information. If it is not practical to establish control locations in accordance with the distance and vind direction criteria, other sites that provide valid background data may be substituted.
d AirMrne part.iculate sample filters shall be analyzed for gross beta r di' e -tivity M hours or more af ter sampling to allow for random and thoron lausi*.r de:ay. If gross beta activity in air particulate samples is greater
- n. times the yearly mean of control samples, gamma isotopic analysis shall
.- 1* , formed on the individual samples.
Gw.ma isotopic analysis means the identificat. ion and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility. O 98
TABLE __S.8 1 (Con _tinued), , TABII NOTATIONS O iThe " upstream sample" shall be taken at a distance beyond significant influence of the discharge. The " downstream" sample shall be taken in an area beyond but near the mixing zone. " Upstream" samples in an estuary must be taken far enough upstream to be beyond the plant influence. Salt water shall be sampled only when the receiving water is utilized for recreational activities. 8A composite sample is our in which the quantify (aliquot) of liquid sampled is proportional to the quantify of flowing liquid and in which the method of samplang employed results in a specimen that is representative of the liquid flow. In this program composite sample aliquots shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g. , monthly) in order to assure obtaining a representative sample, hGroundwater samples-shall be taken when this source is tapped for drinking or irrigation purposes in arear where the hydraulic gradient or reenarge properties are suitable for contamination. IThe dose shall be calculated for the maximum organ-and age group, using the methodology and parameters in this document. dlf harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly._ Attention shall be paid to including samples of tuberous and root O food products. t to 9 4 e k O 99
- - _ - __ -... ~ _ -__
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+ s
- m ws'M O s
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~ O: A G
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< 4 o a m
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. _ _ _______. _ . - -=
~ TABLE 5 1 .
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Lower Limits of Detection (LLD) # VATER AIRBORNE PARTICULATE FISH MILK FOOD FRODUCTS SEDIFINT - ANALYSIS (pCi/1) . .OR GASES (pCi/m3)_ (pCi/kg, vet) (pCi/t) .(pCi/kg, vet) (pCi/kg dry) gross beta 4 0.01 4- 11 - 3 . 2000 15' 130 [Mn-54 , ? Fe-59 30 260 i ' j'Co-58,60 15 130
- Zn-65 30 260 i Zr-Nb-95 15
,.I-131 1 0.07 1 60 l !:Cs-134 15 0.05 '30 15 60 150 ! ) . 18 0.06 150 18 80 180 lCs-137 ; }- , i ' Ba-La-140 15 15 ,
~
i ! t i l^ . t I I . 1 ! !. 101 t
- j. .
I . . . - - -. _ . _ . _ . _ _ . . __ __. _._ _ __ _ _ . _ . . _ . . _._. _. _ __ _ .-.
UNT-005-014
- Administrative Procedure Offsite Dose Calculation Manual Revision 0 O
TABLE 5.b 3 TAM.E N01 ATIONS
*This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together w4th those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
b Required detection capabilities for thermoluminescent dosimeters used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. The LLD is defined, for purposes of these specific tions, as the smallest concentration of radioactive material in a sample that will yield a net count, above system b4.ekground, that vill be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separatio u
.66 s b E . V . 2.22 x 10' . Y , exp(A AT)
Where: LLD is the "a priori" lower limit of detection as defined above, as I microcuries per unit mass or volume, "b 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, A is the radioactive decay constant for the particular radionuclide, and at for environmental samples is the elapsed time between sample collection, or end of the sample collection period, and time of counting Typical valuer of E, V, Y and at should be used in the calculation. 102
. _ . . __ _ ~ _ _ _ _ _ _ _ . . _ ._ _ ...-. . _ ._._ _ _ _ .
._____..-__.m._,
Administrative Procedure U T-005-014 ; Offsite Dose Calculation Manual Revision 0 O l TABLE 5.8-3 (Continued) j TABLE NOTATIONS It should be recognized that the LLD is defined as an a, priori (before the fact) limit representing the capability of a measurement system and not as an a posterf orf (af ter the f act) limit f or a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes..the presence of interfering nuclides, or other uncont.'911able circumstances may render these LLDs unschievable. In such cases. the contributing factors shall be identified and described in the i Annual Radiological Environmental. Operating Report pursuant to Technical Specification 6.9.1.7. l d LLD for drinking water samples. If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used. 6 A e O 4 6 L 4 t 4 i O -
. 103 - , - . . . , _ -_ . . , . . . _ . , ... - _ . . _._ _ ._. ~ ___. _ _. . _ . . _ _ . - _ . . , _ . - _ . . _ . ~ . . . . _ _ _ . _ . _ , _ . _ . . .
Administrative Procedure UNT-005-014 Offsite Dose Calculation Manual Revision 0 0 5.8 KAD10 LOGICAL ENVIRON?iENTAL MONITORING (Cont'd) 5.8.2 Interlaboratory Cc,mparison Program Specifi(ition Analyses shall lie performed on all radioactive materialte supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission. APPLICABILITY: At all times. ACTION:
- a. k'ith 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 pursuant to Technical Specification 6.9.1.7.
SURVEILLANCE REQU1REMENTS The Interlaboratory comparison Program shall be described in , i Section 5.8.5. A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7. l l O 104
Administrative Procedure UNT-005-014 0'ffsite Dose Calculation Manual Revision 0 ( 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.3 Land Use Census Specification A land use census shall be conducted and shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectus of the nearest milk animal, the I nearest residence, and the nearest garden
- of greater than 50 m 2 (5000 ft 2) producing broad leaf vegetation.
APPLICABILITY: At all times. ACTION:
- a. With a land use census identifying a location (s) that p yields a calculated dose or dose commitment greater than l :h the values currently being calculated in Specification l 5.4.3, identify the new location (s) in the next Seiniannual Radioactive Effluent Release Report, pursuant to- Specifict tion 6.9.1.8.
L. With a land use census identifying a location (s) that
-yields a calculated dose or dose commitment (via the same exposure pathway)~20% greater than at a location from v5..a v ; des are currently being obtained in accordance
- witi. f; ecification -5.7.1, add the new -location (s) - to the radiological environmental monitoring program within 30 days. The_samplfag location (s), excluding the control station location, having the lowest-calculated dose or
!- dose commitment (s), via the same exposure pathway, may be deleted fror._this monitoring program after October 31 of the year in which this land ?ise census was conducted. i f'N Pursuant to Technical Specification 6.9.1.8 identify the new location (s) in the next Semiannual Radioactive Effluent Release Report.and-also include in the report p revision of Attachments 6.13, 6.14, 6.16, 6.17, and 6.18 !~ reflecting the new locations (s). i- 105
UNT-005-014 i Administrative Procedure Offsite Dose Calculatio, Manual Revision 0 O 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) SURVEILLANCE REQUJREMENTS The land use census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Technical Specification 6.9.1.7.
- Broad leaf vegetation sampling of different kinds of regetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 5.8-1 Part 4.c. shall be followed, including analysis of control samples.
O 106
. . - . ~ . . . ~ . . .. -...- - -. .~ .- ..~. . . . - . . . - -
Administrative Procedure UNT-005-014
^
Offsite Dose Calculation Manual Revision 0 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.4 Discription of the Radiological Environmental Monitoring Program < The Radiological Environmental Monitoring Program (REMP) is expounded on in Attachment 6.13, and the Sample Location
< Table, Attachment 6.14. Attachment 6.15 explains the sector and zone designations for the sample locations. Attachments 6.16, 6.17 and 6.18 show the sample locations within the 2,10, and 50 mile radius of Waterford 3.
Deviations are permitted f rom the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are O unobtainable due to.sempling equipment malfunction, every i effort shall be made to complete corrective action prior to V the end of the next sampling period. All deviations from the sampling schedule-shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practical continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable alternative media and locations may be chosea for the particular pathway in question and appropriate substitutions'made within 30 days An the Radiological
-Environmental Monitoting Programs.
107
Administrative Procedure UNT-005-014 Offsite Pose Calculation Manual Revision 0 O 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.5 Description of the Interlaboratory Comparison Program As described in Section 5.8.2 the quality assurance in radiological environmental sampling will be maintained through participation in the Environmental Protection Agency's Radiological Laboratory Quality Assurance Program. The summary of results will be presented in tabular form and will include the type of analysis, the preparation (collection) date, the date the results are rcturned, the mean of tl.- analyses (usually triplicate), the standard deviation, the date the values are released for information, the known value, the three standard deviation limit, and a two standard deviacion/three standard deviation warning / action flag. If the sample analysis indicates results outside the three standard deviation range, then the corrective actions taken to prevent a recurrence will be documented and submitted along with all results when the Annual Radiological Environmental Operating Report is , submitted. O 108
UNT-005-014
' Administrative Procedure
' Offsite Dose Calculation Manual Revision 0 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.6 Dispersion Parameters For Critical Locations As per Requirements 5.8.3, the dispersion parameters for the ,
site boundary and where necessary, as identified by the Annual Land Use Census, are listed in Attachment 6.2. This
-table will be subject to changes based on the Annual Land Use Census and historical data.
i e 4 I. u.~ f r-109
n. UNT-005-014 Administrative Procedure Offsite Dose Calculation Manual Revision 0 O 5.8 RADIOLOGICAL ENVIRONMENTAL MONITORING (Cont'd) 5.8.7 Radiological Environmental Monitoring Bases
- a. INTERLABORATORY COMPARISON PROGRAM (Section 5.8.2)
The requirement for participation in an approved Inter-laboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are valid for the purposes of Section IV.B.2 of Appendix-I to 10 CFR Part 50.
- b. LAND USE CENSUS (Section 5.8.3)
This specification is provided to ensure that changes in the use of areas at and beyond tl.e SITE BOUNDARY are identified and that modifications to the radiological environmental monitoring program are made if required by the results of this census. The best information from the door-to-door survey, from aerial survey or from consulting with local agricultural authorities shall be used. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricti-- the census to gardens of greater than 50 m2 provides assurance that l significant exposure pathways via leafy vegetables will be l ' identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/yr) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were made: (1) 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and (2) a vegetation yield of 2.,kg/m2,
' 110
_ ..~. _ . _ . _ _ -. _ _. _ _.. _ .__ _ . _ . _ _ . . _ . _.-.. _ .._ ._-._.-. _ ._. _ _ . _ _ -. _ _ UNT-005-014 Administrative Procedure Revision 0 Offsite Dose Calculation Manual , 5.9 TECHNICAL SPECIFICATION CROSS-REFERENCES Changes to the Technical Specifications (TS) recommended by Generic Letter 89-01 (Reference 2.8) resulted in programmatic controls for radiological effluents, radiological environmental monitoring, and effluent radiation monitoring instrumentation being relocated to the Offsite Dose Calculation Manual. All references of the fonner version of the TS that are contained in current plant operating procedures shall be cross-referenced to specifications contained in the ODCM using Attachment 6.20. Relocated requirements set forth in the ODCM should be incorporated into current plant operating proce- 4 dures as they undergo routine review and revision. 6.0- ATTACi&!ENTS O- Ref er - to -Table of Contents 4 h I e O- 4
. 111
l l SITE BOUNDARY FOR
/
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\ KADI0 ACTIVE CASEOUS AND LIQU'D EFTLUENTS
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A gm l O l Attachment 6.1 (1 of 1) UNT-005-014 Revision 0 112
HISTORICALAVERAGEDISPERSIbHANDDEPOSITION d . PARAMETERS FOR AREAS AT OR BEYOND THE UNRESTRICTED AREA BOUNDARY N4RAL AVDW2 ADO.153120 7 DIS!1361CN NO [E3MITICH PMWCT36 , BMID CN IGF! URIC 34. MEITIMUCICAL IAn NO C138tpff LAND TJ. Q2RE
*/Q fyQ DDecrIt24 SIrltm tu. M (per 32 ;
RrrE2'Itm 1YIT THCH Sr!Y PD CIEM CH IIX:ATI:N Dm ST'IT LOCATION
< stim) (maters) tary 0.80 1287 1.0E 05 2.4E-08 N(a) A Ef!I IQ24IARY 0.60 966 1 6E 05 3.4E-08 PSE(8) B 0.60 966 1.5E=r'? 2.8E-08 HE(a) C 2.5E-08 D 0.60 966 1.6E-OS DE(a) 1287 6.9E 06 1.3E-08 E E 0.80 0.60 %6 1.11-05 2.3E-08 ESE F 3.1E-08 G 0.60 966 1.1E-05 EE 6.3E-06 2.4E-06 H 0.80 1287 SSE 2.71-09 J 1,60 2575 8.9E-07 .
S 7.9E-10 E 3.10 4989 3.0E-07 SW 3.3E-07 9.1E-10
- L 3.40 5472 1.7E46 4.9t-09 W M 1.50 2414 1609 2.3E-06 7.1E-09 W N 1.00 0.80 7.St46 2.7E-08 W P 1287 1.0E45 3.2E-08 W Q 0.80 1287 0.9(L 1448 9.4E-06 2. 4E.:08 ISAJ R 0.90 1448 7.8E-06 1.8E*08 RESIM2CE N' A 2092 3.0E-06 5.8E-09 tee B 1.30 0.90 1448 6.3E-06 1.2E-08 NE C 5
[3 DE D E 0.90 2.20 1448 3541 6.8E-06 7.4E-07 1.1E-08 1.0E-09 E 4.8E 10 ' \ F 3.10 4989 3.7E-07 25E 2.3E-07 3,E-10 G 4.00 6437 SE 1.3E-09 W W 1.00 1609 2.3E-06 0.90 1448 5.6E-06 2.0E-08
' 488d P 2.3E-06 0.90 1448 7.7E-06 W Q 7.7E 1.3E-09 R 3.00 4828 NNW 0.90 1448 *i .7E-06 2.3E-08 W(b) Q 4.11-10 MILK CDW 4.90 7886 2. E-07 W Q 1.00 1609 5.3E-06 8.2E-09 DIE (b) D 3.9E-10 MIIK CEAT 3.30 5311 3.6E-07 E(b) E A 1.00 1609 6.1E-06 1.4E-08 VII2'IAB2 CAR [EN N 3.0E S.8E +
384E B 1 30 2092 C 0.90 1448 6.3E-06 1.2E-06 NE 6.8E-06 1.1E-06 ENE D 0.90 1448 2.30 3541 1.42-07 1.0E-09 2 E 2.30 3541 7.(E-07 1.1E-09 ESE F 2.30 3701 6.2E-07 1.3E-09 st G 4.9E-09 M 1 50 2414 1.7E-06 ' War 5.7E-09 W N 1.10 1770 1.9E-06 0.90 1448 5.6E46 2.0E-08 tSW P 0.90 1448 7.7E-06 2.3E-08 NW Q 1.3E-09 , R 3.00 - 4428 7.7E-06 I8ad
- $150 3.7E-Crf 4.2E-10 E E 3.20 3.6E-10 SEEE CEw 3.50 5633 3.0E-07
#st F 2.8E-10
- G 4.50 7242 1.9E-07 SE 1931 2.7E-06 8 . E-09 wed M 1.20 2.0E-08 0.90 1448 5.6E-06 tSai P 2.3E-08.
0.90 1448 1.7E-06 lef Q 1.3E-06 2.4E-09 R 2.30 3701 38 4# 1he locaticri carrot in
\
] f
- a. Se sits transary in this sector ie lomtml cuer wter.
nmpted crzitiranaly Ear tria life et tra plant.
'u b.1ie ardamin at this locaticri do ruit prtziaan milk for tamari ocristagdai, i
Attachinent 6.2 (l of 1) UNT-005-014 Revision 0 113
/N SITEREl>TEDLIQUIDINGEST[0NDOSECOMMITMENT
/ I
('/ FACTORS (A ) FOR INDIVIDUAL NUCLIDES i Ar.t caCUP3 4DUL1 015CAARGE Pols 1 CitCUL AltkG W182 (into Misst seip6 liver) muCLICE ORGAN Dost Convittlam F4C10a5 Sout Livik 1. BCDT 1kft0!D tibutY LubG GI LLI h3 0.00t+00 2.6M 01 2.66E 01 2.664 01 2.6M 01 2.66E 01 2.6M 01 C 14 3.13E+04 6.2M+03 6.2M 43 6.2M 43 6.2M +03 6.2M+03 6.2M*03 mA 24 4.08t+02 4.08t+02 4.08t 42 4.0aE+02 4.00E +02 4.04t+02 4.08t+02 P 32 4.62t+07 2.87t+06 1.79t+06 0.00t+00 0.00E+00 0.0tE*00 5.19t+06 Ct 51 0.00t+00 0.00t+00 1.2ft+00 7.62f 01 2.818 01 1.69t+00 3.21t+02 mu 54 0.00t+00 4.3C1+03 8.35t+02 0.00t+00 1.30t+03 0.00E+00 1.34t+04 sm 56 0.00E+00 1.10t+02 1.95841 0.00t+C0 1.40E+02 0.00e+00 3.52t+03 FE 55 6.59t+02 4.5M *02 1.06E 42 0.00t+00 0.00t+00 2.54t+02 2.61t+02 Ft 59 1.04t+03' 2.45t+03 9.3M +02 0.00t+00 0.00E 00 6.83t+02 8.15t+03 Co 58 0.00t+00 8.95t+01 2.01t+02 0.00E+00 0.00t+00 0.00E*00 1.81t+03 co 60 0.00t+00 2.57t+02 5.67142 0.00E *00 0.00E+00 6.00t @0 4.83t+03 gV 3.12t+04 2.1M+03 1.05t+03 0.00E+00 0.00E*00 0.00t+00 4.51t+02 al.63 mi 65 1.27t+02 1.64t+01 7.51tt00 0.00t+00 0.006+00 0.00E+00 4.17t+02 CU 64 0.00E +00 1.DCE +01 4.70t+00 0.00t*00 2.52E+01 0.0M +00 8.53f+02 2m 65 2.32t +M 7.37144 3.3M+04 0.00E+00 4.93t+04 0.wt +00 4.64t +M Zu 69 4.9M +01 9.43t+01 6.5M+00 0.00E+00 6.13E+01 0.00E+00 1.422+01 14 83 0.00t+00 0.00t+00 4.06t*01 0.00t+00 0.00E+00 0.00E +00 5.822+M SA + M 0.00E+00 0.00E+00 5.24E+01 0.00E+00 0.00E+00 0.00t+00 4.118 04 ' SR 35 0.00E+00 0.00t+00 '2.15t+00 0.00t 40 0.00t+00 0.00E+00 0.00E+00 al M 0.00E+00 1.01t+05 4.71t44 0.00t+00 0.00r+00 0.00t+00 1.99t +M 36 88 0.00E+00 2.90E42 1.54t+02 0.00E+00 0.00E+00 0.00E +00 4.00E 09 95 89 0.00E +00 1.92E +02 1.3H42 0.00E+00 0.00E+00 0.00E+00 1.121 11 sa.89 2.22E+04 0.00E+00 6.34t42 0.00E+00 0.00E+00 0.00E +00 3.57t+03
-- se 90 5.47t+05 0.00E+00 1.34t+05 0.00t+00 0.00E+00 0.00t+00 1.$at+04 Ee 91 4.09E+02 0.00E*00 1.6H+01 0.00E 40 0.00E+00 0.00t+00 1.95E+03 88 92 1.5H42 0.00t+00 6.71t+00 0.00E+00 0.00E +00 0.00E+00 3.ceE+03 T 90 5.79E 01 0.00E*00 1.55t 02 0.00E 40 0.00t+00 0.00E+00 6.14E+03 T 91m 5.47t 03 0.00t+00 2.12t 04 0.00E+00 0.00E+00 0.00E+00 1.618 02 l
T 91 8.49t+00 0.00E+00 2.271 01 0.0GE+00 0.00E+00 0.00t+00 4.67t+03 Y 92 5.09E.02 0.00E+00 1.49t 03 0.00E+00 0.00E+00 0.00t+00 8.91t+02
. Cawersion f actors are in tritts of erwe/yr per 6Cl/al I
O 1 ( b I l LJ 1 l l l ! UNT-005-014 Revision 0 , Attachment 6.3 (1 of 6) 114
. .- -- . .. --, - - ~ _ _ - ~ . - - - - - ~ . . - _ -
SITE RELATED LIQUID INGESTION DOSE COMMITMENT y FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES 4 Act 08tWP: 400t1 OttCkARGE Polute CitCULATIDG Wattt (int ilssissippi River) muCtipt Okt.Lu Dost Couvtll10N f 4Cical Sout Llytt 1.b3W TNYRCID ElDmET LuhG Gl4LI T.93 1.61E.01 0.00t+00 4.4M .03 0.00t+00 0.00t+00 0.00t*00 5.12f+03 28 95 2.521 01 8.0M.02 5.4M .02 0.00E+00 1.271 01 0.00t+00 2.5M*02 tr 97 1.39t.02 2.811 03 1.288 03 0.00t+00 4.241 03 0.00t+00 8.69t+02 he.95 4.4M +02 2 48t*02 1.34t+02 0.00t+00 2.4M*02 0.00t+00 1.51t+06 MO 99 0.00t+00 1.05t+02 1.99t +01 0.00t+00 2.37t+02 0.00t+00 2.43f 02 i-TC 99M 8.96t 03 2.5M.02 3.2M.01 0.00t+00 3.85441 1.24t.02 1.50t+01 f .- TC.101 e.221 03 1.3M.02 1.30t.01 0.00E+00 2.39E.01 6.79E.03 3.9 % .14 l tu.103 4.50t+00 0.00t 40 1.94t+00 0.00t+00 1.T2t+01 0.00t+00 5.25t+02 tu 105 3.7H .01 0.00t+00 1.48t.01 0.00t+00 4.84t+00 0.00t+00 2.29t+02 RU.106 6.69E 01 0.00t+00 8.44t+00 0.00E 40 1.29E*02 0.00t+00 4.3M +03 4G.110h 8.2M.01 7.6H 01 4.544 01 0.00t+00 1.50E+00 0.00t+00 3.12142 ' ft.125m 2.57t+03 9.30t+02 3.44t42 7.72t+02 1.044 *M 0.00t+00 1.0M +M
.( ................................................................................
75 12718 6.49t+03 2.32t+03 7.90E+02 1.Mt+03 2.63E+M 0.00t+00 2,17t +M 7t.127 1.0M +02 3.78t+01 2.20t+01 7.81t+01 4.29t+02 0.00t+00 8.32t+03 ft.129m ' 1.10E+04 4.112 03 1.74t+03 3.7W +03 4.60t*04 0.00E+00 5.5M +M l 75 129 3.01E+01 1.1M +01 7.33t+00 2.31t+01 1.26t+02 0.00E+00 2.2M+01 ft.131m 1.Mt+03 8.10t+02 6.7M*02
- 28t+03 8.21t+03 0.00t+00 8.0H+04 ft.131 1. set +0i 7. set +00 5.966+00 1.hM+01 8.2M41 0.00t+00 2.67t+00 it.132 2.41t+03 1.5et+03 1.Cl*03 ~ 1.72t+03-1.50t+04 0.00t+00 7.39t+04 3 136 2.74t+01 8.09t+01 3.19t+01 6.ht+03 -1.Nt+02 0.00t*00 6.9M+01 1 131 1.51t*02 2.14t+02 1.244 42 7.00t+04 3.70t+02 0.01d+00 5.70t+01 3 132 7.33+00 1.97t*01 6.85t+00 6. Set *02 3.14t+01 0.00t+00 3.70E+00 3 133 5.15 41 8.96t41 2.73t+01 1.32t+04 1.5et+42 0.00t+00 8.0M+01 l 3.8H+00 1.05t+01_ 3.7C 00 1.81t+02 1.eet+01 0.00E+00 9.115 03 1 134 1 135 1.61t41 4.21t+01 1.5M+01 2.7st+03 6.75t41 0.00t+00 4.7M41 cs 134 2.9et+05 7.09t+05 5.79t+05 0.005 00 2.29t+05 7.61t+04 1.24t+04
- 6. alt +04 9.39E 43 1.40t +04 cs.136 3.12t+04 1.23t+05 8.86t+04 0.00t+00 f ................................................................................
. cs.137 3.82t+05 5.22t+05 3.42t+05 0.00t+00 1.775 05 5.s9t+04 1.01E+04 cs.138 2.64t+02 5.22*+02z 2.Ht+02 0.00t+00 3.84t+02 3.79t+01 2.2M.03 aA.139 9.66t 01 6. Set.04 2.834 02 0.00t+00 6.4M.04 3.90t.04 1.71t+00 Conversion f actors are in udts of area /yr per WCl/el Q
Attachment 6.3 (2 of 6) UNT-005-014 Revision 0 115
, , . -. . - - ~ . - , ~ . - - ~ ~ - . , - -~ . . _ . _ . _ . _ - - . . . - - ~ . -
4 SITE RELATED LIQUID INGESTION DOSE COMMITMENT -r. ( . FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES i Act Gacupi 400L1 Ol5ChAAGE Polkt: CitCLAAlltG Witt Itato mississi@l tiver) uuCLIOE ORCAS Dost CONVitflou fAC1085 tout tivtt 1.00DY INikol0 EIDWtf LUbo Gl.LLI 6A 140 2.02t+02 2.548 01 1.32f+01 0.00t+00 8.638 02 1.45t 01 4.1M +02 SA 141 4.691 01 3.548 04 1.58t 02 0.00t+00 3.P9t M 2.018 M 2.218 10 SA 142 2.125 01 2.10t M 1.3M 02 0.00E+00 1.ME M 1.ZM M 2.99t 19 LA 140 1.518 01 7.59t 02 2.015 02 0.00t+00 0.00t+00 0.00t+00 5.57t+03 LA 142 ~7.711 03 3.518 03 8.73t 04 0.00t+00 0.00t+00 0.00t+00 2.5M *01 CE 141 2.5M 02 1.758 02 1.99t 03 0.00t+00 8.1H 03 0.00t+00 6.71t+01 CE 143 4.571 03 3.3st+00 3.748 M 0.00E+00 1.4M 03 0.00t+00 1.!M +02 CE 144 1.3H+00 5.6M 01 7.2M 02 0.00E+00 3.3H 01 0.00t+00 4.57t+02 Pe 143 5.548 01 2.22t 01 2.7H 02 0.00E+00 1.28t 01 0.00E+00 2.4M+03
~ '
PR 144 1.818 03 7.5M M 9.21E 05 0.00t+00 4.2H-04 0.00t+00 2.618 10
' up 147 3.79t 01 4.3et 01 2.62t 02 0.00t+00 2.568 01- 0.00t+00 2.10t+03 W 187 2.96t+02 2.47t+02 8.6H+01 0,00E+00 0.00t+00 0.00t+00 4.10!+M WP 239 2.00E 02 2.tH U 1.575 m 0.00t+00 8.00E 03 0.00t+00 5.Mt+02 Carwersten f actors are in units of mremryr per gtA4 ne i
p
- }
Attachment 6.3 (3 of 6)
.UNT-005-014 Revision 0
.116
~~.
SITE =RELATEDLIQUIDINGESTIbNDOSEC0MMITHENT . FACTORS (Ag ) FOR. INDIVIDUAL NUCLIDES AGE Gaour: ADup Ol5CnAtr.1 Point ALL 018895 (late 40 Arpent Consh huCLICE ORGAs bott couvitslam F4C10R$ tout LIVit 1.DCrit 7812010 E10st? LUNG Ol L'LI n3 0.00t*00 8.96t+00 8.9M *00 8.9M*00 8.9M *00 8.9M 00 2.9M+00 C 14 3.15t44 6.30t+03 6.30t+03 6.30t+03 6.30t+03 6.30t+03 6.30t+03 mA 24 5.44t+02 5.4N+02 5.4a442 5.48842 5.44t*02 5.44t+02 S C02 1 P 32 4.62t+07 2.87t+06 1.79t+06 0.00t+00 0.00t+00 0.00t+00 5.20E+06 CA 51 0.00t+00 0.00t+00 1.49t+00 4.94 01 3.29t 01 1.9st+00 3.7M+02 les 54 'O.00t+00.4.7M+03 9.00t+02 0.00t+00 1.42t+03 0.00E+00 1.46t+04 1su 56 0.00t+00 1.20E42 2.12E+01 0.00t 40 1.52t 42 0.00t+00 3.82t+03 ft 55 8.87t+02 6.1M+02 1.4M42 0.00t 40 0.00t+00 3.42t+02 3.52t+02 ft 59 1.40t*03 3.29E43 1.2M+03 0.00: 4 0 0.00E+00 9.19t 42 1.10t+04 CD SS 0.00t+00 1.51842 3.39t+02 0.00E+00 0.00: 4 0 0.00t+00 3.0M43 l ' to-60 0.00t+00 4.34t+02 9.5aE+02 0.00E40 0.00E+00 0.00t+00 8.1M+03 al 63 4.19t+04 2.91t+03 1.41t+03 0.00E*00 0.00t+00 0.00t+00 6.07t+02 ul 65 -1.70t+02 2.21t+01 1.01: 4 1 0.00t+00-0.00t+00 0.00E+00 5.61t+02 CU H 0.00t+00 1.Ht41 7.9M +00 0.00E+00 4.24441 0.00t+00 1.44t+03 tu 65 2.368 04 7.50E+04 3.3eE*04 0.00E+00 5.02t+04 0.00t+00 4.73t44 28 69 5.02E41 9.60t+01 6.67t+00 0.00e+00 6.24t+01 0.00E+00 1.44441 M E5 0.00t+00 0.00E*00 4.30E+01 0.00t+00 0.00t+00 0.00E+00 6.30E41 te 54 0.00E+00 0.00E+00 5.67t41 0.00t+00 0.00t+00 0.00E +00 4.45t.04 en 05 0.00E+00 0.00E+00 2.33E*00 0.00t+00 0.00E +00 0.00E+00 0.00E+00 as te 0.00t+00 1.03t+05 4.79E+44 0.00E+00 0.00E+00 0.00t+00 2.05td Re IB 0.00t+00 2.95t+02 1.54t+02 0.00t+00 0.00t+00 0.00t+00 4.075 09 es M - 0.00E+00 1.9M+02 1.37t+02 0.00E+00 0.00E+00 0.00E+00 1.1M 11 et 09 4.7BE+04 0.00E*00 1.371+03 0.00E+00 0.00E+00 0.00t+00 7.64443
-3R 90. 1.18E+06 0.00E+00 2. tee +05 0.00E*00 0.00t+00 0.00E+00 3.40E+04 l 8.79E+02 0.00E+00 3.55841 0.00E+00 = 0.00e+00 0.00t+00 4.194+03 St.91 l
SR42 3.33t+02. 0.00E+00 1.44E+01 0.00t+00 0.000+00' O.00t+00 6.60E+03 l-l T.90 1.3aE+00 0.00t+00 3.685 02 0.00t+00 0.00E+00 0.lwe+00 1.468+04 T 91N 1.30E 02 0.00E+00 5.04E 04 0.00E+00 0.00E+00 0.00E+00 3.82E 02 T41 2.02t+01 0.30E+00 5.30E-01 0.00E+00 0.00E+00 0.00E+00- 1.11t+04 j
.T 92 1.21t 01 0.00t+00 3.5M 03 0.00E+00 0.00t+00 0.00E+00 2.12f+03 i, ................................................................................
I comersion f actors are in mits et aren/yr per nCl/st I t Tg-UNT-005-014 -Revision 0 Attachment 6.3 (4 of 6) 117
SITE RELATED LIQUID INGESTIOh DOSE COMMITMENT O -Q . FACTORS (Ag ) FOR INDIVIDUAL NUCLIDES AGE GROUP: ADULT 015CMARCA Polut e ALL 01NER5 (into 40 Arpent Canal) NJCL10t ORGAh Dost ComVtt$10N f 4Cf 0R$ BONE LIVtt 1.$Cet tuYt010 E10NEY LUhG GI LLI 4 f 93 3.83t*01 0.00t 40 1.0M 02 0.00t+00 0.00t+00 0.00E+00 1.22t+04 2a 95 - 2.771 00 6.8M 01 6.014 01 0.00t+00 1.39t+00 0.00t+00 2.82t+03 20*97 1.538 01 3.09t 02 1.41t 02 0.00t+00 4.671 02 0.00t+00 9.57t+03
................................................................................ ~
ut 95 4.47t*02 2.49t+02 1.34f+02 0.00t+00 2.4M42 0.00t+00 1.51t+06 80 99 0.00t+00 4.62t+02 8.79t +01 0.00t+00 1.05t+03 0.00t+00 1.07t+03 TC 99u 2.94E 02 8.32E 02 1.0M
- 00 0.00t+00 1.2M +00 4.071 02 4,92t+01 TC.101 3.0M 02 4.3M 02 4.2st 01 0.00E+00 7.858 01 2.2M 02 1.318 13
. 80 103 1.90E4) 0.00E+00 ' 8.54t+00 0.00E+00 7.5M+01 0.00t+00 2.31t+03 RU 105 1.65t*00' O.00E+00 6.52E 01 0.00E*00 2.1M+01 0.00t+00 1.01t*03 nu 106 2.9M+02,0.00E+00 3.7M+01 0.00t+00 5.69f 42 0.00E+00 1.91844 3
A4 110M 1.41t41 1.30E+01 7.74E+0n 0.00t+00 2.5M +01- 0.00E+00 5.32E 03 TE 125M 2.79E 43 1.01t+03 3.74E+02 8.39 42 1.1M +04 0.00E+00 1.11t+04 ft.127M 7.0M +03 2.52E+03 8.59E42 1.00E+03 2.8M44 0.00E+00 2.3M+04 . TI 12T 1.14E +02 4.11E+01 2.48t+01 8.4aE41 4.6M *02 0.00E+00 9.CM+03 ft 1294 1.20E+E 4.47t43 1.09(+03 4.11E*03 5.00t+M 0.00t+00 6.03E+04 ff.129 3.2M+01 1.23E+01 7.9M+00 2.51E+01 1.37E42 0.00E +00 2.4M41 TE 131m 1.80E+03 8.81E+02 7.34E+02 1.39E+03 8.92E+03 0.00E*00 8.74E+04 ft 131 ' 2.0M+01 8.5M+00 6.4M+00 1.ME+01 8.9eE+01 0.00E+00 2.90E+00 . ft.132 2.62E+03 1.70E+03 1,59E+03,1.87t+03 1.63E+04 0.00E +00 8.02E44 1 130 - 9.01E+01 2.66E+02 1.0M+02 2.25E*04 4.1M +02 0.00t+00 2.29E*02
-1 131 4 tM +02 7.09E+02 4.0M *02 2.32E+05 1.22E+03 0.00t+00 1.87E+02 1 132 2. W +01 6.47E+01 2.2ed*01 2.26E+03 1.0M+02 0.00E 40 -1.22E+01 1 133 1.69E+02 2.94E+02 8.9M41 4.32E*04 5.13E+02 0.00E+00 2.64442 1 134 1.2M*01 3.43E41 1.2M+01 5.94E+02 5.46E 4 1 0.00E40 2.99E 02 1 135 5.2AE+01 1.3st+02 5.10E+01 9.11E+03 2.22E+02 0.00E+00 1.56E+02 Cs 134 3.03E+05 7.21E+05 5.99E+05 0.00E+00 2.3M *05 7.75E +04 1.2M +04 C3 134 3.17E+04 1.25E+05 9.01E+04 0.00E+00 4.9M44 9.5M+03 1.42E+04 Cs 137 3.seE45 5.31E+05 3,4aE+05 0.00E+00 1.a0E+05 5.99E*04 1.0M+04 08 138 2.6*E+02 5.31E+02 2.63E +02 0.00E+00 3.90E 42 3.85E+01 2.27E.03 BA 139 9.00E+00 6.418 03 2.64E 01 0.00E 40 5.99E 05 3.64E 03 1.60E+01 Cawersion f actors are in units of eram/yr per 441/st A
f \ V Attachment 6.3 (5 of 6) UNT-005-014 Revision 0 118
._...m ..._...__m___._..._ . . ~ -_~._-....-_~___m._._.._.~....._.__m_..m_m__-_.~___
l
+
SITE RELATED LIQUID INGESTION DOSE C0!011THENT TACTORS (Ag ) FOR INDIVIDUAL NUCLIDES AGE GaCUPI 400L1 OttcuAaGE Poluts Att 01ptal tints 40 Arpmt Corell mutt 01 DeGaa DOLI Cumvtallum f AC10at 2 tout Livtt 1.60DY tuYa010 EIDett tuuG GI tLI SA 140 1.tet+03 2.37t+00 1.23t+02 0.00t+00 8.058 01 1.35t+00 3.88t+03 BA 141 4.3M +00 3.30E 03 1.4at 01 0.00t+00 3.07t 03 1'.471 03 2.064 09 6A 142 1.90E+00 2.031 03 1.244 01 0.00t+00 1.72t 03 1.1M 03 2.754 18 LA 140 3.58t 01 1.808 01 4.76E 02 0.00t+00 0.00t+00 0.00t+00 1.32t+04 L4 142 1.8M 02 8.338 03 2.07t 03 0.00t+00 0.00t+00 0.00t*00 6.0at+01 CE*141 8.018 01 5 62t 01 6.151 02 0.00t+00 2.521 01 0.00E+00 2.07t+03 CE 143 1.415 01 1.04t+02 1.164 02 0.00t+00 4.60t*02 0.00E+00 3.90t+03 CE*144 4.18t+01. 1.75t+01 2.24t+00 0.00t*00 1.04t*01 0.00t+00 1.41t+04 pt 143 1.32t*00 5.2st 01 6.52t 02 0.00t+00 3.051 01 0.00t+00 5.77t +03 PR 144 .4.315 03 1.79t 03 2.195 04 0.00E+00 1.01t 03 0.00t+00 6.19t 10 80 147 - 9.006 01 1.04t+00 6.22t 02 0.00t+00 6.00t 01 0.00t+00 4.99t+03
*187 3.04t+02 2.55t+02 8.90t+01 0.00t+00 0.00t+00 0.00t+00 8.34t+04
..............+.................................................................
' MP 239 1.20tt01 1.258 02 6.918 03 0.00E+00 3.91t 02 0.00E+00 2.57t+03 C = reten vecier er. in unit et erevyr 0.c utif t 7 .
N
+
Attachment 6.3:(6-of 6)- UNT-005-014_ Revision 0 119.-
. a . - -
; . . . - .- . - - ,- - ~_ -.
.~ -- - . - . - - . - -.- - .. - - .- -.-
i DOSE FACTORS FOR EXPOSURE TO A SEMI-INFINITE CLOUD OF NOBLE CASES
~
. ,Q V .
p-Skin **(Lg ) Y-Air * (Hg ) y-Body **(Kg ) Nuclide S-air *(Nj ) 2.88E-04 --- 1.93E-05 7.56E-08 Kr-83m 1.97E-03 1.46E-03 1.23E-03 1.17E-03 Kr-85m 1.95E-03 1.34E-03 1.72E-05 1.61E-05 Kr-85 Kr-87 1.03E-02 9.73E-03 6.17E-03 5.92E-03 2.93E-03 2.37E-03 1.52E-02 1.47E-02 Kr-88 Kr-89 1.06E-02 1.01E-02 1.73E-02 1.66E-02 7.83E-03 7.29E-03 1.63E-02 1.56E-02 Kr-90 Xe-131m 1.11E-03 4.76E-04 1.56E-04 9.15E-05 Xe-133m 1.48E-03 9.94E-04 3.27E-04 2.51E-04 Xe-133' 1.05E-03 3.06E-04 3.53E-04 2.94E-04 Xe-135m 7.39E-04 7.11E-04 3.36E-03 3.12E-03 O 'Xe-135 2.46E-03 1.86E-03 1.92E-03 1.81E-03 l-O Xe-137 1.27E-02 1.22E-02 1.51E-03 1.42E-03 Xe-138 4.75E-03 . 4.13E-03 9.21E-03 8.83E-03 Ar-41 3.28E-03 2.69E-03 9.30E-03 8.84E-03
- 3 mrad-m pCi-yr.
** 3 arem-m ,
PCi-yr
' Extracted from Table B-1 of Regulatory Guide 1.109, Revision 1, 1977 UNT-005-014 Revision 0 Attachment'6.4 (1 of 1) v 120
IN11ALATION PATINAY DOSES DUE TO RADIONUCL1 DES OTHER THAN N011LE GASES, Ri V 401 Gaour 6put1 ( 1 Of 3 ) arJCt3DI ORG4h 005! CCmVltiloh FAC10R$ 50W1 LIYtt 1.3001 1strol0 titutt tumG GI tt! W.3 0.00t+00 1.2M*03 1.2M+03 1.26t+03 1.26t+03 1.2M*03 1.2M+03 C 14 1.82t +k 3.41t+03 3.41t*03 3.41t+03 3.41t*03 3.41t*03 3.41t*03 mA 24 1.028 04 1.02t*04 1.02t*04 1.02t
- 1 02t
- 1.02t
- 1.02t+04 P.32 1.32f+06 7.71t+04 5.01t+04 0.00t*00 0.00t+00 0.00t+00 8.ut+04 -
Cs 51 0.00t+00 0.00t*00 1.00t*02 1.95t*01 2.2eE+01 1.44t+04 3.32t+03 nu de 0.00E*00 3.%E M 6.30t*03 0.00t+00 9.kt+03 1.40t+06 7.74t+04 e 56 0.00t+00 1.24t+00 1. UE 01 0.00t*00 1.30t+00 9.44t+03 2.02t*04 ff 55 2.4M +04 1.70t+04 3.ht+03 0.00E+00 0.00E+00 7.21t+04 6.01t+03 ft 59 1.10t*04 2.70t+04 1.0M *04 0.00E*00 0.00t+00 1.02t+06 1,84E+05 Co 58 0.00t+00, 1.5N+03 s.07t+03 0.00t+00 0.00t*c0 9.2N+05 1.0M +05 C0 60 0.00f.+00. 1.15t+04 1.48t+04 0.00E+00 0.00t+00 5.97t+06 2.05f +05 88 63 4.325 05 3.14t *M 1.45t
- 0.00t*00 0.00t+00 1.78t+05 1.34t+04
( b ................................................................................ al.65 1.54t+00 2.10E 01 9.1M 02 0.00E+00 0,00E+00 5.60t*03 1.234
- CU M 0.00t+00 1.4M+00 6.158 0*1 0.00E*00 4.62E+00 4.70t+03 4.90t * .
2a.65 3.24t+04 1.0M +05 4.6et
- 0.00t+00 6.90t+04 8.Et*05 5.34t
- 2n 69 3.468 02 6.11t 02 4.528 03 0.00t+00 4.22E 02 9.20E+02 1.63t+01' 98 83 0.00E+00 0.00t+00 2.41t+02 0.00E*00 0.00E +00 0.00t+00 2.32t+02 se 84 0.00E+00 0.00E+00 3.13t+02 0.00t+00 0.00t+00 0.00t+00 1.EE 03 9A 85 0.00E+00 0.00t+00 1.2m+01 0.00t*00 0.00E+00 0.00E+00 0.00t+00
, 30 86 0.00E+00 '1.3M +05 5.90E*04 0.00t+00 0.00E+00 0.00t+00 1.66t+06 R8 88 0.00t+00 3.87t*02 1.914+02 0.00t+00.0.00E+00 3.00t*00 3.344 M
* .................................,...+...........................................
Re se 0.00t+00 2.54t+02 1.70t+02 0.00E+00 0.00E+00 0.00E+00 9.20E.12
- 88 89 . 3.kt+05 0.00f+00 8.7N+03 0.00t+00 0.005*00 1.40E+06 3.50t*05 sa.90 9.NE+07 0.00t+00- 6.10t+46 0.00E+00 0.00E+00 9.60E+06 7.22E+05 34*91 6.19t+01 0.00E+00 2.50t+00 0.00t+00 0.00E+00 3.65t+04 1.91t+05 se 92 6.74E+00 0.00E+00 2.91E 01 0.00E+00 0.00t+00 1.65t+M 4.3M4 Y 90 2.09t+03 0.00t+00.5.61t+01 0.00E+00 0.00t+00 1.70t+05 5.0M+05 l_
! 7 91m 2.618 01 0.00E+00 1.02E 02 0.00E+00 0.00E+00 1.92E+03 1.3M+00 T 91 4.62t+05 0.00E+00 1.24t+04 0.00t+00 0.00t+00 1.70E+06 3.8H+05 f T.92 1.03E+01 0.00E+00 3.02t 01.0.00t+00 0.00E+00 1.575+M 7.3H+04 Carmreten f actors are in mits of eren/yr per ucl/cels seter. m l [a\ Attachment 6.5 (1 of 12) UNT-005-014 Revision 0 121
INHALATION PATINAY DOSES DUE TO p RADIONUCLIDES OTHER THAN NOBLE CASES, R i< y 4Gt ca p : adult i 2 or 3 ) muCLIDE CRGAs Dost COWill10m f 4t1085 f#ft010 ElDat? Lt*G Gl*LLI SONE LIVit 1.tCEV t.03 9.44t+01 0.00t+00 2.61t+0C 0.00t+00 0.0M*00 4.8H +04 4.22t+05 2a.95 1.07t+05 3.44t+04 2.3M+M 0.00t+00 5.42t+04 1.77t+06 t.50t+05 2e.97 9.64t+01 1.9M +01 9.04t+00 0.00t+00. 2.97t41 7.4M+04 5.23t+05 ma 95 1,41t+04 7.82143 4.21t*03 0.00t+00 7.74143 5.05t*05 1.04t + 05 mo.99 0.00t+00 1.21t+02 2.30t+01 0.00t+00 2.91142 9.12t+04 2.4M+05 ft 994 1.0M 03 2.918 03 3.70t.02 ...."0.00f*00 n o u n.4.426
" n o 02o "7.64t*02
" " " " " 4.1M43
............................u
...........u TC.101 4.1M .05 6.021 05 5.90t.04 0.00t*00 1.0M*03 3 M *02 1.0M.11 au.103 1.53t+03 0.00t+00 6. Sat +02 0.00t+00 5.n3t+03 5.05t+05 1.10t 45 av.105 7.90t*01 0.00t+00 3.111 01 0.00t*00 1.02t+00 1.10t+04 4.821*04 3u.106 6.91t+04 0.00t+00 8.77t+03 0.00t+00 1.34t +05 9.3M+06 9.12t+05 4c.11m 1.00t+04 1.00t44 5.Mt+03 0.00E+00 1.9M3.14t45 +04 4.6M+06 7.0M+M 3.02t+05 ft.125m 3.42t+03 1.5aE+03 4.67t+02 1.05t+03 1.24t *M
( .............................................................*.......*...*....*.
- 4. Sat +M 9.60t+05 1.50t+05 it.127W 1.2M+M 5.TM+03 1.5M43 3.29:43 ft 127 1.40E+00 6.428 01 3.10t.01 1.06t+00 5.10t+00 6.51t43 5.74t+04
( 1. Set +03 3.44t+03 3.6M+04 1.1M +06 3.43f+05 ' tt.129M 9.7M+03 4.6M +03
........................................+.................... ............*.. **
- ft.129 - 4.9et.02 2.39t.02 1.24t 02 3.90s.02 1.8M.01 1.Mt+03 1.57t+02 ft.131m 4.99t +01 4.3M+01 2.90541 5.50t41 3.M 42 1.46t45 5.5M+05 ft.131 1.118 02 5.958 03 3.5M 03 9.36t.03 4.37t M 1.3M +03 1.8M+01 -
78 132 . 2.60E42 2.15t+02 1.62t42 1.90E+02 1.4et+03 2. set +05 5.10E45 f 4.5N45 1.34t+44 5.18t+03 1.14t+46 2.0eE+04 0.00E+00 - 7.69643 1 130 i*131 2 M+44 3.5GE+44 2.05t+04 1.19E47 6.1M+04 1.00E40 6.20t43 I.132 1.1M+03 3.3M43 1.1M +03 1.1M e05 5.tets c.0M+00 8. set 43 4.0M+02
- l*133 8. eat +03 1.4aE+04 4.5M+03 2.15t+06 2.5eE+04 0.00E+00 1
1 134 6.44E42 1.73E+03 6.15t+02 2. tee +04 2.75t+03 0.00E+00 1.01t+00
.......................o ...................................+...................
f' 8 135 2.64t+03 6.90E+03 2.5M+03 4.44t+05 1.11t+04 0.000+00 5.258 43 Cs.134 3.7M+05 8.4at45 7.288 45 0,00t+00 2.00E+05.9.76t+04 1.04t+04 Cs.136 3.90t+04 1.4M *05 1.10E+05 0.00E+00 8.5M+04 1.20t+44 - 1.1M+04 I Cs.137 4.78t+05 6.21t*05 4.20t*05 0.00E*00 2.22E+05 7.5M +04 8.40E+03 C5 138 3.31t+02 6.21842 3.24t+02 0.00t*00 4.00E+02 4.tM41 1.8M.03 f 54 139 9.3M 01 6.6M 04- 2.74E 02 0.00t+00 6.225.M 3.7M43 8.96442 Corwersten factors are in mits of arsWyr per dl/ciele meter. A
- tj Attachment 6.5 (2 of 12)
UNT-005-014 Revision 0 122
~ -- =
2 ' IN11A1.AT10N PATINAY DOSES DUE TO 0 RADIONUCLIDES OTHER THAN NOBLE GASES, R 3 I AGE GRCUPi 40utt ( 3 08 3 )
)
' mucL10t a san 00st Ca nesson #4C+oas tout Llvtt 1.M)1 INTRO 10 EIDetf LUE0 01 LLI sa.140 3.90t+04 4.90t+01 2.57t+03 0.00t+00 1.671*01 1.24 +M 2.18t*05
$A.141 1.00E 01 7.534 05 3.3M 03 0.00t+00 7.00t 05 1.94t+03 1.1M.07 SA*i42 2.634 02 2.70t*05 1.NE 03 0,00t+00 2.29t 05 1.19t
- 03 1.771 16 LA 140 3.44t+02 1.741+02 4.$at+01 0.00t*00 0.00t+00 1.3M 05 4.50t*05 LA 142 6.tM
- 01 3.10s.01 7.72t 02 0.00t+00 0.00t*00 6.33t 03 2.11t+03 CI 141 1.99t+M 1.35t+04 1.5M+03 0.00t+00 6.2M *03- 1.62t+05 1.20E+05
- Ct.143 1.tM+02 1.38t+02 1.53t+01 0.00t+00 6.00t+01 7.9et+04 2.2M+05 Cla144 3.4M +M 1.4M+M 1.84t+M 0,00t*00 8.40t*05-7.7st+06 8.1M +05 Po 143 9.3M*03 3.75t+03 4.Mt+02 0.00t+00 2.1M +03 2.ttt+05 2.00t+05
_ Pt 144 3.015 02 1.254 02 1.5M 03 0.00t+00 7.05t 03 1.02t+03 2.158 08 i- e*147 5.27t+03- 6.10t+03 3.658 02 0.00t+00 3.5M +03 2.21t+05 1.7M*05 W 187 8.48t+00 7.00E+00 2.48t*00 0.00E*00 0.00t+00 2.90t+04 1.15t+05 WP 239 : 2.30t+02 2.2M+01 1.24t+01 0.00t+00 7.00E+01 3.* M +W 1.19t*05
- C =reien 't.cs.c. er. in mite et w /yr per u:t/cate ter.
\
J: Attachment 6.5 (3 of 12)
~ UNT-005-014 Revision 0_
123
INHALATION PATINAY DOSES DUE TO RADIONUCLIDES OTHER TRAN NOBLE GASES Rg 4GE Gampi tEtt ( 1 et 3 ) huCL10E ORGAs post conviettom f actors towE L IVE R 1. E42Y tuYE010 E10sti LLMG 01 LLI 4 e3 0.00E+00 1.2M 43 1.2 t+03 1.2 M *03 1.2M43 1.2 M +03 1.27t+03 C 14 2.60E 4 4.87t+03 4.871*03 4.7 M +03 4.87t+03 4.87t+03 4.87t+03 ma.24 1.344
- 1.3ad *M 1.3 ate 1.+JE+04 1.3aE +04 1.36E+04 1.364+04 P.32 1.89E+06 1.10E*05 7.164 +M 0.00E+00 0.00E+00 0.00E +00 9.20E *M Ca 51 0.00E +00 0.00E+00 1.35t+02 7,50E 41 3.07t 41 2.10E*04 3.00E43 mm 54 0.00E+00 5.11t+04 8.40E43 0.00E+00 1.27t+04 1.90E+06 6.6eE+04 NN 56 0.00E+00 1.70E+00 2.52E 01 0.00E+00 1.79E+00 1.52E+04 5.74t+04 FE 55 3.34t
- 2.3aE +04 5.54t*03 0.00E+00 . 0.00E+00 1.24t+05 6.39E+03 FE 59 1.59E 41 3.70E+04 1.4M+04 0.00E +00 0.00E+00 1.53t+06 1.78E 45
/ \ to 58 0.00E+00 2.07t+03 2.7BE+03 0.00E +00 0.00E+00 1.34t+06 9.52144
.k CD-60 al 63 0.00E+00 1.51844 1.9eE+04 0.00E*00 0.00E +00 8.72E 46 2.59E+05 5.00E+05 4.34t+04 1.fe2+04 0.00E+00 0.00E+00 3.07E45 1.42E*04 Wi 65 2.18E40 2.9M 01 1.27E 01 0.00E*00 ,0,00E+00 9.36t+03 3.67E44 CU-64 0.00E+00 2.03t+00 S.48E 01 0.00E+00 6.41t+00 1.11E+04 6.14E+04 2m 65 3.464+04 1.34t+05 6.24t+04 0.00E+00 8.64t+04 1.24t+06 4.664+04 tu 69 4. M 02 9.20E 02 6.46t @ 0.00E+00 6.02E 02 1.55+05 2.85t+02 ea43 0.00E+00 0.00E +00 3.44t+02 0.00E+00 0.00E40 0.00E *00 0.00E*00 BA 44 0.00E+00 0.00E+00 4.33E+02 ' O.00E+00 0.00E+00 0.00E +00 0.00E+00 9a 85 0.00E+00 0.00E+00 1.83E*01 0.00E+00 0.00E +00 0.00E *00 0.00E+00 Re 86 0.00E+00 1.90E+05 8.40E+04 0.00E*c0 0.00E+00 0.00E+00 1.7M+04 as 88 0.00E+00 5.468+02 2.7M+02 0.00E*00- 0.00E 40 0.00E+00 2.92E.05
, at 09 0.00E 40 3.52E42 2.33E42 0.00E+00 0.00E+00 0.00E+00 3.3at 07 se 89 4.34E+05 0.00E+00 1.2H+06 0.00E+00 0.00E.00 2.42E +06 3.71E+05 sa 90 1.00E*08 0.00E+00 6.6eE+06 0.00E+00. 0.00E+00 1.6M*07 7.65t+05 sa 91 4.80E+01 0.00E+00 3.51E+00 0.00E*00 0.00E+00 6.07E*04 2.59E+05 9a 92 9.52E+00 0.00E+00 4.06E 01 0.00E+00 0.00E +00 2.74844 1.19E 45 T=90 2.90E+03 0.00E+00 8.00E41 0.00E*00 0.00E+00 2.9M45 5.59E45 Y 91N 3.70E 41 0.00E+00 1.42E 02 0.00E+00 0.00E +00 1.20E+c3 3.02E 11 T 91 6.61E45 0.00E+00 1.TTE+04 0.00E +00 0.lWE*00 2.94E46 4.09E+05 T 92 1.47t+01 0.00E+00 4.29E 01 0.00E+00 0.00E+00 2.68E+04 1.65t+05 -
. [N Carwersion f actere are in wilts of aren/yr per 448/cnLic aster.
\' ..
Attachment-6.5 (4 of 12) l UNT-005-014 _ Revision 0 l' 124
_ __ - . . __ _ _ - ~ - _ _ _ _ _ _ . _ . _ __ _ . _ _ _ . - _ INHALATION PATINAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES Ri. AGE Camps fits ( 2 pp 3 ) eutLIDI ceG4a 0051 CONVttiICm 8at1on& 1.taDY latecto tibett tuhG Gt.Ltl tout Livtt 5.Mt+05 7 93 1.35t+02 0.00E+00 3.72t+00 0.00t+00 0.00t+00 B.32E .E 2s.95 1.44t+05 4.54t+04 3.15t +M 0.00t.00 6.748 04 2.69t+06 1.49t+05 2a.97 1.3af+02 2.72t+01 1.26t+01 0.00t+00 4.12t+01 1.30E+05 6.30t+05 es.95 1.tu +04 1.03t+04 5.6M+03 0.00t+00 1.00t+M 7.51t+05 9.68t+04 mo 99 0.00t+00 1.69t+02 3.12t41 0.00t+00 4.11t+02 1.54E+05 2.69t+05 TC.99u 1.30E 03 3.ht.03 4.99t.02 0.00t 40 5.76t.02 1.1H +C3 6.13t+03 TC.101 5.921 05 8. m *05 8.248 04 0.00t+00 1.525 03 6.67t+02 8.7M.07 av.103 2.10E+03 0.00E+4 4.9M*02 0.00t+00 7.43E+03 7.83E+05 1.09t+05 kW.105 1.12t+00 0.00E+00 4.344 01 0.00E+00 1.41t+00 1.82t+04 9.04t+04 2u.106 9.kt+04 0.00E+00 1.24t+04 0.00t+00 1.90E+05 1.61t+07 9.60t+05 44 11th 1.3M+04 1.31t+M 7.99t+03 0.00E+00- 2.50E+ M 6.75f 4 2.73t+05 it.125as 4.CaE+03 2.24E+03 6.m+02 1.40E *03 0.00t 40 5.3M+05 7.5M+04 ft.127M 1.80t +M t.1M+03 1.70t+03 4.3at+03 6.54t+M 1.6M+M 1.5M+05 78 127 '2.01t+00 9.12E.01 4.42E.01 1.42E +00 7.20t+00 1.12E+04 8.0eE+04 ft.1294 1.39E+04 6.SeE+03 2.25t+03 4.laE+03 5.1M+04 1.tet +M 4.0H +05
- 1. m +03 TI 129 7.10t.02 3.3af.02 1,7M.02 5.1N.02 2.Mt.01 3.30E*03
,71 1314 9.ME+01 6.01841 4.02E+01 7.2H+01 4.3M+02 2.3aE+05 6.21t+05 TD131 1.5aE.02 8.32E.03 5.ME 03 1.24t.02 6.10E.02 2.34t+03 1.51t41 TE.132 3.60t+02 2.90E*02 2.1M+02 2.444*02 1.95t+03 4.4M+05 4.63E+05
.. 1 130 6.24t+03 1.79E*04 7.17t+03 1.4M +46 2.7M+04 0.00E+00 9.12t+03
- 0. tee +00 6.4M+03 1 131 3.54t+04 4 tie +04 2.Me+04 1.4aE+07 S.40E*04 ,
1 132 1.59E+03 4.30t+03 1.5aE+03:1.51t+05 6.ME+03 0.00E+00 1.27E*03 f.133 1.22E+04 2.05t+04 6.22E+03. 2.93E+06 3.HE+M 0.00E*00 1.03E+04 1 134 8. set +02 2.32E+03 4.40e42 .3.95e+04 3.Me+03 0 Oet+00 2.04E*01- ; I.135 3.70E+03 9.44t+03 3.49t+03 6.21g+05 1.4M+04 0.00E+00 6.9H+03 . Cs.134 5.02E+05 -1.13E+M 5.4M+05 0.OoE+00 3.7M+05 1.4M+05 9.76t+03 Cs.136 5.15t+04 1.Mt +05 1.37t+05 0.Det+00 1.10E+05 1.7st+04 1.09t+04 . CS 137~ 6.70E+05. 8.48E+05 3.11t+05 0.00E+00 3.044+05 1.21E+05 8.4aE+03
.Cs.138 4.M4+02 8.54E+02 4.4M42 0.00E+00 6.62E+02 7.87t+01 2.7eE.01
..t-SA.139- 't.34E+00 9.444 04 3.90E.02 0.0eE+00 4. set.04 6.4M+03 6.4H+03 Comersian f actors are in units of eren/yr per utt/cela ester,
-? -
l i AtCachment 6.5 (5 of'12)_
.UNT-005-014 Revision 0 I l
125 ._ j
. ,. _ _ . . _ - - ~ _ . _ .
INHALATION PATHWAY DOSES DUE TO (
' RADIONUCLIDES OTHER THAN NOBLE GASES, R 1
**.E GaQuer lite t 3 00 3 )
uuCLIDE ORGAN 0058 Cm vit$1 m FAtt0R$ 5 Gl;tti boot LIVtt 1.amt tutt010 ElDatt Lums SA 140 5.47t +k 6.70t+01 3.52t+03 0.00t+00 2.2N +01 2.0M *06 2.29t+05 BA 141 1.428 01 1.0M E 4.744 03 0.00t+00 9. set 05 3.29t+03 7.4M 04
. SA 142 3.706 02 3.706 05 2.271 03 0.00t+00 -3.144 05 1.91t*03 4.79t 10 LA 140 4.79t+02 2.3M +02 6.2M+01 0.00E+00 0.00t+00 2.1+t+05 4.471+05 4 LA 142 9.606 01 4.254 01 1.064 01 0.00t+00 0.00E+00 1.02t+04 1.20t+04 Ct 141 2.84t+04 1.90t+k 2.17t+03 0.00E+00 8.ast+03 6.144+05 1.2M
- 05 Ci 143 2.66t+02 1.94E+02 2.1M+01 0.00t+00 8.64t+01 1.30t+05 2.55t+05 CE 144 .4.89t+06 2.02t+06 2.62t+05 0.00f.00 1.21t+06 1.34t+07 8.64t+05
- N 143 1.34t+04 5.31t+03 6.62t+02- 0.00t+00 3.09t+03 4.8M+05 2.14t+05 Pe *144 - 4.30E 02 1.7M 02.2.18t 01 0.00t+00 1.01t 02 1.75t+03 2.354 04 mD*147 7.86t+03 8.56t+03. 5.13t+02 0.00t+00 5.02t+03 3.72t+05 1.825 05 W 187- 1.20t+01 9.7M +00 3.4M +00 0.00t+00 0.00t+00 4.74t+04 ' 1.77t+05 WP 239 3.30t+02 3.19E*01 1.77t*01. 0.00t+00 1.00t+02 6.49t+04 1.32t+05 Conversion f actors are in mits of area /yr per dt/ celt ester.
4 2 5, Attachment 6.5 (6 of'12) UNT-005-014 Revision'0 126
I 4 l
- INHALATION PATWAY DOSES DUE TO i
( RADIONUCLIDES OTHER THAN NOBLE GASES, R g C AGt 08:UPt CNILO ( 1 Of 3 ) mutt:08 was post ConvitstDh fAC10Pt tuYR010 E10 MET tukG Gl*Ltl East Livte 1. S@ Y M3 0.00t+00 1.12t+03 1.12i+03 1.12t+03 1.12: 4 3 1.12t+03 1.12t+03 C 14 3.5M +M 6.73t+03 6.73t+03 6.Dt+03 4.73t+03 6.73t,+03 6.73t+03 mA 24 1.61E *M 1.61t+04 1.61t+04 1.61t+04 1.61t+04 1.61t+04 1.61t+04
.................... .....................................................*.*.a.
P 32 2.60t+06 1.14t+05 9.68t+04 0.00t+00 0.00t+00 0.00t+00 4.22t+04 , 1.08t+03 ca.51 0.00t+00 0.00t+00 1.54t+02 8.55E+01 2.43t+01 1.70E +M un 54 0.00t+00 4.29t+04 9.51t+03 0.00t+00 1.00t+04 1.58t
- M 2.29t+M
......................................................................+ **....*.
me.56 0.00E+00 1.66t+00 3.12t.01 0.00E+00 1.67t+00 1.31t+04 1.Z38 05 78 55 4.74t+04 2.52t+M 7.77t+03 0.00t+00 0.00t+00 1.11t+05 2.67t+03 88 59 2.07t +04 3.34t *M 1.67t+M 0.00t+00 0.00t+00 1.27t+06 7.0M +M CD 58 0.00E+00 1.77t+03 3.1N+03 0.00t+00 0.00t+00 1.111 06 3.44t+04 CD 60 0.00t+00 1.31t+M 2.26t +M 0.00t+00 0.00t+00 7.07t*06 w &2t+04 O bl.63 4.21E+05 4.63E+04 2.80t+04 0.00E+00 0.00E+00 2.75t+05 6.33t+u3
!' ..................................... ~........ " "." ." " " " ..." " " " " " "
al 65 2.99t+00 2.9M.01 1.641 01 0.00t+00 0.00t+00 8.16t+03 8.40t +M CU.64 0.00E+00 1.99t+00 1.071 40 0.00E*00 6.03t+00 9. Sat +03 3.671+04 2m 65 4.26t+04 1.13t 45 7.03t+04 0.00E+00 7.14t+04 9.95t+05 1.63t *M 2m-69 6.70t.02 9.668 02 8.92t-03 0.00t 90 5.8$t.02 1.42t+03 1.02t+04 ta 83 0,00E+00 0.00E+00 4.744+02 0.00E+00 0.00E+00 0.00t+00 0.00t+00 ga 84 0.00t+00 0.00t+00 5.40t+02 0.00t40 0.00E+00 0.00t+00 0.00t*00 34 85 0.00E+00 0.00t+00 2.53t+01 0.00E+00 0.00t 40 0.00t+00 0.00t+00 as.86 0.00t+00 1.9et+05 1.14t+05 0.00t+00 0.00t+00 0.00t+00 7.99t+03 88 88 0.00t 40 5.62t+02 3.6et+02 0.00t+00 0.00t+00 0.00t+00 1.72f+01 1.09t+00 88 99 0.00t+00 3.45t+02 2.90t+02 0.00t+00 0.00t+00 0.00t +W SR.99 5.99t+05 0.00t+00 1.72t+M 0.00E+00 0.00t+00 2.16t+J6 1.67t+05 sa 90 1.01t+08 0.00t+00 6.44t+06 0.00t+00 0.00t+00 1.4aE +07 3.43t+05 sa.91 1.21E+02 0.00E+00 4.59t+00 0.00t+00 0.00E.00 5.33E+04 1.74E+05 St.92 1.31841 0.00t*00 5.25t 01 0.00t+00 0.00s+00 2.40t+M 2.42E+05 T.90 4.11t+03 0.00t+00 1.11t+02 0.00t+00 0.00E+00 2.62t+s5 2.68t+05 Y 914 5.071-01 0.03E +00 1.848 02 0.00t+00 0.00t+00 2.81t+03 1.72t+03
' 1* 9.14t+05 0.00t+00 2.44t+04 0.00E+00 0.00t+00 2.63t+06 1.84t+05 T.92 2.04t+01 0.00t+00 5.8tt.01 0.00t+00 0.00t+00 2.39t+04 2.39t+05 Cawersion f actors are in units of eren/yr per til/cstc amiter.
O UNT-005-014 Revision 0 Attachment 6.5 (7 of 12) 127
._ .._ _ _ . _ . _-_.m -._ _ _.. _ _ _ -. _ . _ __ _ _ _ _ _ - _ ____
INHALATION PATHWAY DOSES DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, R i AGE GaGuh CulLD ( ) 07 3 ) caGAm 00st Ctavttstom f AC10R$ muttlet 4 tumG Gl.tti tivte 1.em>1 tuf001D LID #EY BWE ' Y.93 1.8M +02 0.00t+00 5.11t+00 0.00t.00 0.00t+00 7,66t+04 1,e9t +05 '
.1.90E*05 4.1st +M 3.70t +M 0.0M +00 5.96t+04 2.23t+06 6.11t
- Zs 95 re 97 1.ase+02 2.72t +01 1.60t+01-0.00t+00 3.ser41 1.tH +05 3.51t +M me 95 2.3H+04 9.14t+03 s.5H+03 0.00t+00 8.62443 6.16t+05 3.70t+04 No.99 0.00t+00 1.72t+02 4.26441 0.00t +00 3.92t+02 1.35t+05 1.27t +05 1C.99M 1.788 03 3.64f.03 5.77t.02 0.00t+00 5.071 02 9.51142 4.81t+03 TC.101: 8.10t.05 8.518 05 1.Qst.03 0.00t+00 1.4H 03 5.05t+02 1.63t+01 Ru.103 2.79t+03 0.00t+00 1.07t +03 0.00t+00 - 7.0M*03 6.42545 4.44t+M au.105 1.5M +00 0.00t+00 5.5H.01 0.00t+00 1.34t+00 1.59t+04 9.VH+M ,
tv.106 1.3et+05 0.00t+00 1.69t +06 0.00t+00 1.844*05 1.4M +07 4.29t+05 5.60E+06 1.00t+05 AG 110M 1.69t+04'1.16t+04 9.14t+03 0.00E+00 2.12t +M T!*175m 6.7M +03 2.3M +03 9,14t+02 t.92t+03 0.00t+00 4.77t +05 3.38t+06 1.40E+06 T.14t+04
-ft.127W 2.49t +M 8.55t+03 3.02t+03 6.07t+03 6.36t +M
- 5. m *04 78 127 2.77t+00 9.51E.01 4.115 01 1.96t+00 7.0M+00 1.00t+04 ft.129M - 1.92E+04 6.e5843 : 3.06t43 6.3M43 5.0M +04 1.76t+06 1.82f 45 ft.129 9.7M.02 3.50t.02 2.34E.02 7.144 02 2.5M 01 2.9H+03 2.55t+04'
- 4. cot +02 2.04E45 3.0et+05 -
73 131m 1.34t+02 5.9M+01 5.0M+01 9.7M*01 72 131' 2.1M 02 4.644 03 6.59t 03 1.70E 02 5.est42 - 2.0H+03 1.3M+03
-7t.132 -4.81t+02 2.7N +02' 2 6H+02 3.1M+02 1.7M+03 3.7M+05 1.388+05 ,
I.130 - 4.1m+03 1. %f,+M t.44t+03 1.54+06 2.4W+M 0.00E*00 5.11843 1,131 4.81t+06 4.81t+M 2.7M+06 1.65 +07 7.00E+44 0.00t*00 2.06t43 8 132 2.1N43 - 6.0M+03 1.08t+03 1.96445 4.2H43 0.00E+00 3.20E*03 l.133 .1.6st+06 2.ast+06 : 7.75+03 3.058 06 3.3m+06 0.seE+00 5.4eE+03 l.134 1.17E 03 2.14443 9.9H+02 5.0M+M 3.38t+03 0.00E+00'9.3M+02
'l.135 4.9H+03 8.73t*03 4.16843 7.93t*05 1.34t+46 0.00t+00-4.44t+03 CS*134 6.51t+05 1.01t+06 2.2H+05 0.00t+00 3.3cE45 1.24t+05 3.sH+03 ts*136 6.51544 - 1.71E+05 1.14E+05 0.get+00. 9.5 M +06' 1.4 H +06 4.18t+03 - .
l es.137. 9.07t+05 S.25t+05 1.1st+05 0.seE+00 2.82t45 1.064+05 3.62E45 - i CS.138 6.33t+42 8.60t42 - 5.5M+02 0.00t+00 6.23e42 6.81441 2.7eE+02 1.068+00 9.844 06. 5.3M 02 0. set +00 s.63E 04 5.77t +03 5.7M+04 ! i BA.139 Corwerslen f acters are in mits of erge/yr per uCl/c4(c meter. .
. Attachment 6.5 (8 of:12)
-UNT-005-014 ' Revision O. .
'128
-a- - .. a.- .. - - -
~- . - . , . - . . -- . ._+.._.,~...~.- -_--. -
9
-INHALATION PATHk'AY DOSES DUE TO RADIONUCLIDES OTHER THAN' NOBLE GASES, R k i AGE GA3JPt CNILD ( 3 Of 3 )
NUCLlet cacAs Dost COWyttS10m FAC10tl Sout LIWR 1.DCCY TNTt010 ElDutY LuuG GI LLI DA 140 7.46t*04 4.48t+01 4.33t+03 0.00t+00 2.11t+01 1.74t+06 1.02t+05 nA 141 1.9M 01 1.09t 04 6.3M 03 0.00 +00 9.47t 05 2.92t+03 2.75t*02 SA 142 5.00t 02 3.60E 05 2.79t 03 0.00t+00 2.918 05 1.64t+C3 2.74t*00 LA 140 6.44E+02 2.25t*02 7.55t+01 0.00E+00 0.00t+00 1.8M*05 2.2M+05 LA 142 1.30t+00- 4.118 01 1.29E 01 0.000+00 0.00t+00 8.70t+03 7.59t+04 C1 141 3.92t+04 1.95t+04 2.90t+03 0.00t+00 8.55t+03. 5.44t+05 5.4M *04 CE 143 3.44t+02 1.99t+02 2.87t+01 0.00t+00 B.3M+01 1.1M+05 1.27t+05 f2 144 6.77t+06 2.12t+06 3.61t+05 0.00t+00 1.17t+0i 1.20t+07 3.89t+05 M 143 1.85t +M 5.55t+03 9.14t*02 0.00E+00 3.00t+03 4.i'3t *05 9.73t+04 M 144 5.9M 02 1.8M.02 3.00E 03 0.00t+00 9.771 03 1.5M+03 1.97t+02 uo.147 1.08t+04 8.7M+03 6.81t+02 0.00E+00-4.81E+03 3.28t+05 8.21E*04
. W 187 1. W +01 9.4ef +GC - 4.3M+00 0.00t+00 0.00t+00 4.11t*04 9.1Lt+04
'(Y - ............ ..................... ............................................. uP 239 4.6M*02 3.34t+01 2.3M +01 0.00t+00 9.738*01 5.81t+M 6.10t+04 Comersian facters are in mits of aren/yr per uCf/cels astof.
\
Attachment 6.5 (9 of.12) UNT-005-014 -Revision 0: ,
.129
1 1 O INHALATION PATHWAY DOSES DUE TO l ( RADIONUCLIDES OTHER THAN NOBLE GASES, R $ 404 Camps luf asi ( 1 Of 3 ) NUCLIDE DeGAa 0051 Ctavit$10m f4C10sl - k lWit 1.8@f inYt010 E10 sty tuhG Cl 4LI Sout M3 0.00E +00 6.47t+C2 6.47E*02 6.47t+02 6.47t+02 6.47t+02 6.47t+02 C 14 2 6%+M 5.31E*03 5.31t+03 5.31t+03 5.31t+03 5.31t*03 5.31t+03 i 1.0M +04 1.0M +04 1.0M *04 1.0M +M 1.0M +04 1.06t+04 1.0M +04 mA 24 P 32 2.03E*06 1.12145 7.74t+04 0.00E+00 0.00E+00 0.00E+00 1.61t+04 Ct 51 0.00t+00 0.00t+00 8.95t*01 5.75f+01 1.32841 1.28E+04 3.571*02 em 54 0.00t+00 2.53t+04 4.98t+03 0.00t+00 4.98E+03 1.00t+06 7.0M +03 em 56 0.00E+00 1.54t+00 2.211 01 0.00t+00 1.10t+00 1.25t+04 7,17E+04 Ft 15 1.975 04 1.17t+04 3.33t+03 0.00E+00 0.00E*00 8.69t +M 1.09t+03 Ft 59 1.3M44 2.35t+04 9.484+03 0.00E +C0 0.00E+00 1.02t+06 2.481+04 CO 58 0.00E +00 1.22t+03 1.82t+03 0.00E+00 0.00(+00 7.7M+05 1.11t+04 CD-60 0.00E+00 8.02t+03 1.18E+04 0.00E *00 0.00E+00 4.51t+06 3.19t+04 O. ul-63 3.39t+05 2.04444 1.1M +04 0.00t+00 0.00t+00 2.09t*05 2.42t+03 (" ................................................................................ al.65 2.39t+00 2.848 01 1.234 01 0.00t+00 0.00E +00 B.121 03 5.01t+M Cu-64 0.00E+00 1.88t40 7.744 01 0.00t+00 3.98t+00 9.30t+03 1.50E +M 1m 65 1.93E+04 6.26E+04 3.11t+04 0.00E +00 3.25t+M 6.47t+05 5.14t+04 1s 69 5.39t.02 9.6M.02 7.1st 03 0.00t+0u 4.025 02 1.47t+03 1.32t+M 8A 83 0.00E+00 0.00t+00 3.81t+02 0.00E+00 0.00E +00 0.00E+00 0.00t+00 sa.84 0.00t+00 0.00t+00 4.00E+02 0.00t+00 0.00E+00 0.00E+00 0.00E+00
......................................................................4...
sa 85 0.00E+00 0.00t+00 2.04t+01 0.00E+00 0.00t+00 0.00E+00 0.00E+00 38 86 0.00t+00 1.90E+05 8.82t+04 0.00E+00 0.00E+00 0.00t+00 3.04t+03 as.88 0.00E+00 5.57t+02 2.87t+02 0.00t+00 0.00t+00 0.00E+00 3.39t+02 98 99 0.00t+00 3.21t+02 2.06t+02 0.00E +00 0.00E+00 0.03E+00 % 828 01 sa 89 3.98t+05 0.00E 4 0 1.14t +M 0.00E+00 0.00t+00 2.03t+06 6.40E+04 sa-90 4.09t*07 0.00E*00 2.59t+06 0.00E40 0.00E+00 1.12t+07 1.31145 sa.91 9.5M+01 0.0(It+00 3.4M+00 0.00t+00 0.00t+00 5.26t+M 7.34t+04 sa 92 1.05t+01 0.00E+00 3.918 01 0.00E +00 0,00t+00 2.38t+04 1.40E+05 T 90 3.29t+03 0.00E+00 8.82t+01 0.00E *00 0.00E +00 2.69t+05 1.04t+05 Y.91n 4.07t-01 0.00t+00 1.391 02 0.00E+00 0.00t+00 2.79t+03 2.35t+03 f.91 5.88t+05 0.00E.00 1.5M+04 0.00t+00 0.00t+00 2.45t+M 7.03t+04 Y.92 1.64t+01 0.00E+00 4.61t 01 0.00E+00 0.00t+00 2.454+04 1.27t+05 Corwersion f actore are in units of mren/yr per att/ cele amter.
/m '
Attachment 6.5 (10 of 12) UNT-005-014 Revision 0 l l 130
l I!MALATION PATINAY DOSES DUE TO O 1
;O RADIONUCLIDES OTHER THAN NOBLE GASES, R i i
4GE GROUP: thf Aki ( 2 0F 31 auCtlDE C8GAA 00$f CDsVttilCW F ACiutt f . 82 T TuftCIO ElDutY LLWG Cl tLI S0st Livit V 93 1.50f+02 0.00t+00 4.07t
- 00 0.00t+00 0.00E+00 7.64t+04 1.671*C5 28 95 1,15t*C4 2.79t*04 2.03t+04 0.00t+00 3.11t+04 1. 75t + 06 2.171+04 2t 97 1.50t+02 2.5M*01 1.17t +01 0.00t*00 2.59t+01 1.10E+05 1.40t+05 wa P5 1.57t+04 6.43t+03 3s78t+03 0.00t+00 4.72i+03 4.79t+05 1.27t+04 pe> 99 0.00t+00 1.65E+02 3.2M*01 0.00t+00 2.65t+02 1.35t+05 4.87t +M TC 99u 1.40f 03 2. sat 03 3.721 02 0.00t+00 3.111 02 8. M t +02 2.035 03 TC 101 6.511 05 8.23E 05 8.121 04 0.00t 40 9.7W M 5.Mt+02 8.44t+02 te 103 2.02t+03 0.00t*00 6.79t+02 0.9)E+00 4.24t+03 5.52t+05 1.61t+04 tu 105 1.22t+00 0.00E+00 4.10t 01 0.00t+00 8.9M 01 1.5M44 4.Et +M au 106 8.64t44 0.00t+00 1.09t+04 0.00t+00 1.07t+05 1.16t+07 1.64t+05 4G.110s 9.9et+03 7.22t+03 5.00t+03 0.00t+00 1.09t+04 3.6M+M 3.30s.04 m 4.7M +03 1.99t+03 6.58t+02 1.62t+03 0.00t+00 4.47t+05 1.2W+04 ft 1254
[ T tj It*127M 1.67t+M 6.90143 2.07t+03 4.871+03 3.75t+04 1.31t +M 2.7M+04 TE 127 2.2M+00 9.5M 01 4.89t 01 h85t+00 4.8M+00 1.0M +M 2.44t +M 78 129M 1.41E+M 6.0M +03 2.23t+03 5.47t+03 3.184+04 1.68t+06 6.90t +M 11 129 7. set 02 3.471 02 1.8at 02 6.756 02 1.751 01 3.00t+03 2.63t+04 ft 131N 1.07t+02 5.50t+01 3. m +01 8.9M+01 2 65t+02 1.9M+05 1.195+05 TE 131 1.74t 02 8.22E 03 5.00E 03 1. Sat 02 3.99t 02 2.06t+03 8.22E43 T1 132 3.721+02 2.375+02 1.76E+02 2 79t+02 1.03t+03 3.40t+05 4.418+04 1 130 6.3M*05 1.39E +M 5.57t+03 1.60s+06 1.534.M 0.00t+00 1.991+03 l'131 3.7M+M 4.44t +M 1.9M+M 1.44t*07 5.18t+M 0.00t+00 1.0M+03 1 132 1.69t+03 3.54443 1.2M+03 1.69E+05 3.954 03 0.00t+00 1.90t 43 1 133 1.32t +M 1.92t +M 5.60t+03 3.5M+06 2.24444 0.00t+00 2.1M +03 1 134 9.21t+02 1.84E+03 6.m42 4.45E +M 2.09t+03 0.00t+00 1.29t+03 1 135 3.8M+03 7.60t+03 2.77t+03 6.96t+05 8.47t+03 0.00t+00 1.83E+03 1.334+03 C3 1M 3.964+05 7.03t+05 7.454 +M 0.00E+00 1.90t+05 7.975 +M
- 1. m +C3 C5 136 4. m +04 1.35E+05 5.2M44 0.00t+00 5.64t 44 1.1aE+04 C3 137 5.49t+05 6.12t+05 4.55t44 0.00t+00 1.72t+05 7.1M+04 1.33t+03 Cs 138 5.05t+0? 7.81t+02 3.9ef+02 0.00t+co 4.10t+02 6.54E+01 8.7M+02 BA 139 1.44t+ce 9.844 04 4.30t.02 0.00t*00 5.921 M 5.95t+03 5.10E +M Carmreton f actors are in mits of eren/yr per uCl/ctble poter.
(h 1
\v/
l l Attachment 6.5 (11 of 12) UNT-005-014 Revision 0 . 131
INHALATION PATHWAY DOSES DUE TO p> RADIONUCLIDES OTHER TilAN NOBLE GASES, R 3
\.m/
AC4 GACLP: IntAuf ( 3 Of 3 ) OkGAm 0051 CCmyttitch FACTORS suCLIDI 1.kTV tuft 010 E108t1 LumG Cl LLI tant Livtt 54 140 5.60E+04 5.60t+01 2.90t+03 0.00t+00 1.348+01 1.60t+06 3.64t+04 6a.141 1.57t.01 1.00f.04 4.975 03 0.00t+00 6.50E-05 2.97t+03 4.75t+03 6A.142 3.96E.02 3.30t 05 1.9et.03 0.00t+00 ~1.90t.05 %.55t+03 6.93t+02 LA.140 5.05t+02 2.00t*02 5.15t+01 0.00E+00 0.00t+00 1.64t+05 8,48t+04 LA.142 1.03t+00 3.775 01 9.041 02 0.00t+00 0.00t+00 6.22t+03 5.95t+04 Cf.141 2.77t+04 1.675+06 1.9W+03 0.00t+00 5.25t+03 5.171+05 2.16t+04 Ct.143 2.93t+02 1.93t+02 2.21E+01 0.00t+30 5.64t+01 1.16t+05 4.97t+04 Ct.144 3.19t+04 1.21t+06 1.76t+05 0.00t+00 5.3M*05 9.84t+06 1.48t+05 M 143 1.40t+04 5.24t+03 6.99t+02 0.00E+00 1.97t*03 4.33&+05 3.T21*04 M 144 4.79t.02 1.858 02 2.418 03 0.00t+00 6.721 03 1.61t+03 6.28t+03 no 147 7.94t+03 8.1M +03 5.00E+02 0.00t+00 3.15t+03 3.22f+05 3.12t+04 .f W.187 1.30E+01 9.02t+00 3.12t+00 0.00t+00 0.00E+00 3.9d +04 3.562 04 (s ................................................................................ be 239 3.71F+02 3.32t+01 1.88t+01' O.00E+00 6.62E+01 5.95E+04 2.49t+04 Conwesian futors are in mits of aren/yr per wunete meter. f ()
'V UNT-005-014 Revision 0 Attachment 6.5 (12 of 12) 132
e CROUND - PLANE DEPOSITION PATINAY DOSE PACTORS DUE TO RADIONUCLIDES OTHER TilAN NOBLE GASES. Ri Af.! Ge p i ALL t 1 Of 3 ) suCL10s Wf.As Dost cowviellom f attosi f.6@t $(la t a3 0.00t*00 0.00t*00 t.16 0.00t
- 00 0.00t+00 ta.te 1.1st*07 1.3M +07 P.12 0.tht+00 0.00t*00
. Ct 51 4.64d +M l . lit +M m le 1.398+09 1. W +09 m.$6 9.0H + 0$ 1.0M*M Ft 15 0.00t+00 0.00t+00 70 99 2.TM*# 3. tit +M to 54 3.79E*00 4.64t+48 to 60 f.1H+10 2.5M +10 ti41 0.008+00 0.00E+00 81 65 2.9M*H 3.4H+M CU M 6.0M+05 6.00t+M tu Al f.47t+08 8.99t+06 is M 0.00E+e0 0.00t+eo >
0s 03 4.sM.03 7.08t+05 MN 3.0M *05 2.3M+M As N 0.00E+00 0,00E+00 to M 8.98t4 1.0N +07 00 5 3.31t+06 3.7W +46 . se W 1.III+05 1.68 +05 IA M !.14t+46 2.51(+46 e4 90 0.00t+00 0.004 2.1M*05 f.11( 4 te.91 ga.93 f.TM *05 8.W +M 1 90 4.4M+03 5.31t+03
~
f.91n 1.00t*05 1.lef +M t.91 1.07t4 1.218 4 f.93 1.act+05 2.16t+05 c.rwe,i.n twi.e. .r. in ette of e.mre =ter wwyr per utt/**. Attachment 6.6 (1 of 3) UNT-005-014 Revision 0 133
- _ - - - . . . . . . _ , _ _. , , .. * ' " " + --p3-- .-ys, ,-. . .,.,,.g ,_
1 CROUND - FLANE DEPOSITION PATliVAY DOSE FACTORS DUE TO RADIONUCLIDES OTilER TilAN NOBLE CASES, Ri c 48 640urs 6Lt i ! Of 3 3 ext M car.as Ocst tarvieston f actces
- 1. tapt 6als r
t.93 1,6M*M 2.$ tt *M te*96 f.4St.04 f.kt*W IA 97 3.tet.M 3.64t *M 1 me 95 1.34*08 1.6tl*00 no 99 3.99t *N 6.6M*W TC 99u 1.Et *M 2.ltl*M tt.101 f.kt46 f .26t +N , tu.101 1.00t.00 1.!W.08 eu 1M 6.36t +M f.f tf *H 69 106 6.!N +48 ' $.0M*00 -
. M 110m 3.644.M 4,01949 f t .129st 1.$H+M 2.1M*M 1 ft.127m 9.1st+04 1.00t +M 11 127 2.tu e03 3.tet+03 C 1.95 47 3.31047
\ ft tMu
......................................... y if *iN 2.6K +N 3.iN+04 I
.Tiet31a 8.8M46 9,64t *H 18 131 2.tN+N 3.6M+01 ,
ft.112 6.2.M +# 6.90846 i 1 130 $.918 46 6 eeE46 lat31 1.7N 47 2.90E47 !
...................................-c....
1 133 1.fle*e6 1.64f+46 *
. 1 138 2.6Mee6 2.9W+46 1 1M 6.6M+04 8.3st+05
......................................... i l.tM 2.1M*46 2.95t+46 ,
C8 1M 6.eM49 4.00f+09 C8 1M 1.518+0B 1.716+48 - i
.............................e...........
l Cl.137 1.08t+10 1.2et+10 . - Es.1M 3.$0t+05 6.tNeel M.tM 1.tN +05 1.19t+05 f ......................................... temees ten settere sre in V-ste et esere enter *ennWyr per stilset. r J 1 h UNT-00$~014 Revision 0 a; Attachment 6.6 (2 of 3) , 134
~ . _ _ . . . _ . - _ . , . . . . . _ . _ , . . _ . _ _ _ . _ _.
1 1 l i l GROUND - Pl.ANE DEPOSITION PATINAY DOSE FACTORS DtIE 'l0 RAD 10NUC1.1 DES OTilER TilAN NOBl.E GASES, Rg ( ALI thrte Att t 3 of 3 3 aut4tpl car # tost Corvtttttu entitet
- 1. h@v Sat.
6A.160 f.Mt +07 f .35t *0 f 6A.141 4.171 +M 6.Mi'M
&A.142 4.49t ek $ .11l *M 44 160 1.92te07 f.tht*07 LA.167 7.60t
- M 9.111 + M (t.161 1.371*07 1.448*07 Cf.10 2.31t*06 2.Ml+04 Ct 164 6.Mt*0f 8.06t *C f P. 161 0.00t+00 0.031*00 70 164 1.Ut*01 2.111+03 HDelef 0.39t ete 1.01t*07 W il? 2.15t +M 2,TH+M O NP.239 1.fil +M 1.9NeM c., . . , . . ... . . u .. ,. ... - ,, ,, e t,. .
+
i t v Attachment 6.6 (3 of 3) UNT-005-014 Revision 0 135
I l COW's MILK PA'lWAY DOSE TACTORS DUE TO KAD10NUCL10ES OTHER THAN NOBLE CASES. Kg a t,( t.4 0L* : abutt 1 of 1 ) escttDt (8CAs 005t traviellom f atitel Livil 1.43' '8'801D eld *tt L L* 4 &I LLI Scot e.) 0.00t+00 f.ut*02 f.6M *02 f.61t +N 7.ut*02 F.63t+02 7.61t+0! t.14 2 6k +08 S .14 +07 S.2ft*07 S.Ift*07 1.2 4 *07 l'.!fid? l.!?t*07 u.26 3,ut +06 f ute 2,ut@ I ul@ I.41 @ 2.ut @ 2.ut @ P.lt 1.f't+90 1.ht+09 6.611 04 0.00t*00 0.00t+00 0.00t*00 1.92t+09 f9 51 0.00t+00 0.00t*00 2.u4 @ 1. f1i @ 6. 30t
- 03 3.19%+04 7.19t
- em . 54 0.00t+00 0.411 @ 1.61I @ 0.00t+00 f.50t*06 J. Dot +00 2.lld .07 mm 56 0.00t*00 4.11t 01 7.364 04 0.00t+00 5.271 01 0,00t*00 1.371 01 ft.ll 2. lit +0? 1.764 07 4.Mt +c6 0.00t+00 0.00t+0C 9.68t*06 9.Mt @
ft.19 2.97t+07 6.98d*07 2.64t*07 0.00t*00 0.00t+00 1.95t+0? 2.33t+08 Co lo 0.00s @ 4.711+06 1.0M *07 0.00f*0C 0.00s+00 0.00s*00 9.llt of co 60 0.00s.00 1.64t+07 3.6?t+0F 0.00t+00 0.00t+00 0. M *00 3.Ont*0s
- 9. 73t +0?
81 63 4.734+0* 4.6M *06 2.t M
- 04 0.00t+00 0.00t+00 0.00t*00 al.6% 1.70t.01 4.018 02 2.19t 02 0.00t*00 0.0m .00 0.00t+00 1.22:*00 tv M 0.00t+0c 2.38t+06 1.17t *06
- 0.00t+00 6.01t*04 0.00t+00 3.05t @
19 65 1.37t+09 4.37t*09 1.971+09 0.00t+00 2.97t+09 0.00t*00 2.75t+J9 In 69 2.095 12 4.006 12 2.?st.13 0.00t+00 2.60t 12 0.00t+00 6.018 13 H . B.3 0.00t+00 0.00t+00 1.171 02 0.00t+00 0.00t+00 0.00t+00 1.6at.02 68 64 0.00s*00 0.00f+00 1.934 24 0.00t+00 0.000+00 0.00t+00 1.121 79 64 ti - 0.008+00 0.00t+00 0.00s+00 0.00s*00 0.00s+00 0.00s+00 0.00s*00 t9-t1 0.00t+00 2.59E+09 1.211+09 0.00t+00 0.00s*00 0.00t *00 1.12t+04 a6 04 0.00t+00 0.00s*00 0.00t*00 0. 008 +00 0.0(u+00 0.00s*00 0.00t +00 St M 0.00t+00 0.00t+00 0.00860 0.03t*00 0.0N+00 0.00t+00 0. tot +00 84 09
- 454+09 0.00t+00 4.1fd+07 0.00t+00 0.00t+00 0.00t+00 2.334*06 ta 90 4.f,8f*10 0.00s+00 1.'.50 +10 0.00 +00 0.00t+00 0.00t*00 1.358+09 St 91 2.09t+04 0.00t+00 1.i h +03 0.00t+00 0.00t*00 0.00t+00 1.3M+0S ta+91 4.684 01 0.00t*00 3.11t.02 0.00t+00 0.00t+00 0.00t+00 9.6st+00 1 90 7.Det+01 0.00t+00 1.90t+00 0.00t*00 0.00t+00 0.00t+00 7.11t+0S 1 91p S 9et.70 0.00E+00 2.321 71 0.00E+00 0.00t+00 0.00t+00 1. fed.19 f.91 8.59t+03 0.00t.00 2.30t*02 0.00t+00 0.00t+00 0.005 00 6.734 4 1 9P 5.lat.05 0.00t+00 1.638 06 0.00t+00 0.00t+00 0.00t*00 9.nt 01 cmreiwi tacter er, in etc. .: more ter.wwn rer ette.c ter ett uhwe us.pt e 3 #ic6 is in mite .: wwn E.r uctices ter.
Attachment 6.7 (1 of 12) l UNT-005-014 Revision 0 1"!6
s COV's MILE PATWAY DOSE h' ACTORS DUE TO . RADIONUCLIDES OTHER TRAN NOBLE CASES, R g act caaet eat < ! Oe 3 i tualtt teLAs Dost 0mitellom 86Ct088 D:mt Liv 10 1.0@t tettotD tlDatt tuk6 Cl*tti v.93 2.23t 01 0.00t+00 6.175 03 0.00t+00 0.004 00 0.00t+00 7. 0M *03 18 95 9.41142 3.01442 2.05t 42 0.00t*00 4. 75t *02 0. 00t + 00 9.19t
- 05 10 97 4.338 01 8.748 02 4.00t 02 0.0N+00 1.12t.01 0.00t*00 2.71444 al.95 s.2M 44 4.l9t +06 2.471 4 0.00t+00 4.54t*04 0.00t*00 2.79t+08 se 99 0.00t+00 2.4M 47 4. fit *06 0.00t*00 l.61847 0.00t*00 S.74t+07 ft.99u 3.12t+00 9.1M *00 1.20t*02 0.00t+00 1.41142 4.60E
- 00 5.lll*03 .
1C.401 0.00t+00 0.00t+00 0.00440 0.00s+00 0.00s*00 0.00t*00 0.00t+00 89 103 1.0M*03 0.00t*00 6.39t+0! 0.00t*00 3.t9t43 0.00t*00 1.19t*05 tv 10$ 8.$ 71 04 0.00t*00 3.34t.04 0.00t+00 1.11842 0.00t +00 1.24t 01 tv.the 2.kt*04 0.00t+00 2.lM+03 0.00t*00 3.Mt* 0.00t +uo 1.328 06 44 iiOM l.82t+07 l.39t+07 3.20t47 0.00t*00 1.0W 48 0.00t+00 2.20t*10 ti.125m 1.63t+07 S,90t+06 2.1 N +06 4.908 4 6.63t+0? 9.00t+00 6.50t+07 5 18 127m 4.5M +07 1.64447 5.58t+06 1.17:47 1.6M +08 0.00t+00 1.544 08 b 11 127 6.lst*02 2.34442 1.41842 4.84t*02 2.6M +03 0.0N +00 5.15t M tt.129u 6.02t+07 2.25847 9.lMW ' 2.07147 2.11t+08 0.00t+00 3.0M *08 it*129 2.821 10 1.0M 10 6.8M.11 2.171 10 1.19t .09 0.008 40 2.1M.10 18 13186 3.61t+05 1.771*05 1.47t+05 2.80t+05 1.79t +06 0.00t+00 1.75847 18 131 3.60E.33 1.118 33 1.14E.33 2.9M.33 1.lW .52 0.00t+00 1.10t.54 18 132 2.40t*06 1.llt+06 1.4M W 1.T2t+06 1.$0t*07 0.00t+00 7.35447 1 130 4.20t+05 1.24t+06 4.99t+0S 1.05t+08 1.9M +06 0.00t+00 1.07t+06 1 131 2.968+08 4.23t+08 2.4M +08 1.39t*11 7.2M +08 0.00t+00 1.12t+08
..................... e.......>... 3............................................
1 132 1.Mt 41 4.39t.01 1.548 01 1.%541 7.00t.01 0.00t+00 8.255 02 1 133. 3.87t+06 6.7M 46 2.05t 46 9.99t +08 1.17t+07 0.00t+00 6.05t+06 1 154 2.021 12 1.48E.12 1.9M 12 9.49t.11 8.718 12 0.00t*00 4.T7t.15 1 135 1.2M+04 3.14t+04 1.24t 44 2.22t+06 1.3M +04 0.00t+00 3.80t+04 Cl.1% 1.65t+09 1.35t*10 1.10t*10 0.00t+00 4.35t+09 1.45t+09 2.35t+C4 C5-136 2.65t+08 1.04t+09 7.4M +08 0.00t+00 9.7M +08 7.93t+07 1.1M+08 Cs.137 7.34E+09 1.01t+10 6.61t+09 0.00t+00 3.43t+09 1.14t+09 1.95t+08 ts.158 9.04t.24 1.79t.23 8.851 24 0.00t+00 1.318 23 1.30s.24 7.621 29 EA.139 4.421 08 3.158 11 1.29t 09 0.00t+00 2.944 11 1.795 11 7.kt 08 Carwersics) f acters are in mits of egare meter.oree/yr per gl/see f or ell ruellers escept h*3 tAlCtl 16 in mile et aravyr per di/ Celt eeter. l UNT-005-014 Revision 0 Attachment 6.7 (2 of 12) 137
. _ _ _ _ . _ _ ~ _ _ _ . _ - _
COW's MILK PAT}NAY DOSE FACTORS DUE TO RADIONUCLIDES OTHER THAN NOBl.E GASES, R i Att Gears ADAt t 3 0, 3 3 eMcLIDI cer.As 00st couvtantos f actual DONI L t Wit 1.031 teYe0lD tl0mit Luke 41.ht! I M.140 2.69t*07 3.3M*06 1. fM *M 0.00 ten 0 1.15t *M 1.tM
- 04 1.llt*07 M.141 0.00t+00 0.00t*00 0.00t*00 0.00t+00 0.00t*00 0.00t*00 0.00t+00 '
H.142 0.008+00 ,0.008+V . "00 0,00s*00 0.00t+00 0.00s+00 0.00t+00
............................ o.. .. . . . . . ..............................
LA.140 4. lit *00 3.IPt + t .WJ.i '
- no v 00 0.00s.00 1.ift*05 '
LA 142 1. W .11 0.4H.s t,15. fi k ## u, h% 0.00t*00 6.1Ft.08 tt.141 4.kt+03 3.20t *O
- 24 3 ' .'p*M _
.l.143 0.00t*00 1.F5t+0?
. i Cf.143 4.1M *01 3.0FleM 3.40t+00 0 00t*00 1.3H+0i 0.0dt*00 1. ill* M '
Ct.144 3.50t+0S i.50t*05 1.0M *k t,00t+00 8.0ft *M 0.00t+00 1.21t*00 . Pe*143 1.50t*02 6.3M*01 f.4M *00 6. M *00 3.66t
- 0.00t+00 6.9M*M P8 144 0.008+00 0.008+00 0.00s+00 0.00s+00 0.00 +00 0.00t*00 0.004 *M No.147 0.4M +01 l.00t*02 6.51t*00 0.00t*00 6.36t*01 0.00t*00 5.tM *01 W 107 6. lit *03 1.4H +03 1.00t+03 0.00t+00 0.00t*00 0.00t+00 1.70t *M pp.230 4.60t+01 6.1M+00 1.40t+00 0.00t*00 1.41t+01 0.00t*00 0.27t+0S l
l l c weten vectore ere in ette et re ester.wwyr pr wife.c ter ett t
' eintte eneses e.3 ele to in ette et erwre pc wiewt ester.
s' d
- i e I l
L
,t l
l . Attachment 6.7-(3 of 12) UNT-00$-014- Revision 0. , 138
i i i l l COW s MILK PATINAY DOSE TACTORS DUE TO . RADIONUCLIDES OTHER TilAN NOBLE GASES, R 3 M4 &# UPt tile i 1 of 3 ) uJCLibt tot.At Dott Ctavttlita f &tical 6out LIVit 1.6@ t frft0lD flDett LUuG $1 441 , e*3 0.00t+00 9.ht*02 9.ht +02 9.ht *02 9.ht.02 9.94t+02 9.ht*02 ( 14 4.ht*04 9.ftt+07 9.ftt
- 07 9. tit +0? 9.ftt+0? 9.ftt*07 9.724 07 u 24 4.tH +06 4.tM *06 4.tM*M 4.tM *06 4.tM4 4.lM*M 4.!M
- 06 P.!! 3.15t*10 1.95t*09 1. tit *09 0.004 00 0.00t+00 0.00t+00 2.6%t*09 Ca li 0.00t*00 0.00t+00 4.99t
- 2.77t
- 1.09t+04 7.1H 4 8.39t*06 m 54 0.00t+00 1.40t*07 2.70t+06 0.00t+00 4.1M+M 0.00t+00 2.87t*07 aus.56 0.00E+00- 7.364 03 1.311 03 0.00t+00 9.318 03 0.00t+00 4.648 01 fi SS 4.45t*07 3.1M+0F f.36t*06 0.00t*00 0.00t+00 1.00t*07 1.371 07 78 59 S .1M *07 1.21t+08 4.6ft +07 0.00t*00 0.00t*00 3.81t*07 2. tM *08 to.l4 0,00t*00 7.Mt +M 1.6M*07 0.00t+00 0.00t+00 0.00t*00 1.09t+0s CD 60 0.00t+00 2.70t*07 6.2M +07 0.00t+00 0.00t*00 0.00t+00 3.62t+0s al O 1.ite+10 0.3H.08 4.91t+08 0.00t+00 0.00t*00 0.00t*00 1.!M*00 r
si+el 6.771 01 0.6H 02 3.Mt 02 0.0at+00 0.00t+00 0.00t+00 6.Me@0 CU M 0.00t+00 4.!H+04 2.00t+06 0.Ont+00 1.07t+0) 0.00t*00 3,79E*06 ta 65 f.11E+09 7.3at+09 3.41t+09 0.coE+00 4.60t *M 0.00t+00 3.10:49 tu 69 3.0H 12 F.kt*12 1.1M*13 0.00t+00 4.79t.12 0.00t+00 1.3H 11 0e+83 0.00E*00 0.00t+00 2.1H 02 0.00t+00 0.00t+00 0.00E+00 0.00E*00 08 M 0.00t+00 0.00t+00 3.4H le 0.00t+00 0.001+00 0.or1 00 (.00t*00 08 el 0.008+00 0.00t+00 0.00t+00 0.00t+d 0.008+00 0.est+00 0.0er+00 De M 0.00t+00 4.7M +M 2.2M +09 0.get+00 0.0e1+00 0.008+40 7.00s+08 - et 88 0.tet+00 0.ast+e0 0.00t+00 0.Det+eo 0.est+40 0.000+00 0.00s+00 to M 0. Dot +00 0.DeE+00 0.00E+00 0.00t+00 0.0tu+00 0.00t+00 0.00t+00 es.M I.67t+09 0.00f+00 F.ht+0T 0.goE+00 0.00t+00 0.00t+00 3.19t*e8 Da.90 6.61t+10 0.00E+00 1.Ot+10 0.0m +00 0.00E+00 0.00t+00 1.tet*M 88 91 l.31t+04 0.00t+00 2.11t+03 0.00t+00 0.00E+00 0.00t+00 2.41t*05 l 08 92 8.Mi 01 0.00t.yJ 3.81t 02 0.00t+00 0.0et+00 0.00t+00 2.20t+01 1 90 1.30t+02 0.00E+00 3.511+00 0.00s+00 0.00s+00 0.00s+00 1.071+M f*9in 1.108 19 0.00t+00 4.194 21 0.00t+00 0.coE+eo 0.00t+00 1.17f.18 T 91 1.lat+M 0.00E+00 4.24t+CJ 0.00t+00 0.00t+00 0.00t+00 6.48t+06 f*tt 1.0M 06 0.00t+00 f.900 M 0.00t+00 0.00t+00-0.00t+00 2.8M *00 Carwersten f acters are in mits of somre ester.wesvyf per di/tec for ett ructises oncept 0 3 eAlsh te in mits of wentyt per Wl/cWie enter. 1 UNT-005-014 Revision 0 Attachtoent 6.7 (4 of 12) 139
- - . - _ _ = _ _ . - - - - _ _ _ - - . --- -- -_ .. --. - . _ . - _ _ - _
I 1 COW's H11X PATWAY DOSk TACTORS DUE TO . RADIONUCLIDES OTHER TilAN NOBLE GASES, R. 4 4t.t C,80L* tile t 2 08 3 ) aucktbt ter.an post (omygeggga gaggoog 1 i j Dht tivt t 1.es t toteolD tit *tt t unt. f.l . t t i ) 1 93 4.121 01 0.00040 1.131 02 0.00t+00 0.00s+00 0.006*00 1.248 + 06 ft.95 1.65843 S.200 Of 3.lM
- 02 0.0Ct*00 7.4St+02 0.00t*00 1.20t *M tt.97 7. net.01 1.5M.01 7.196 42 0.00t 00 2.171 41 0.00t*00 4.12t*06 he 95 1.41t*05 7.61t
- 06 4.30t
- 06 0.00t+00 7.17t *06 0.00t*00 3.34teb8 so.99 0.00t*00 4.47147 t.HE
- M 0.00t*00 1.02t*0s 0. hot *00 8.01t*07 1C tm 1.7M
- 00 1.61t*01 2.Mt42 0.00t+00 2.39t*02 8.92f+00 1.05t*C6 It 101 0.008+00 0.001+00 0.004+00 0.00f*00 0.00t*00 0.008+00 0.00t*00 9u.103 1. tit *03 0.00t*00 7.74t 42 0.006 40 6.3M 41 0.00t @ 1. lit
- M 99 105 1.5M 43 0.00t*00 6.071 04 0.00E+00 1.971 02 0.00t*00 1.2M*00 99 106 2.99t *04 0.00t @ 4.73t*03 0.00t+00 7.24t
- C .00t *fe 1. 40t *M 64 11tM 9.6M *07 9.111 47 1.548 4 7 0.00t*00 1.74f 48 0.001*00 2.lM *10 18+12%m 3.00t47 1.Det 47 4.02t +M S.391+06 0.00t*00 0.001*00 8.6M 47 18 127m 4.44f 47 2.99t+07 1.00t 47 2.01t 47 3.421W 0.00t+00 2.10t
- 06 18 127 1.218*03 4.296*02 2.604+02 8.351 42 4.90t43 0.00 *00 9.348 +04 18 129m 1.10t*08 4.09t47 1.76147 3.15t 47 4.61t*06 0.00t*00 4.13t*06 it.129 1.208 10 f .ht .10 1.1M .10 3.711 10 2.18t 49 6.00t*00 2.664 M 18 131u 6.57 +M 3.1H +M 2.6M+M 4.748 *M 3.29t*06 0.Nr40 2.13847 18 131 4.548 33 2.711 33 2.0M .33 1.0?t.33 2. net 32 0.00t40 1.4M 44 it.132 4.29t+M 2.72t +M 2.5M+M 2.87t M 2.61t+07 0.00t+00 8.61847 1 130 7.34t 45 2.148+06 8.lM +0S 1.744+08 3.295 +M 0.00s*c0 1.Mt*04 1 131 $.375+08 7.518 4 4,044+08 2.198+11 1.2M+09 0.00t*00 1.4M +08 3 132 2.91841 7.62141 2.741 01 2.574 01 1.20f 40 0.000+00 3.328 01 1 133 7.07%*c6 1.20t 47 3.6M W 1.67t *M 2.10t 4 7 0.004+00 9.07t +M 1 134 3.let.12 9 $0t.12 3.418 12 1.$48 10 1.lfit 11 0.03t+00 1.254 13
................................................................................ 6. lit +M 1 131 2,20f*04 8.87t *M 2.18t+04 3.ftt W 9.27t+N 9.00i.00 C8 134 9.42t+09 2.31t*10 1.07t
- 10 0.00t+00 7.34t*09 2. tot +09 2.87t +M C8 1M 4.48t*08 1.7M +09 1.18849 0.00t*00 9.60t+08 1.51t+08 1.42t*08 ts.137 1.544*10 1.79t*10 6.20t+0+ 0.00t+00 6.0M+09 2.35t+09 2.lM +06 C3 138 1.kt 43 3.155 23 1.171 23 0.00t+00 2.3M .23 2.718 24 1.4 M .26 64 1H 4.171 06 S . 7H .11 2.30E.09 0.00t*c0 l,42t.11 3.968 11 7.29t 07 Conversion f acters are in etts of 64ere mete **aren/rr per st/sec for ett nuctices oncept e 3 iAlch is in etts of erentyr per dt/rms ester.
/
( Attachment 6.7 (5 of 12) UNT-005-014 Revision 0 140
COW's MILY. PATINAY DOSE TACTORS DUE TO RADIONUCLIDi.S OTilER TRAN NOBLE GASES, R i Atil W auP tttt i 3 08 3 ) s.stl let (sue bc44 ttavitlita f atttet LIWI 142t tett0lb I lbei t L 4m t. 61 441 tent 6A 160 4. Bit *07 1.95t*04 3.11t
- M 0.00t*00 2.02t*04 6.000 04 F.448*0f ta t41 0.00s*00 0.00f*00 0.008+00 0.00t*00 0.00t*00 0.00t+00 0.00t*00
&a.e62 0.00t*00 0.00t*00 0.00t*00 0.00t*00 0.00t*00 0.DM *00 0.00t*00 La 140 4.10t*00 3.98t*00 1.0M+00 0.00f*00 0.00t*00 0.00t*00 2. 29t
- 05 LA.162 3.35t.11 1.49t.11 3.714 12 0.00t*00 0.0N*00 0.00t*00 4.114 07 ti.141 0.6M
- 03 l.91t*01 6.81t*02 0.00t*00 2. 79t
- 03 0.00900 1.70t*07 (l.143 F.648*01 l$d*M 6.21t*00 0.00t*00 2.49t*01 0.00t*00 1.6Ple M 08 164 6.56t
- M 2.721 05 3.S&t*06 0.000 00 1.61s*05 0.004 00 1.64 *08 Pt.141 2.90t*02 1.16t*02 1.641 01 0.006 00 6.T3t*01 0.00 BOO 9 $4t*0$
De.164 0.00t+00 0.008+00 0.00t*00 0.00t+00 0.00 *00 0.00t*00 0.00t*00 eso.147 1.81t+02 1.97t+02 1.ibt*01 0.00t*00 1.16t*02 0.01D00 f.11t*05 W.187 ?.$tt+06 9. Fit +03 3.60t*03 0.00t*00 0.00E*00 0.00t*00 2.61t *M WP.239 8.70f*01 8.2&f*00 4.60t*00 0.00t*00 2.60t*01 0.00t*00 1.31t *M Omvers ten f utors are in mits of somre ester.oree/yr ser dt/sw f or ett rixtteers eatept a 3 Atch to in ette of areWyr per uti/cets enter. At t achtnent 6.7 (6 of 12) UNT-005-014 Revision 0 141
COW'O HILE PATHWAY DOSE FACTORS DUE 70 RADIONUCLIDES OTHER THAN NOBLE GASES R i r 6st Escurs telL0 e 1 Of 3 ) i sJtit0tl cet.as post canellOh Mt f($ $ tatt Livt e f .bco t tettol0 t ilamit LumG GI Lil !
#*) 0. 00t
- 00 l.lft*03 1.17t*03 1.17t 03 1.lM.03 1.lft*03 1.lM *03
(*14 1.1M *09 2. M *04 f .3M +08 2.3M *08 2.3M
- 00 2.39t @ f .3 M
- 04 '
66 24 4.05t @ 4.85t*07 0. 85t *M 8.851 4 8.85t*06 8.85t @ 8,8%t @ P 31 f.70teto 3.Mt*09 3.00t*09 0.00t*00 0.00t*00 0.00t+00 3.151 09 ta li 0.00t+00 0.00t*00 1.0N*M l.65t+M t .54 t *M 1.CM*M 1.60t *M em.54 0.006 00 f.10t*07 5.19t @ 0.00t*00 l.Ma*06 0.00t*D0 1.76t*07 mu le 0.00E*00 1.20t.02 f 90s.01 0.00t@ 1.llt 02 0.00t*00 1. W *00 ft ll 1.0M
- 08 l .FM
- 07 1.kt*07 0.00t*00 0.00t*00 3.15t+07 1.10t*07 ft 19 1.20t @ 1.95t*06 9.69t*0f 0.00t*00.0.00t*00 S.kt*07 f.CH 4 CD 58 0.00t*00 1. tit +07 3.71t*07 0.00t+00 0.00E*00 0.00t*00 f.CM*07 to 60 0.00t*00 4.3M*07 1.!M*M 0.00f*00 0.00t*00 0.00t*00 2. M *06 ti 63 2.06t*10 1.59t +09 1.Mt*09 0.00t*00 0.00t*00 0.001 00 1.0M *06 1.H4+00 1.lM 01 9.10t 02 0.00t+00 0.00t*00 0.00t @ 1.91t*01 ul.65 CV M 0.00t+00 f.6M +04 4. lit *M 0.00t+00 1.00t *M 0.00t*00 3.101 4 24 61 4. t w +09 1.185*10 6.05t *M 0.00t+00 6 MI 09 0.00t*00 1.FM*09 28 90 9.4M 12 1.37t 11 1.3M .12 0.00t+00 $.30t.12 0.00t+00
- 625 10 M'03 0.008*00 0.008+00 S.30s*02 0.00t+00 0.00s*00 0.00s*00 0.001+00 '
es.M 0. set +00 0.008+00 7.0tt 36 0.00t+00 0.00t+00 0.00s+00 0.00s+00 04 + 0'. 0.008+00 0.001+00 0.008+00 0.00t*00 0.00t+00 0.00t+00 0.00E+00 Beata 0.00t+00 8.771*00 5.399 W 0.00t*00 0.00t*00 0.00t+00 S.M8*08 00+0B 0.00t+00 0.000+00 0.00E+00 0.00t+00 0.00E+00 0.00 tee 0 0.00t*00
.....................................+..........................................
t8 90 0.00t*00 0.008+00 0.00900 0.008+00 0.006 @ 0.00s+00 0.008+00 88 99 4.6JE *M 0.tieE 40 1.00G*06 0.00t*00 0.00t+00 0.00t+00 2.56t+08 88 90 1.13t*11 0.00E+00 2.8M*10 0.00t+00 0.00t+00 0.00t+00 1.51t+09
..................................s.............................................
98 91 1.30t +M 0.00t+00 4.9M +03 0.00t*00 0. Dot +00 0.00t*00 2.08t+05 98 92 2.10i+00 0.00E*00 8.751 02 0.00t+00 0.00t+00 0.00t+00 4.1M+01 U90 3.22t+02 0.005 00 8.43t+00 0.00E+00 0.00t+00 0.0M+00 9.1M +05 f.9ta 2.Hg.17 0.00E+00 9.?6t 21 0. gut +00 0.00t+00 0.00t*00 1.264 16 Y+91 3,908+06 0.004+00 1.kt+03 0.008+00 0.00t+40 0.00t+00 S.20E+06 fatt 2.lM G 0.00t+00 7.768 06 0.00t+00 0.00t+00 0.00t*00 f.31t*00 Corwerslm f atters 60s in mits of newsre ester.oren/g per gl/sec for ett antisee eu.et s.3 onich to in mite et er /n Der etreets meter. Attachment 6,7 (7 of 12) UNT-005-014 Revision 0 142
i l I . 1 COV's MILK l'AT1NAY DOSE TACTORS ME TO KADIONUCLIDLS OTHER TilAN NOBLE C;9 J. Ri Act Daouri Dite t 2 08 3 ) uJctIDtl cat.An tot crmyttlict f acites 1.K01 1916010 libhti ttniG Gl.LLI Ett litte 1 93 1.01t+00 0.00t+00 2.78t 02 0.00t*00 0.00t*00 0.00l+00 1.118 4 28 95 3.434+03 8.42t 42 7. lot +02 0.out +00 1.211+03 0.00t+00 8.79t+05 10 97 1.97t+00 2.Tft .01 1.648 01 0.00t*00 3.9N 01 0.00t*00 6.20t*06 et 95 3.1M +0% 1.26t +0S 0.64t+06 0.00t +00 1.1M +0S 0.00t *00 2.291 4
- 6. Tit *07 80 99 0.00t*00 8.14t+07 2.01b07 0.00t*00 1.76t*06 0.00t*00 it Wu 1.178*01 2.19t*01 4.29t 42 0.00t+0D 3.?W +02 1.3?t+01 1.4 ft
- it.101 0.00t*00 0.00t+00 0.00t*00 0.00t+00 0.00t*00 0.00t+00 0.006*00 eu 103 4.2N e03 0.00t *00 1.6%t+03 0.00t*00 1.0M + 04 0.00t*00 1.11t+0$
su.105 3.42t.03 0.03t *00 1.39t.03 0.00t*00 3.34 02 0.00t+00 2.69t 00 tu.106 9.268+04 0.00t*00 1.111+ 06 0.00t+00 1.2$t+05 0.00t+00 1.664
- AG.11tm 2.09t+04 1.61t+0B 1.1M
- 06 0.00t+00 2.Mt48 0.00t*D0 1.6At*10 13 125m f.3444f 2.00t 47 9.66t
- 06 2.0Tt+0F 0.00E*00 0.00t 00 f.17t 41 11 12fu 2.00E+08 5.60s+07 2.4ft+07 4.9 ft *07 5.934+08 0.000+00 1.6at+04 11 127 2 vet +03 8.02t+02 6.1N e02 2.0M +03 6.4ft+03 0.00t+00 1.1M +05 13 12su 2.713 04 f.59t+07 4.21147 4.75847 7.97t+08 0.00l+00 3.31848 18 129 1.2M 09 3.$at.10 3.064 10 9. int.10 1.75t 09 0.00t*00 f.9M . 06 18 131a 1.60t
- 5.53t+05 5. 99t +05 1.14t +M l.35t+06 0.00t+00 2.26147 18 131 1.62312 4.FM 53 4. tit.13 1.26t.12 4.998 12 0.00t*00 4.69t.32 18 112 1.02t47 4.11E+M 1.64t +M 6.60t +M 4.21t*07 0.00t+00 4.lft+07 1 130 1.TM+M 3.49t +06 1.60t+06 3.66t+08 5.22t *M s.00E+00 1.tM +06 1 131 1.30t+09 1.31t+09 f.454 0e 4.134*11 2.1M 49 0,00t+00 1.171 06 1*1 12 6.D98 01 1.2ft+00 1.821 01 1.lft*01 1.94440 0.00E*00 1.49t +00 1 111 1.72R*07 2.12t 47 8.cM+M 3.kt49 3.54t+0F 0.00t+00 4.1M +06 1 114 8.64t.12 1. Sat.11 7.2%I.12 3.623 10 2.414 11 0.00t+00 1.044 11 1 135 5.60t +M 9.72t+M 4.60t+4 8.61t+06 1.49t 45 0.00t+00 f.40t+04 C$.154 2.2M *10 3.72t+10 7 kt+09 0.00t*00 1.15t+10 4.13t*09 2.00t+06 t$ 136 1.01t+09 2.6M +09 1.60849 0.00E+00 1.6M +09 2.21t+06 9.T7t 47 C1 137 3.22t*10 3.09t*10 4.5%449 0.00t+00 1.01t*10 3.62t+09 1.9 M *00
- Cs.134 3.9et.23 1.5M 23 1.11t.23 0.00t+00 3.99t.23 4.195 24 2.118 23 EA 139 2.01t.07 1.078 10 1,821 09 0.00t+00 9.5M.11 6.5M.11 1.1M 05
...........................+....................................................
Cerwoeottm f actere are in mile of eSere notee*aren/yr por itt/sec fee ett rution enom e.3.etcw is in mite ev aravre per $ctramic ==ter. Attachment 6.7 (8 of 12) UNT-005-014 Revision 0 14'l
'==-um .-
COW's MILE PATHWAY DOSE TACTORS DUE TO l RADIONUCLIDES OTHER THAN NOBLE GASESe R i AGt 640UPt tulL0 4 3 of 3 )
#JCLlDel DaCAs Dost COWWillite f attool Ocot LlWit 1.0001 1stt01D tibatt tue4 61 448 94 140 1.iFl*00 1.0M +M 6.kt*06 0.00t*00 3.344*06 6.12t*04 l.93047 64 141 0.00t+00 0.00t+00 0.00t+00 0.00t*00 0.00t*00 0.004 00 0.00t*00 p.142 0.008*00 0.00t*00 0.006*00 0.00t+00 0.00t*00 0.000 +M 0.00t*00 1
LA 160 1.kl*01 6.70t+00 2.11t+00 0.00t+00 0.00t+00 0.00t*00 1.cet*05 l La.142 8.10t.11 2.50s.11 8.004 12 0.00t+00 0.00t*00 0.00t
- 00 S. tit M '
Clai41 2.19t*04~1.Det*04 1.Mt+03 0.00t*00 4.fot +M 0.00t*00 1.ht *07 Ct.163 1.875 02 1.0M*05 1.47t+01 0.00t+00 4.2M 41 0.00E*00 1.49t+06 CI.144 1.621+06 1.005+0S 8.6M+M 0.00t40 2.42t*05 0.00t+00 1.3M+00 Pe*143 7.10t*02 2.1M *02 3.ht *01 0.00t*00 1.1Fl*02 0.00t*00 7.F5t+0S
................................................................................ l Pt.164 0.001+00 0.00s+00 0.00t+00 0.00f*00 0.00s*00 0.008+00 0.00s*00 up.147 4.459+02 3.60s 42 2.79841 0.00s+00 1.9et+02 0.00t*00 5. Tot +0S W.it? 2.08t+06 1.Tif+04 F.60t+03 0.00E+00 0.00t+00 0.00t*00 2.40t*06 eP 239 2.iM+02 1.llt+01 1.089+01 0.00t+00 4.60t 41 0.00t*00 1.15t+06 l
i Camerelen f acters are in units of espero setee.weWyr per dt/sec for all rustlese esceet 8 3 iAlsh is in mits of weWre per dt/ celt enter. ; I i l l Attachment 6.7 (9 of 12) UNT-005-014 Revision 0 j
- I 144 l
..m. , . , - _ . . _,, , - , _ . . _ . _ . _ , . , . . . . _ . ~ . _ . , _ , _ _ . _ _ . _ . - , - . , . . _ . . , , . , _ . , _ _ . . , , _ , _ _ _ , , .
1 l l i C0k" s MILK l'ATHWAY DOSE TACTORS DUE TO RADIONUCLIDES OTHER THAN NOBLE GASES, Ri , t At.t IApi inf ant ( 1 Op 3 3
- l
#JCLIPs te(.ta Dest etuvtaliom sat 1as !
f 1:19010 sitiet t tvus st.its bout tivte 1.tet e.) 0.00t*00 t.30t 43 I.50t*03 I.30843 f.30t 43 2.34f 43 2.30t 43 t.14 2.34t
- M l.00t+04 1.00t+08 l.00t*06 1.00t+06 1.00t+0E l.00t+t4 haele 1.548+07 1.54847 1.54i+07 1.54447 1.544 4 ? 1.54441 1.540+0f P 32 1.60t+11 9.4M
- W 6.It t +M 0.00t*00 0.00t+00 0.00t+00 f 4.17t *M Forde Coal 1 0.00t+00 0.00t*00 1.61t *M 1.Mt + M t.3M 46 2.Mf +M ,
as 54 0.00t 40 3.90t47 4.Ml+06 0.00t+00 4.64t*06 0.00t+00 1.6M47 ; sue.le 0.00t+00 3.14t 42 S.428 03 0.00t*00 2.70t.02 0.00t*00 2.8Sf*00 i fiell 1.35t+04 8 FM+07 f.3M47 0.00840 0.00t +00 4.tFt+07 1.11847 Pt49 2.241 00 3.9M*08 1.54t+08 0.00t*00 0.00t+00 1.16t+0s 1.87t*04 CO 58 0.00t+00 2.42147 6.0H+07 0. cot +00 0.00t+00 0.00E+00 6.06847 00 60 0,00t+00 8.Mt+07 2.00E*00 0.00t*00 0.00t+00 0.00t+00 2.10t+08
#1 63 3.49t*10 2.16t +M 1.21t*M 0.00140 0.00t*00 0.00E+00 1.0?t+08 81 69 3.50t*00 3.971 01 1.00t 01 0.004 40 0.00t+00 0.00t+00 3.0M 41 CU H 0.00t+00 1.Mt 45 8.let +M 0.00140 3.14t *M 0.00t*00 3.81t*06 2e el $.lM*M 1.90t+10 8.70t*M 0.00s+00 9.238+0e 0.006+00 1.61t+10
.........................................................i......................
Za 69
' 2.0M.11 3.63t.11 2,7st.12 0.00t+00 ~ 1. lit 11 0.00t+00 2.9M.09 M 83 0.00s+00 0.00t+00 1.1N.01 0.Sta40 0.00540 0.005+00 0.001 4 0 Mak 0.00t 40 0.00t*00 1.li,t.23 0.00E*00 0.00t+00 0.000+00 0.00t+00 Sr.04 0.00t+00 0.Jel+00 0.0st+00 0.001 00 0.00t+00 0.00540 0.00t+00 00 06 0,out*00 2.238+10 1.10e+10 0.est+00 0.008+00 0.008*00 1.00548 09 08 0 faI+00 0.u0t+00 0.08840 0.00t+00 0. gee +00 0.00t+00 0. Set +00 !
+ 00.M 0.ast+00 0.00t40 0.00t+00 0.000+00 0. tee +00 0.00E+00 0.00f*00 se.M 1.3M+10 0.00540 3.61t*05 0.00t+00 0.08t+00 0.00t+00 2.5M 08
- p.90 1.3M*11 0.00l*00 3.10E*10 0.00t+00 0. Dot +00 0.00t+00 1lM*M i
M.t1 2.12E +M 0. cot +00 9.BM 43 0.00t+00 0.00t+00 0.00t+00 3.7Ii*M u.92 4.Mt+00 0.00t+00 1.FM*01 0.00t+00 0.00t+00 0.00t+00 5.00:41 Y.90 6.81542 0.00t+00 1.838+01 0.008+00 0.000*00 0.008+00 9.41t+0S
....................................................................+. *..**....
t41n 1.67t 19 0.00E+00 1.93t.30 0.00t 4 0 0.00E 40 0.0er+00 1.0M.15 V41
-7,3M*04 0.00t+00 1.9M+03 0.00t+00 0.00t+00 0.0st+00 5.25t+06 f.92 S.30t 04 0.08t+00 1.518.M 0.00t*00 0.000*00 0.00E*00 1.0M +01 Corwersten f acters are in wits of essere astee.aren/ye por utt/sec for all itallass oncept 0 3 selch le in mite of aren/yf por WCl/ celt aster.
I Attachinent 6 *7 (10 of 12) UNT-005-014 Revision 0 145-
Cff a MILE PATINAY DOSE EACTORS DUE TO RADIONUCLIDES OTHER TilAN N0liLE GASES, R3 Af.! GROUP: lbfA41 ( 2 0F 3 ) WuftlDt fsLAs Dolt tauvill10h $&Ct($$ Dokt k lVtt 1.6@T tutt01D tt0sti tuuG Gl.LLI
, 1 93 2,iM *00 0.00t*00 S.671 02 0.00t*00 0.00t*00 0.00t+00 1.70t*04 28 9% 6. tM +f J 1.6M*03 1.1N
- 03 0.00t*00 1.79t +03 0.00t*00 4.26t*05 24 97 6.06t*00 6.fM.01 3.184 01 0.00t*00 7.0M .01 0.004 00 4.4$t
- ht 95 S .9M *05 2.44t +M 1.418 05 0.00t.00 1. 75t *M 0.00t*00 2.0M
- 06 mo 99 0.00t+00 2.0N
- 06 4.0M *07 0.00t*00 3.11t*06 0.00t+00 6.85147 ft.9eu 2.75t+01 1.671+01 7.30t42 0.00040 6.10t*02 2.9et*01 1.61t*04 10 101 0.00t+00 0.00t+00 0.00t+00 0.008 40 0.00t+00 0.0M
- 00 0.00t*00 89 103 8.67143 0.00t+00 2.90t+01 0.00f+00 1. tot *04 0.00t+00 1.0$t +M bu.105 4.0M 03 0.00t+00 2.718 03 0.00t*00 5.928 02 0.00t+00 3.2M+00 su. t h 1.90t +M 0.00t40 2.3et
- 0.00s+00 2.258 *M 0.00t*00 1.448 *W AG.110pt 3.ht +M 2.42t *W 1.tM 48 0.00t+00 4. 0M *08 0.00t+00 1.4et*10
- 1I 12Ss 1. lit *0s 5.068+0? 2.06447 1.0M47 0.00t*00 0.00s+00 7.1M +07
...............................................+.................***...*.....*..
ft.127m 4.21t+06 1.60 48 $.10t*07 1.228 08 1.064 *M 0.00t*00 1.7M*04 TE.127 6.32t+03 2.12t*03 1.ht +03* l.16E43 1.56t*04 0.00t+00 1.3M +M ft.12su 5.lM +08 1.91t+04 8.54t47 2.16t+0s 1.HE* M 0.00t+00 3.3M*08 it.129 2.728.M 9.371 10 6.354 10 2.20t. M 6.TM* M 0.00t+00 2.175 07
. ft.131u 3.38t*06 1.3M*06 1.12t+06 2.7M+M 03M+06 0.00t+00 2.Nt+0?
'ft.131 3.4M 32 1.275 32 9.62t:33 3.06t.33 4.7M.32 0.00t+00 1.Mt.30 ft.132 2.11t+07 1.044*07 9.7M+06 1.54447 4.lM47 0.00t+00 3.87t+07 1 130 3.5M+06 7.81846 3.1M+06 8.75t+08 4.let+M 0.00t+00 1.6?t *H 0.00t+00 1.14t+08 3 131 2.72E+09 3.20t*W 1.41t*M 1.0M *12 3.76t *M 1 132 1.4M+00 2.90t+00 1.0M+00 1.3et+02 3.24t*00 0.00t+00 2.35t+00 1 133 3.63t+07 S.2eE 4 7 1.55t+0? 9.60t+09 6.21847 0.0c?*00 8.tM*N 1 134 1,768.'1 3.601 11 1.208 11 8.488 10 4.0M.11 0.00t+00 3.7M.11
[}}