ML20070E346
| ML20070E346 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1990 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-2371, NUDOCS 9103050390 | |
| Download: ML20070E346 (238) | |
Text
I901 Chouteau twerum Pos! O!W Box 149 b St Iouh. M:swwi 62166 314 554 2560 UNION Euicnuc February 27, 1991 CT """"
g U.S. Nuclear Regulatory Commission Attn- Document "ontrol Desk Mail Stop Pl-13'i Washington, D.C. 20555 ULNRC-2371 Genticmon:
DOCKET NUMBER 50-483 CALLAWAY PLANT SEMIANNUAL ' RADIOACTIVE EFFLUENT PZLEASE REPORT The enclosed semiannual Radioactive Effluont Release Report for the second half of 1990 is submitted pursuant to Section 6.9.1.7 of the Callaway Plant Technical Specifications.
If there are any questions relating to this information, please contact us.
Very truly yours,
$ tty Donald F. Schnell BFH/sla Enclosure h
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9103050390 901231
_PDR ADOCK 05000483 R PDR 3
4 cc:. T. A. Baxter,.Esq.
Shaw, Pittman, Potts & Trowbridge
, 2300 N. Street, N.-W.
Washigton, D.C. 20037 Dr.. J. O. Cormak CFA, Inc.-
4' Professional Drive (Suito 110)-
Gaithersburg,- MD 20879 ,
R. C. Knop s Chief, Reactor Project Branch 1 V U.SL.-_ Nuclear _ Regulatory Commission Region III 799 Roosevelt Road Glen'El' lyn, Illinois 60137
'Bruco Bartlett Callaway Resident Office U.-S. Nuclear' Regulatory Commission RR$1 Steedman, Missouri 65077 M. D. Lynch- -
Officc~of Nuclear Reactor Regulation F{
l U.S. Nuclear Regulation Commission L
.1 White Flint, North, Mail Stop 13E21
- 11555 Rockville Piko Rockville,-MD 20852 L . Manager, Electric Department L Missouri Public Service Commission l -PO BoxE360
~Jofferson City, MO 65102-E . William Kosler Regional-Administrator l Dopartment of Natural Resources-L ' Central Regional. Office
-PO_ Box 176 Jefferson City, MO 65102
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Release Report .
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SEMIANNUAI. RADI0 ACTIVE EFFLUEbNI REIJASE REPORT CAIAAWAY NUCLEAR PLANT UNION ELECTRIC COMPANY 1ICENSE NPF - 30 JULY - DECEMBER 1990 -
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I TABLE OF CONTENTS I
1.0 INTRODUCTION
2.0 SUPPLEMENTAL INFORMATION 2.1 Regulatory Limits 2.2 Maximum Permissible Concentrations 2.3 Average Energy 2.4 Heasurements and Approximations of Total Radioactivity 2.5 Batch Releases 2.6 Abnormal Releases 3.0
SUMMARY
OF GASEOUS RADICACTIVE EFFLUENTS 4.0
SUMMARY
OF LIQUID RADIDACTIVE EFFLUENTS 5.0 SOLID WASTES S!!IPMENTS 6.0 RELATED INFORMATION 6.1 Unplanned Releases l
6." Changes to the Process Control Program 6.3- Changes to the Offsite Dose Calculatior Manual
, 6.4 Major Changos to Radwaste Treatment Sy: tems 6.5 Land Use Census Changes 6.6 I 7.0 Inoperability of Effluent Monitoring Instrumentation METEOROLOGICAL DATA 8.0 ASSESSMENT OF DOSES 8.1 Dose at the Site Boundary and Nearest Residence From Gaseous Effluents
-I 6.2 Dose to the MEMBER OF Ti!E PUBLIC from Activities Within the SITE BOUNDARY E 8.3 Total Dose Due to the Uranium Fuc t Cycle 8.4 Dose Due to Liquid Effluents
I Table 1A Semiannual Summation of Gaseous Releases Table IB Semiantiual Airborne Continuous and Batch Releases Table 2A Semiannual Summation of 1.1guld Releases Table 2B Semiannual Idquid Continuous and Batch Releases Table 3 Solid Waste and Irradiated Fue' niipments Table 4 Curaulative Joint Frequency Dlutributions Table 5 Dose at the SITE BOUNDARY and Nearest Resident Table 6 Dose to the MEMBER OF THE PUBblC from Activities within the SITE BOUNDARY Table 7 Total Dose Dae to the Uranium Fuel Cycle Table 8 Dose Due to 1.1guld Effluents i
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1 1.0 IKfR0_DQCTl_0N I In accordance with the requirements of Collaway Plant Technical Specification 6.9.1. 7, Union Electric Company herewith submits its Semiannual Radioactive Effluent Release Report for the Calloway Plant. This report covers the period from July 1, 1990 through December 31, 1990.
The format of the report conforms with Appendix B of Regulatory I Guide 1,21, Revision 1, June 1974.
and gaseous effluents, and solid waste quantitles released from the plant are included within the report.
Summarios of radioactivo 11guld All 11guld and gaseous offluents discharged during this reporting period were in compliance with federal regulations and the limits of Union Electric's procedurn APA-ZZ-01003.
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-i 2.0s i SUPPLEMENTAli INFORMATION
' < ? 2.1'- b ulatory Limits--
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' Specified as; Lfollows are .the APA-ZZ-01003, Section -9 limits applicable to. the-; release of radioactive material in: liquid -and ,
fgaseous effluents.- '
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- 2;1.13 Fission and Activation Gases (Noble Gases) s
, The dose-- rste due to radioactive noble gases released in gaseous
, . of fluents, from - the site to areas _ at and beyond the site boundary l
- shal1~ 'be L11mited to'.less than or equal to 500 mrem /yr to the total !
body;and-less than.or equal to 3000 mrem /yr to the skin. t y*. , . ..
i M- The air dose due to noble gases released in' gaseous offluents, from r
each unit. to areas at and beyond the' site boundary shall-be limited cg =to tho'following0
'a., During - any : calendar : qua rte r: Lest, than or equal to 5 mrad for
.: gamma raalation_ cnd less then. or -equal to 10 mrad for . beta
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' 1 b,, (During any'. calendar year: Less than or ' equal to l'0 mrad = for- !
. gamma : radiation and-less- than' or equal to 20 mrad for beta -
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, 4 1i2l :Radioiodine, Tritium, and Particulates 1
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. The i dos e rate- due to LIodine 131: and-- 133, . tritium and .all iradionuclides in particulate. form with half lives greater than eight i
o, ,. t ((8): days released lin gaseous' effluents from the site =to areas at and i beyond the' site-boundary shall bo' limited to'less than or equal'to
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1 Th Mdose to.a member of the public from Iodine-131 and;:133, tritium,- )
- andi all; radionuclidesninL particulate form withs half-lives? greater -
$. (th'an "eight L (8) Edays in gaseous effluents released to = areas _ at and
- beyond tho' sitec boundary shall be limited to Lth'e following:
y , a Ja? -During any calender qu'artert. Loss than or equal.to 7,5 mrom to rany organ--and,- ;
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During any cnlnndnr ynar: hons than or equal to 15 mrem to any- ,j
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6 2.1.3- Liquid Effluents "he concentration of radioactive material released in- ~ liquid t.ffluents to unrestricted areas 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 concentratlon shall be limited to 2.0E-04 microcuries/ml total activity.
The dose or dose commitment to an Individual from radioactive materials in liqu ic' effluents released to unrestricted areas shall be limited:
- a. During any-calender quarter to less than or equal to 1.5 mrem to the total body and less than or equal to 5 mrem to any organ, and
- b. During any calendar year to less than or equal to 3 mrom to the whole body and to Ices than or equal to 10 mrem to any organ.
~2.1.4 Uranium Fuel Cycle Sources The annual (calendar year) dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limite/ - less than or equal to 25 mrom to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem, 2.2 piaximum' Permissible Concentrations 2.2.1 - The maximum pernissible concentrat. ton values specified in 10CFR20, Appendix P, Table II, Column 2 are used to calculate release rates 4_
and perrissible concentrations of liquid radioactive effluents at the unrestricted area boundary. A value of 2.0E-4 microcuries/ml is used as the MPC for dissolved and entrained noble gases in 11guld l effluents.
- 2. 2. 2 -' For gaseous - ef fluents, maximum permissible concentrations are not utilized in release rate calculations since the applicable limits are based on dose rate at the unrestricted area boundary. The
" Percent of Tech Spec Limit" for Table 1A is therefore not applicable to the Calloway Plant.
1 2.3 '_ Average Energy This is not applicable to the Callaway Pinnt's radiological effluent
- technical specifications.
2.4 Measurements and Approximations of _ Total Radioactivity The quantification of radioactivity in 11guld and gaseous effluents was accomplished by performing the sampling and radiological analysis of effluents in accordance with the requirements of Table 9.3-A and Table 9.6-A of APA-ZZ-01003, Offsite Dose Calculation Manual.
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Gamma spectroscopy was the primary analysis technique used to determine the radio' uclide composition and concentration of ' liquid
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and gaseous effluents. Composite samples were analyzed for Sr-89, Sr-90, and Te-55 by an independent. laboratory. Tritium and alpha were measured for both 11guld and gaseous effluents using 11guld scintillation counting and gas flow proportional counting techniques, respectively.
The total radioactivity in effluent releanes was determined from the measured concentrations of each radionuclido present and the total volume of effluents discharged. Gross beta or gamma radioactivity measurement techniques were not utilized to approximate the total radioactivity in effluonts.
2.5 Batch Releases 2.5.1 Jdqu151 Nutc.ber of batch releases: 95 Total time period for batch releases: 30,899 minutes Maximum time period for a batch release: 635 minutes Average time period for batch releases: 325 minutes
.,. . Minimum time period for a batch release: 1 minute Average stream flow during periods of release of effluent .into a flowing stream: 53,040 cfs*
- Re f: Letter, United States Department of the Interior - Geological Survey-- Missouri, dated January 18, 1991.
2.5.2 Gaseous Total for the Rcporting Period Number of batch releases: 59 Total time period for batch releases: 84,588 minutes Maximum time period for a batch release: 10,415 minutes Average time pnrind for batch relensas: 1,'434 minutes-
-Minimum time period for a batch relenae: 41 minuten 2.6' Unplanned Releases 2.6.1 Liquid Number of releases: 0 Total Activity released: 0 1 4 L______________.______________. _ _ _ _ _ _ __ . . . _ . . . _ . . . . _ . _, __ , _ _ ~ _ _ _ __ . _ _ .
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- 2;6.2- Gaseous Number of releases: 1 Total Activit; teleased: 9.0E-05Ci 3.0-
SUMMARY
0F GASEOUS RADIOACTIVE EFFLUE_NIS-
'3.1 The quantitles of radioactive material released in gaseous effluents are summarized in Tables 1A and IB. Note that for this reporting >
period.no gaseous effluents were considered as clovated releases.
4.0
SUMMARY
OF LIAUID RADI0 ACTIVE EFFLUENTS 4.1 The_quantitles of radioactive material released in 1Iquid offluonts-are summarized in Tables 2A and 28.
5.0 SOLID WASTES 5.11 The quantities' of - radioactive material released in shipments of ,
solid waste and irradiated fuel transported from the site during the '
reporting period are summarized 11 Table 3. The activity and-fractional abundance of each nuclide was determined for each waste type by an independent laborar.ory based upon radiochemical analysis of samples of that waste type. The curie amount of each nuclide listed in-Table 3 was determined as the product _of-the fractional abundance and the total curies shipped. Those nuclides which -
comprise at least 17. of the total activity for a particular . waste
. type are presented in Table 3.
5.2- All dry compressible _ waste, contaminated equipment.,- etc. was shipped to reprocessing f acilities for supercompaction, decontamination, or incineration.. "Other" . wastes shipped off-site consisted of contaminated oil which will be -incinerated by a vendor to achieve
= volume reduction. Final burial ' volumes after reprocessing.elli.be reported at a later date, j 6.05 RELATED INFORMATION i 6.1 - ~ Unplanned Releases Unplanned- releases are: 1) Inadvertent or accidental releases o _f radioactive material; 2) Rnleases of radioactive material via normal pathways.without a release permit, proper authorization, or proper sampling and analysts; nnd 3) Releases which are conducted in such a manner as to result in significant deviation f rom the requirements of the release permit.
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There was one unplanned release during the reporting period.
On October 2, 1990, the auxiliary boiler was sampled and found to be contaminated, Isotopic analysis indicated that.1-131_was present at a concentration. of 2,4E-8 pC1/ gram and Xe-133m was present at a concentration of 8,3E-8 pC1/ gram.
The plant operations department was notified immediately to ensure that area drains and boiler blowdown were routed to the liquid radwaste' system. Attempts were also made to remove- the contamination by blowdown, however very low levels of I-131 still remained.
A 100FR50.59 evaluation was initiated immediately along- with - an investigation to determine the source of the activity which had concentrated in the auxillary boiler. It is belicved that this contamination . originated f rom a small leak.in the liquid radwaste evaporator, although a specific source could not be identified.
To assure that no of fsite dose limits would . be approached with continued' operation of the auxillary boiler during Refuel 4, a conservative dose calculation was performed. The dose rate at the >
. site boundary was calculated to be 7.5E-4 mrom/ year to the critical organ. The dose rate .to a member of the public from this release was calculated to be 7.5E-3 mrem for the critical-organ.
The safety evaluation reviewing this event was documented In Request for Resolution (RFK) 08547 Rev..A. This event was also described by Suggestion Occurrence Solution (SOS) 90-1899.
6,2 .Channes tt .he Process Control Program There were no changes to the PCP during the reporting period.
6.3 Changes ' to the of fsite Dose !C alculation' Manual i
Revision 1. of APA-ZZ-01003, Offsite Dose Calculation Manual- was approved October 8, 1990. This revision Incorporated Amendment 20 to the-- Callaway Plant Operating License which revised Action ,
-Statement 41 of Table 9,2-A for GT-RE-22/GT-RE-33_ Containment Purge '
Monitors to allow continued purging for_24 hours with the number of channels operable one less than the minimum _ required.
L A complete - copy o f APA-ZZ-01003, Of fsitn Dose Calculation Manual, Rev. 1 .is included as Attachment 1-.
6i44 Maior Changes to Radwaste Treatment Systems During the. period f rom July _ - December 1990, there_were no changes-to the plant which could be considered a major change to a Liquid, Gaseous, or Solid Radwaste Treatment System.
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6.5 Land Use Census Changes There were .no changes in critical receptor locations for dose calculations during the reporting period.
6.6 Jnoperability of Ef f h" . tionitoring instrumentation All effluent monitori instrumentation was OPERABLE within the limits specified by APA-ZZ-01003, Sections 9.1.1 and 9,2.1, during the reporting period.
7.0 METEOROLOGICAL DATA Meteorological data for t.he reporting period is presented in Table 4 as Cumulative Joint Frequency Distributions for both 10 and 60 motor elevations.
8.0 ASSESSJ1EtH_OF_ DOSES The assessment of doses to the maximum exposed individual from Gaseous and Liquid offluents was performed for locations representing the maximum dose. In all cases, doses worn wnli below Technical Specification l im it s .
8.1 Dose at the SITE BOUNDARY From_G_aseous Effluen_ts An assessment of doses from gaseous effluents was performed in accordance with the Callaway Plant ODCt! for the maximum exposed individual at the SITE BOUNDARY location with the highest ground level concentration of radioactive material, based upon actual meteorological conditions existing during the year. Doses were assessed at each location considering the noble gas submersion inhalation and ground plane pathways. This assessment was performed for each age group, with the Child age group receiving the highest dose.
Th calculations for the SITE BOUNDARY location conservatively assumed a hypothet ical maximum exposed individual. The results of the assessment for the Child age group are presented in Table 5.
8.2 Dose at the Nearest Residence lrom_ Gaseous _FfD e uen_ts An assessment of doses from gaseous effluonts was pnrformed in accordance with the Callaway Plant ODCt1 for the maximum exposed individual at the Nearest Residence location with the highest ground level concentration of radioactive materini, based upon actual meteorological conditions existing during the year. Doses were assessed at each location considering the noble gas submersion, inhslation, ground planc, and ingestion pathways. The ingestion pathways considered were the produce, vegetable, goat's milk, cow's milk, and meat pathways. This assessment was performed for the Child age group.
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The results of the assessment for the Child age group are presented in Table 5. The calculations for the Nearest Residence are for a "real" individual. It is conservat ively assumed that nach ingestion pathway exists at the Nearest Residence location, and that the Child age broup exists at each location.
8.3 Dose to the MEMBER OF Tile PUDhlC f: Activities Within the SITE BOUNDAR1 The assessment of dose to the MEMBER OF TliE PUBLIC from activities within the SITE BOUNDARY was performed in accordance with chapter 4 of the Callaway Plant ODCh. The dose to the MEMBER OF Tile PUBhlC from activities within the SITE BOUNDARY is presented in Table 6.
8.4 Total Dose Due to the Uranium Fuel Cyc_le Since there are no other Uranium Fuel Cycle facilities within 8 km of the Callaway plant, the total dose to the most likely exposed MEMBER OF THE PUBLIC results from direct radiation and radioactive effluents from the C a l l ow..y Plant. The methodology for assessing this dose is described in Chaptar 4 of the Callaway Plant ODCM.
. The Total-Dose from the Uranium Fuel Cycle was evaluated for the MEMBER OF THE PUBLIC who may use portions of the area within the SITE BOUNDARY for purposes not associated with plant operations.
The Total Dose to the MEMBER OF THE PUBhIC (Table 7) is the sum of the dose due to activities within the SITE BOUNDARY (Table 6) and the dose due to gaseous effluents at his residence (Table 7). The food ingestion pathways do r exist at the residence locatien.
The Total Dose at the Nearest Residence is dun to the dose f om gaseous effluents, assuming that each food inges t ion pathway ex'.sts at this location (Tabic 5).
In each case, the whole body gamma dose from Noble Gases and ground plane exposure is added to the organ dose f rom - the inhalation and ingestion pathways.
The Total Dose from the Uranium Fuel Cycle is presented in Table 7.
8.5 Dose Due to Liquid Effluonts The total done to the maximum exposed individual from liquid effluents released from the Calloway Plant during the year is presentod in Table 8.
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TABLE 1A i
SEMIANNUAL SUMMATION OF GASEOUS RELEASES l.
ALL AIRBORNE EFFLUENTS QUARTERS 3 AND 4, 1990 UNIT THIRD FOURTH EST TOTAL TYPE OF EFFLUENT QUARTER QUARTER ERROR %
A. FISSION AND ACTIVATION GASES
- 1. TOTAL RE. LEASE CURIES 5.61E+02 4.01E+01 20 I
2- , AVERAGE RELEASE RATE FOR PERIOD uCi/SEC 7.05E+01 5.05E400
- 3. PERCENT OF TECH SPEC LIMIT % N/A N/A B.. RADICIODINES
1. TOTAL IODINE-131 CURIES 1.35E-05 ?.57E-05
- 2. AVERAGE RELEASE RATE OF PERIOD uCi/SEC 1.70E-0G 3.23E-06 3 PERCENT OF TECH SPEC LIF IT % N/A N/A
- C..PARTICULATES
-1. . PARTICULATE (HALF-LIVES ^> 8 DAYS) CURIES 1,23E-07 2.39E-06 30 2.; AVERAGE RELEASE RATE OF PERIOD uCi/SEC 1.55E-08 3.01r.-07
- 3. PERCENT-OF_ TECH SPEC' LIMIT % N/A N/A
'4.. GROSS ALPHA' RADIOACTIVITY CURIES 7.45E-07 1,18E-06 g .D.3 TRITIUM
- 1.-TOTAL-RELEASE CURIES. 7.88E+00 1.53E+01 14 2.' AVERAGE
.'.---.. ..______.____- RELEASE RATE _.. FOR _ PERIOD ._. ._ _.uCi/SEC. .--.. 9.92E-01 1.93E+00 L 3:.3 PERCNT -1 N/A N/A
. .. ._.___OF-TECH: SPEC-LIMITL _________-- ._...___.
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l TABLE IB SEMI ANNUAL AIRBORNE CONTINUCUS AND BATCH RELEASES GROUND LEVEL RELEASES FISSION GASES, IODINES, AND PARTICULATES QUARTERS 3 AND 4, 1990 CONTINUOUS RELEASES DATCH RELEASES THIRD FOURTH THIRD FOURTH NUCLIDE UNIT QUARTER QUARTER QUARTER QUARTER
- l. FISSION GASES Kr-85M CURIES 8.60E-01 4.89E-02 1.53E-02 0.00E+00 Kr-85M CURIES 0.00E+00 0.00E400 3.86E+00 4 . 01 E4 00 Kr-87 CURIES 0.00E400 0.00E+00 6.95E-05 0.00E400 Er-SS CURIES 1.20E-01 0.00E40n 0,000400 0,00E.00 Xe-131M CURIES 0.00E+00 0.00E4 00 3.9GE+00 1.65E-01 Xe-133 CURIES 9.06E+01 1.76E400 4.360+02 3.28E&01 Xe-133M CURIES 0 00E+00 0.00E400 4.63E400 0.00Ei00 Xe-135 CUR 1ES 75E401 1.32E+00 2.51E+00 8.44E-u4 Xe-135M CURIES s.00E+00 0.00E400 0.000+00 0.00E+00 Xe-138 CURIES 0.00E+00 0.00E+00 0.00E400 0.00E400 Ar-41 CURIES 0.00E+00 0.00E+00 0.51E-01 2.68E-02 TOTAL FOR PERIOD CURIES 1.09E+02 3.13E+03 4.52E+02 3.70E+01
- 2. IUDINES I-131 CURIES 5.16E-06 9.80E-06 8.36E-Oc 1. 5 9 E- %
I-132 CURIES 0.00E+00 0,00E+00 7.63E-0; 0.00E CO I-133 CURIES 3.68E-08 0.00E400 5.24E-07 0.000,00 I-135 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 TOTAL FOR PERIOD CURIES 5.20E-06 9.80E-06 9.65E-06 1.59E-05
- 3. PARTICULATES CO-57 CURIES 0.00E+00 0.00E400 0.00E+00 2.91E-10 Co-58 CURIES 1.18E-07 S.26E-07 0.00E+00 1.S4E-06 CO-60 CURIES 0.00E+00 0.00E+00 0.00E400 1.27E-08 Sr-89 CURIES 0. 00E4 00 0. 00E+ 00 0.00E+00 0.00E+00 Sr-90 CURIES 5.32E-09 1.15E-OS 0.OnE+00 0.00E4 00 Cs-134 CURIES 0.00E+00 0.00E+00 C 00E+00 0.000 00 Cs-137 CURIES 0.00E+0C 0.uGE*00 .u0E+i"> u.00L e Co-141 CURIES 0.00E+00 0.00Et00 . 0 ?E + N 0 ?E G ALPHA CURIES 4.4GE-07 2.01E-07 2 ME-07 9.83E-05 TOTAL FOR PERIOD CURIES F.09E-07 7.39E-07 2.E9E-07
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SEMIANNUAL SUMMATION -OP LIQUID RELEASES ALL LIQUID EFFLUENTS QUARTERS. 3 AND 4, 1990 THIRD FOURTN EST TOTAL
. TYPE OF EFFLUENT UNIT QUARTER QUARTER ERROR %
A. FISSION-AND ACTIVATION PRODUCTS I. TOTAL RELEASE (NOT' INCLUDING '
. TRITIUM, GASES, ALPHA) CURIES 5.40E-03 3.25E-02 20
, 2.--AVERAGE-DILUTED ~ CONCENTRATION I DURING PERIOD uCi/ML 1.49E-08 1.17E-07
=3. PERCENT OF APPLICABLE LIMIT % N/A N/A B.; TRITIUM-
- 1. TOTAL RELEASE CURIES 1.55E+02 1.07E+02 14 1 2.oAVERAGE= DILUTED CONCENTRATION DURING PERIOD .uCi/ML 4.2BE-04 3.85E-04
= 3 L PERCENT - OF APPLICABLE _ LIMIT % N/A N/A )
- C. DISSOLVED AND ENTRAINED GASES '
1.-TOTAL RELEASE CURIES 1.43E-01 3.47E-02 27 12',; AVERAGE DILUTED CONCENTRATION DURING-PERIOD ; uCi/ML 3.96E-07 1 ~. 2 5 E-07 l
- D~<. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE . CURIES 4.03E-O'4 4.19E-04 29 LE. WASTE VOL RELEASED (PRE-DILUTION) GAL 4*57E+06 3.55E+06-- 10 F.. VOLUME OF DILUTION = WATER USED GAL 9.09E407 6.99E*01 10 t-i- PAGE.1.OF. 1 '
TABLE 2B
=
_ SEMIANNUAL LIQUID CONTINUOUS AND BATCH RELEASES TOTALS FOR EACH NUCLIDE RELEASED QUARTERS 3:AND 4, 1990 NUCLIDE -CONTINUOUS RELEASES-BATCl! RELEASES THIRD FOURTH THIRD FOURTH
.ALL NUCLIDES UNIT QUARTER QUARTER QUARTER QUARTER H-3 CURIES 0.00E+00 0.00E+00 l'. 5 5E+ 0 2 1.07E+02 Na-24' -CURIES 0.00E+00 0.00E+00 0.00E+00 0.00Et00
-Rb CURIES 0.00E+00 0.00E+00 0.03E+00 0.00E+00 "
.Cr-51 CURIES- 0.00E+00 0.00E+00 6.16E-04 5.55E-03
'Mn-54 CURIES -0.00E+00 0.00E+00 -3.74E-04 2.23E-03 Po - 5 5 ' CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 CURIES- 0.00E+00 0.00E+00 3.36E-05 4.13E-04
.Co-57 D CURIES 0.00E400 O'.00E+00 0.00E+00 0.00E+00 Co-58'- CURIES 10.00E+00 0.00E+00 2.00E-03 1.52E-02 Co-60 = CURIES 0.00E+00 0.00E400' 1.44E-03 4.77E-03 Zn-65 CURIES 0.00E+00 0.00E+00 0.00E+00 9.50E-05
..Sr-89 -CURIES 0.00E+00 0.00E+00 0.00E+00 5.48E-06 Sr-90 CURIES 0.00E+00 0.00E+00 0.00E+00 5.67E-06
'Zr-95 -CURIES - 0.00E+00 0.00E+00 9.65E-05 1.24E-03
'Nb-95 : CURIES 0.00E+00 0.00E+00 1.60E-04 2 . 0 */ E - 0 3 4
=Mo-99 CURIES- 0.00E+00 0.00E+00 4.30E-06 0.00E400 1 Tc-99M CURIES 0.00E+00 0.00E+00 4.30E-06 0.00E+00
'Ag-110M CURIES. O.00E+00 0.00E+00 0.00E+00.5.29E-0$ -
Csr134 CURIES- 0.00E+00 0.00E+00 - 2,33E-04-2.12E-04 '
Cs-136 CURIES 0.00E+00 0.00E+00 0.00E+00 0.00E400
.Cs-137 . CURIES 0iO0E+00.0.00E+00 2.84E-04 1.6SE-04 Ba-139 CURIES 0.00E+00 0.~00E+00 8. 41E-05 0. 00E4 00
<Sb-125 CURIES- 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Ce-144- CURIES 0.00E+00 0.00E+00 0.00E+00.1.13E-04 Su-113: CURIES . O.00E+00-0.00E+00 0.00E+00 1.17E-04 W-187 -CURIES 10.00E+00 0.00E+00- 0.00E+00 0.00E+00 H f-181'_ -CURIES 0.00E+00 0.00E+00 0.00E+00 1.59E-05 Ba-140 . CURIES 10. 00E+ 00: O . 00E+00 = . 9.36E-06;0.00E400
~I-131' CURIES-- 0. 00E+00: 0. 00E+00 4.87E-05 1.42E-04 I-132_- . CURIES .0.00E+00 0.00E+00 0.00E+00.0.00EiOO
.I-133J CURIES ~ 0,00E+00 0.00E+00 9.70E-07 0.00E+00-
_I-135 -
CURIES 0.00E+00 0.00E+00 0.00E+00-0.00E400 TXe-131M CURIES 0.00E+00 0.00E+00 7.95E-04 0.00E400
-Xe-133 CURIES O'.00E+00 0.00E+00 1. 4 0 E-01 3._4 D E-0 2
-Xe-133M- -- CU RI ES 0.00E+00-0.00E+00 1.55E-03 1.15E-04 -"
Xe-135~ 1 CURIES' O.00E+00 0.00E+00 5.13E-04 5.2SE-05 ;
JXe-135M CURIES 0.00E+00 0.00E+00 0. 00 C+ 00 : Oc00E 00'
- G: ALPHA - CURIES 0.00E+0C-0,00E+00 - 4.03E-04 4.19E-04
' UNIDENTIFIED CURIES 0.00E+00 0.00E+00 0.00E+'00
~
. .. . ..--___. . - . ... . -_ ___'O.00C600 LTOTALS ' FOR_ PERIOD CURIES ' . 0.00E+00-0.00E+00 1.55E+02 1.07L+02 PAGE 1 OF 1
'*gg mu r"*rf 3aJ' -
TABl.E 3 SOLID k'ASTE & 1RRADI ATED FUEL SillPMr.NTS QUARTERS 3 6 4, 1990 A. SOLID k'ASTE SilIPPED OFFSITE FOR BURI Al, OR DISPOSAL (DOES NOT INCLUDE IRRADIATED FUEL)
TYPE OF k'ASTE 6-MONTil EST. TOTAL
['ER I OD ERROR L%.)_
- a. Spent resins, filter sludges 12.7 m' 125%
evaporator bottoms, etc. 2.58E+2C1 P_ercent Ahndance Curies.
Co-60 26.196% 6,76E+01 Fe-55 23.615% 6.10E+01 Cs-137 18.095% 4.67E401 Ni-63 12.357% 3.19E+01 Cs-134 9.956% 2.57E401 Mn-54 7.630% 1.97E401 Co-58 1.247% 3.22E+00
- b. Dry compressible waste, 4S1.0 m' 125%
contaminated equipment, etc. 1.24El Ci Fe-53 46.371% 5.74E+00 Cc-58 22.239% 2.75E+00 Co-60 13.546% 1.68E+00 Nb-95 S 837% 1.09E+00 Mn-54 7.286% 8.89E-01 3 7.r - 9 5 1.820% 2.25E-01 Irradiated components, controi 0 m' Ic.
reds, etc. G Cl
- d. Other 0 m' O Ci Page 1 of 2
r l
1
- Solid. Vast e Dispqs._1.tjpn i Number of Modo of Class of Solid Typo.of !
Shipments .T.ran s po r t a t ion- postination Weste Shipped Container 1 Cask Richland, WA A t.S A> A '
2 Cask Barnwell, SC D LSA 4 Truck Oak Ridge, TN A LSA (QUADREX) 1 5 Truck Oak Ridge, TN (SEG) A LSA l
, 1 Solidification Anent Cement (applicable to waste type "a" only)
- B. IRRADI ATED FUE_L SHIPttENTS__ (DISPOSITIOJ1 Humber of Shipments Mode of Transportation Destinatiot! !
N/A N/A :
Page 2 of 2 i
..~c. - -,-.-,-.m . , _ . _ _ -_-.-.-m_. , .. - . . .. - - - - . ~ . _ . -_ _ . - -- - -
CADLE 4 CUMULATIVE JOINT FREQUENCY DISTRIDUTIONS '
)
' 1990 MIB PAGE 1 OF 1 Y
REPORT-CATEGORY t METEROLOGICAL. RAW DATA INPUTS. j TYPE OF ACTIVITY : HOUR AVERAGES FILE
- 1:00 HRS = 01:00AM JANUARY 1, 1990 !
= REPORT START TIME : 8759:00 HRS = 11:00PM DECEMBER 31, 1990 J
REPORT END T4ME i
- : ; 4 GOOD :
- UNIT : INPUT : DATA :
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .: . . . . .E . . . . . .: . . . 911 STABILITY CLASS
- A-G ,
- CM. : 2.04 E 02 : 931 PRECIPITATION :LANGLY/ MIN: 1.00E 00 : 0%
SOLAR RADIATION
- M/S : 2.20E 00 : 93% .
10.M LEVEL WIND SPEED : DEG i 1.90E 02 : 93%
" " WIND DIRECTION : 1.09E 01 : 93% :
" " WIND DIRECTION VARIABILITY : DEG
- DEG C : 1.39E 01 : 91% !
REFERENCE TEMPERATURE : 6.26E 00 : 93%
DEWPOINT : DEG C .
. . " . . . . " . . . . . . . . . . . . . . . . . . . . . . . . . . . .: M/S
. . . . . . . . .: . 3.30E. . . . 00 . . :-
. . . .91% ......
60 M LEVEL WIND SPEED : DEG : 2.01E 02 : 91%
" " WIND DIRECTION : 7.64E 00 : 914 WIND DIRECTION VARIABILITY : DEG
- DEG C : 0.00E-01 : 0%
" " DEWPOINT
- DEG C : 3.05E-01 : 91%
10 M - 60 M TEMPERATURE DIFFERENCE s
n
.l
+
.i.
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIDUTIONS 1990 MIC PACE 1 0F 7 REPORT CATEGORY : METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990 REPORT END TIME : 8759:00 HRS = 11:00PM DECFMBER 31, 1990 STABILITY CLASS : A ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL
- 1-3 1 4-7 : 8-12 13-18 : 19-24 : >24 : TOTAL :
N : 0.00E 1.00E 00 ; 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 t 1.00E 00:
NNE: 1.00E 00 : 1.00E 00 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00:
NE : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
ENE: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
E : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E 00:
ESE: 0.00E-01 : 3.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.00E 00:
SE : 0.00E-01 : 1.80E 01 : 5.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.60E 01:
SSE: 1.00E 00 3.00E 01 : 2.80E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 6.10E 01:
S : 2.00E 00 : 2.80E 01 : 4. 2 0E 01 : .1.70E 01 : 0.00E-01 : 0.00E-01 : 8.90E 01:
SSW: 1.00E 00.: 2.50E 01 : 3.50E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 7,30E 01:
SW : 0.00E-01 : 1.20E 01 : 1.80E 01 : 5.00E 00 : 1.00E 00 : 0.00E-01 : 3.60E 01:
WSW: 1.00E 00 : 8.00E 00 : 1.10E 01 : 2.00E OL : 3.00E 00 : 0.00E-01 : 2.50E 01:
W : 1.00E 00 : 5.00E 00 : 1.00E 01 : 8.00E 00 : 2.00E 00 : 0.00E-01 : 2.60E 01:
WNW: 3.00E 00 : 4.00E 00 : 1.60E 01 : 2.20E 01 : 2.00E 00 : 0.00E-01 : 4.70E 01:
NW : 2.00E 00 : 4.00E 00 : 8.00E 00 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 2.60E 01:
NNW: 0.00E-01 : 4.00E 00 : 8.00E 00 : 0.00E-01-: 0.00E-01 : 0.00E-01 : 1.20E 01:
TOT: 1.30E 01 : 1.43E 02 : 1.83E 02 : 8.30E 01 : 8.00E 00 : 0.00E-01 : 4.30E 02:
PERIODS OF CALM (HOURS): 0.000E-01 HOURS OF ItrVALID DATA : 1.000E 00
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MIC Pact 2 OF
- REPORT CATEGORY : METEROLOGICAL DATA. QUARTERLY TOTALS OF HOUks AT l-EACH WIND SPEED AND DIRECTION PER200 OF-RECORD- : QUARTER # ***
REPORT: START TIME
- 1:00 HRS = 01:00AM JANUARY 1, 1990
-REPORT:END TIME.
.: 8759: 00 HRS = 11:00PM DECEMBER 31, 1990 GTABILITY CLASS : B l ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL ,
4 7- 8 12 13-18 : 19 24 : >24 : TOTAL
- . 13 : :
H 'UO 00E.01': 1.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E.01 : 0.00E-01 : '2.00E c:
NNE: 0.00E.01 : 1.00E 00 : 1.00E 00 : 0.00E 01 : 0.00E-01 : 0.00E-01 : 2.00E :'
1.00E 00 : 1.00E 00 : 0.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.00E 00 NE EENE: 0.00E.01 :-0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E.01 : 0.00E.01-: 0.00E.]:
...............................................................................+
E :~1.00E 00 : 1.00E 00 : 4.00E 00 : 1.00E 00 : 0.00E.01 : 0.00E-01 : 7.00E ::
ESE: ~1.00E 00 : 7.00E 00 2.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.2?E 0.
SE : 1.00E 00 : 1;00E 01 : 6.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.00E 0'.
SSE:'4.00E 00 : 2.00E 01 : 2.80E 01 : 7.00E 00 : 0.-00E.01 : 0.00E.01 : 5.90E 01
.S' ~; 1.00E 00 .t 1.60E 01 : 2.00E 01 : 1.20E 01 : 0.00E.01 : 0.00E-01 : 4.90E 01 SSW: 0.00E.01 : l.70E 01 : 1.90E 01 : 8.00E 00 : 0.00E.01 : 0.00E.01 .: 4.40E 01 SW:: 3.00E 00--: 1.30E 01 : 2.00E 01 : 2.00E 00 : 0.00E.01 : 0.00E-01 : 3.80E 01
-WSW: 1.00E 00-: 8.00E 00 :-9.00E 00 : 2.00E 00 : 1.00E 00 : 0.00E.01 : 2.10E 01
- J1.00E 00 : 5.00E 00 :'7.00E 00 : 5.00E 00 : 2.00E 00 : 0.00E.01 : 1.50E :1 W
WNW: 'O 00E 01 : 7.00E 00':-8.00E 00 : 1.00E 01-: 0.00E.01 : 0.00E.01 : 2.50E OL NW : 0.00E 011: 8.00E 00 : l'.50E'01': 7.00E 00-: 0.00E 01 : 0.00E.01- : 3.00E 01:
1
- NNW: 0,00E 01L: 3.00E 00 :- 8.00E 00 : 0.00E.01 : 0.00E-01 : 0.00E-01 : 1.10E 0'.:
1.43E 02 : 5.70E 01 : 3.00E-00 -0.00E.01 : 3.35E 02.
TOT:-1.40E 01 : 1.18E 02
' PERIODS OF CALM (HOURS): 0.000E-01
- HOURS OF INVALID DATA
- 1.000E 00-
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS l
1990 MIC PAGE 3 0F 7 l l
l REPORT CATEGORY- : METEROLOGICAL DATA. QUARTERLY TOTALS'OF HOL'RS AT
- EACH WIND SPEED AND DIRECTION
- QUARTER # ***
~
PERIOD OF RECORD REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990 JREPORT END TIME : 8759:00 HRS = 11:00PM DECEMBER 31,-1990 STABILITY CLASS : C -
ELEVATION : 10 METERS l i
WIND SPEED (MPH) AT 10 METER LEVEL
- 1-3 : 4-7 : 8-12 : 13-18 : 19-24 : >24 : TOTAL :
N! :-0.00E-01.: 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 2.00E-0:: .
..NNE: : 7.00E 00 : 2.00E 00 : 1.00E 00 : 0.00E-01 0.00E-01 : 1.00E . ' .
--....'O.00E-01...........................................................................
NE : 1.00E 00 : 3.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.00E 00:
ENE: 0.00E-01 : 3.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 00:
E '.0.00E-01
- : 6.00E 00 : 1.20E 01 : 0,00E-01 : 0.00E-01 : 0.00E-01 : 1,30E 01:
1.70E 01:
2SE: 2.00E 00 : 1.00E 01 : 4.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 SE : -0.00E-01 :.1.50E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.50E 01:
SSE: 1.00E 00 : 6.00E 00.: 1.70E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.70E 01; S : .2.00E 00 : ic50E 01 t 2.10E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 : ,4.60E 01:
'SSW: 1.00E 00 :=1.60E 01 : 1.20E 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 3.30E 01:
.SW :- :- 1.40E 01 : 2.60E 01 : 3.00E 00 : 2.00E 00 : 0.00E-01 : 4.SOE 01:
......3.00E 00........................ _..... .................. ........................
- WSW: 0.00E-01 : 5.00E 00 1 9.00E 00 : 1.00E 00 : 2.00E 00 : 0.00E-01 : 1.70E 01:
W : 2.'00E 00 : 1.30E 01 : 1.30E 01 : 6.00E 00 : 0.-00E-01 : 0.00E-01 : 3.40E 01:
'WNW: 2',00E 00.: 4.00E 00 : 7.00E 00 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 1.60E 01 NW :'2.00E 00 :o2.00E 00 : 1.00E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 2.00E ; '. -
NNW: 0.00E-01': 9.00E 00 : 1.20E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 2.30E.01:
-TOT: 1.60E 01 <
1.28E 02 : .1.59E 02 : 3.80E 01 : 4.00E-00 : 0.00E-01 : 3.45E 02:
L.........................................
JPERIODS OF CALM (HOURS): 0.000E-01 l HOURS OF INVALID DATA : 3.000E 00 1
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990
~
MIC PAGE 4 OF REPORT CATEGORY : METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER a ***
REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1. 1990
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990 REPORT END TIME
- STADILITY CLASc D ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL-8-12 13-18 : 19-24 : >24 : TOTAE 1-3 4-7 : :
N -:.4.00E 00 : 1.60E 01 : 1.90E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 4.00E '.
NNE: 7.00E 00 :.3.70E 01 : 3.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.40E 2.90E 01 : B.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.30E
.....0':
NE : 1.60E 01 ..__................................................__...............
7.20E : '. :
ENE: 1.4t 01 : 2.80E 01 : 1.80E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 1.3]E :.-
- 6.00L 00 : 5.80E 01 : 5.70E 01 : 1.10E 01 : 1.00E 00 : 0.00E-01 E
0.00E-01 : 9.20E ;'.
ESE: 9.00E 00 : 4.10E 01 : 3.80E 01 : 4.00E 00 : 0.00E-01 SE : 1.40E 01 : 5.90E 01 : 4.70E 01 : 1.00E 00 : 0.002-01 : 0.00E-01 : 1.21E ;;
1.10E 01 : 5.40E 01 : 8.70E 01 : 1.40E 01 : 1.00E 00 : 0.00E-01 : 1.67E ;1:
SSE:
- 9.00E 00 : 5.70E 01 : 9.50E 01 : 2.90E 01 : 1.00E 00 : 0.00E-01 : 1.91E 02; S
SSW: 8.00E 00 : 7.40E 01 : 6.40E 01 : 3.00E 01 : 4.00E 00 : 0.00E-01 : 1.80E 02:
SW : 9.00E 00 : 4.40E 01 : 5.40E 01 : 1.80E 01 : 0.00E-01 0.00E-01 : 1.25E
......... ................................................................__.... 0.00E-01 : 7.10E 01 WSW: 8.00E 00 1 2.10E 01 : 2.60E 01 : 1.40E 01 : 2.00E 00 .
- 8.00E 00 : 4.10E 01 : 4.10E 01 : 2.40E 01 : 1.00E 00 : 0.00E-01 : 1.15E ;;;
W
~WNW: 1.30E 01 : 2.90E 01 : 5.00E 01 : 3.00E 01 : 0.00E-01 : 0.00E-01 : 1.22E C;:
NW : 9.00E 00 : 3.40E 01 : 4.80E 01 : 1.40E 01 : 1.00E 00 : 0.00E-01 : 1.06E 02:
NRW: 6.00E 00 : 6.20E 01 : 5.60E 01 : 7.00E 00 : 0.00E-01 : 0.00E-01
......._................_...........__.-.._____.................. : 1.31E :::
0.00E-01 : 1.79E :::
TOT: 1.51E 02 : 6.84E 02 : 7.38E 02
.. .. .......___.................. : 2.09E 02 : 1.10E 01 PERIODS OF CALM (HOURS): 1.000E 01 HOURS OF INVALID DATA : 8.000E 00
TABLE 4 CUMULATIVE JOINT TREQUENCY DISTRIBUTIONS l 1990 MIC PAGE 5 or 7 REPORT CATEGORY : METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1: 00 HRS = 01: 00 AM J ANUARY 1, 1990 REPORT END TIME
- B759:00 HRS = 11:00PM DECEMBER 31, 1990 STABILITY CLASS : E ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL 4-7 B-12 : 13-18 : 19-24 : >24 : TOTAE
- 1-3 : :
- 3.50E 01 : 3.70E 01 : 4.00E 00 : 1.00E 00 : 0.00E-01 : S.2DE ;i:
...........00........__..................._.......................................
N : 5.00E NNE: 3.30E 01 : 5.50E 01 : 9.00E 00 : 1.00E 03 : 0.00E-01 : 0.00E-01 : 9.30E NE : 3.00E 01 : 2.60E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 6.60E 01:
ENE: 1.80E 01 : 6.60E 01 : 3.10E 01 : 1.00E 00 : 0.00E-01 0.00E-01 : 1.1E E C 2 : .
- 3.40E 01 : B.20E 01 : 2.70E 01 : 3,00E 00 : 1.00E 00 : 0.00E-01 : 1 47 E 02 -
E ESE: 3.00E 01 : 8.80E 01 : 3.60E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.54E :2:
SE : 3.00E 01 : 1.39E 02 : 1.00E 02 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.72E 0;;
SSE: 2.00E 01 : 1.22E 02 : 1.52E 02 : 2.40E 01 : 0.00E-01 : 0.00E-01 : 3.15E :2:
S : 3.60E 01 : 1.36E 02 : 2.00E 02 : 2.60E 01 : 0.00E-01 : 0.00E-01 2 3.9BE 32:
SSW: 1.40E 01 : 6.70E 01 : 4.40E 01 9.00E 00 : 3.00E 00 : 0.00E-01 : 1. 3 7 E 0 2 r SW : 1.10E 01 : 5.10E 01 : 3.50E 01 : 5.00E 00 : 1.00E 00 : 1.00E 00 : 1.04E 02:
WSW: 2.80E 01 : 2.90E 01 : 2.40E 01 : 9.00E 00 : 1.00E 00 : 0.00E-01 : 9.10E 01:
W : 2.20E 01 : 5.70E 01 : 5.00E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 1.39E 01:
WNW:-2.20E 01 : 8.10E 01 : 7.20E 01 : 1.00E 01 : 2.00E 00 : 0.00E-01 : 1.87E 0 :
0,00E-01 : 1.45E ^2:
NW : 2.60E 01 : 6.80E 01 : 4.00E 01 : 8.00E 00 : 3.00E 00 NNW: 1.70E 01 : 9.20E 01 : 5.70E 01 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 1.71E 02:
TCT: 3.76E O2 : 1.19E 03 : 9.24E 02 : 1.18E 02 : 1.20E 01 : 1.00E 00 1 2.6]E 03:
PERIODS OF CALM (HOURS): 6.100E 01 HOURS OF INVALID DATA : 2.000E 00
_ _ _ _ . ~ - - - - - - - - - - - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MIC PAGE 6 Or 7 REPORT CATEGORY : :1ETEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990 REPORT END TIME : 8759:00 HRS = 11:00PM DECEMBER 31, 1990 STABILITY CLASS : F ELEVATION :' 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL
- 1-3 : 4-7 : 8-12 : 13-18 : 19-24 : >24 : TOTAL N- : 7.00E 00 : 1.40E 01 : 1.90E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 0; NNE: 1.80E 01 : 2.10E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.50E :;
..............._................................................................ 5.60E ;;:
NE : 2.70E 01 : 2.70E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 ENE: 3.60E 01 : 8.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.50E 0.:
E : 2.90E 01 : 2.80E 01 : 1.80E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 7.50E . ..
ESE: 4.60E 01 : 3.20E 01 : 1.00E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 9.00E ^;
SE : 5.30E 01 : 1.91E 02 : 1.90E 01 : .1.00E 00 : 0.00E-01 : 0.00E-01 : 2.64E 02:
SSE: 3.90E 01 : 2.05E 02 : 3.30E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.77E 02:
S : 3.40E 01 : 1.81E 02 : 6.10E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 2.77E 02:
SSW: 1.60E 01 : 6.40E 01 : 1.90E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.01E 02:
SW : 2.10E 01 : 5.40E 01 : 1.80E 01 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 9.40E 01:
WSW: 2.10E 01 : 1.30E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E 0'1:
W : 2.90E 01 : 4.00E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.90E 01:
WNW: 2.70E 01 : 2.80L 01 :-4.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 6.10E 01:
- NW : 2.30E 01 : 5.70E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 9.20E 01:
NNW: 1.00E 01 : 4.90E 01 : 1.90E 01 : 2.00E 00 1 0.00E-01 : 0.00E-01 : 8.00E 01:
2:
. TOT:
4.36E 02 : 1.01E 03 : 2.57E 02
....................................................c.............o...........
- 1.10E 01 : 0.00E-01 : 0.00E-01 : 1.7eE PERIODS OF CALM (HOURS): 3.300E 01 HOURS OF INVALID DATA : 0.000E-01
_- _ _ _ _ _ . _ _ _ _ - - - " " ' - - " - - - - - __.______m_____ , _ , _ _ _ _ _ _ _ _
s ._ ._ ._ . . -- _ _- .-_ _ _ _ _ - .
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MIC PAGE 7 or -
- METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT-REPORT CATEGORY EACH WIND SPEED AND DIRECTION PERZOD OF RECORD QUARTER # ***
REPORT START TIME :-1:00 HRS a 01:00AM JANUARY 1. 1990
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990
- REPORT END TIME
. STABILITY CLASS : G ELEVATION : 10 METERS WIND SPEED (MPH) AT 10 METER LEVEL <
4-7 S-12 : 13-18 : 19-24 : >24 : TOTAL '
......................o.........................................................
- 'l - 3 : :
0.00E-01 : 1.00E ^0.
N. : 1.00E 00 : 0.00E-01 ; 0.00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.00E : :
..............................................~.................................
'NNE: 1-00E 01 : 0.00E-01 NE : 7.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 7.00E 00:
ENE: ~1.20E 01 : 1.00E 00 1 0,00E-01 : 0.00E-01 : 0.00E-01 0.00E-01 : 1.30E 31:
0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.70E ..-
- 1.50E 01-: 2.00E 00 E
0.00E-01 : 0.00E-01 : 2.20E J1: ;
- ESE: 1.80E:01 : 3.00E 00 : 1.00E 00 : 0.00E-01 SE :.3.20E 01 : .4.20E 01 : 8.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 8.10E 01:
- 7.10E 01 : 6.00E 00 : 0.00E-01 : 0,00E-01 : 0.00E-01 : 1.14E.... 02:
- SSE: 3.70E
...........01.....................................................................
- 1.70E 01 : 2.10E Ol' : 0 . 0 0 E- O'1 : 0.00E-01 : 0.00E-01 : 0,00E-01 : 3.80E 01:
tS
- 3.30E 01 3.00E 00 0.00E-01 : 0.00E-01 l-0.00E-01 : 4.90E 01:
SSW:
. . . . .' 1.' 3 0 E 01...........................................................................
SW' :: 1~90E 01 : 2.50E 01 : 1.00E 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.40E-01: i 6.00E:00 : 3.00E 00 : 0,00E-01 : 0.00E-01 : 0.00E-01 : 1.80E 01:
-WSW: 9.00E 00 W: -: 1.70E 01 : 5.00E'00 : 1.00E 00 ,: 0.00E-01 : 0.00E-01 : 0.00E-01 : 2.30E-01:
WNW:13.60E 01 : 8.00E 00 : 'O.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.40E 01:
- ~3.'10E 01 : 3.00E 00.: 0.00E-01 : 0.00E-01-: 0.00E-01.: 4.70E 01:
.NW1:
. . . ..' 1.' 3 0 E 101...........................................................................
0.00E-01 : 2.20E 01:
-NNW:-8.00E 00 : 1.20E 01 :-1.00E 00 : 1.00E 00 : 0.00E-01 ......................
TOT: '2.64E 02 : 2.60E 02 : 3.60E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01,: 5.62E 02:
EPERIODSEOF' CALM (HOURS): 3.400E 01 HOURS'OF INVALID DATA : 0.000E-01
-HOURS OF GOOD DATA : 7.944E 03 = 90.7% OF TOTAL HOUES
I TABLE 4 )
i CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS ,
-1990 MID PA0E 1 Or 7
' REPORT CATEGORY -: METEROLOGICAL DATA. QUARTERLY TOTALS O'F HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD-OF RECORD, -
QUARTER # ***
REPORT START TIME 1 : 00 HRS = 01 : 00 AM J ANU ARY 1, 1990 REPORT END TIME t 8759:00 HRS = 11:00PM DECEMBER 31, 1990 STABILITY CLASS : A
-ELEVATION' : 60 METERS
, WIND SPEED (MPH) AT 60 METER LEVEL 4-7 13-18 19-24 : >24 : TOTAL
- 1-3 : : 8-12 :
N : 0.00E-01 : 0.00E-01 : 2.00E 00 : 0.00E-01 : 0.00E-01-: 0.00E-01 : 2.00E 00:
0.00E-01 : 1.00E 00 : 0.00E-01 :-0.00E-01 : 0.00E-01 2.00E 00:
NME: l'.00E 00 NE : 0.00E-01 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-D1:
.ENE : 0.00E-011: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
-E- : 0.00E-01 : 0.00E-01 : 0.00E-11 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01:
- 2.00E 00 ! 2.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 5.00E nc ES E :................__.........................................................
.... '. O . 0 0 E - 01 SE : 1;00E 00 : 6.00E 00-: 7.00E 00 : 4.00E 00 : 1.00E 00 : 0.00E-01 : 1.90E 01: c
.- SSE: 0,00E-01 : 1.00E 01 :. 2.10E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 . 4.80E 01:
.S : 1.00E'00 : -1.20E-01 : 3.80E 01 : 3.20E 01 : 8.00E 00 : 0.00E-01 : 9.10E 01:
o ......_.....__..................................................................
- SSW: 0.00E-01': 7.00E 00 : 2.80E Ol': 2.10E 01 : 4.00E 00 : 0.00E-01 : 6.00E 01:
SW : 0.00E-01 : 2.00E 00 : 2. 2 0E 01 : 1.60E 01 : 4.00E 00 : 1.00E 00 : 4.50E 01:
WSW: -1.00E 00 : 2.00E 00 : 1.20E 01 : 8.00E 00 : 0.00E-01 : 2.00E 00 : 2.50E 01:
W :E2.00E 00 : 2.00E-00 9.00E 00 : 5.00E 00 : 0.00E-01 : 4.00E 00 : 2.20E 01.
WNW: 1,00E-00.: 3.00E 00 : 8.00E 00 : 1.00E 01 : 1.40E 01 : 8.00E 00 : 4.40E 01:
NW : 0.00E-01 : -3.00E 00 : 4.00E 00 :-1.40E 01 : 9.00E 00 : 3.00E 00 : .3.30E 01:
NNW:n0.00E-01 : 2.00E 00 : 1.00E 01 : 1.00E 00 : 0.00E-01 : 14 00E 00 : 1.40E 01:
TOT: 7.00E 00 :-6.00E 01 : 1,64E 02 : 1.20E 02 : 4.00E 01 : 1.90E 01 : 4.10E 02:
................................................................................ I PERIODS O' CALM (HOURS): 0.000E-01 HOURS OF .NVALID: DATA : 2.100E 01 a
1
TABLE 4 i
1 CUMULATIVE - JOINT FREQUENCY DISTRIBUTIONS 1990 -
MID PAGE 2 CE REFORT CATEGORY : METERCLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1:00 HRS = 01:00 AM JANUARY 1, 1990
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990 REPORT END TIME STABILITY CLASS : B ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL
........................................................ 13-18 19-24 : >24 : TOTAL 1-3 4-7 8-12 : :
- 0.00E-01 : 0.00E-01 : 2.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 3.00E 0,:
N
.......................................................... 0.00E-01 : 0.00E-01 : 0.00E-01 3.00E ..
NNE: 0.00E-01 : 1.00E 00 : 2.00E 00 0.00E-01 : 3.00E 00 : 0.00E-01 : 0,00E-01 : 0,00E-01 : 0.00E-01 : 3.00E 0' NE :
O.00E-01 : 0.00!-:.
ENE: 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 0.00E-01
- 0.00E-01 : 2.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 4.00E ::
E EEL: 0.00E-01 : 0.00E-01 : 5.00E 00 : 4.00E 00 : 0.00E-01 : 0.00E-01 : 9.00E SE : 2.00E 00 : 7.00E 00 : 9.'00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.90E 0; SSE: 1.00E 00': 1.10E 01 : 2. 00E 01 : 7.00E,00 : 2.00E 06 : 0.00E-01 : 4.10E i'.
1.30E 01 : 2.20E 01 : 1.70E 01 : 5.00E 00 : 0.00E-01 : 5.70E ; '.
S : 0.00E-01 1SSW: 1.00E 00 : 5.00E 00 : 2.60E 01 : 9.00E 00 : 5.00E 00 : 0.00E-01 : 4.60E : '.
SW : 1.00E 00 : 1.10E 01 : 9.00E 00 : 1.80E 01 : 3.00E 00 : 0,00E-01 : 4.20E 0;
- 1.00E 01 : 9.00E 00 : 4.00E 00 : 1.00E 00 : 1.00E 00
- 2 . 5 0 E C '. '
'WSWi 0.00E-01
- 1.00E 00 : 5.00E 00 : 4.00E 00 : 0.00E-01 : 5.00E 00 : 1.00E 00 : 1.60E 01
.W
........_.............................................. 0'.*
WNW: 0.00E-01 : 2.00E 00 : 1.00E 01 : 1.00E 00 : 9.00E 00 : 2.00E 00 : 2.40E NW : 0.00E-01 : 4.00E 00 : 2.00E 00 : 1,70E 01 : 5.00E 00 : 0.00E-01 : 2.SOE
................................................................................0'..
NNW:
..... 0.00E-01 : 2.00E 00 : 6.00E 00 : 5.00E 00 : 1.00E 00 : 0.00E-01 : 1.40E 6.00E 00 : 7.60E 01 : 1.28E 02 : 8.40E 01 : 3.60E 01 : 4.00E 00.: 3.34E 0;:
TOT:
PERIODS OF CALM (HOURS): 0.000E-01 HOURS OF INVALID DATA : 2.000E 00
--- -- ___ - - - ^ - - ^ - - - - - _ _ _ _- _ __
TABLE 4 CUMULATIVE JCINT FREQUENCY DISTRIBUTIONS 1990 ~
MID PAGE 3 0F
- METER 0 LOGICAL DATA. QUARTERLY TOTALS OF HOURS AT REPORT CATE00RY.
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990 REPORT END TIME STABILITY CLASS : C ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL 4-7 8-12 : 13-18 : 19-24 : >24 : TOTAE 1-3
- 0.00E-01 : 2,00E 00 : 6.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 9.00E 0.:
N 0.00E-01 : 6.00E 00 : 8.00E 00 : 1.00E 00 : 1.00E 00 : 0.00E-01 : 1.60E 0; NNE:
NE : 0.00E-01 : 2.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.00E 00:
ENE: 0.00E-01 : 2.00E 00 : -1.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 3.00E
- 1.00E 00 : 4.00E 00 : 7.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.40E J '.
E 1.00E 00 : 6.00E 00 ; 6.00E 00 : 3.00E 00 1 0.00E-01 : 0.00E-01 . 1.60E 01:
ESE:
SE : 0.00E-01 : 1.00E 01 : 1.30E 01 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 2.50E 0;:
SSE: 1.00E 00 : 4.00E 00 : 2.00E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 3.10E C;;
- 0.00E-01 : 5.00E 00 : 1.80E 01 : 1.0CE 01 : 2.00E 00 : 0.00E-01 : 3.50E 31:
S SSW: 2.00E 00 : 8.00E 00 : 1.60E 01 ; 4.00E 2) : 3.00E 00 : 0.00E-01 : 3. 3 0 E 01:
SW : 3.00E 00 : 1.10E 01 : 2.00E 01 : 1.50E 01 : 3.00E 00 : 2.00E 00 : 5.40E Ol' 1.00E 00 : 4.00E 00 : 6.00E 00 : 7.00E 00 : 1.00E 00 : 2.00E 00 : 2.10E ];:
WSW: ...........
..........._...._......_.......... _................................ e.20E ;;.
- 2.00E 00 : 4.00E 00 : 8.00E 00 : 4.00E 00 : 2,00E 00 : 2.00E 00 .
W
?.10E :.:
l'.00E 00 : 2.00E 00 : 6.00E 00 : 5.00E 00 : 4.00E 00 : 3.00E 00 WNW:
NW : 0.00E-01 : 5.00E 00 : 5.00E 00 : 6.00E 00 : 4.00E 00 : 1.00E 00 : 2.10E ;;:
............................_..............._................................... 2.30E 01 NUW: 0.00E-01 : 3.00E 00 : 1.50E 01 : 5.00E 00 : 0.00E-01 : 0.0^E-01 _. _...........
TOT: 1.20E 01 1 7.80E 01 : 1.56E 02 : 7.10E 01 : 2.00E 01 : 1.00E 01 : 3.47E 02:
PERIODS OF CALM (HOURS): 0.000E-01 HOURS OF INVALID DATA . 1.000E 00
TADLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MID PAGE 4 OF 7 REPORT CATEGORY : METER 0 LOGICAL DATA. QUARTERLY TOTALS Of HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # ***
REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990 REPORT END TIME
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990 STABILITY CLASS : D ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL 4-7 8-12 13-18 : 19-24 : >24 : TOTAL :
1-3 : : :
- 0.00E-0.1 : 1.40E 01 : 2.90E 01 : 1.50E 01 : 0.00E-01 : 1.00E 00 : 5.90E 01:
N NNE: 3.00E 00 : 3.10E 01 : 3.60E 01 : 1.10E 01 : 0.00E-01 : 0.00E-01 : 8.10E ?l:
NE : 5.00E 00 : 3.00E 01 : 1.00E 01 : 5.00E 00 : 4.00E
.................................................... 00 : 1.00E 00 : 5.50E 01:
_.......................... ' 9.60E ;1:
ENE: 1.00E 01 : 1.80E 01 : 2.60E 01 : 3.40E 01 : 2.00E 00 : 6.00E 00 3.10E 01 : 4.10E 01 : 1.30E 01 : 5.00E 00 : 1.00E 00 9.50E 01:
- 4.00E 00 E
ESE: 1.10E 01 : 3.20E 01 : 4.40E 01 : 8.00E 00 : 0.00E-01 : 0.00E-01 : 9.50E ;;;
SE : 8.00E 00 : 3.20E 01 : 5.30E 01 : 9.00E 00 : 3.00E 00 : 1.00E 00..............
............___......._...............________................... : 1.06E 02:
SSE: 6.00E 00 : 3.60E 01 : 6.70c 01 : 2.70E 01 : 6.00E 00 : 0.00E-01 : 1.42E 02:
- 9.00E 00 : 4.80E 01 : 6.30E 01 : 7.70E 01 : 1.70E 01 : 1.00E 00 : 2.15E 02:
S SSW: 1.00E 00 : 3.40E 01 : 4.30E 01 : 5.10E 01 : 1.70E 01 : 1.00E 00 : 1.47E 02:
SW : 3.00E 00 : 5.40E 01 : 4.60E 01 : 5.60E 01 : 1.10E 01 : 5.00E 00 : 1.75E 02 WSW: 2.00E 00 : 1.50E 01 : 2.70E 01 : 1.30E 01 : 1.00E 01 : 3.00E 00 : 7.00E 01:
- 1.00E 00 : 1.90E 01 : 3.00E 01 : 1.60E 01 : 1.70E 01 : 7.00E 00 : 9.70E 01:
W WNW:-5.00E 00 : 1.60E 01 : 2.10E 01 : 3.10E 01 : 2.80E 01 : 8.00E 00 : 1.09E 02:
................................................-_.............................. 1.60E 01 : 6.00E 00 : 1.1]E 02:
NW : 1.00E 00 : 2.30E 01.: 3.10E 01 : 3.60E 01 NNW: 3.00E 00 : 2.90E 01 : 6.10E .....,................
.............__................. 01 : 3.00E 01 : 7.00E 00..: 0.00E-01 : 1.30E 02:
TOT: 7.90E 01 : 4.62E 02 : 6.28E 02 : 4.32E 02 : 1.43E 02 : 4.10E 01 : 1.79E 03:
PERIODS OF CALM (HOURS): 1.300E 01
. HOURS OF INVALID DATA : 1.300E 01
I TABLE 4 i CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS
! 1990
' MID PAGE 5 OF 7 REPORT CATEGORY : METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD- QUARTER # ***
REPORT START TIME : 1:vo HRS = 01:00AM JANUARY 1, 1990 REPORT END TIME : 8759:00 HRS = 11:00PM DECEMBER 31, 1990 STABILITY CLASS : E ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL 1-3 4-7 : 8-12 : 13-18 : 19-24 : >24 : TOTAL .
N : 3.00E 00 : 1.80E 01 : 4.90E 01 : 2.60E 01 : 2.00E 00 : 0.00E-01 : 9.80E 01:
NNE: 2.00E 00 : 2.90E 01 : 7.00E 01 : 2.00E 01 : 2.00E 00 : 0.00E-01 : 1.23E 02:
NE : 4.00E 00 : 2.70E 01 : 3.90E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 7.30E 01:
ENE: 3.00E 00 : 2.40E 01 : 6.00E 01 : 2.00E 01 : 0.00E-01 : 0.00E-01 : 1.07E 22:
E : 4.00E 00 : 2.40E 01 : 7.50E 01 : 2.00E 01 5.00E 00 : 1.00E 00 : 1.29E 02:
ESE: 3.00E 00 : 2.60E 01 : 1.07E 02 : 1.90E 01 : 0.00E-01 : 0.00E-01 : 1 57E 02:
SE : 6.00E 00 : 2.70E 01 : 1.0BE 02 : 8.50E 01 : 2.00E 00 ; 0.00E-01 : 2.28E D2:
SSE: 5.00E 00 : 3.50E 01 : 1.17E 02 : 1.09E 02 : 9.00E 00 : 1.00E 00 : 2.76E 02:
S : 4.00E 00 : 3.30E 01 : 9.90E 01 : 2.01E 02 3.00E 01 : 0.00E-01 : 3.67E 02:
SSW: 3.00E 00 : 3.60E 01 : 6.00E 01 : 8.40E 01 : 1.40E 01 : 3.00E 00 : 2.00E 02:
SW : 5.00E 00 : 1.70E 01 : 4.80E 01 . 3.90E 01 : 5.00E 00 : 2.00E 00 : 1.16E 02:
WSW: 4.00E 00 : '2.10E 01 : .30E 01 : 3.50E 01 : 1.00E 01 : 1.00E 00 : 1.04E 02:
W : 8.00E 00 : 1.10E 01 : 4.40E 01 : 4.30E 01 : 6.00E 00 : 0.00E-01 : 1.12E 02:
- 1. 2 0 E 01 : 1 42E 02:
WNW: 3.00E 00 : 1.20E 01 : 5.20E 01 : 4.60E 01 : 1.70E 01 :
NW : 6.00E 00 : 1.80E 01 : 1.06E 02
...._____............................ : 4.40E 01 : 8.00E 00
_ ......................_ : 5.00E....__..
...___.. 00 : 1.87E 02:
NNW: 2.00E 00 : 2.30E 01 : 9.00E 01 : 4.30E 01 : 3.00E 00 : 2.00E 00 : 1.63E 32:
TOT: 6.50E 01 : 3.83E 02 : 1-.16E 03 : 8.37E 02 : 1.13E 02 : 2.70E 01 : 2.58E 03:
...................... ..................... ... ~..__.............__...........
PERIODS OF CALM (HOURS): 4.800E 01 HOURS OF INVALID DATA : 5.800E 01
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MID PAGE 6 Or i
- METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
' REPORT CATEGORY
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD .: QUARTER # ***
. REPORT START TIME : 1:00 HRS = 01:00AM JANUARY 1, 1990
- 8759:00 HRS = 11:00PM DECEMBER 31, 1990 REPORT END TIME STABILITY CLASS : F ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL J
............................................_ B-12 : 13-18 :
19-24 : >24 ..............
- TOTAL
- 1-3 : 4-7 :
- 1.00E 00 : 4.00E 00 : 3.90E 01 : 1.50E 01 : 0.00E-01 : 0.00E-01 : 5.90E 0 '. '
N NNE: 2.00E 00 : 1.80E 01 : 2.40E 01 : 5.00E 00 : 0.00E-01 : 0.00E-01 : 4.90E ;;
NE
.....: 2.00E CO : 1.80E 01 : 3.70E
...__................ 01 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 5.70E 31' 5.;3E ;1:
ENE: 0.00E-01 : 1.60E 01 : 3.10E
.................................................____........................... 01 : 4.00E 00 : 0.00E-01 : 0.00E-01 3.00E 00 i 1.30E 01 : 4.40E 01 : 1.60E 01 : 0.00E-01 : 0.00E-01 : 7.60E 01 E
0'.'
/ ESE: 3.00E 00 : 2.10E 01 : 4.60E 01
_........................................................ .._............ : 2.10E 01 : 1.00E 00 : 0.00E-01 : 9.20E
..m...
% SE : 5.00E 00 : 2.10E 01 : 9.90E 01 : 3.20E 01 : 0.00E-01
...._...................................___........... : 0.00E-t1 : 1.57E 02:
2'.00E 00 : 2.50E 01 : 1 40E 02 : 6.50E 01 : 4.00E 00 : 0.00E-01 : 2.36E 0;:
( ........................ ........... ....._......................................
SSE:
.: 3.00E 00 : 2.40E 01 : 1.46E 02 : 9.00E 01 : 4.00E 00 : 0.00E-01 : 2.67E 02:
S SSW: 2.00E 00 : 1.80E 01 : 9.40E 01 : 1.15E 02 : 3.00E 00 : 0.00E-01 : 2.32E 02:
SW : 1.00E 00 : 1.50E 01 : 4.80E 01 : 4.80E 01 : 0.00E-01 : 0.00E-01 : 1.12E 02:
.................. _ ................................... ___.............5.00E .
01:
WSW: 2.00E 00 : 1.20E 01 : 1.60E 01 : 1.80E 01 : 2.00E 00 : 0.00E-01
- 1.00E 00 : 1.20E 01 : 3.60E 01 : 1.30E 01 : 0.00E-01 : 0.00E-01 : 6.20E 0;;
W WNW: 1.00E 00 : 7.00E 00 : 3.50E 01 : 1.90E 01 : 3.00E 00 : 0.00E-01 : 6.50E 0'.:
NW :-1.00E 00 : 7.00E 00 : 4.10E 01 : 1.80E 01 : 0.00E-01 : 0.00F-01 : 6.70E ?;;
NNW: 2.00E 00 : 1.40E 01 : 3.60E 01 : 3.30E 01 : 2.00E~00 : 0.00E-01 : 8.70E 01:
TOT: 3.10E 01 : 2.45E 02
__....................._ : 9.12E 02 : 5.12E_...__._............______.........
.........__......._ 02 : 1.90E 01 : 0.00E-01 : 1.72E 03:
7,000E 00 PERIODS OF -CALM (HOURS) :
HOURS.0F INVALID DATA : 2. 00E 01
- - - -- - - _ _ - - _ _ - - _ - _ _ _ ~-'~- --^"-^---~u m
l l
TABLE 4 CUMULATIVE JOINT FREQUENCY DISTRIBUTIONS 1990 MID PA0E 7 or -
REPORT CATEGORY
- METEROLOGICAL DATA. QUARTERLY TOTALS OF HOURS AT
- EACH WIND SPEED AND DIRECTION PERIOD OF RECORD : QUARTER # *** 1, 1990
- 1: 00 HRS = 01: 00 AM J ANUARY REPORT START TIME : 8759:00 HRS = 11:00PM DECEMBER 31, 1990 REPORT END TIME STABILITY CLASS : G ELEVATION : 60 METERS WIND SPEED (MPH) AT 60 METER LEVEL b
B-12 : 13-18 : 19-24 : .................
>24 : TOTAE -
^
1-3 4-7
- 2.00E 00 : 3,00E 00 : 7.00E 00 : 8.00E 00 : 0.00E-01 : 0.00E-01 : 2.00E 31:
kN................................................................................ 1. 2 0 E ; '. -
NNE: 2.00E 00 : 4.00E 00 : 4.00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 :
NE . 0.00E-01 : 1.00E
................... 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 0.00E-01 : 1.60E ..:
ENE: 1.00E 00 : 4.00E 00 : 6.00E 00 : 1.00E 00 : 0.00E-01 : 0.00E-01 : 1.20E L : 1.00E 00 : 4.00E 00 : 9,00E 00 : 2.00E 00 : 0.00E-01 : 0.00E-01 : 1.60E .1:
ESE: 2.00E 00 : 5.00E 00 : 1.50E 01 : 6.00E 00 : 0.00E-01 : 0.00E-01 : 2.80E :.:
.................................................................................. 0'.
SE : 2.00E 00 : 1.50E 01 : 1.00E 01 : 1.20E 01 : 0.00E-01 r 0.00E-01 : 3.90E SSE: 2.00E 00 : 1.70E 01 : 2.70E 01 : 9.00E 00 : 1.00E 00 : 0.00E-01 : 5.60E 0;
- 2.00E 00 : 1.90E 01 : 5.90E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 9.20E 01:
S
__ ....____......_..........._.........._........ _............... . 5.90E G1:
SSW: 1.00E 00 : 1.70E 01 : 2.60E 01 : 1.50E 01 : 0.00E 01 : 0.00E-01 SW ; 1.00E 00 : 6.00E 00 : 2.30E 01 : 3.70E 01 : 2,00E 00 : 0.00E-01 : 6.90E 31:
WSW: 0.00E-01 : 4.00E 00 : 1.30E 01 : 1.20E 01 : 0.00E-01 : 0.00E-01 : 2.90E 01.
- 0.00E-01 : 5.00E 00 : 2.10E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 : 2.90E 31:
W
_....... . ............................... ........................ . 2.50E 31:
WNW: 0.00E-01 : 3.00E 00 : 1.90E 01 : 3.00E 00 : 0.00E-01 : 0.00E-01 NW :-0.00E-01 : 3.00E 00 : 2.40E 01 : 8,00E 00 : 0.00E-01 : 0.00E-01 : 3.50E s.:
..............................r..........
2.00E 00 : 1.00E 00 : 1.80E 01 : 1.80E 01 : 0.00E-01 : 0.00E-01 : 3.90E 31:
NNW:
TOT: 1.80E
........... 01 : 1.20E 02 : ..
__.....____.. 2.87E 02 : 1.4SE 02 : 3.C'E 00 : 0.00E-01 : 5.76E
_...__..........................._......... ......... 01:
PERIODS OF CALM (HOURS): 0.000E-01 HOURS OF INVALID DATA : 2.000E 01
- 7.821E 03 = 89.31 OF TOTAL HOURS HOURS OF GOOD DATA
TABLE L DOSE AT Tl!E SITE DOU!iDARY AND TO Tile NEAREST RESIDE 11" FROM GASEOUS EFTLUENTS ORGAN SITE BOUNDARY HEAREST RESIDE!1T LOCATION: 2.3km NW LOCATION: 2. 87km N!!W AGE GROUPt CllILD AGE GROUP: CllI LD DOSE % LIMIT (a) DOSE % LIMIT (b)
Gamma Air 1.27E-02 0.13 7.81E-03 N/A Dono (mrad)*
Bota Air 3.73E-02 0.19 2.29E-02 N/A Doco (mrad)*
Whole Body (mRom)* 1.09E-02 !!/A 6.71E-03 ll/A Skin (mRom)* 2.87E-02 !!/A 1. 7 '., E - 0 2 N/A Dono (mrem)** 1.22E-07 N/A 1.750 05 0.00 Liver (mRom)** 1.19E-03 N/ /. 6.45E-03 0.04 Total Body (mRom)** 1.19E-03 NA 6.44E-03 0.04 Thyroid (mrem)** 1.21E-03 IJA 1.14E-02 0.08 Ridney (mrem)** 1.19E-03 N/A 6.4SE-03 0.04 Lung (mRom)** 1.19E-03 N/A 6.43E-03 0.04 $
<k GI-LLI (mRom)** 1.190-0J N/A 6.430-03 0.04 -
- Dono from Noble GnSos only
- Doso from Tritium, Radiciodinos and Particulatos only (a) Annual dose limits of APA-ZZ-01003, Section 9.7.1.1 of 10 mrad gamma air dose and 20 mrad beta air doso.
(b) Annual dono limits of APA-ZZ-01003, Section 9.8.1.8 of 15 mRom to any organ from I-131,-I-133, 11 - 3 and particulato rad.onuclidos with half-lives greatcr than 8 days.
Page 1 of 1
TABLt 6 Dott 10 THE MEMbit (J f Mt PUBLIC PROM Attivilits WitklN th! Litt (13JNDARY l
ORGAN (FFLUtkit DOSI DIRECT RADIA110N DIRtti RA01Ai!ON TOTAL Dost W11HIN THE llit fROM TMt UN11 FROM OU510t 1ANKS FOR fti YtAR B3)NDAkV (ntem) (neem) (pe rV1100hr ) (dem)
Skin % 6Bt 03 N/A N/A $.60t 03 Bone 1.80t 08 9.00t 03 1.04t 06 S . 0'..r 03 s
Liver 2,80t 04 9.00t 03 1.04t 06 9.7 % 03 Tetel Body 2.45t 03 9.00t 03 1.04t 06 1.14t C?
Thytold 2.64t 04 9.00E 03 1.04t 06 9.29t*C3 KIdnev 2.60t 04 9.00t 03 1.04h 06 9.28t 03 Lung 2.53t 04 9.00t 03 1.04E 06 9.28t*03 GI LLI 2.80E 04 9.00t 03 1.04t 06 9.200 03 l
N Pege 1 of 1
e TABLt 7 TOTAL Dost DUE 10 THE URAWlVM FVIL CYCLE (MEMBER Of 1FE PUBLIC)
ORGAN Dost At THE tt$1DtWCE D0tt IRCN Ati!Vlfitt 101 AL Dott 10 THE MIMDER % !.lpli LOCAflDN (nSea) VlfN!W THE $11t Of THE NELit (nAem) 40CfRiV0' B3)NDARY ('rtem)
$ kin 4.81E 03 5.68t 03 1.05t 02 0.04 Bone 1.381 08 9,00E 03 9.00t 03 0.04 inver 2.14t 04 9,2Bf 03 9.50t 03 0,04 total Body 2.05t 03 1.14t 02 1,35t 02 0,05 Thyroid 2.17t 04 0.29t 03 9.50t*03 0.01 Kidney 2.14t 04 9,2Bt 03 9,50t 03 0,04 tmg 2.14t 04 9.2BE 03 9.50E 03 0,04 Cl LLI 2.14t 04 9.2BE 03 9,50t 03 0.04
- Annual dose Limits f rom 40CFR190.10(a) of 25 neem whole body, 75 cAem to the thyroid, and 25 neem to any other organ.
Page 1 of i
TABLE 8 ,
DOEI DUE TO LIQUID ErrLUE!!TS 1990 ORGA!J DOSE LIMIT * ' LIMIT t
(mrem) (mRom)
DO!1E 2.85E-03 10 3E-02 LIVER 7.05E-03 10 7E-02 TOTAL BODY 5.72E-03 3 2E-01 THYROID 2.06E-03 10 2E-02 KI D!1EY 3.61E-03 10 4E-02 LUNG 2.45E-03 10 2E-0?
GI-LLI 3.10E-02 10 3E-01
- Annual donc limits of APA-ZZ-01003, Sect. ion 9.4.1.1.
Page 1 of I
.h (a.
Licence 111'r 30 callaway Plant Semiannual Radioactive Effluent Release Report July - December 1990 Attachment 1 APA-ZZ-01003, Offsite Dose Calulation Manual 4
rs
- L., s APA ZZ-01003 Revision 1 October 8, 1990 j
. l
} NUCLEAR FUNCTION l
- ADMINISTRATIVE PROCEDURE APA-ZZ-01003 OFFSITE DOSE CALCULATION MANUAL RESPONSIBLE DEPARTMENT --,
po /77( f/ vJ,'c f 7
-PREPARED BY '/2 .lh #ff A%L DATE,/p/f/90 APPROVED BY- /M' DATE t!f' fe ~
'l l ,
) DATE ISSUED //) -' P- 9 6 # h ISSUED OCT091990
- **i?#5128'8 ll3 This procedure contains the following: A .~
Pages ,
I through 191 Attachments through Tables 1 through 12 Figures 4 through 5 Appendices through
. Checkoff Lists- through !
- p% 4: , h%
INFORMATION OhLY -
f f"l.?% ..\v11) U s cohTkoLLED H*%,%ws/g/ . COPY
..-- --..-.-_.....-- -. .-.- - - . . . - , - . . - . , _ . - . - - - . . ~ , . . - - , , -
APA-ZZ-01003 Rev. 1
} Table of Contents Section Page Number
1.0 Purpose and Scope
1 2.0 Liquid Effluents 1 2.1 Radioactive Effluent Contruts (REC) Section 9.1.1.1 1 2.2 Liquid Effluent Monitors 2 2.3 Calculation of Liquid Effluent Monitor Setpoints 5 2,4 Liquid Effluent Concentration Measurements 11 2.4.1 REC Section 9.3.1.1 11 2.4.2 Liquid Effluent Concentration Measurements 11 2.5 Dose Due to Liquid Effluents- 12
, 2.5.1 REC Section 9.4.1.1 12 l 2.5.2 The Maximum Exposed Individual 12 2.5.3 Calculation of Dose from Liquid Effluents 13 2.5.4 Surmary, Calculation of Dose Due to Liquid Effluents 15 2.6 Liquid Radwaste Treatment System 19 2.6.1 REC Section 9.5.1.1 19 2.6.2 Operability of the Liquid Radwaste Treatment System 20
, 3.0 Gaseous Effluents 21 3.1 REC Section 9.2.1.1 21 3.2 REC Section 9.6.1.1 21
! 3.3 Gaseous Effluent Monitors 21 3.4 Calculation of Gaseous Effluent Monitor Setpoints 25 3.4.1 Total Body Dose Rate Setpoint-Calculations 26 3.4.2 Skin Dose Rate Setpoint Calculations 28
- 3. 4. 3 - Gaseous Effluent Monitors Setpoint Determination 30 3.4.4 Summary, Gaseous Effluent Monitors Setpoint Determination 32 3.5 Calculatd.on of Dose from Gaseous Effluents 32 l
3.5.1 ~ Calculation of Dose Rate 32 3.5.1.1 Noble Gases 32 3.5.1.2 Radionuclides Other Than Noble Gases 34
-3.5.2 Individual Dose Due to Noble Gases 39 3.5.2.1 REC Section 9.7.1.1 39 3.5.2.1.1 Noble Gases 40 3.5.2.2 REC Section 9.8.1.1 42 3.5.2.2.1 Radionuclides Other Than Noble Gases 42 3.6' . Gaseous Radwaste Treatment System 77' 3.6.1 REC Section 9.9.1.1 77
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, APA-g"-01003 '
Rev. 1 l ) Table of Contents l
Section Page Number 3.6.2 Description of the Gaseous Radwaste Treatment System 77 i 3.6.3 Operability of the Gaseous Radwaste Treatment System 77 4.0 Dose and Dose Commitment from Uranium Fuel Cycle Sources 78 4.1 REC Section 9.10.1.1 78 4.2 Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources 78 4.2.1 Identification of the MEMBER OF THE PUBLIC 80 4.2.2 Total Dose to the Nearest Resident 80 4.2.3 Total Dose to the Critical Receptor Within 81 the SITE BOUNDARY i 5.0 Radiological Environmental Monitoring 86 l 5.1 REC Section 9.11.1.1 86 5.2 Description of the Radiological Environmental Monitoring Program 86 5.3 Performance Testing of Environmental
) Thermoluminescence Dosimeters 87 l
6.0 Determination of Annual Average and Short Term Atmospheric Dispersion Parameters- 105 6.1 Atmospheric Dispersion Parameters 105 l 6,1.1 Long-Term Dispersion Estimates 105 !
-6.1.2 Determination of Long-Term Dispersion Estimates ,
for Special Receptor Locations '06 4 6.1.3 Short-Term Dispersion Estimates 106 l
7.0 Semi-Annual Radioactive Effluent Release Report 114' 8.0 -Implementation of ODCM Methodology 120 9.0 Radioactive Effluent Controls (REC) 121 I 9.1 -Radioactive Liquid Effluent Monitoring !
Instrumentation 123
~9.2 Radioactive Gaseous Effluent Monitoring l Instrumentation 130 9.3 Liquid Effluents Concentration -138 9.4- Dose 144 )
9.5 Liquid Radwaste Treatment System 146 9.6 Gaseous Effluents Dose Rate 148 9 ~. 7 Dose-Noble Gas 154 l
) ,
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l APA-ZZ-01003 Rev. 1 Table of contents l
)
Section Page Number 9.8 Done-Iodine-131 ar.d 133, Tritium, and Radioactive Material in Particulate Form 156 Garious Radwaste Treatment System 9.9 158 9.10 Total Dose 160 9.11 Radiological Environmental Monitoring Program 164 9.12 Radiological Environmental Monitoring Land Use Census 180 9.13 Radiological Environmental Monitoring Inter-
- laboratory Comparison Program 183 10.0 Administrative Control 184 i 10.1 Major Changes to Liquid and Gaseous Radwaste Treatment Systems 184 10.2 Changes to the offsite Dose calculation Manual (ODCM) 185 ,
11.0 References 186 Figure 4.1 Site Area Closed to Public Use 85 Figure 5.1A Airborne & TLD Sampling Network 200
) Figure 5.1B Airborne & TLD Sampling Network 101 Firure 5.2A Location of Aquatic Sampling Stations 102 Figure 5.2B Location of Aquatic Sampling Stations 103 Figure S.3 Food Products Sampling Locations 104 1
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APA-ZZ-01003 Rov. 1 Table of Contents
}
Section Page Number Table 1 Ingestion Dose Commitment Factor (Ag) for Adult Age Group 16-17 Table 2 Bioaccumulation Factor (BFg ) Used in the Absence of Site. Specific Data 18 Table 3 Dose Factora fot.- Exposure to A Semi-Infinite Cloud of Noble Gases 31 Table 4 Dose Parameter (P g ) for Radionuclides Other
. Than Noble Gases 36-38 Table 5 Pathway Dose Factors (R g ) for Radionuclides Other Than Noble Gases 46-76 Table 6 Radiological Environmental Monitoring Program 88-95 Table 7 Reporting Levels for Radioactivity Concentrations in Environmental Samples 96 Table 8 Maximum Values for.the Lower Limits of Detection 97 Table 9 Highest Annual Average Atmospheric Diepersion Parameters - Radwaste Building Vent 110 2able 9.1-A Radioactive Liquid Effluent Monitoring
) Instrumentation 125-127 Table 9.1-B Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 128-129 Table 9.2-A Radioactive Gaseous Effluent Monitoring Instrumentation 132-134 Table 9.2-B Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 135-137 Table 9.3-A Radioactive Liquid Waste Sampling and Analysis Program 140-143 Table 9.6-A Radioactive Gaseous Waste Sampling and Analysis Program 150-153 Table 9.11-A Raddological Environmental Monitoring Program .
168-174 Table 9.11-B Repor ting ~ Levels for Radioactivity Concentrations In Environmental Samples 175 Table 9.11-C Detection Capabilities for Environmental Sample Analysis 176-179 Table 10 Highest Annual Average Atmospheric Diepersion Parameters - Unit Vent 111 Table 11 Short Term Dispersion Parameters .
112 Table 12 Application of Atmospheric Dispersion Parameters 113 l
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APA-22-01003 Rev. 1 i
)
Record of Revisions i
Revision Reason Number Date for Revision i l
Rev._O March 1983 ll
.Rev. 1 November 1983 Revised to support the current RETS submittal and to incorporate NRC i Staff comments Rev. 2 March 1984 Revised to incorporate NRC Staff comments Rev.-3 June 1985 Revised to incorporate errata identified by ULNRC-803 and changes I to the Environmental Monitoring i Program. Incorporate results of ;
)
1984 Land use Census.
Rev.'4 February 1987 Minor clarifications, incorporated 31-day projected dose methodology.
Change in the utilication of areas within the Site Boundary. i l
Rev 5 January 1988 Minor. clarifications, revised descriptions of liquid and gasecus rad monitors, revised liquid setpoint methodology to incorporate monitor background, revised dose l.
calculations for 40CFR190 requirements, Revised Table 6 and Figures 5.1A and 5.1B to refine descriptions of environmental TLD ,
stations, incorporated descriptien of environmental TLD testing required by Reg.-Guide 4.13, l- revised Tables 1,-2, 4,-and 5 to add additional nuclides, deleted redundant material from Chapter 6.
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APA-ZZ-01003 Rev. 1
) Record of Revisions Rev. 6 May 1989 Revised methodology for calculating maximum permissible liquid effluent discharge rates and liquid effluent monitor setpoints, provided methodology for calculating liquid effluent monitors response correction factors, provided an enhanced description of contro?s on liquid monitor background limits, provided additional liquid &
gaseous dose conversion factors and bioaccumulation factors (Tables 1, 2, 4 & 5), provided description of the use of the setpoint required by Technical Specification 4.9.4.2 during Core Alterations, added discussion of gaseous & liquid monitor setpoint selection in the event that the sample contains no detectable activity, added minimum holdup requirements for Waste Gas
} Decay Tanks, revised dispersion parameters & accompanying description per FSAR Change Notice 88-42.
APA-ZZ-01003 August 1989 Radiological Effluent Technical Rev. O Specifications were moved from the Callaway Plant Standard Technical Specifications to Section 9.0, Radioactive Effluent Controls, of the ODCM as per NRC Generic Letter 89-01. At the same time, in order to formalize control of the entire ODCM, it was converted to APA-Z"-01003, OFFSITE DOSE CALCULATION MANUAL.
)
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APA-ZZ-01003 Roy. 1 0FFSITE DOSE CALCULA1 ION MANUAL l 1.0 PURPOSE AND SCOPE 1.1 The OFFSITE DOSE CALCULATION MANUAL (ODCM) describes the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM also contains the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semi-annual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6 and 6.9.1.7. The ODCM also contains a list and descriptt,on of the specific sample locations for the radiological environmental monitoring.
program.
2.0 , LIQUID EFFLUENTS 2.1 RADIOACTIVE EFFLUENT CONTROLS (REC) SECTION 9.1.1.1 i
41838 The radioactive liquid effluent monitoring.
instrumentation channels shall be OPERABLE with their alarm / trip-setpoints set to ensure that the limits of Section 9.3.1.1 are not exceeded. The 41840 alarm / trip setpoints of these channels shall be adjusted to the values determined in accordance with the methodology and parameters in the ODCM.
1 l
l
APA-ZZ-01003 Rev. 1
) 2.2 Liquid Effluent Monitors Cross radioactivity monitors which provide for automatic termination of liquid effluent releases are present on the liquid effluent lines. Flow rate measurement devices are present on the liquid effluent lines and the discharge line (cooling tower blowdown). Setpoints, precautions, and limitatiorno applicable to the '
operation of the callaway Plant liquid effluent monitors are provided in the appropriate Plant Procedures. Setpoint values are calculated to r assure that alarm and trip actions occur prior to exceeding the Maximum Permissible Concentration (MPC) limits in 10 CFR Part'20 at the release point to the UNRESTRICTED AREh. The calculated alarm and trip action setpoints for the liquid effluent line monitors and flow measuring devices must satisfy the following equations t 1
cf < C
~
F+f (2.1)
] Where:
C= the liquid effluent concentration limit (MPC) implementing Section 9.3.1.1 for the site in (pci/ml).
c= The setpoint, in-(pC1/ml), of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, which is inversely related to the volumetric flow of the L
effluent line and directly related to the volumetric flow of the dilution stream plus the effluent stream, represents a value, which, if exceeded, would result in concentrations exceeding the limits of 10 CFR Part 20 in the UNRESTRICTED AREA.
2
) -
e APA-20-01003 Rev. 1 f= The flow setpoint as measured at the radiation monitor location, in volume per 4
unit time, but in the same units as F, belen.
, F= The dilution water flow setpoint as measured prior to the release point, in volume per unit time. (If (F) is large compared to (f), then F + f a F), t (Ref. 11.8.1)
If no dilution is provided, then c < C.
The radioactive liquid waste stream is diluted by the plant discharge line prior to entry into the Missouri River. Normally, the dilution flow is '
, obtained from the cooling tower blowdown, but should this become. unavailable, the plant water 'i
. treatment facility supplies the necessary dilution flow via a bypass line. The batch release limiting concentration (c) which corresponds to the liquid radwaste effluent line monitor setpoint is to be calculated using methodology from the expression above.
1 o
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APA-ZZ-03003 i
, Rev. 1 L ,
j i
) Thus, the expression for determining the setpoint on the liquid radwaste effluent line monitot becomes:
c5 c(r + f) (vci/ml) ,
f (2.2)
The alarm / trip setpoint calculations are based on the minimum dilution flow rate (cooling tower blowdown, 5000 gpm), the' maximum effluent stream flow rate,-and the actual isotopic analysis. Due '
to the possibility of a simulataneous release from more than one release pathway, a portion of the-total site release limit is allocated to each -
pathway. The determination and usage of the allocation factor is discussed in Section 2.3.
In the event the alarm / trip setpoint is reached, an evaluation will be performed using actual dilution and effluent flow values and actual g- - - isotopic analysis to ensure that Section 9-,3.1.1 at limits were not exceeded.
- 2.2.1 continuous Liquid Effluent Monitors The radiation detection monitors associated with continuous liquid effluent releases are (Ref.
11.6.1, 11.6.2):
j Monitor I.D. Description BM-RE-52 Steam Generator Blowdown Discharge Monitor LE-RE-59 Turbine Building Drain Monitor 4-
\
)
M
- -- i g ew -*v*,**7gsyfMN -W-e-w
- 4 w og,tp ? y?- w-pe-fe--we-1- fve9eier-we-
- GT y 6 w' f v-g w g-v t- w-
_ _ _ . - . ~
i 6 APA-ZZ-01003 Rev. 1
- . )
These effluent streams are not consicered to be radioactive unless radioactivity has been detected by the associated effluent radiation monitor or by laboratory analysis. The sampling i frequency, minimum analysis frequency, and type i
of analysis performed are as per Table 9.3-A. i Since the Turbine Building Drain is not a -
designated liquid radioactive effluent discharge point, its setpoint is established as a function of background, t
2.2.2 Radioactive Liquid Batch Release Effluent '
Monitors The two radiation monitors which are associated I with the 11guld effluent batch release systems !
, are (Ref. 11.6.4, 11.6.5):
MONITOR I.D. Description HB-RE-18 Liquid Radwaste Discharge Monitor ;
HF-RE-45 Secondary Liquid Waste i 1 System Monitor c
b These effluent streams-are normally considered to be radioactive. The sampling frequency, minimum 4 analysis frequency, and the type of analysis ,
performed are as per Table 9.3-A. !
2.3- Calculation of Liquid Effluent Monitor Setpoints i
The dependence of the setpoint'(c), on the radionuclide distribution, yields, calibration, ;
and monitor parameters, requires that several variables be considered in setpoint calculations. 1 (Ref. 11.8.1) 1
APA-22-01003 Rev. 1
) 2.3.1 Calculation of the MPC Sum l The isotopic concentration of the release (s) being considered must be determined. This is obtained from the analyses required per Table 9.3-A, and is used to calculate an MPC sum (MPCSUM):
MPCSUM =
(I(C,)1 (MPCg)3)+(C,/MPC,)*;C,/MPC,)+(C
/ g /MPCt )+(Cf /MPC f ) (2.3) ,
i Where (Cg)g = the concentration (Cg) of each measured gamma emitting nuclide, 1, observed by gamma-ray spectroscopy of the waste sample.
)
C,* = the measured concentration (C,) of alpha emitting nuclides observed by gross alpha analysis.
C,* = the measured concentrations of Sr-89 and Sr-90 as determined by analysis of the quarterly composite sample, C g * = the measured concentration of H-3 in liquid offluents.
Cf * = the measured concentration of Fe-55 in-liquid waste as determined by analysis of lL the quarterly composite sample..
l
= Values for these concentrations will be based on previous composite sample analyses as vs ' ired by Table 9.3-A.
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.. _. .. ~ . _ - _ _ . . . . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . - _ . .
APA-22-01003 Rev. 1 y
MPC a are the limiting 9 , MPC,, MFC,, MPCf, MPC t concentrations of the appropriate radionuclides from 10CFR 20, Appendix B, Table II, Column 2.
For dissolved or entrained noble gases, the concentration shall be limited to 2x10 pC1/mi !
total activity. j SF = the safety factor; an administrative factor used to compensate for statistical fluctuations and errors of measurements. :
This factor also provides a margin of l' safety in the calculation of the maximum liquid effluent discharge flowrate (f,,x).
The value of SF chould be $1. i For the' case MPCSUM $ 1, the monitor tank effluent concentration meets the limits of section 9.3.1.1 without dilution and the effluent '
may be released at any desired flow rate. If MPCSUM > 1 then dilution is required to ensure compliance with Section 9.3.1.1 concentration limits. If simultaneous releases are occuring or are anticipated, an allocation fraction, N, must j 3 be applied so that available dilution flow may be ,
I apportioned among simultaneous discharge '
pathways. .The value of N may be any value ;
between 0 and 1 for a particular discharge point,- i provided-that the sum-total allocation fractions for all discharge points must be.$ 1.
} :
. . _ . , _ - . ~ . . ._.- _ _ . . _ . . _ . , _ . _ _ _ _ _ _
AFA-ZZ-01003 Rev. 1
' ) 2.3.2 Calculation of the Maximum Permissible Liquid Effluent Discharge Flowrate l 1
,The maximum permissible liquid effluent discharge
., flourate is calculated by: l f,,x $ (F + f ) (SF) p (H) + (MPCSUM) (2.4) 1 Where l f,,x = Maximum permissible liquid effluent discharge flowrate, in (gallons / minute);
f = the expected undiluted liquid effluent p
flowrate, in gpm.
i N= the allocation fraction which apportions dilution flow among simultaneous discharge pathways (see discussion above)
F, SF, & MPCSUM, are as previously defined.
The minimum value of F is 5000 gpm, which is used as a default value. The dilution water supply is
) furnished with a flow monitor which-isolates the liquid effluent discharge if the dilution fivw rate falls below the 5000 gpm minimum value.
In the event that f,,x is less than f p, then the value of f,,x is substituted into the equation for f p and a new valueoof f,,x is calculated. ,
This substitution is performed for three ,
iterations in order to calculate the correct value of f,,x.
h t
=) -
.s. ,
11 l
AFA-ZZ-01003 Rev. 1
')
2.3.3 Calculation of Liquid _Ef fluent Monitor Setpoint The liquid effluent monitors are Na!(Tl) based systems and respond primarily to gamma radiation.
Accordingly, their setpoint is based on the total concentration of gamma emitting nuclides in the effluents e = BKG + (I(C9)g
- SF) pCi/ml (2.5)
L
)
I Where c= the monitor setpoint as previoucly defined, in (pC1/ml);
BMG = the monitor background prior to discharge, in (VCi/ml);
C, and SF are as previously defined, j The monitor's background is controlled at an 1 appropriate limit to ensure adequate sensitivity.
U+.ilizing the methodology of ANSI N13.10-1974 (Ref. 11.21), the background must be maintained at a value of less than or equal to 2.23E-6 pCi/ml (relative to CB-137) in order to detect a change of 1E-7 pC1/ml of I-134 (the moet restrictive nuclide in Table 1 of reference 11.21).
In the event that there is no detectable gamma activity in the effluent or if the value of (I(Cg)1*SF) is less than the background of the monitor, then the monitor setpoint vill be set at twice the current background of the monitor.
ATA-0Z-01003 Kev. 1
) As previously stated, the monitor's response is dependent on the gamma emitting radionuclide distribution of the effluent. Accordingly, a new database conversion factor is calculated for each release based upon the results of the gamma spectrometric analysis of the effluent sample and the measured response of the monitor to the National Bureau of Standards (NBS) traceable calibration sources:
DBCF c = (I(Cg)3 )+ (CMR) x (ECF) (2.6)
Where:
DBCF = the monitor data base conversion factor c
which converts count rate into concentration (VCi/ml);
CMR = the calculated response of the radiction monitor to the liquid effluent; ECF = the conversion factor for Cs-137, which
) converts count rate into concentration
( pCi/ml ) .
C g
is as previously defined.
The new value of the DBCF c is calculated and entered into the monitor data base prior to each discharge. A more complete discuesion of the derivation and calculation of the CMR is given in reference 11.14.7.
- 10 -
)
r APA-ZZ-01003 Rov . - 1 2.4 Liquid Effluent Concentration Measurements 41846 2.4.1 REC Section 9.3.1.1 4160 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS 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 2.0 E-04 pC1/ml total activity.
2.4.2 Liquid Effluent Concentration Measurements
, Liquid batch releases are discharged as a discrete volume and each release is authorized based upon the sample analysis and the dilution flow rate existing in the discharge line at time of release. To assure representative sampling, each liquid monitor tank is isolated and thoroughly mixed by recirculation of tank contents prior to sample collection. The methods for mixing, sampling,.and analyzing each batch
.) are outlined in applicable plant procedures. The allowable release rate limit is calculated for '
each. batch based upon the pre-release analysis, dilution flow-rate, and other procedural conditions, prior to authorisation for release.
The radwaste liquid effluent discharge is ;
monitored prior to entering the dilution oischarge line and will automatically be terminated if the pre-selected alarm / trip !
setpoint is exceeded. Concentrations are determined primarily from the gamma isotopic, H-3, & gross alpha ana' lyses of the liquid batch sample. For Sr-89, Sr-90, & Fe-55, the measured concentration from the previous' composite analysis is used. Composite samples are collected for each batch release and. quarterly- l analyses are per. formed in accordance with Table i 9.3-A.
i 1.
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,.-.1._,. . _ . _ . , , - - . _ . _ _ . , _ . _ . , . . _ _ _ . . - _ . _ . _ . . , . _ _ _ _ . _ . _ . . _ c. _
I ATA-ZZ-01003 Rev. 1
) Doses from liquids discharged as continuous releases are calculated by utilizing the last measured values of samples required in accordance j with Table 9.3-A.
2.5 Dose Due to Liquid Effluen*s 41849 2.5.1 REC Section 9.4.1.1 4160 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid l effluents released, to UNRESTRICTED AREAS thall 1 be limited: !
r a. During any calendar quarter to less than or l equal to 1.5 mrem to the whole body and less l than or equal to 5 mrem to any organ, and u
- b. During any calendar year to less than or equal i to 3 mrem to the total body and to less than l or equal to 10-mrem tn any organ. l 2.5.2 The Maximum Exposed Individual The cumulative dose determination considers the-
-)
dose contributions from the maximum exposed individual's consumption of fish and potable i;
! water, as appropriate. Normally, the adult is ,
considered to be the maximum exposed individual. l (Ref, 11.8.3)
The Callaway Plant's liquid effluents are discharged to the Missouri _ River. As there are no potable water intakes within 50 miles of the !
discharge point (Ref. 11.7.1, 11.6.6), this ;
pathway does not require routine evaluation.
Therefore, the dose contribution from fish consumption is expected to account for more than 95% of the total man-rem dcse from discharges to the Missouri River. Dose from recreational activities is expected to contribute the 3 additional 5%, which-is considered to be negligible. (Ref. 11.6.7)
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ii i i Agu APA-ZZ-01003 Rev. 1
) 2.5.3 Calculation of Doce From Liquid Ef fluents 2.5.3.1 calculation of Doce contributions The dot.e contributions for the total time period m
IAt g tu1 are calculated at least once each 31 days and a cumulative summation vi the total body and individual organ doses is maintained for each calendar quarter. Thece doce contributions are calculated for all radionuclides identified in liquid offluents released to UNRESTRICTED AREAS using the following expression (Ref. 11.8.3) m D, = I [Ah I 6t g C it F) g (2.12) i g,y Where:
D t = the cumulative dose commitment to the total body or any organ, t, from the liquid effluents for the total period m
Ibt g ini in mrem.
j - 13 -
APA "Z-01003 Rev. 1
) Atg = the length of the tth time period over which C gg and Fg are averaged for all liquid releases, in hours. At g corresponds to the actual duration of the release (s).
C yg a the average measured concentration of radionuclide, i, in undiluted liquid effluent during time period At g from any liquid release, in (uci/ml).
A = the site related ingestion dose commitment 3
factor to the total body or any organ t for each identified principal gamma and beta emitter listed in Table 9.3-A, (in mrem /hr) per (uci/ml). The calculation of the A it values is detailed in Ref. 11.14.5 and are given in Table 1.
Ft u the near field average dilution factor for C gg during any liquid effluent release.
) f t =
I max (F+ f,ag) 89.77 Where f = maximum undiluted effluent flow rate ngx during the release F= average dilution flow 89.77 = site specific applicable factor for the mixing effect of the discharge structure. (Ref 11.5.1)
The term C is the undiluted concentration of it radioactive f.aterial in liquid waste at the common reloade point determined in accordance with Section 9.3.1.1, Table 9.3-A, " Radioactive Liquid Waste Sampling and Analysis Program". All dilution factors beyond the sample point (s) are included in the F t t*#**
s 1
ATA-02-0 003 Rev. 1
) The nearest municipal potable water intake downstream from the liquid effluent discharge ,
point into the Missouri River is located near the city of St. Louis, Mo., approximately 78 miles downstream. As there are currently no potable water intakes within 50 river miles of the discharge point, the drinking water pathway is not included in dose estimates to the maximally exposed individual, or in dose estimates to the population. Should future water intakes be constructed within 10 river miles downstream of the discharge point, then this manual will be ,
revised to include this pathway in dose estimates. (Ref. 11.6.6).
2.5.4 Summary, Calculation of _ Dose Due _',o Liquid Effluents The dose contribution for the total time period m
16t g t=1
) is determined by calculation at least once per 31
/ days and a cumulative summation of the total body and organ doses is maintained for each calendar quarter. The projected dose contribution from liquid effluents for which radionuclide concentrations. are determined by periodic composite and grab sample analysis, may be approximated by using the last measured value.
Dose contributions are determined for all radionuclides identified in liquid effluents released to UNRESTRICTED AREAS. Nuclides which are not detected in the analyses are reported as "less than" the nuclide's Minimum Detectable
,.- Activity (MDA) and are not reported as being present at Ethe Lower Level of Detection (LLD) level for that nuclide. The "less than" values are- not used in the required dose calculations.
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AtA*!! 01003 Kev. I 1 AI LL 1 IN0tST!DN DD50 COMMITFLNT IACTOR (Ag) EDk ADVLT AOL CLD"P (aren./ ht) pe r (wc t/a l) l 1 i l Total I i i i I INucittel tone 1 Live' I tow l Tbyreid I ridney i Iw r, t 01 Lt1__1 l lb 3 (No Data 10. 6t *01 l:.:t t*01l2.26L 01 12.:(t*0112.260 0112.000 0!!
I te*7 l1.30t 02l:.96t*0: l1.45t*02tNo Data 13.15t*0:lNo Data 15. lt t+001 l C 14 13.13t+0416.06t+03 l6.26t+0316.26t+03 l6.:tt+0316.2(t+0316.26t+03l l Na 24 14.07t+0214.071+0 14.07t+02l4.07t+0 l4.07t+0:14.07t+0:14.07t+02l l t*3 14.t :L+07):.67t+06 l1.7tt+0ilho Data lho Data INo Data 15.19t+061 l Cr*51 lNo Data INo Data 11.27t*0017.6 t 01 l2.61 01 11.t9t+00l3.00t+0: 1 1 Mn 54 INo Deta 14,36t+03 16 J5t+02lNo Date l1.300+03lNo Data 11.34t+04!
l Mn*St. INo Data l1.100+0: 11.95t+011No Data 11.40t+0' INo Dat a 13.5:E+03l 1 Te*55 16.57t+C:14.54t+0: 11.06t+0:lho Data INo Data 12.53t+0:12.61t+0:1 l te*59 l1.04t+0312.44t+03 19.34L+021No Data lho Data 16.611+C:lB.13t+03) l Co 57 lNo Data l2.09t+01 13.46t+011No Dat a INo Data (Na Data 15.310+0: 1 l Co*S6 INo Data 16.94t+01 l .00t+021ho Data lhe Data lNo Data 11.61t+031 l Co*60 lNo Data 12.57t+0 15.t6t+02iNo Date lNo Data INo Data 14.6:t+031 1 Ni 63 13.11t+04):.15t+03 11.0t.t+031No Data (No Date lNo Date l4.49t+021 1 Nt*65 11.26t+0:ll.64t+01 l7.461+00lho Data lNo Data INo Data l4.16t+02l l Cu 64 INO Data 11.00t+01 l4.69t+00!ho Date l2.5 t+01lNo Data 16.50t+C21 I n 65 I:.3:I+0417.3tt+04 13.33t+04iNo Data 14.93t+041No Data l4.65t+04l I Zn t9 l4.93t+0119.44t+01 16.5tt+0DINo Data It .13t+011No Dat a l1.4;t*01) i Er 62 INo Data lNo Data 10.DI+031No Data lho Date lNo Data 12.600+03)
I tr 63 lNo Data (No Data l4.04t+01lNo Data lNo Data INo Data 15 Bit +011 l tr*64 INo Dat: INo Data 15.:(1+01)no Data INo Data INo Data l4.13t*0el I tr*85 INo Data lNo Data 12.15t+00lNo Data lNo Data lho Data 1 0 l I kb 66 the Data 11.01t+05 l4.71t+04tho Data INo Data INo Data 11.99t+041 l lib 56 INo Data 12.900+0: 11.54t+0:lNo Data lhe Data iho Data 14.00t*091 1 Rb 69 lho Data 11.90t+02 11.35t+02lNo Data lNo Dats lho Data 11.12t 111 l $r 49 10.01E+04lNo Data 16.35t+0:lSo Data lNo Dt's INo Data 13.55t+0]
l $r*90 15.44E+051No Date l1.3eI+05tNo tate the Dr.a lho Data 11.57t<041 l Er 91 14.07t+021ho Data l1.t+L+01lNo Data INo Data {ho Data 11.94t+0'l i Sr*9: 11.54E+02lNo Data 16 4BI+00lNo Data the tata INo Data ILO6t+03) l Y 90 15,75t*011No Data 11.54t 0 lNo Data lNo Date lNo Data lt.10t*031 1 Y 91M l5.440 03lNo tata l2.10t*04lho Data lNo Data INo Data 11.60I 02l l Y 91 16.43t+00lNo Data 12.05t*01lho Data lho Data INo Data 14.64t+03l l Y 92 15.05t 0;lNo Data 11.46t*031No Dv'e INe Data INo Data 16.65L+0 l l Y*t3 11.6:t*01lNo Data 14.4;t*03lNo Data INo Data iho Data 15.06t+03) 1 Zr*95 If.40t*0117.70t*0: 15.21I 0:lho Data 11.21L*01lNo Data 10.44t+0:1 l 3r 97 11.33t*0:12.66t*03 l1.22t*03tNo Data 14.0et 03lNo nata 16.30t+0: 1 l Nt>*95 14.47t+0:l: .46t+0: 11.3et+0:lNo Data l 46t+0:lVo Data 11.51t+0tl 1 Mo*99 lNo Data 11.03t+0: 11.9ft+01lNo Data l0.33t+C:lNo Data 12.39t+0: 1 1 Tc 99Hl6.67t 0312.51t*0: lL 19t*01lho Data 13.610 0111,03t 02l1.46t+01]
l Tc 10119.11t 05l1.31L*0: 11.09t 011No Data 10.3tt 0116.70L*03l 0 l 1 ku 10314.4:f+00lNo Data 11.90t+00lho Data l1.69t+011No Data 15.17t+00l 1 ku 10513,66t 011No Data 11.45t*011No Data l4.76t+00lNo Data 12.25t+02l l Ru 10616.5)E+011No Data IB.3:l+00lNo Data 11.27t+0 lNo Data l4. 5E+031 1 Cd 1091No Data 15.54t+02 11.94L+01lNo Data 15.31t+0:lNo Data 15.59t+031 i Sn*1'315.6tts 11.6103 13.06t3 19.160 INo Data INo Data 11.t9t5 l l Sb.1:4l6.69t+00l1. tt 01 10.65t+00ll.t:t*0: the Data l5.01E+00ll.9;t+00l
}
.u.
i- .z L APA !!*01003 Kev, 1-1 f TABLE 1 (Continued)-
INCEST 10N DOSE C0!!MITMENT TACTOR (Ah) TOR AGULT ACE CROL'P j p (mrem /ht) per (pci/ml)
I.
j'- ..l- l i .I Total l l l l l
.lNuclidel Bow I Liver I Body -l Thyroid I ridney I Lunt I Cl LL! I ISb 125'l4 48E+0014 J6E 02.11.02E+0014.35E 03 (No Data 13.30E+0014.71E+01 lTe=1:5!!)2.57t+03l9.30E+02 l3.44E+02l7.7:E+02 11.04E+04lNo Data 11.02E+04 ITe 127Hl6.47t e03): 3:E+03 17.90E+0211.66t+03 l .63E+04lNo Data 12.17E+04l-lTe 127 11.0$t+0:13.76E+01 l .:EE+01l7.60E+01 14 49E+02 lNo Data- l8.30E+03l -
lTe 129till.10E+04l4.11E+03 l1.74E+0313,76E+03 14.60E+04lNo Data 15.54E+04l ITe 129 l3.01E+01l1.13E+01 l7.33E+00l2.31E+01 \146E+0 lNo Date l2,27t+01l-lTe 131?;1.66t+03l8.09E+02 l6.75E+0 l1 46E+03 16.21E+03lNo-Data l8.03E+04l i
(Te 131 11.89E+0117.66E+00 l5.96E+0011.55E+01 l6.25E+t,1lNo Data - l2.67E+001 (Te 132 l2.41E+03l1.56E+03 ll.47E+03l1,7 E+03 II,50E+04lNo Data 17.36E+041
-11 _130 12.711'+0116.01E+01 13.16E+0116.790+03 11.25E+02lNo Data 16.89E+01l l1*131 11.49E+0:12.14E+0 11a:E+0:17.00E+04 l3.66E+02lNo Data 15.64E+011-Ily132 17.29E+00l1.95E+01 16.8:E+00l6.6:E+02 3.11E+0llNo Date 13.66t+00l-11 133 15.10E+01l8,67E+01 l2.70E+0111. JOE +04- 1.53E+00P.o Data 17.97E+011
!! 134 13.81E+00ll .03E+01 13. 70E+00l1.79E+00 - l1.e4E+01lNo Data l9.01E 03l -
1lI 135 -l1.59E+01l4.16E+01 (1.54E+01}:.75E403 l6.66E+01lNo Dats l4.70E+01l lCs 134 l0.96E+05l7.09E+05 15.80E+05lNo Data 12.29E+05l7.6:E+0411,24E+04l
' lCo 136 13.1:E+04 lla3E+05 l6.86E+04lNo Dat a --l6.65E+04l9.39E+0311.40E+04l-3 lCs 137.l3.8 E+05)$ 2:E+05.13.4:E+05lNo Data- l1.77E+05l5.69E+0411.01E+041-
.) lCs 138 12.64E+0215.22E+02 l2.59E+02lNo Date l3.64E+0213.79E+01l2.23E 03l (Ba*139 19 49E 0116.62E 04 l:.7:E 0 lNo Data- l6.19E 0413.76E 0411.65E+00j lBa 140 11.94E+02l2.44E 01 l1.27t+01lNo Data '18.31E 0 l1,40E 01I4.00E+0:1 IBa 141 14.50E 01l3440E 04 l1.52E 02lNo Data l3.16E 04l1.93E 04l2.1:E 101-(Ba 142 l2.04E 01l2.09E 04 l1.28E 0:lNo Data ,ll.77E 04l1'19E 04l 0 l-lLa 140-l1.50E 01l7.53E 02 l1.99E 02iNo Date (No Data lNo Data 15.53E+031
, flLa 142 17.65E 0313.48E 03 (8.e6E 04lNo Data INo Datis lNo Dat'a 12.54E+01l lCe 141 l 44E 0:ll.51E 00'11.7:E 03lNo Data l7.03E 03]No Data l5.76E+01l lCo 143 l3.94E 03l0.92E+0013.23E 04lNo Data - ll.08E 03lNo Data 11.09E+02l -
lCo 144 l1.17E+00l4.68E 01 l6.06E 02lNo Data 12.89E OllNo Data 13.94E+0 !
1 . lPr 143 15.5U 01l0.21E 01. l2.73E 0:lNo Data. .1147E-011No Data l ,41E+0Ji -
ilNd 147-j3.76E*0114.35E 01 l2.60E 00lNo Date 12.54E 01lNo Data 10,09E+031 leu 154'l3.67El 14.52E0 -l3.21E0lNo Data- 12.16El- lNo Data 13- DE3 'l l:
lHf 181 l3.99E 02l1.94E-01 l1.80E 0:lNo Data 14.17E-02lNo Data l2 21E+0:1 lW 187 l 96E+00l2,47t+02'l6.64E4011No Data INo Data lNo Date lE.09E+04l INp 239 12,84E 02l .60E 031ll.54E 03lNo Data; 18.72E 03lNo Data 15.74E+0:1 -)
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l 17 l.
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!?
APA-ZZ-01003 Rev. 1 TABLE 2
) BIOACCUNULATION FACTOR (BF3) USED IN THE ABSENCE OF SITE-SPECIFIC DATA"
,(pCi/kg) per (pCi/ liter)
BF 3
Element Fish I. Freshwater)
H 9.0 E - 01 Be 2.0 E + 00 C 4.6 E + 03 Na 1.0 E + O2 P 1.0 E + 05 Cr 2.0 E + O2 Mn 4.0 E + O2 Fe 1.0 E + O2 Co 5.0 E + 01 Ni 1.0 E + O2 Cu 5.0 E + 01 Zn 2.0 E + 03 Br 4.2 E + O2 Rb 2.0 E + 03 Sr 3.0 E + 01 Y 2.5 E + 01 Zr 3.3 E + 00 Nb 3.0 E + 04
) Mo Tc 1.0 E + 01 1.5 E + 01 Ru 1.0 E + 01 Rh 1.0 E + 01 Cd 2.0 E + O2 Sn 3.0 E + 03 Sb 1.0 E + 00 Te 4.0 E + O2 7 1.5 E + 01 Cs 2.0 E +-03 Ba 4.0 E + 00 La 2.5 E + 01 Co 1.0 E + 00 Pr 2.5 E + 01 Nd 2.5 E + 01 Eu 2.5 E + 01 Hf 3.3 E + 00 W 1.2 E + 03 Np 1.0 E + 01 (a). Values from Regulatory Guido 1.109, Rev 1, Table A-1 and References 11.14.4 and 11.14.8.
) -
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APA-ZZ-01003 Rev. 1
)-- 2.6 LIQUID RADWASTE TREATMENT SYSTEM r -4160 2.6.1 REC Section 9.5.1.1 41851 The LIQUID RADWASTE TREATMENT SYSTEM shall be OPERABLE and appropriate portions of the system shall be used to reduce releases of radioactivity when the pro.4ected doses due to the liquid effluent, to UNRESTRICTED AREAS, would exceed 0,06 mrem to the total body or 0.2 mrem to any organ in a 31-day period.
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APA-ZZ-01003 l Rev. 1
' \ .-
I 2.6.2 OPERABILITY Of The LIQUID RADWASTE TREATMENT SYSTEM '
The LIQUID RADWASTE TREATMENT SYSTEM is capable of varying treatment, depending on vaste type and product desired._ It is capable of concentrating, '
gas stripping, and distillation of liquid wastes through the use of the evaporator system. The demineralization system is capable of removing radioactive ions from solutions to be reused as makeup water. Filtration is performed on certain liquid wastes and it may, in some cases, be the only required treatment prior to release. The system has the ability to absorb halides through the use of charcoal filters prior to their release.
'The design and operation requirements of the LIQUID RADWASTE TREATMENT SYSTEM provide assurance that releases of radioactive materials in liquid effluents will be kept "As Low As Reasonably Achievable" (ALARA).
The OPERABILITY of the LIQUID RADWASTE TREATMENT SYSTEM ensures this system will be available for 3
-) use when liquids require treatment prior to their
~
release to the environment. OPERABILITY is demonstrated through compliance with Sections <
9.3.1.1 and 9.4.1.1. :
Projected doses due to liquid releases to UNRESTRICTED AREAS are determined each'31 days by dividing the cummulative annual total by the number of elapsed months.
s
APA-ZZ-01003-Rev. 1 , 1
-2902 '3.O GASEOUS EFFLUENTS 41842 3.1 REC Section 9.2.1.1 4160 The radioactive gaseous effluent monitoring -!
instrumentation channels shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 9.6.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be adjusted to the values determined in accordance with the methodology and parameters in the ODCM.
41853 3.2 RE'? Secti on 9. 6.1.1 4160 The Cose rate due to radioactive materials-released in gaseous effluents from the site to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. For noble gases: Less than or equal to 500 mrem /yr to the total body and less than or equal to 3000 mrem /yr to the skin, and b, For Iodine -.131 and 133, for tritium, and for all radionuclides in particulate form with
) half 13ves greater than 8 days: Less than or equal to 1500 mrem /yr, to any organ,.from the inhalation pathway only.
3.3 Gaseous-Effluent Monitors Noble gas activity monitors are present-on-the containment building ventilation system, plant
-unit ventilation 1 system,'and radwaste building
- ventilation system.
HThe alarm / trip (alarm u trip) setpoint for any
-gaseous effluent radiation monitor is determined l based on the instantaneous noble gas total body l
and skin dose rate limits of Section 9.6.1.1, at L the SITE BOUNDARY location with the highest
[ annual average X/Q value. (Figure 5.1B) l' 1
h
_ m - _ . __ . . . . . _ . ._.
APA-ZZ-OlOO3 Rev 1 7
Each monitor channel is provided with a-two level system which provides sequential alarms on increasing radioactivity levels. These setpoints are designated as alert setpoints and alarm / trip setpoints. (Ref. 11.6.3)
The radiation monitor alarm / trip setpoints for each release point are based on the radioactive noble gases in gaseous effluents. It is not considered practicable to apply instantaneous alarm / trip setpoints to integrating radiation monitors sensitive to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases. Conservative assumptions may be necessary in establishing setpointo to account for_ system variables, such as the measurement system efficiency and detection capabilities during normal, anticipated, and unusual-operating conditions, the variability in release flow and principal radionuclides, and the time lag between alarm / trip action and the final isolation of the radioactive effluent. (Ref, 11.8.5.) Table 9.2-B provides the instrument surveillance _ requirements, . such as calibration, source checking, functional testing, and channel checking.
}
3.3.1 Continuous Release Gaseous Effluent Monitors The radiation detection monitors associated-with continuous gaseous effluent releases are (Ref.
11.6.8, 11.6,9):
Monitor I.D. Description-GT-RE-21 Unit Vent GH-RE-10 Radwaste Building Vent Each of the above continuously monitors gaseous i
radioactivity concentrations-downstream of the last point of potential influent,'and therefore l measures-effluents and not inplant L
concentrations.
\
I
.APA-ZZ-01003-Rev. 1 l i
The Unit Vent monitor continuously monitors the effluent from the unit vent for gaseous radioactivity. The Unit Vent, via ventilation exhaust systems, continuously purges various tanks and sumps normally containing low-level i radioactive aerated liquids that can potentially generate airborne activity.
The exhaust systems which supply air to the unit vent are from the fuel building, auxiliary building,-the access control area, the containment purge, and the condenser air discharge.
The Unit Vent monitor provides alarm functions only, and does not terminate releases from the Unit Vent.
The Radwaste-Building Ventilation effluent monitor continuously monitors for gaseous radioactivity in the effluent duct downstream of
-the exhaust filter and fans. The flow path provides ventilation exhaust for all parts of the- l building structure and components within the building and provides a discharge path for the waste gas decay tank release line. These
}+ components represent' potential sources for the release of gaseous and air particulate and iodine activities in addition to the drainage sumps, tanks, and equipment purged by the waste processing system.
This monitor will' isolate the waste gas decay ,
tank discharge:line upon a high gaseoue radioactivity alarm. i l~
. __ ._ _ . .~ . _
APA 2'2-01003 Rev. 1
)
The continuous gaseous effluent monitor setpoints are established using the method'> logy described in Section 3.4. Since there are.two continuous gaseous effluent release points, a fraction of the total dose rate limit (DRL) will be allocated to 2ach release point. Neglecting the batch releases, the plant Unit Vent monitor has been allocated 0.7 DRL and the Radwaste Building Vent-monitor has been allocated 0.3 DRL, These allocation factors may be changed as required to support plant operational needs, but shall not be allowed to exceed unity (i.e. 1.0), Therefore, a particular monitor reaching the setpoint would not necessarily mean the dose rate limit at the SITE BOUNDARY is being exceeded; the alarm only indicates that the specific release po *tt is contributing a greater fraction of the 40se rate limit-than was allocated to the associated monitor, and will necessitate an evaluation of
'both systems,
'3,3.2 Batch Release Gaseous Monitors The radiation monitors associated with batch release gaseous effluents are-(Ref, 11.6.9,
) 11.6.10, 11,6,11):
Monitor I.D. Description GT-RE-22 Containment Purge System GT-RE-33 GH-RE-10 -Radwaste Building Vent The Containment Purge System monitors continuously monitor the containment purge exhaust duct during purge operations for-gaseous radioactivity. The primary purpose of these monitors is-to isolate the containment purge system on high gaseous activity via the ESFAS.
The sample points are located outside the containment between the containment isolation
APA-ZZ-01003 Rev.-1 dampers and the containment purge filter:adsorber unit.
The Radwaste Building Vent nonitor was previously described in Section 3.3.1.
Setpoints for the batch gaseous effluent monitors are calculated using the methodology described in Section 3,4.
A pre-release isotopic analysis is performed for each batch release to determine the identity and quantity of the principal radionuclides. The alarm / trip setpoint(s) is adjusted accordingly to ensure that the limits of Section 9.6.1.1 are not exceeded.
3.4 Determination of Gaseous Effluent Munitor Setpoints The alarm / trip setpoint for gaseous effluent monitors is determined based on the lesser of the total body dose rate and skin dose rate, as calculated for the SITE BOUNDARY.
T.uring. core alterations, the setpoint for the-1 Containment Purge Monitors, GT-RE-22 and GT-RE-33 is set at a value of less than or equal to SE-3 pCi/ce, as required by Technical Specification .
4.9.4.2. The actual setpoint value will be reduced according to the Instrument Loop Uncertainty Estimate (ILUE). This value will also be uti'lized in the event that there is no ;
detectable noble gas activity in the containment ,
atmosphere sample analyzed in accordance with Section 9.6.1.1. The full derivation of-this value is discussed in reference 11.14.~6.
l l
}
l
l
~APA-ZZ-01003 i Rev. 1 ,
I
} 3.4.1 Total Body Dose Rate Setpoint Calculations-To ensure that the limits of Section 9.6.1.1 are n,e t , the alarm / trip setpoint based on the total body dose rate is calculated according to:
Stb $ D tbN tb F ,F, (3.1)
Where:
Stb = the alarm / trip setpoint based on the total body dose rate (pCi/cc).
Dtb = Section 9.6.1,l' limit of 500 mrem /yr, conservatively interpreted as a continuous-release over a one year period.
F,= the safety factor; a conservative factor g_ used to compensate for statistical
.) fluctuations and errors of measurement.
(For' example, F, = 0.5 corresponds to a
-100% variation.) -Default value is F, =
1.0; F = the allocation factor which will modify the a
required dilution factor such that simultaneous gaseous releases may be made without exceeding.the limits of Section 9'6.1.1.
. The default value is 1/n, where n is the number of pathways planned for release.
L f
I APA-ZZ-01003 Rev. 1 l i
~
Rtb = factor used to convert dose rate to the effluent concentration as measured by the effluent monitor, an (pCi/cc) per (mrem /yr) to the total body, determined according to:
Rtb = C + [(X/Q)i IKQ)33 (3.2)
Where:
C= monitor reading.of a noble gas monitor corresponding to the sample radionuclide concentrations for the batch to be released. Concentrations are determined in accordance with Table 9.6-A. The mixture of radionuclides determined via grab sampling of the effluent stream or source is correlated to a calibration factor to T determine monitor response. The monitor 1 response is based on concentrations, not release rate, and is in units of (pC1/cc) .
E7Q = the highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY in (sec/m'). Refer to Tables 9, 10, and.12.
Kg= the total body dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrem /yr) per (pCi/m 8 ).
(Table 3)
Q1= rate of release of noble gas radionuclide, i, in (pCi/sec).
)
APA-ZZ-01003 Rev. 1 l
I I )
- Q 3 is calculated as the product of the ventilation path design flow rate and the measured activity of the effluent stream as determined by grab sampling. Flow rates fer the ventilation pathways can be found in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21, 3.4.2 Skin Dose Rate Setpoint Calculation To ensure that the limits of Section 9.6.1.1 are met, the alarm / trip setpoint based on the skin dose rate is calculated according to
S, 5 D,P.,F,F, (3.3)
Where F, and F, are as previously defined in Section j 3.4.1.1.
S,= the alarm / trip setpoint based on the skin dose rate.
D,= Section 9.6.1.1 limit of 3000 mrem /yr, conservatively interpreted as a continuous release over a one year period.
I l
l APA-ZZ-01003 l Rev 1 1
l R, =- factor used to convert dose rate to the !
effluent concentration as measured by the effluent monitor, in (pCi/cc) per (mrem /yr) to the skin, determined according to:
R, = C + [(X/Q) I (Lg + 1.1Mg ) Q3) (3.4) i Where:
Lg= the skin dose factor due to beta emissions for each identified noble gas radionuclide, 3
in . (mrem /yr) per (pCi/m ) . (Table 3) 1.1 = conversion factor: 1 mrad air dose = 1.1 mrem skin dose, a-J- My= the air dose factor due to gamma emissions for each. identified noble gas radionuclide, 3
in (mrad /yr) per (pC1/m ) . (Table 3)
C,-(X/Q) and Q 3 are as previously defined.
l:
l-l.
l 1
<- APA-ZB-01003 Rev. 1
') 3.4.3 Gaseous Effluent Monitors Setpoint-Determination The results of Equation (3.1) and Equation (3.3) are compared. The setpoint is then selected as the lesser of the two values.
1 J.
. . . . .. . ~ a - ,-- -. ..- ,. ~ _ . - .. , . . . . . ~ .
m -
- O: -m
-Q G
. Q" ' . .N .
- N
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+++++++++++++++
aw a WWWWWWWWWWWWWWW a -w 6 co%AmecmweemeNAc 08 0 0E A Lf tc s % C. e. m. O. m. o. c. ". M. O. M. c. N. N. N.
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- N r- N = = p N N a # M O e L .
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>= 0 O V W
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0-a 4 m C=
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(' W C L 4 E.M.N.M.O.N.>=.m. O.*. c.N.e-@ . .
= h I ***m NwP=# mM N p " # N E
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= L
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OO @ WWWWWWWWWWWWWWW C w
~w e =a l
1- @ >. w N k @ C h *= 3 N e= N m c 0 h
.m M *. e ae.-L '-W . .a .c. m. M. @. e. m
. -e. m. . tO. #. c. o. w
_QW h -.-N w a @ r= " " m N N M a c' C C
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'l l APA-ZZ-01003- -
Rev. .. l! [
s
)
~
3,4.4 Summary, Gaseous Effluent Monitors Setpoint! !
Determination-The gaseous effluent' monitors setpoints are calculated-according-to equations-(3.1) and (3,3)',las described-in Section-3.4. However, it should be noted that a batch-release will alter.
the' flow rate characteristics at the Unit Vent
- and therefore the concentration-as sensed by the monitor. For. example, inithe case of a mini- '
purge,' the setpoint for the Unit Vent monitor must be re-calculated to include both the 4 continuous and batch sources. !
l t
3.5- - Calculation of Dose From Gaseous Effluents- 1 Dose; rate calculations are performed for gaseous effluents.to ensure-compliance with Section 9.6.1.1.
3.5,1 Calculation of Dose Rate
- The following methodology is applicable'to the
. location (SITE BOUNDARY.or beyond) characterized. !
C by the: values'of<the parameter-(X/Q) which ,
'^
- results in the maximum total body or skin dose
). Lrate.
In.the event that the analysis indicates a-different-location for.the total body and-skin dose-limitations, the location selected for
- consideration is.that~which minimizes the I allowable release values. (Ref. 11.8,6) I
- The factors:Kg ,- L1,'and-Mg relate ~the y g radionuclide-airborne concentrations to various 3 dose rates, assuming-a= semi-infiniteLcloud:model, ;
and are-tabulated in Table-3.
l
' 3 . 5 .1,1 - Noble' Gases d m -The release rateflimitofor-noble gases is _
1 ll determined according'to the following-generalo a . : relationships (Ref..ll.8.6): ,
y; r
1
! 4
[r I
+5 i" -~r ,.yy , , . , ,
. _ . . _ . . _ . _ = _ . . . ~ . . . _ . _ .
APA-22-01003 Rev. 1 l
r; Dtb
- I IK ((X/Q)Q i ))
3 $ 500 mrem /yr (3.5) i D, =-I [(L g + 1.1 M g)((X/Q)Q g)) 5 3000 mrem /yr (3.6) i Where:
Dtb = Total body dose rate, concervatively-averaged over a period of one year.
Kg= Total body dose factor due to gamma emissions for each iaentified noble gas 9 radionuclide, in (mrem /yr) per (pCi/m 3),
} (Table 3)
(X/Q) = The highest calculated annual average relative concentration for any area at or beyond the SITE BOUNDARY. Refer to Tables 9, 10, and 12.
Q3 = ~_The release rate of noble gas radionuclides, 1, in gaseous effluents, from all vent releases in (uCi/sec).
Qg= is calculated as-the product of'the ventilation path design flow rate and the measured activity of the~ effluent stream.as determined by grab = sampling. Flow rates' for the ventilatien pathways can be found in references 11.6.18, 11.6.19, 11.6.20, and 11.6.21.
D.=
s Skin dose rate, conservatively averaged over a period of one year.
)
APA-23-01003 >
Rev. 1 l
) Skin dose factor due to beta emissions for L3=
each identified noble gas radionuclide, in (mrem /yr) per (pCi/m') (Table 3).
1.1 = Units conversion factor; 1 mrad air dose =
1.1 mrem skin dose.
Mg= Air dose factor due to gamma emissions for each identified noble gas radionuclide, in (mrad /yr) per (uCi/m') (Table 3).
3.5.1.2 Radior.uclides Other Than Noble Gases The release rate limit for Iodine-131 and-133, for tritium, and for all radioactive materials in particulate form with half lives greater than 8 days is determined according to (Ref. 11.8.7):
D, = I P [(x/Q)Q g )3 5 1500 mrem /yr (3.7) i Where D = Dose rate to any critical organ, in o
(mrem /yr).
Pg= Dose parameter for radionuclides other than noble gases for the inhalation pathway for the child, based on the critical organ, in ,
(mrem /yr) per (vCi/m'). (Table 4)
Q=g The release rate of radionuclide, i, in gaseous effluents, from all vent releases, in (pC1/sec ) . Qg is calculated as the product of the. ventilation path design flow rate and the measured activity of the effluent stream as determined by grab
. sampling. Flow rates for the_ ventilation pathways can be found in references
-11.6.18, 11.6.19, 11.6.20, and 11 6.21.
F l o l
l-
APA-ZZ-01003 Rev. 1 (X/Q) is as previously defined.
The dose parameter (P g )-includes the internal dosimetry of radionuclide, 1, and the receptor's-breathing rate, which are functions of the receptcr's age. Therefore the child age group has been selected as the-limiting age group.
For the child exposure, separate values of P g are tabulated in Table 4 for the inhalation pathway.
These: values'were calculated according to (Ref.
11.8.8):
Pg = 10 (BR) DFA g (3.8)- E Where:
K' = Units conversion factor: 1pCi = 1E06 pC1.
LBR= The breathing rate of the maximum exposed i child age-group, 3700 m'/yr. (Regulatory 27 Guide 1.109, Table E-5).
DFAg= The maximum organ inhalation dose factor for the child age group for.the ith radionuclide, in_(mrem /pCi). The total body.is considered as an organ in the selection of DFA g. (Ref. 11.11.5 and 11.14.4)
Note: All'radioiodines'are assumed to be released in elemental form. (Ref.11.8.7) l
-)
L
1 d
APA ZZ-01003-Rev. 1 ,
TABLE 4
[
DOSEPARAMETER(Pj)FORRADIONUCLIDESOTHERTHANNOBLEGASES" Inhalation Pathway (mrom/yr) per (NC1/m') !
1 l l l- l Total l l l l l lNuclidel Bone l Liver i Body 1 Thyroid i Kidney l Lung i GI-LLI l '
l H-3 ~l ND l1.12E3 'll.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 l l Be 7 l8.47E2 -l1.44E3 -19.25E2 l ND l ND 16.48E4 l2.55E3 l l C-14 .l3.59E4 l6.73E3 l6.73E3 l6.73E3 l6.73E3 16.73E3 16.73E3 l l Na 24 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l1.61E4 l-l P 32_ l2.60E6 l1.14ES. l9.88E4 l ND l ND l ND l4.22E4 l l Cr-51 l ND l ND l1.54E2 l8.55El l2.43E1 11.70E4 l1.08E3 l ,
l Mn 54 l ND l4.29E4 _19.51E3 l ND l1,00E4 jl.58E6 l2.29E4 l l Mn-56 l ND _ l1.66E0 l3.12E-1 l ND l1.67E0 11.31E4 l1.23E5 l l Fe-55-l4.74E4- 12.52E4 l7.72E3 l ND -l- ND l1.11ES l2.87E3 .l
-l Fe 59 l2.07E4 l3.34E4 l1.67E4 l ND l ND l1.27E6 l7.07E4 l j _l Co 57 l-_ ND_ _l9.03E2 l1.07E3 i ND l ND 15,07ES l1.32E4 l
') _ l Co 58'l ND l1.77E3 l3.16E3 -l ~ ND l ND l1.11E6 13.44E4 l l Co 60 l ND. l1.31E4 l2.26E4 .l ND l ND l7.07E6 19.26E4 l j.Ni-63_l8.21E5 l4.63E4 -l2.80E4 l ND- l ND l2.75ES l6.33E3 ,l l Ni 65 l2.99E0 l2.96E 1 l1.64E-1 l ND l ND l8.18E3 l8.40E4 l l:Cu-64 l ND _ l1.99E0 l1.07E0 l .ND l6.03E0 l9.58E3 l3.67E4 l l Zn-65'l4.26E4 _l1.13E5 l7.03E4 l ND l7.14E4 19.95ES l1.63E4 l l-Zn_69 16.70E 2 l9.66E 18.92E-3 l ND l5.85E 2 l1.42E3 11.02E4' l l Br-82_l ND l ND- -l2.09E4 l ND l; ND l ND .l ND l- 1
_l-Br 83.l ND l= ND l4,74E2 .I ND' l ND l ND l 0 -l l Br-84 l ND, l ND l5.48E2 l ND l ND l ND l 0 l ;
l Br-85 l ND. l ND l2.53E1 l ND l 'ND' l ND l 0 l l Rb-86 l .ND l1.98E5 l1.14E5 l ND l-ND l 'ND l7.99E3 l l Rb-88.l ND 'l5.62E2 l3.66E2. l ND j ND l ND l1.72E1 l l Rb-89;l lND l3.45E2 l2.90E2 l ND l ND _ 'l ND ll,89E0' l l.Sr-89-l5.99E5 l ND -l1.72E4 l ND- l ND l2.16E6 -l1.67E5 l Ll Sr-90Jl1.01E8 l ND -16.44E6 'l ND 1 ND .l1,48E7 13.43E5 1 <
l'Sr-91.l1.21E2 l .ND l4.59E0 l ND l ND- l5.33E4 l1.74E5 l l Sr-92 l1.31El' l ' ND .
l5.25E-1 l- ND l- ND l2.40E4 12.42E5 l l Y-90 l4.11E3 l ND l1.11E2' -l ND l ND l2.62E5 l2.68E5 l-
APA-ZZ-01003=
Rev. 1
} TABLE 4 (Cont'd.)-
a DOSE PARAMETER (Pg ) POR RADIONUCLIDES OTHER THAN NOBLE GASES Inhalation Pathway I (mrtm/yr) per (VCi/m ) 3 l l l l Total l l l l l lNuclide! Bone- l Liver I Body I Thyroid l Fidney l Lung i GI-LLI l l Y-91m 15.07E-1 l- ND- l1.84E-2 l ND l ND l2.81E3 .l1.72E3 l l Y-91 l9.14E5 l ND 12.44E4 i ND ND l2.63E6 - 11.84E5 1 l Y 92 l2.04E1 l ND l5.81E-1 l ND l ~ ND l l2.39E4 l2.39E5 l' l Y-93 '1.86E2 l ND l5.11E0 l ND l ND l7.44E4 13.89E5 l l Zr-95 l1.90E5 _l4.18E4 l3.70E4 l ND l5.96E4 l2.23E6 16.11E4 l
_l Zr 97 l1.88E2 l2.72E1 l1.60E1 l ND l3.89El l1.13E5 l3.51ES l l Nb-95 12.33E4 19.- 18E 3 l6.55E3 l ND l8.62E3 l6.14E5 13.70E4 l l Mo-99 l ND l1.72E2 l4.26El l ND l3.92E2 l1.35E5 11.27E5 l l Tc-99ml1.78E-3 l3.48E 3 15.77E 2 l ND -15.07E-2 l9.51E2 -l4.81E3 l l Tc-101l8.10E-5 l8.51E-5 l1.08E-3 l ND l1.45E 3 j5.85E2 l1.63El- l T l Ru-103l2.79E3 l ~ND l1.07E3 l ND l7.03E3 l6.62ES l4.48E4 l I l_Ru-105l1.53E0 l ND 15.55E 1 l ND l1.34E0 l1.59E4 19.95E4 l l'Ru-106l1.36E5 l ND l1.69E4 l ND l1.84E5 l1.43E7- l4.29E5 l lAg-110 mil.69E4 11.14E4 l9.14E3 l ND l2.12E4 l5.48E6 11.00E5 l
- l Cd-109l ND .l5.48E5 l2.59E4 l ND l4.96ES l1.0$E6 _l2.78E4 l
_l Sn-113l1,13E5- -l3.12E3 -l8.62E3 l2.33E3 l ND l1.46E6 l2.26ES -l l Sb-12415.74E4 l7.40E2 l2.00E4- l1.26E2 l ND l3.24E6 ll.64E5 l l Sb-125l9.84E4 ]7.59E2 l2.07E4_ l9,10E1 l ND l2.32E6 (4.03E4- l lTe-125ml6;73E3 12.33E3 19.14E2. l1.92E3 l - ND -l 4. 7 7E5 l3.38E4 l-
-lTe-127ml2.49E4 18,55E3 l3.02E3 l6.07E3 l6.36E4 l1,48E6 l7.14E4 l
'lTe-127 l2.77E0 l9.51E l6.11E 1 l1.96E0 l7.07E0 11.00E4 15,62E4 l lTe-129ml1.92E4 l6.85E3 13.04E3 16.33E3 l5.03E4 l1.76E6 l l'. 82E5 -l
- j. lTe-129 l9.77E-2 l3.50E-2 l2.38E-2 j7 :'iE-2= l2.57E-1 12.93E3 12.55E4 l l lTe-131 mil.34E2 .-15.92E1 l5.07El l9.77El l4.00E2 l2.06ES l3.08E5 _ l --
lTe 131-l2.17E-2 18.44E-3 l6.59E-3 l1.70E-2 15.88E 2 l2.05E3 11.33E3 l
-lTe-132-l4.81E2 l2.72E2 l2.63E2 l3.17E2- l1.77E3 l3.77E5. l1.38E5 l lI-130_ l8.18E3 l1.64E4- 18.44E3 l1.85E6_ l2.45E4 l ND l5.11E3 l lI-131- l4'81E4 -l4.81E4 l2.73E4- 11.62E7 ]7.88E4 -l ND l2.84E3 l lI-132- 12.12E3 l4.07E3 l1.88E3 l1.94E5 l 6'. 2S E 3 l ND l3.20E3 l lI-133 -l1.66E4 l2.03E4 17.70E3_ l3.85E6 l3.38E4 l ND l5.48E3. l
}I-134 l1.17E3 l2.16E3 l9.95E2 -l5 07E4 l3.30E3 l ND l9.55E2 l lI-135 _ l4.92E3 l8.73E3 l4.14E3 l7.92E5 l1.34E4 l ND l4.44E3 l
\
- 37.-
APA ZZ-01003 Rev. *
, TABLE 4 (Cont'd.)
)
DOSE PARAMETER (Pg ) FOR RADIONUCLIDES OTHER T}iAN NOBLE GASES" Inhalation Pathway (mrero/yr) per (pCi/m')
l l l l Total l l l l l lNuclidel Bonc 1 Liver I fedy l Thyroid l Kidney I Lung 1 01-LLIj lCs-134 l6.51E5 l1.01E6 l2.25E5 l ND 13.03E5 l).21ES l3.85E3 l lCs-136 16.51E4 l1.71E5 11.16E5 l ND 19.55E4 l1.45E4 14.18E3 l lCs-137 l9.07ES 18.25E5 l1.2BE5 l ND l2.72E5 11.04E5 13.62E3 l lCs-138 l6.33E2 l8.40E2 l5.55E2 l ND 16.22E2 l6.81El 12.70E2 l lBa 139 11.84E0 l9.84E 4 15.37E-2 l ND l6.62E 4 l5.77E3 15.77E4 l lBa-140 17.40E4 l6.48E1 '4.33E3 l ND l2.11El l1.74E6 l1.02E5 l lBa 141 12.19E-1 11.09E-4 16.36E-3 I ND 19.47E-5 12,92E3 12.75E2 l lBa-142 l5.00E-2 13.60E-5 12.79E-3 1 rid 12,91E 5 l1.64E3 12.74E0 )
lLa-140 16.44E2 l2.25E2 l7.55El l ND l ND l1.83E5 l2.26E5 l lLa-142 l1.30E0 l4.11E-1 l1.29E-1 l ND l ND l8.70E3 l7.59E4 l lCe-141 13.92E4 l1.95E4 l2.90E3 i ND l8.55E3 15.44E5 15.66E4 l
) ICc-143 l3.66E2 11.99E2 12.87El l ND 18.36El 11.15ES l1.27ES l lCo-144 l6.77E6 12.12E6 l3.61ES l ND 11.17E6 l1.20E7 l3.89ES l lPr-143 11.85E4 l5.55E3 19.14E2 1 ND 13.00E3 14.33E5 l9.73E4 l lPr-144 15.96E-2 l1.85E-2 13.00E-3 l ND l9.77E-3 l1.57E3 l1.97E2 l lNd-147 11.08E4 18.73E3 l6.81E2 l ND 14.81E3 13.28E5 18.21E4 l lEu-154 11.01E7 l9.21E5 18.40E5 l ND l4,03E6 l6.14E6 11 10E5 l liif-181 l2.78E4 11.01ES l1.25E4 l ND l2.05E4 l1.06E6 l6.62E4 l lW-187 11.63E1 l9.66E0 14.33E0 l ND l ND 14.11E4 19.10E4 l lNp-239 l4.66E2 13-34E1 l2.35El l ND l9.73E1 15.81E4 l6.40E4 l (a) The child age group; refer to reference 11.14.5.
l
-APA-ZZ-01003 Rev, 1
$ 3.5.2 Dose Due To Caseous _ Effluents 41858 3.5.2.1 REC Section 9.7.1.1 4160-The air dose due to noble gases released in gaseous effluents, to areas at and beyond the SITE BOUNDARY shall be limited to the following:
- a. During any calendar quarter:- Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and,
- b. During any calendar years Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
t 4-i i
I' l
l l l
. ~ ,
1 APA-ZZ-01003 Rev. 1 i
3.5.2.1.1 Noble cases The air dose at the SITE BOUNDARY due to noble gases released from the site is calculated according to the following methodology (Ref.
11.8.9):
During any calendar quarter, for gamma radiation l D, = 3.17E-08 I (Mg ((X/Q)_Qg + (X/q) g g)) 55 mrad (3.9) i f
During any calendar quarter, for beta radiation Db = 3.17E-08 I [Ng ((X/Q) Qg+ (X/q) q1)) $ 10 mrad (3.10) 1 During any ca'lendar year, for gamma radiation: r D = 3.17E-08 I [Mg ((X/Q) Q3+ (X/q) g g )) $ 10 mrad (3,11) g i
During any calendar year, for beta radiation L ,
i l
Db = 3.17E-08.1 [Np ((X/Q) - Qg + (X/q) gg )) $ 20 mrad (3.12) 4 i ;
a
.h
APA-ZZ-OlOO3 Rev. 1
) Where: -
D g
= Air dose from gamme radiation due to noble gases released in gaseous effluent.
Db= Air dose from beta radiation due to noble gases released in gaseous effluents.
(X/q) = The relative concentration for areas at or beyond the SITE BOUNDARY for short-term releases (equal to or less than 500 hrs / year). Refer to Tables 9, 10, 11, and 12.
gg= The average release of noble gas raddonuclides, i, in gaseous effluents from all vent releases for short-term releases (equal to or less than 500 hrs / year), in (vC1). Releases are cumulative over the calendar quarter or year, as appropriate.
N3= The air dose factor due to beta emissions for each identified noble gas radionuclide, 1, in (mrad /yr) per (pCi/m'). (Table 3)
Qg= The average release of noble gas radionuclides, i, in gaseous effluents from all vent releases for long-term releases (greater than 500 hrs / year), in (pC1).
Releases are cumulative over the calendar quarter or year, as appropriata.
(X/Q) = The highest calculated annual average relative concentration for areas at or beyond the SITE BOUNDARY for long-term releases (greater than 500 hrs /yr). Refer to Tables 9, 10, and 12.
3.17E-08 = The inverse of the number of seconds per year.
M 3
is as previously defined. (Refer to Section 3.4.1.2)
APA-ZZ-01003 I Rev. 1 l
, 41860 3.5.2.2 REC Section 9.8.1.1 4160 The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, to areas at and beyond the SITE BOUNDARY shall be limited to the following (Ref.
11.8.9):
- a. During any calendar quarter: Less than or equal to 7.5 mrem to any organ and,
- b. During any calendar year: Less than or equal to 15 mrem to any organ.
3.5.2.2.1 Rpdionuclides Other Than Noble Gases The dose to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, to areas at and beyond the SITE BOUNDARY, is calculated according to the following expressions:
I During any calendar quarter:
D 1
= 3.17E-08 I R g [W Qg + w q1) 5 7.5 mrem (3.13) i During any calendar year:
Dg = 3.17E-08 I R3 [W Q 3 + w g g) 5 15 mrem (3.14) i Where:
D 3
= Dose to a MEMBER OF THE PUBLIC from radionuclides other than noble gases.
42 -
l APA-ZZ-01003 Rev. 1 Qg = The releases of radiciodines, radioactive materials in particulate form, and radionuclides other than noble gases, 1, in gaseous offluents, for all long-term vent i releases (greater than 500 hrs /yr), in (yC1). Releases are cumulative over the calendar quarter or year as appropriate, gg= The releases of radiciodineo, radioactive materials in particulate form and radionuclides other than noble gases, i, in gaseous effluents for all short-term ven'.
releases (equal to or less than 500 hrs /yr), in (vC1) . Releases are cumulative over the calendar quarter or year as appropriate.
Rg= The dose factor for each identified radionuclide, 1, in m'(mrem /yr) per (pCf/sec) or (mrem /yr) per (pCi/m 8). (Table 5)
W=- .The dispersion parameter for estimating the
- dose to an-individual at the controlling d location for long-term releases (greater than 500 hrs /yr):
W =-(X/Q) for the inhalation and tritium pathways, in(sec/m').
W= (D/Q) for the-food and ground plane
. pathways, in(meters ~8).
Refer to' Tables 9, 10, and 12.
)
APA-ZZ-OlOO3 Rev. 1
..)
w= The disperr. ion parameter for estimating the dose to an individual at the controlling location for short-term releases (equal to or less than 500 hrs /yr):
w= (X/q) for the inhalation pathway, in(sec/m ) 8 w= (D/q) for the food and ground plane pathway, in (meters"8 ) . Refer to Tables 9,.
10, 11, and 12, 3.17 E-08 = The inverse of the number of seconds per year.
(D/Q) = the average relative deposition of the offluent at or beyond the SITE BOUNDARY, considering depletion of the plume during transport, for long term releases (greater than 500 hrs /yr), in (meters" 8).
(D/q) = the relativo deposition of the effluent
.. at or beyond the SITE BOUNDARY,
) considering depletion of the plume during transport, for short term releases (less than or equal to 500 hrs /yr), in (meters'8).
l l
~ APA- Z-01003 Rev. 1 Note: For the direction sectors with existing pathways within 5 miles from the site, the appropriate R g values are used. If no real pathway exists within 5 miles from the "j eenter of the building complex, the cow-milk R value is used, and it is assumed 3
that this pathway exists at the 4.5 to 5.0 mile distance in the limiting-case sector.
If the R 3 for an existing pathway within 5 4
miles is less than a cow-milk R g at 4.5 to ,
5.0 miles, then the value of the cow-milk Rg at 4.5 to 5.0 miles is used. (Rev.
9.8.10.)
Although the annual average relative concentration (X/Q) and the average relative deposition rate (D/Q) are generally considered to be at-the approximate receptor location in lieu of the SITE BOUNDARY for these calculations, it is acceptable to consider the ingestion, inhalation, and ground plane pathways to coexist
.at the location of the nearest residence with the
$ highest value of (X/Q). (Ref. 11.8 9) The Total J Body dose from ground plane deposition is added to the dose for each individual organ. (Ref.
11.11.3)
The cumulative critical organ doses for-a monthly, quarterly or annual evaluation aru based i on the calculated. dose contribution-from each 4 specified time period occurring during the reporting period, r
i i
I.
4 l
APA 32 01003 Rev. 1 1
)'
l- TABLE 5 PATHVAY DOSE TACTORS (Rg ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES" Inhalation Pathway (mrem /yr) per (vC1/m')
l l l l Total l l l l l lNuclidel Bone l Liver l Body l Thyroid i Eidney l Lung i GI-LLI l lH3 l ND l1.12E3 l1.12E3 l1.12E3 l1.12E3 l1.12E3 11.12E3 l l Be 7 l8.47E2 l1.44E3 l9.25E2 l ND l ND l6.48E4 12.55E3 l l C-14 13.59E4 l6.73E3 16.73E3 l6.73E3 l6.'3E3 l6.73E3 l6.73E3 l l Na-24 l1.61E4 11.61E4 l1.61E4 l 1 '. 61E4 ll.61E4 l1.61E4 l1.61E4 l l P 32 l2.60E6 l1.14E5 l9.88E4 l ND l ND l ND l4.22E4 l l Cr-51 l ND l ND l1.54E2 1 8.55El l2.43E1 l1.70E4 11.08E3 l l Mn 5.- l ND l4.29E4 19.51E3 ,
ND l1.00E4 l1.58E6 12.29E4 l l Mn 56 i ND 11.66E0 ja.12E 1 ,
ND l1.67E0 l1.31E4 11.23E5 l l Te 55 l4.74E4 l2.52E4 !7.72E3 .
ND l ND l1.11ES l2.87E3 l l Te 59 12.07E4 l3.34E4 !1.57E4 l ND l ND l1.27E6 l7.07E4 l l Co-57 l ND 19.03E2 l1.07E3 l ND l ND 15.07ES [1.32E4 l l Co 58 l ND l1.77E3 13.16E3 1 ND l ND ll.11E6 l3.44E4 l l Co 60 l ND l1.31E4 l2.26E4 l- ND l ND 17.07E6 l9.26E4 l l N1-63 l8.21ES l4.63E4 l2.80E4 l ND l ND l2.75E5 l6.33E3 l l Ni 65 l2.99E0 12.96E 1 l1.64E 1 l ND l ND 18.18E3 l8.40E4 l l Cu 64 l ND ,ll 99E0 11.07E0 l ND 16.03E0 l9.58E3 13.67E4 l l En 65 l4.26E4 l1.13E5 17.03E4 l ND l7.14E4 19.95ES 11.63E4 l j 2n 69 l6.70E 2 l9.66E 2 l8.92E 3 l ND 15.85E 2 l1.42E3 l1.02E4 -l l Br 82 i ND- l ND l2.09E4 'l ND l ND l ND l ND l l Br 83 l ND l ND l4.74E2 ; ND i ND l ND l 0 l l Br 84 l ND l ND 15.48E*. l ND l ND l ND l 0 l l Br 85 l. ND l ND l2.53E' l ND l NL l ND -l 0 l l Rb 86 l ND l1.98E5 l1.14E5 l ND l ND l ND l7.99E3 }
l Rb 88 l ND l5.62E2 l3.66E2 l ND l ND l ND l1.72E1 l l_Rb 89 l ND l3.45E2 12.90E2 l ND l ND l ND ll.89E0 l l-Sr 89-l5.99E5 -l ND ll.72E4 l ND l ND l2.16E6 l1.67ES l l Sr 90 l1,01E8 l ND l6.44E6 l ND l ND l1.48E7 13.43E5 l l Sr-91 l1.21E2 l ND l4.59E0 l ND l ND l5.33E4 l1.74E5 l l Sr-92 l1.31El l ND l5.25E-1 l -ND l ND l2.40E4 l2.42E5 l l Y 90 l4.11E3 l ND l1.11E2 l ND l ND l2.62E5 l2.68E5 l I ,
46 -
m APA ZZ 01003
'4v . 1
) TABLE 5 (Cont'dj PATINAY DOSE EA0 TORS (Rg ) POR RADIONUCLIDES OTl[ER TilAN NOBLE GASES" Inhalation Pathway (mrem /yr) per (pCi/m')
l l lNuciddel Bonc I
Liver i Total l l l l 'l l l___ Body i Thyroid 1 1:idney l Lung l Gl+LLI l l Y-91m l5.07E 1 l ND l1.84E 2 l ND l ND l2.81E3 l1.72E3 l l Y-91 l9.14E5 l ND l2.44E4 l ND l ND l2.63E6 11.84E5 l l Y 92 l2.04E1 l ND !5.21E 1 l ND l ND l2.39E4 l2.39E5 l l Y 93 11.66E2 i ND '* 11E0 l ND
. l ND l7.44E4 l3.89E5 l l Zr-95-l1.90E5 l4.18E4 3.70E4 l ND l5.96E4 l2.23E6 l6.11E4 l l Zr-97 l1.88E2 12.72E1 l1.60E1 l ND l3.89El l1.13E5 l3.51E5 1 l Nb 95 l2.33E4 l9.18E3 16.55E3 l ND l8.62E3 16.14E5 13.70E4 l l Mo-99 l ND l1.72E2 l4.26El l ND 13.92E2 l1.35E5 l1.27E5 l l Tc-99 mil,78E 3 l3.48E 3 15.77E 2 l ND 15.07E 2 l9.51E2 14.81E3 l l Tc-101l8.10E 5 18.51E 5 l1.08E 3 l ND l1.45E 3 l5.85E2 l1.63E1 _l l Ru-103l2.79E3 l ND l1.07E3 -l ND 17. 03E'l l6.62E5 l4.48E4 l l Ru-205l1.53E0 l ND l5.55E 1 l ND l1.34E0 l1.59E4 19.95E4 l l Ru 306l1.36E5 l ND ll.69E4 l ND l1.84E5 l1.43E7 l4.29E5 l lAg 110 mil.69E4 l1.14E4 l9.14E3 l ND l2.12E4 15.48E6 l1.0005 l l'Cd-1091 ND l5.48E5 l2.59E4 l ND l4.96ES l1.0$E6 l2.78E4 l l Sn-11311.13E5 13.12E3 l8.62E3 12.33E3 l ND l1.46E6 l2.26EL l l Sb 12415.74E4 17.40E2 l2.00E4 ll.26E2 l ND l3.24E6 l1.64L5 l l Sb 125l9.84E4 l7.59E2 l2.07E4 19.10E1 l ND l2.32E6 l4.03E4 l lTo 125ml6.73E3 l2.33E3 l9.14E2 l1.92E3 l ND l4.77E5 l3.38E4 l lTc 127ml2.49E4 l8.55E3 l3.02E3 l6.07E3 16.36E4 11.48E6 l7.14E4 l lTe 127 l2.77E0 l9.51E-1 16.11E 1 l1,96E0 l7.07E0 l1.00E4 l5.62E4 l lTe-129 mil.92E4 l6.85E3 l3.04E3 l6.33E3 15.03E4 l1.76E6 l1.82E5 l lTe 129 19.77E 2 l3.50E 2 12.38E 2 l7.14E 2 12.57E 1 12.93E3 l2.55E4 l lTe 131 mil.34E2 l5.92E1 l$.07El l9.77El l4.00E2 l2.06ES l3.08E5 l lTe 131 1".17E 2 l8.44E-3 16.59E 3 l1.70E-2 15.88E 2 l2.05E3 l1.33E3 l lTo-132 l4.81E2 l2.72E2 l2.63E2 13.17E2 l1.77E3 l3.77ES l1.38E5 l lI 130 l8.18E3_l1.64E4 18.44E3 -l1.85E6 l2.45E4 l ND 15.11E3 l lI 131 la.81E4 14.81E4 l2.73E4 l1.62E7 l7.8&E4 l ND l2.84E3 l 11-132 12.12E3 l4.07E3 l1.88E3 l1.94E5 16.25E3 l ND l3.20E3 l lI 133 11.66E4 l2.03E4 l7.70E3 l3.85E6 13.38E4 l ND 15.48E3 l lI 134 l1.17E3 l2.16E3 l9.95E2 l5.07E4 l3.30E3 l ND l9.55E2 l I
47 -
APA ZZ 01003 Rev. 1
) TABLE 5 (Cont 'd.)
PAT}NAY DDSE FACTORS (Rg ) FOR RADIONUCLIDES OTl!ER T}(AN N0bLE GASES" Inhalation Pathway (mrem /yr) per (pC1/m')
l l 1 I Total l l l l l lNuclidel _Fone i Elver i _Pody l Thyroid l Kidney _l Lung 1 01 LL1 l l1 135 l4.92E3 lB.73E3 l4.14E3 17.92E5 l1.34E4 l ND l4.44E3 l lCs-134 l6 51E5 11.0106 12.25E5 l ND 13.03E5 11.21E5 13.0$E3 l lCs-136 16.51E4 11.71E5 11.16E5 l ND l9.55E4 11.45E4 l4.16E3 l lCs 137 19.07E5 16.25E5 11.26E5 i ND l2.72E5 11.04E5 13.62E3 l lCs 136 l6.33E2 l6.40E0 15.55E2 l ND 16.22E2 l6.81El l2.70E2 l lBc.139 11,64E0 l9.64E 4 l5.37E 2 l ND lB.62E 4 15.77E3 l5.77E4 l lBa 140 17.40E4 16.46El 14.33E3 i ND l2.11El l1.74E6 l1,02E5 l lBa 141 l2.19E 1 11.09E 4 l6.36E 3 l ND 19.47E 5 12.92E3 12.75E2 l lBa 142 l5.00E 2 13.60E 5 l2.79E 3 l ND 12.91E 5 l1.64E3 l2.74E0 lLa 140 16.44E2 12.25E2 l7.55El l ND l ND l1.83E5 l2.26E5 l I
lEa 142 11.30E0 l4.11E 1 l1.29E 1 l ND l ND l8.70E3 l7.59E4 l ice 141 13.92E4 11.95E4 l2.90E3 i ND 18.55E3 l5.44E5 l5.66E4 l lCc 143 l3.66E2 l1.99E2 12.87El l ND l8.36El l1.15E5 l1.27E5 l lCc-144 l6.77E6 l2.12E6 l3.61ES l ND ll.17E6 l1.20E7 13.69E5 l lPr 143 l1.65E4 15.55E3 19.14E2 i ND l3.0003 l4.33E5 l9.73E4 l lPr-144 l5.96E-2 l1.851. 2 l3.00E 3 l ND 19.77E-3 l1.57E3 l1.97E2 l lNd-147 l1.0BE4 10.73:3 16.61E2 l ND l4.61E3 13.28E5 l8.21E4 l IEu 154 11.01E7 19.21E5 18.40E5 l ND l4.03E6 l6.14E6 l1.10E5 l lllf-181 l2.78E4 l1.01ES l1.25E4 l ND 12.05E4 l1,06E6 16.62E4 l lW 187 l1.63E1 l9.66E0 14.33E0 1 ND l ND l4.11E4 l9.10E4 l lNp-239 14.66E2 13.34E1 12.35El l ND 19.73E1 l5.81E4 l6.40E4 l (a) The child age group; refer to reference 11.14.5.
)
48 -
I j APA ZZ 01003
, Kev. 1 i
)
. TAB 1.E 5 (Cont'd.)
a PAT}NAY DOSE TACTORS (R )g TOR RAD 10NUCL1 DES OTHER THAN NOBLE GASES Ground Plane Pathway (m' mrem /yr) per (VCi/sec) l Nuclide Total tody Skin Be 7 2.24E7 3.21E7 g_ Na 24 1.19E7 1.39E7 Cr 51 4.65E6 5.51E6 Mn 54 1.39E9 1.63E9 tb 56 9.03E5 1.07E6 i
re 59 2.72E8 3.20E8 Co 57 2.98E8 4.37E8 Co*58 3.79E8 4.44E8 Co 60 2.15E10 2.53E10 Ni 65 2.97ES 3.45ES
.Cu 64 6.07E5 6.88E5
,.' j Zn 65 7.47E8 8.59EB j
/ Br 82 3.14E7 4.49E7 3 Br 83 4.87E3 7.08E3 i Br 84 2.03E5 2.36E5
' Rb 86 8,99E6 1.03E7 Rb 88' 3.31E4 3.78E4 Rb 89 -1.23E5- 1.48E5
-5r*B9 2.16E4- 2.51E4 i
Sr-91 - 2,15 E 6 ' 2.51E6 I : -
Sr 92 7.77E5 8.63E5 l Y-90 4.49E3- 5.31E3 '
Y 91m 1.00ES- l'.16E5 i
Y 91 1.07E6 1.21E6 Y 92- 1.80ES- 2.14E5 Y 93 1.83E5 2.51ES Zr 95 2.45E8 2.84E6 Er 97- 2.96E6 3.44E6 Nb 95 .1.37E8 1.61E8-Ho 99. 3.98E6 4.62E6
.49 - I o
~ . . - - - - . - . - . - - . - . . -
l 4
APA ZZ 01003 g Rev. 1 3
I l
]
c ' )
TABLE $ (Cont'd. )
l PATHWAY DOSE TACTORS (Rg ) FOR RADIONUCLIDES OTHER THAN NOBLE GASES
- 4 4
Ground Plano Pathway l (m8 mrem /yr) per (VCi/sec) 1 Nuclide-Total Body Skin 2
Tc 99m 1.84E5 2.11E5
.Tc 101 2.04E4 - 2.26E4
- . Ru 103 1.08E8 1.26EB y Ru 105 6.36E5 7.21E5 Ru 106 4.22E8 5.07E8 i i Ag 110m 3.44E9 4.01E9 Cd-109 3.76E7 1.54E8 Sn 113 1.43E7 4.09E7 Sb 124 8.74E8 1.23E9 Sb 125 3.57E9 5.19E9 Te 125m 1.55E6 2.13E6 Te 127m 9.16E4 1.08E5
) Te 127 2.98E3 3.28E3 i
, Te 129m 1.98E7 2.31E7 I Te-129 2.62E4 3.10E4 Te 131m- 8.03E6 9.46E6
- 4. 6 98E6 !
1 130 5.51E6 6.69E6 I I+131 1.72E7 '2.09E7 -l I 132 1.23E6 1.45E6 I 133 2.45E6 2.98E6 I 134 4.47E5 3.30E5 1 135 2.51E6 2.93E6 Cs-134- .6.86E9 8.00E9 o
Cs-136 1.53E8 1.74E8 i
, Cs 137 1.03E10 1.20E10 Cs 138 3.59ES '4.10E5 ;
Ba 139 1.06E5 1.19ES-Ba-140- 2.05E7 2.35E7 i
l l \
1
. = _ . _ _ _ _ ______._._______._s._.._._ . . _ ,
APA ZZ 01003 l
Rev. 1 TABl.E 5 (Cent'd.)
a PKTINAY DOSE TACTORS g(R ) TOR RAD 10 MMS OUER WAN NOM.E GASES Ground Plane Pathway (m8 mrem /yr) per (pC1/sec)
Nuclide Total Body Skin Ba 141 4.15E4 4.73E4 Ba 142 4.44E4 5.06E4 La 140 1.92E7 2.18E7 La-142 7.40E5 6.89E5 Cc 141 1.37E7 1.54E7 Cc 143 2.31E6 2.63E6 Cc 144 6.96E7 6.04E7 Pr 144 1.64E3 2.11E3 Nd 147 6.41E6 1.01E7 Eu 154 2.21E10 3.15E10
}{f 181 1.97ES 2.82ES
. V-187 2.36E6 2.74E6
) Np 239 1.71E6 1.98E6 (a) Refer to reference 11.14.5 for calculational details.
APA ZZ 01003 Rev. 1 A
TABLE 5 (Cont'd.)
a PATWAY DOSE FACTORS (Rg) F0E RADIONUCLIDES OT1[ER T}!AN NOBLE GASES Mest Pathway (m8 mrem /yr) per (UC1/sec) !
I i l l l Total l 1 l l l lNuclidel Bonc l Liver l Body l Thyroid l Kidney l Lunt, i GI-LLI l l }{ 3 l _ND l2.34E2 l2.34E2 l2.34E2 12.34E2 l2.34E2 l2.34E2 l l Be 7 l7.37E3 11.26E4 18.06E3 l ND l1.23E4 l ND 17.00E5 l l C-14 l3.83EB l7.67E7 l7.67E7 l7.67E7 l7.67E7 l7.67E7 l7.67E7 l l Na 24 l1.78E 3 l1.78E-3 l1.78E 3 l1.78E-3. l1.78E 3 l1.78E 3 l1.78E 3 l l P 32 l7.41E9 13.47E8 l2.86E8 l ND l ND l ND 12.05E8 l l Cr-51-l ND l ND l8.79E3 l4.88E3 11.33E3 l8.91E3 l4.66ES l i'
l Mn 54 l ND 18.01E6 l2.13E6 l ND l2.25E6 l ND l6.72E6 l l Mn 56 i ND l 0 1 0 l ND l 0 l ND l 0 l l Fe-55 l4.57EB l2.42E8 l7.51E7 l ND l ND l1.37E8 l4.49E7 l l Fe-59 l3.76E8 !6.09E8 l3.03E0 l ND l ND l1.76ES l6.34E8 l
)8- l Co 57 ND l5.92E6 l1.20E7 l ND l ND l ND l4.85E7 l l Co 58 . ND l1.64E7 l$.02E7 l ND l ND l ND l9.58E7 l l Co 60 l ND l6.93E7 12.04E8 l ND l ND l ND 13.84E8 l l Ni-63 12.91E10 11.56E9 l9.91E8 l ND l ND l ND l1.05EB l l.-Ni 65 l 0 l 0 l 0 l ND l ND l ND' l 0 l l Cu 64 l ND 12.97E-7 l1.79E-7 l ND 17.17E-7 l ND l1.39E 5 l l Zn 65 l3.75E8 11.00E9 l(.22E8 l ND l6.30E8 l ND - l1.76E8 l l In-69 l . 0 l 0 1 0 l ND l 0 l ND l 0 l l Br-82 ND l ND l1.52E3 i ND l ND l ND- l ND l l Br-83 ND l ND l ND l ND l ND l ND l ND l l Br-84 l ND l ND l ND l ND l ND l ND l ND l l Br-85 l ND l ND l ND l . ND l ND l ND l ND l l Rb-86 l ND l5.82E8 l3.58E8 l ND l ND l ND l3.74E7 l l Rb 88 l ND l 0 l 0_ l ND l _ ND l ND 'l 0 l 7 l Rb 89'.] -ND l 0 l 0 l ND l ND l ND l 0- l l St 89 l4.82E8 l ND ll.38E7 l ND l ND l ND l1.86E7 l l Sr 90 l1.04E10-l ND _l 2.64E9 l ND- l ND l ND l1.40E8.l_
l Sr 91 l2,40E-10l_ ND_ l 0 l ND l ND -l ND l5.29E-101
_l Sr 92.I O l ND l -0 l ND l ND l ND I O l-l Y-90 11.71E2 l ND l4.59E0 l ND- l ND l ND 14.88E5 l
)
APA ZZ+01003 Rev. 1 TABLE _5_(Cont'd.)
a
/ATINAY DOSE l' ACTORS (R g) I'OR RADIONUCLIDES OTlIER T}lAN NOBLE GASES Meat Pathway (m' mrem /yr) per (VCi/sec) l l l l Total l l l l l
.lNuclidel Bone I Liver l Body i Thyroid l 1:idney i Lung l GI LLI l 1
l Y 91m j 0 l ND l 0 l ND l ND l ND l 0 l l Y-91 l1.80E6 l- ND l4.82E4 l ND l ND l ND l2.40E8 l l Y 92 l 0 l _ND l 0 l ND l ND l ND l 0 l i
Y 93 l -0 l ND l 0 l ND l ND l ND l1.55E 7 l Er 95 l2.66E6 - l5.85E5 15.21ES l ND l8.38E5 l ND l6.11E8 l l Zr 97 l3.20E-5 14.63E 6 l2.73E-6 l ND [6.65E 6 l ND l7.02E-1 l l.Nb 95 l3.09E6 l1.20E6 l8.61E5 l ND l1.13E6 l ND l2.23E9 l l Mo 99 l ND l1.15E5 l2.84E4 l ND l2.46E5 l ND l9.51E4 l 1.Tc 99ml 0 l 0 -l 0 l ND l 0 l 0 l 0 l l Tc 101l 0 -l 0 l 0 l ND l 0 l 0 l 0 j l Ru 103l1.55E8 l ND j$.96E7 l ND l3.90E6 l ND (4.01E9 l
) l Ru-105l 0 l ND l -0. l ND j. 0 l ND l 0 l l Ru 106l4.44E9 l ND l5.54E8 l ND l$.99E9 l ND l6.90E10 l lAg-110ml8.40E6 l5.67E6 l4.53E6 l ND l 1. 06E 7_ - l ND 16.75E8 l lCd 109 l ND l1.90E6 18.83E4 l ND l1.70E6 l ND l6.18E6 l lSn 113 12.18E9 l4.4SE7 l1.24E8 l3.31E9 l ND l ND- l1.54E9 l
_lSb 124;l2.93E7 I3.79E5 l1.02E7_ l6.45E4_ l ND_ l1.62E7 l1.83E8 l_
lSb 125 l2.85E7 l2.20E5 15.97E6 l2.64E4 l ND l1.59E7 l6.80E7 lTe 125ml5.69E8 l1.54E8 l7.59E7 ll.60E8 l ND l ND 15.49E8
-lTo-127ml1.77E9 l4.78E8 l2.11E8 l4.24E8 l5.06E9 i ND- l1.44E9 l lTe 127 l4.11E 10l1.11E 10 l 0 l2.85E 10 11.17E-9 l ND l1.61E 8 l lTe 129ml1.79E9 l4.99E8 l2.77E8- l5.76E8 - .l5.25E9 - l _ ND l2.18E9 'l lTe 129 l 0 l 0 l 0 1 0 l 0 l ND- l 0 l
-lT6 131m 7.00E2 l2.42E2 l2.58E2 l4.98E2 l2.34E3- l ND l9'82E3 l lTe-131 _0 l 0 l 0 l 0- l 0 l ND _l 0 l lTe-132 l2.09E6 19.26E5 l1.12E6 l1.35E6 _l8.60E6 l ND 19.33E6_ l lI-130 13.04E-6.l6.13E-6 l3.16E 6 l6.76E-4 l9.17E 6 l ND l2.87E 6 l l I-131 'll.66E7
~
l1.66E7 l9.46E6 l5.50E9 l2.73E7 l - ND_ l1.48E6 l I-132 ~ l 0 l 0 l- 0 l 0 l 0 l ND- l 0. l L I-133 l6 16E 1 l7.61E-1 12.88E-1 l1.41E2 l1.27EO l ND 13.07E-1 l l1-134 l -0 .l 0 1 0 l 0 l 0 l hT -l 0 l
-h 1
rh 3 r e a --. .-.,y., r. r- . . - - , w -- -..w--.c-- . .. .---.r- . .-.-,..-.~~ew ----er=*-~---m-------
APA ZZ 01003 hev. 1
) TABLE 5 (Cont'd.)
PATHVAY DDSE TACTORS (Rg ) TOR RADIONUCLIDES OTHER T)lAN NOBLE GASES *
~
Meat Pathway (m8 mrem /yr) per (uCi/sec) l l l l Total l l l l l lNuclidel Bonc l Liver 1 Body l Thyroid l )*1dney l Lung l GI LLI l l1 135 l 0 l 0 l 0 l 0 1 0 l ND l 0 l lCs-134 l9.22EB l1.51E9 l3.1vL8 l ND l4.69EB 11.6SEB l8.16E6 l lCs 136 l1.61E7 14.43E7 l2.66E7 l ND l2.36E7 l3.51E6 l1.56E6 l lCs 137 11.33E9 l1.2BE9 l1.6BES l ND l4.16E6 l1.50EB 17.99E6 l lCs 136 1 0 l 0 l 0 l ND l 0 1 0 l 0 l lBa-139 l 0 l 0 1 0 l ND l 0 l 0 l 0 l lBa-140 l4.3SE7 l3.64E4 l2.56E6 l ND 11.25E4 l2.29E4 12.22E7 l lBa 141 l 0 l 0 l 0 l ND l 0 1 0 1 0 l lBa 142 l 0 l 0 1 0 l ND l 0 l 0 l 0 l lLa-140 15.69E 2 11.99E 2 16.70E 3 ) ND l ND l ND l5.54E2 l
, lLa-142 l 0 l 0 l 0 l ND l ND l ND l 0 l
) lCc-141 l2.22E4 l1.11E4 l1.64E3 l ND l4.65E3 l ND l1.3BE7 l lCc 143 l3.17E 2 l1.72E1 l2.49E 3 l ND l7.21E-3 l ND l2.52E2 l Ice 144 l2.32E6 l7.26E5 \ 1 '!4E5 l ND l4.02E5 l ND ll.69E6 l lPr 143 l3.35E4 l1.00E4 l1.66E3 i ND l5.44E3 l ND 13.61E7 l lPr 144 l 0 1 0 l 0 l ND l 0 l ND l 0 l lNd 147 l1.17E4 l9.50E3 l7.35E2 } ND 15.21E3 l ND l1.50E7 l lEu 154 l1.12E7 11.01E6 l9.20E5 l ND l4.42E6 l ND 12.34E8 l lHf-161 14.76E6 l1.73E7 l2.15E6 l ND 13.52E6 l ND l6.40E9 l lW 187 l3.35E 2 11.96E-2 l8.91E 3 l ND l ND l ND l2.79E0 l lNp-239 l4.20E 1 l3.02E 2 l2.12E-2 1 ND lt. 72E 2 l ND 12.23E3 l (a) The child age group; refer to reference 11.14.5.
)
54 - I
- _ _ - _ _ _ - - _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -- - _ - . .. .a
APA %E 01003 i q Rev. 1 ,
i TABLE 5 (Cont'd d l PAT}NAY DOSE FACTORS g (R ) FOR RADIONUCLIDES OTHER T}{AN NOBLE L'i45"
~
Grass Cov4111k Pathwa)
(m8 mrem /yr) per (pC1/sec) l l l l Total l l l l l
, INuclidel Bonc l Liver l Body l Thyroid i Kidney l Lung l GI LI.1 l l 11 3 l ND l1.57E3 l1.57E3 l1.57E3 l1.57E3 l1.57E3 l1.57E3 l l Be-7 l7.49E3 11.28E4 18.19E3 -l ND ll.25E4 l ND l7.11ES l l C 14 11.19E9 12.39E8 12.39E8 l2.39EB l2.39E8 12.39EB l2.39E8 l '
, 1 Na 24 l8.89E6 18.89E6 l8.89E6 18.89E6 l8,89E6 18.89E6 l8.89E6 l l P 32 l7.77E10 l3.64E9 13.00E9 l ND l ND l ND 12.15E9 l l Cr 51 l ND l ND l1.03ES- l5.65E4 11.56E4 11.04E5 l$.40E6 l l Mn 54 l ND 12.10E7 l5.59E6 l ND l$.88E6 l ND l1.76E7 l l Mn 56-l ND l1.29E 2 l2.90E 3 l ND l1.56E 2 l ND l1.86E0 l l Te 55 11.12E8 l5.93E7 l1.84E7 l ND l ND 13.35E7 l1.10E7 l l Te 59 11.20E6 11.94E8 l9.69E7 l ND l ND l5.64E7 12.02E8 l 4
l Co 57 i ND l3,84E6 l7.76E6 l ND l ND l ND 13.15E7 l
) l Co 58 l ND -l1.21E7 l3.71E7 l ND l ND l ND l7.07E7 l l Co 60 l ND l4.32E7 l1.27E8 l ND l ND l ND l2.39E8 l l N1 63 l2.96E10 l1.59E9 11.01E9 l ND l ND l ND 11.07E8 l l Ni 65 11.66E0 l1.56E 1 l9.01E 2 l ND l ND l ND 11.91El l l Cu 64 l ND l7.46E4 14.51E4 l ND 11.80E5 l ND 13.50E6 l l Zn 65 l4.13E9 l1.10E10 16.85E9 l ND l6.94E9 l ND l1.93E9 l l Zn-69 0 l- O l- 0 l- ND l 0 l ND l1.12E-9 l l Br 82 ND l ND l1.15E8 l ND l ND l ND l ND l l Br 83 l ND l ND -l ND l ND l ND -l ND l ND l l Br 84 l ND l ND l ND l ND l ND l ND l r l l Br-85-l ND l ND l ND l ND l ND l ND l ND !
l Rb 86 l ND 18.80E9 15.41E9 l ND l ND l ND 15.66E6 l i l Rb 88-l' ND
~
l 0 l 0 l ND l P- l @ l 0 l l l Rb 89 l ND l 0 l 0 l ND l ND l- ND l 0 l l
l Sr 89 l6.62E9 l ND-l1.89E8 l ND l ND l ND l2.56E8 l l Sr 90,11,12E11 l ND l2.83E10 l ND l ND l ND l1.51E9 l l St-91 l1.30E5 l- ND l4.92E3 i ND l ND' l ND l2.88E5 l
[ l-Sr+92 l2.18E0 l ND~ l8.75E 2 l ND l ND -l ND 14.13E1 l p l Y 90 l3.22E2 l ND l8.62E0 l ND l ND l ND l9.17ES l 3
. APA*2 *01003 Rev. 1
) TABEE 5 (Cont 'd. )
PAT}NAY DOSE TACTORS (Rg.) TOR RADIONUCLIDES OTIIER THAN NOBLE CASES" Grass Cow Hilk Pathway (m8 mrem /yr) per (vC1/sec)
'l l l l Total l l l l l lNue11 del Bone i Liver i Bodt l Thyroid 1 ):fdney I Lung l G1-LLI l l Y 91m l 0 l ND l 0 l ND l ND l ND l 0 l lY91 l3.90E4 l ND ll.04E3 l ND l ND l ND l5.20E6 l l Y+92 l2.53E-4 l ND l7.24E 6 l ND l ND l ND l7.31E0 l l Y-93 l1.0$E0 l ND l2.90E 2 l ND l ND l ND l1.57E4 l 3 l Zr 95 j3.83E3 l8.42E2 17.50E2 l ND l1.21E3 l ND l8.79E5 l Zr 97-l1.92E0- l2.77E 1 l1.64E-1 l ND l3.98E 1 l ND l4.20E4 l Nb-95 13.18E5 l1.24t5 18.84E4 l ND l1.16E5 l ND l2.29E8 l 1
ll Mo 99 l ND l8.14E7 l2.01E7 l ND l1.7408 l ND l6.73E7 l l Tc 99ml1.32E1 _ (2.59El 14.29E2 l ND 13.76E2 l1.32E1 l1.47E4 l l Tc-101l 0 l 0 l 0 l ND l 0 l 0 l 0 l l Ru 103l4.28E3 l ND l1.65E3 l ND l1.06E4 l ND l1.11E5 l
}s l Ru 105l3.f1E 3-l ND l1.39E 3 l ND l3.36E 2 l ND l2.49E0 l t
l Ru-106l9.24E4 l ND 1 1.15E4 l ND l1.25ES 1 ND l1.44E6 l lAg-110ml2.09E8 l1.41E8 l 1.13E8 l ND l2.63E8 ND l1.68E10 l lCd 109 l ND l3.86E6 1.79E5 l ND l3.45E6 l ND l1.25E7 l f lSn-113_l6.10E6 l1.25E7 13.48E7 l9.27E8 l ND l ND l4.31E8 l
- lSb-124 l1.08E8 l1.41E6 13.81E7 l2.40E5 l ND 16.03E7 l6.79EB l lSb 125 l8.70E7 l6.71ES l1.83E7 18.06E4 l ND l4.85E7 J2.0EE8 l lTe 125ml7.38E7 l2.00E7 19.84E6 l2.07E7 l ND - l ND l7.32E7. l lTe 127ml2.08E8 l5.60E7 l2.47E7 l4 07E7 l5.93:8 l ND 11.6BE8 l lTe 127 13.05E3 l8.22E2 16.54E2 l2.11E3 18.67E3 l ND l1.19E5 l lTe-129ml2.71E8 17.57E7 l4.21E7 l8.74E7 l7.96E8 l ND l3.31EB l .
lTe-129 l 0 l 0 l 0 l 0 l2.90E-9 l ND l6.17E 8 l '
lTe 131ml1.60E6 l5.53E5 l5.89ES l1.14E6 l5.35E6 ND l2.24E7 l lTe 131.l 0 0- l 0 l 0 l 0 ND l 0 l
.lTo-132 l1.02E7.. l4.52E6 l l5.46E6 l6.58E6 l4.20E7 l ND l4.55E7 l.
lI-130- l1.73E6 l3.49E6' l1.80E6 l3.84E8 l5.22E6 l ND ll.63E6 l l1.30E9 l1.31E9 l7.45E8 l4.33E11 l2.15E9 l ND l1.17E8 l lI 132 _ !6.02E 1-11.11E0 lI-131 15.08E 1 15.13E1 11.69E0 l ND ll 30E0 l
- lI-133- ll.74E7 l2.15E7 -l8.13E6 l3,99E9 l3.58E7 i ND l8.66E6 l l1-134 - l- 0 l 0 j 0 1 0 1 0- l ND l 0 l
)
- 56
%we--- , - - n -y,--n-%e e,-w,,w-... .- y,---. % -I-- ,-,e--m,w.-,-.,- e., -w.w,.,.,,..w,,-..---,--
, ,w.---# .. -,.---<,-,v,.--.--,.e--- - - =,v,,A
APA 22 01003
, Rev. 1
) TABLE 5 (Cont'd.)
PATHWAY DOSE TACTORS (Rg ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES" Grass. Cow Hilk Pathway i
(m' mrem /yr) per (pC1/sec) l l l l Total 8 l l l l lNuciptj_ Bone I Liver l Body i thyroid i 1:1dney ] Lunt, l G1-LLI l l1-135 15.401:4 l9.72E4 l4.60E4 l8.61E6 l1.4SE5 l ND l7.40E4 l lCs 134 l2.26E10 13.77E10 l7.84E9 l ND l1.15E10 14.13E9 l2.00E8 l
\Cs-136 l1.01E9 l2.77E9 l1.79E9 l ND l1.48E9 l2.20E8 l9.74E7 l lCs 137 l3.22E10 l3.09E10 14.56E9 l ND l1.01E10 13.62E9 11.93EA l ICs 138 l 0 l 0 l 0 l ND l 0 1 0 l 0 l lBa 139 l1.89E 7 1 0 l5.48E 9 l ND l 0 l 0 l1.09E 5 l lBa 140 l1.17EB l1.03E5 16.84E6 l ND l3,34E4 16.12E4 l5.93E7 l lBa'141 l 0 l 0 l 0 l ND l 0 l 0 1 0 l lBa-142 l 0 l 0 l 0 l ND l 0 1 0 l 0 l lLa 140 l1.95El l6.80E0 l2.29E0 l ND l ND l ND l1.90E5- l lLa142 0 l 0 1 0 l ND l ND l ND l2.90E 6 l
=) - lCe 141 2.19E4 11.09E4 l1.62E3 l ND 14.78E3 l ND l1.36E7 l lCe 143 il.87E2 l1.02E5 l1.47El l ND l4.26El l ND l1.49E6 l lCe 144 l1.62E6 15.09ES l8.66E4 l ND l2.82E5 l ND l1.33E8 l lPr 143 l7.19E2 12.16E2 l3.57El l ND l1.17E2 l ND l7.75E5 l lPr 144 l 0 l 0 l 0 l ND l 0 l ND l 0 l lNd-147 l'. 45E2 l3.61E2 l2.79El l ND l1.98E2 1 ND 15.71E5 l lEu 154 19.41E4 18.47E3 17.73E3 l ND l ND l1.97E6 l lHf 181 l6.43E2 l2.35E3 l2.90E2 l ND l3.72E4 l4.75E2 . l NDl8.65E5 l lW 187 -12.91E4 l1.73E4 l7.73E3 l ND- l ND l ND l2.42E6 l lNp 239 11.72E1 l1.23E0 18.68E-1 l 'ND l3.57E0 l ND l9.14E4 l (a) The child age group; refer to reference 11.'14.5.
57 *
..w,1.:- , , . . --. .w.-, , e ew +m--,.r- ., .,-
..---c . . . , - - -
. ~ - - . , . , , . m,-*7
APA ZZ 01003 Rev. 1 TABLE 5 (Contd.)
PATINAY DOSE TACTORS (Rg ) TOR RADIONUCLIDES OTHER T}lAN NOBLE GASES
- Grass Goat Miik Pathway (m nrem/yr) per (vC1/sec) 8 l l l l Total l l l l l i
lNuclidel Bene i Liver l Body 1 Thyroid i Kidney l Luns: 1 GI-LLI l l li 3 l ND l3.20E3 l3.20E3 l3.20E3 l3.20E3 13.20E3 l3.20E3 l l Be 7 l8.98E2 11.53E3 l9.82E2 l ND l1.50E3 l ND : 8.53E4 l l C-14 l1.19E9 12.39EB- l2.39EE l2.39E8 l2.39E8 l2.39E8 2.39E8 l l Na 24 t i.07E6 11.07E6 l1.07E6 l1.07E6 l1.07E6 l1.07E6 1.07E6 l l P 32 9.33E10.l4.37E9 13.60E9 l ND l ND l ND l2.58E9 l
- l Cr-51 ND l ND l1.23E4 16.78E3 l1.87E3 ll.2SE4 l6.48E5 l l Mn 54 l ND l2.52E6 l6.70E5 l ND l7.06ES l ND l2.11E6 l Hn-56 l ND l1.54E*3 l3.49E 4 l ND l1.87E-3 l ND l2.24E-1 l Te 55 l1.45E6 l7.71E5 12.39E5 l ND l ND l4.36E5 l1.43E5 l
, I Te 59 11.56E6 l2.53E6 1.26E6 l ND l ND 17.33E5 2.63E6 l L Co 57 l ND 4.60E5 9.31ES l ND l ND l ND 3.77E6 l 3 l Co 58 l ND 1.45E6 (4.45E6 l ND l ND l ND 8.49E6 l 1
, l Co-60 l ND 15.18E6 ll.53E7 l ND l ND l ND l2.87E7 l )
l N1 63 13.56E9 l1.90E6 11.21E8 l ND l ND l ND l1.28E7 l l Ni 65 '1.99E 1 l1.87E 2 l1.09E 2 l ND l ND l ND l2.29E0 l l Cu 64 ND l8.31E3 l5.02E3 l ND 12.01E4 l ND l3.90E5 l l Zn 65 14.96E8 l1.32E9 l8.22E8 l ND' l8.33E8 l ND l2.32E8 l
-l Zn 69 l 0 l 0 l 0 l ND l 0 l ND ll.35E 10l l Br 82 l ND l ND l1.38E7 l ND l ND l ND l ND l Br 83 l ND l ND l ND l ND l ND l ND l ND l Br 84 l ND l ND .l ND- l ND l ND l ND l ND l Br-85.I ND l ND l ND l- ND l ND l ND l ND l Rb 86'l ND l1.06E9 l6.50E6 l ND l ND l ND l6.80E7 l Rb 88 l ND l 0 1 0 l ND l ND l ND l 0 l l Rb-89 l ND l 0 l 0 l ND l ND l ND l 0 l j Sr-89 11.39E10 l ND l3.97E8 l ND l ND l ND- 15.38E8 l l Sr 90'l2.35E11 l ND l5.95E10_l- ND l ND l ND 13.16E9 l l Sr-91 l2.74E5 l ND l1.03E4 l ND l ND l ND l6.04E5 'l i )
- 58 -
-i
. _ . . . . . . , . _ _ _ , - . . _ . . . . ,m,..s.... , . _ . - , . . , , , _ . . _ . . _ , _ . , , , _ _ , . _ . _ . _ _ , _ _ . . _ _ . _ . _ , , . - . _
APA EZ 01003
- Rev. 1 i
l i
') - TABLE 5 (Contd.)
TATINAY DOSE TACTORS (R g) TOR RAD 10NDCL1 DES OTl!ER TilAN NOBLE GASES
- Grass Goat Milk Pathway (m' mrem /yr; per (pC1/sec) l l l Liver l Total l l l l "l lNuclidel Bone I i Body l Thyroid 1 Kidney l Lung l G1 LLT__1 Sr 92 1 4.58E0 l - ND l1.84E 1 l ND l ND l ND l8.68E1 l Y 90 3.87El l ND l1.03E0 l ND l ND l ND l1.10E5 l l Y 91m .
0 l ND l 0 l ND l ND l ND l 0 -l Y 91 l4.68E3 l ND l1.25E2 l ND l ND l ND l6.24E 5 l L Y 92 l3.04E 3 l ND l8.69E 7 l ND l ND l ND l8.77E 1 l l_Y 93 l1.27E 1-l ND l3.4EE 3 l ND l- ND l ND l1.89E3 l l Zr 95 l4.60E2 l1,01E2 l9.00E1 l ND l1.45E2 l ND l1.05ES l Zr 97 'l'!.30E 1 13.33E 2 l1.96E 2 l ND l4.7&E 2-l ND. 15.04E3 l Nb 95.l3.81E4 l1.48E4 l1.06E4 l ND l1.39E4 l ND - l2.75E7 l Ho*99 l ND l9.76E6 l2.42E6 l ND l2.09E7 l ND l8.08E6 l 4 Tc-99ml 1.59E0 3.11E0 15.15El l ND I
l4.52E1 11.58E0 11.77t3 l Tc-101: O' , O l 0 l ND l 0 l 0 l 0 l l Ru 103, 5.14E2 ND l1.98E2 l ND l1.29E3 l ND l1.33E4 l l Ru 105 :4.58E 4= ND l1.66E 4 l ND l4.03E 3 l ND l2.99T. 1 l l Ru 106 1.11E4 l ND l1.38E3 l ND l1.50E4 l ND l1.72E5 l lAg 110ml2.51E7- l1.69E7 l1.35E7- l ND l3.15E7 l ND l2.01E9 l lCd-JO9_l ND l4.63E5 l2.15E4 l ND 14.13E5 l ND ll.50E6 l lSn-113-l7.32E7 l1.50E6 14.17E6 11.11E8 l ND .ND l5.17E7 lSb 124 l1.30E7 l1.69ES' 14.56E6 -l2.87E4 l ND 7.22E6 l8.14E7 i lSb 125-l1.04E7 l8.04E4 l2.19E6 l9.66E3 l ND l 2. 491' 7 l lTe 125ml8.85E6 l2.40E6 11.18E6 l2.48E6- l ND ll5.81E6 ND . 18.54E6 l lTe-127m 2.50E7 16,72E6 l2.96E6 l5.97E6 -l7.12E7 l ND. l2.02E7 l
!; lTe 127 , 3.66E2 l9.86El l7.85El-l2.53E2 ll.04E3 l ND l1.43E4 l lTe 129m 3.25E7 19.09E6 l5.05E6 l1.0$E7 l9.55E7 l ND 13.97E7 -l lTe 129{ l 0 l. 0 l 0 l O l 0 _l ND l7.40E 9 l
t lTo 131ml1.92E5 l6.64E4 17.07E4 ll.37E5 -l6,43E5 l Nu l2.69E6 lTe 131 l . 0 l 0 l 0 l 0 l 0 I ND l 0 l l
iTe 132 11.23E6 l5.42E5 l6.55E5 17.90E5 15.04E6 l ND 15.46E6 l l1-130 l2.07E6 l4.19E6 l2.16E6 l4.61EB' 16.26E6 l ND l1.96E6 l.
59 -
E E- e , = -. [ E r . .,w..-%--~+,--.w.v45-v-~.-,---. ..w-. .--.eme,--,.--- - , , . - . , . . . , . - . ~ , . - . . , , , . , , , , . , .r-,-
.,v., ,-,,vww,el-----vv.- ,eme- --m b
APA ZZ-01003 hev. 1 TAbtE 5 (Contdj PAT}NAY D?SE TACTORS (R1) POR KAD10NUCLIDES OT}iER T}lAN NOBLE GASES" Grass Goat Milk Pathway (m' mrem /yr) per (VCi/sec) l l l l Total l l l l l lNuclidel bone l Liver l Fody l Thyroid i Kidney i Lunt. 1 Gl*LLI l 11 131 11.5fE9 l1.57E9 l8.94E8 15.20E11 l2.5EE9 l ND l1.40E6 l l1-132 l7.22E 1 11.33E0 16.10E-1 16 15El l2.03E0 l ND ll.56E0 l l1 133 12.09E7 l2.56E7 l9.76E6 14.79E9 14.30E7 l ND 11.04E7 l l1 134 l 0 l 0 l 0 1 0 l 0 l VD l 0 l 11 135 16. 4 6EI. 11.17ES l5.52E4 l1.03E7 11.79ES l ND l8.88E4 l lCs 134 l6.79E10 l1.11E11 l2.35E10 l ND 13.45E10 11.24E10 16.01EB l lCs 136 13.03E9 18.32E9 l5.3BE9 l ND 14.43E9 16.61EB l2.92E8 l lCs 137 19.67E10 19.26E10 11.37E10 l ND l3.02E10 11.09E10 i3.80E8 l lCs 138 l 0 1 0 l 0 l ND l 0 1 0 l 0 l lBa 139 12.27E B l 0 1 0 l ND l 0 1 0 11.31E 6 l
., lBa 140 l1.41E' l1.23E4 l8.20E5 l ND l4.01E3 l7.34E3 l7.12E6 l
) lBa 141 l 0 l 0 1 0 l ND l 0 l 0 1 0 l lEa 142 l ') l 0 1 0 l ND l 0 l 0 1 0 l lLa 140 l2.34E0 18.17E 1 12.75E-1 l ND l ND i ND l2.26E4 l lLa-142 l 0 l 0 1 0 l NE l ND l ND l3.49E 7 l lCc 141 l2.62E3 11.31E3 11.94E2 1 ND 15.74E2 i ND l1.63E6 l lCo-143 12.25El 11.22E4 11.77E0 l ND l5.12E0 l ND l1.79E5 l lCo-144 l1.95ES 16.11E4 l1.04E4 l ND 13.3SE4 l ND l1.59E7 l lPr 143 l8.62E1 12.59El 14.28E0 l ND ll.40E1 l ND l9.30E4 l lPr 144 1 0 l 0 l 0 l ND l 0 l ND l 0 l lNd 147 l5.34E1 14.33E1 13.35E0 l ND l2.37El l ND l6.85E4 l lEu-154 ll.13E4 11.02E3 19,27E2 l ND I4.46E3 l ND l2.36E5 l liif-181 17.71El 12.81E2 l3.4EE1 l ND 15.7001 1 ND ll.04E5 l IV 187 l3.49E3 12.07E3 19.27E2 l ND l ND 1 ND 12.90E5 l lNp 239 12.06E0 11.46E-1 l1,04E-1 l ND l4.28E-1 l ND l1.10E4 l (a) The child age troup; refer to reference 11.14,5.
1
l APA-ZZ 01003 Rev. 1 TABLE 5 (Contd.)
PATlNAY DOSE TACTORS (Rg) TOR RADIONUCLIDES OTl!ER THAN NOBLE GASES" YeEetation Pathway (m rarern/yr) per (UC1/sec) 8 l l l l Total l l I l l lNuclidel Bone l Liver l %dy l Thyroid l )*idney 1 Lung l GI LLI [
l 11-3 l ND l4.01E3 l4.01E3 14.01E3 14.01E3 14.01E3 l4.01E3 l l Ec 7 l3.36E5 15.76E5 13.70E5 l ND 15.64E5 l ND 13.21E7 l l C 14 l6.89EB 11.7EES 11.76EB l1.76E6 l1.76EB l1.78EB l1.78E8 l l Na-24 l3.75ES l3.75E5 13.75E5 13.75ES 13.75E5 13.75E5 l3.75E5 l l P-32 13.37E9 11.57EB ll.30E6 l ND l ND l ND 19.30E7 l l Cr-51 l ND l ND l1.17E5 16.50E4 l1.76E4 l1.19ES l6.21E6 l l Mn-5* l ND 16.65ES 11.77E6 i ND l1.66E6 l ND 15.56EB l l Mn-56 l ND l1.6BE1 l4.24E0 l ND l2.27El l ND 12.72E3 l l Te-55 l8.01EB l4.2SE8 11.32EB l ND l ND 12.40EB l7.67E7 l l Te-59 l3.97EB l6.43E8 l3.00E6 l ND l ND l1.66E6 16.69ES l g l Co-57 l ND l2.98E7 16.04E7 l ND l ND l ND l2.45E6 l J l Co-58 l ND 16.44E7 ll.97E8 l ND 1 ND l ND l3.76E8 l l Co-60 l ND l3.7EEB l1.10E9 l ND l ND l ND 12.10E9 l l Ni-63 13.95E10 12.11E9 11.34E9 l ND l ND l ND l1.42E6 l l Ni 65 11.05E2 19.69E0 l5.77E0 l ND l ND l ND l1.21E3 l l Cu-64 l ND l1.10E4 l6.64E3 l ND l2.66E4 l ND l5.16E5 l l Zn-65 l8.12E8 12.16E9 11.35E9 i ND 11.36E9 l ND l3.60E6 l l En-69 l1,09E-5 ll.57E 5 11.45E-6 l ND 19.52E-6 l ND l9.11E 4 l l Br 62 1 ND l ND l2.04E6 l ND l ND l ND l ND i l Er 63 l ND l ND 15.37EO l ND 1 ND l ND l 0 l l Br-64 l ND l ND 1 0 l ND l ND l ND l 0 l l Br-85 1 ND l ND l 0 l ND l ND l ND l 0 l l Rb-66 l ND l4.56EB l2.62EB l ND l ND l ND l2.94E7 l l Rb-SB l ND l 0 1 0 l ND l ND l ND l 0 l l Rb-69 i ND l 0 1 0 l ND l ND l ND l 0 l l Sr 69 l3.59E10 1 ND l1.03E9 l ND l ND l ND l1.39E9 l l St 90 11.24E12 l ND l3.15E11 l ND l ND l ND 11.67E10 l l Sr 91 15.24E5 l ND 11.96E4 l ND l ND l ND l1.16E6 l l Sr-92 l7.26E2 l ND l2.92E1 l ND l ND l ND 11.36E4 l l Y 90 l2.31E4 l ND 16.18E2 l ND i ND l ND l6.57E7 l 1
61 -
APA 32 01003 Rev. 1
) TABLE 5 (Contdj t
PATINAY DOSE TACTORS (Rg ) TOR RADIDNUCEIDES OTHER THAN NOBLE GASES" Yegetation Pathway (m mrem /yr) per (VCi/sec) 8 l l l l Total l l l l l lNuclidel Bonc i Liver i Body l Thyroid l Kidney 1 Lung l GI ELI l l Y 91m l8.87E 9 l ND l3.23E 10l ND l ND l ND ll.74E 5 l l Y-91 11.86E7 l ND l4.99E5 l ND l ND l ND l2.48E9 l l Y-92 l1.58E0 l ND 14.53E-2 l ND l ND l ND l4.58E4 l l-Y 93 13.01E2 l ND 18.25E0 l ND l ND l ND l4.48E6 l l Zr-95 13.86E6 l8.45E5 l7.55ES l ND l1.21E6 l ND l8.b4E8 l l Zr-97-15.70E2 l8.24E1 l4.86El l ND l1.18E2 l ND l1.25E7 l J Nb 95 l4.10E5 11.59E5 l1.14E5 l ND ll.50E5 l ND l2.95E8 l-l Ho-99-l ND l7.71E6 l1.91E6 l ND l1.65E7 l ND 16.38E6 l l Tc 99ml4.71E0 l9.24E0 l1.53E2 l ND l1.34E2 l4.69E0 15.26E3 l l Tc-101l 0- l 0 l 0 l ND l 0 l 0 l 0 l l Ru 10311.54E7 l ND 15.90E6 l ND l3.87E7 l ND l3.97E8 l
_?) l Ru 105l9.16El l ND l3,32E1 l ND l8.0$E2 l ND l5.9BE4 l i l Ru-106l7.45E8 l ND 19.30E7 l ND 11.01E9 l ND ll.)6E10 l lAg 110ml3.22E7 l2.17E7 l1.74E7 l ND l4.05E7 l ND l2.58E9 l lCd-109 l- ND l2.45E8 11.13E7 l ND l2.18E8 -l ND l7.94EB l
, lSn-113-l1.58E9 l3.25E7 19.00E7 l2.40E9 l ND l ND l1.12E9 l lSb-124 l3.52E8' 14.56E6 11.23EB l7.76E5 l ND 1 1.95EB l2,20E9 l lSb-125 l4.99E8- l3.85E6 - l1,05E8 l4.62E5 l ND 2.78E8 .l' . 19E9 l (
lTe 125ml3.51EB l9.50E7 ! 't . 67 E 7 l9.84E7 l ND ND l3.38E8 l
-lTe 127 mil.32E9 13.56E8 11.57EB 13.16E8 l3.77E9 ND 11.07E9 l lTe 127 11.00E4 l2.69E3 12.14E3 l6.91E3 l2.84E4 l ND 13.90E5 l lTe-129ml8.38E8 l2.34E8 l1.30EB- l2.70E6 l2.46E9 l ND ll.02E9 l
-lTe-129 11.16E 3 l3.23E 4 l2.75E-4 18.26E 4 13.39E 3'l ND l7.20E 2 l lTe-131 mil.54E6 l5.33E5 l5.68E5 l1.10Eu' 15.16E6 l ND l2.16E7 !
i lTe 131 1 0 l 0 1 0- l 0; l 0 l ND l 0 lTe-132 l6.98E6 13.09E6 l3.73E6 l4.50E6 12,87E7 l ND -l3.11E7 11-130 l6.16ES -ll.24E6 l6.38E5 l1.37E8 l1.86E6 l ED l5.79ES l lI 131 11.43E8 11.44E8 18.17E7 l4.75E10 12.36E8 l ND l1.28E7 l ll 132 18.58E1 l1 58E2 17.25El l7.31E3 l2.41E2 l ND- l1.86E2 l lI 133 13.56E6 -l4.40E6 l1.67E6 l8.18E8 l7.34E6 l ND ll.77E6_l-lI 134 11.55E 4 12.88E 4 11.32E 4 l6.62E 3 l4.40E 4 l ND 11.91E-4 l lI-135 16,62E4- 11.13E5 l5.33E4 l9.97E6 -l1.70E5 l ND l?.58E4 l
)
APA42 01003 Rev. 1 TABLE 5 (Contd. )
PATfMAY DOSE PACTORS (Rj) EOR RADIONUCL1 DES OTHER THAN NOBLE GASE8" Yegetation Pathway (m rnrem/yr) per (tCi/sec) 8 l l l l Total l l l l l lNuclidel Bone ! Liver l Body 1 Thyroid l Kidney l Lunt 1 01 LLI l lCs 134 l1.60E10 12.63E10 l5.55E9 l ND 18.15E9 12.93E9 l'.42E8 l lCs 136 8.17E7- l2.25E8 11.45E8 i ND l1.20E8 l1.78E7 l7.90E6 l lCs 137 2.39E10 l2,29E10 13.38E9 l ND l7.46E9 l2.68E9 l1.43EB l lCs 138 l 0 1 0 l 0 l ND l 0 1 0 l 0 l lBa*139 14.80E-2 12.56E 5 l1.39E 3 l ND 12.24E 5 l1.51E 5 12.77E0 l lBa-140 l2.77E8 12.42E5 l1.62E7 l ND l7.89E4 l1.45ES l1.40E8 l lDa 141 l 0 l 0 l 0 l ND l 0 l 0 l 0 l lBa 142 l 0 1 0 1 0 1 ND l 0 l 0 l 0 l lLa-140 l3.25E3 11.14E3 l3.83E2 l ND l ND l ND 13.17i.7 l lLa 142 l2.50E 4 17.98E 5 12.50E 5 l ND l ND l ND 11.58E1 l lCe 141 16.56E5 l3.27ES l4.86E4 l ND l1.43E5 l ND 14.08E8 l
') ' lCe-143 11.72E3 l9.31E5 ll.35E2 l ND l3.91E2 l ND l1.36E7 l lCe 144 l1.27E8 l3.98E7 l6.78E6 l ND l2.21E7 l ND l1.04E10 l lPr-143 l1.46ES l4.38E4 l7.25E3 l ND 12.37E4 l ND l1.58E8 l lPr 144 ) 0 l 0 1 0 _l ND I O l ND l 0 l lNd 147 l7.17E4 15.81E4 14.50E3 l ND 13.19E4 l ND l9.20E7 l lEu 154 l1.66E8 11.50E7 l1.37E7 l ND l6.57E7 l ND l3.40E9 l lHf 181-l4.90E5 11.79E6 l2.21E5 -l ND -l3.62E5 l ND l6.59E8 l lW 187 l6.47E4 l3.83E4 l1.72E4 l ND l ND l ND 15.38E6 l lNp 239 12.55E3 11.83E2 l1.29E2 l ND 15.30E2 l ND l1.36E7 l (a) The child age group; refer to reference 11.14.5.
). .
63 -
i APA ZZ 01003 Rev. 1 TAliLE $ _ (Contd . )
)
ADULT PAT)NAY DOSE TACTORS (R )g TOR RAD 10NUCE1DEG OTHER THAN N0!!LE GASES
~
Inhelation Pathway (mrero/yr) per (VCi/m ) 8 l l l l Total l ~l l l l lb'utl id e l Fone l Liver i Body 1 Thyroid l Kidney _
l Eung 1 01.EL1 J lH 3 i ND l1.26E+03 11.26E+03 l1.26E+03 l1.26E+03 l1.26E+03 l1.26E+03 l lBe 7 l4.27E+02 l9.6SE+02 14.70E+02 1 ND l ND l4.21E+04 l5.35E403 l lC 14 11.82E+04 l3.41E+03 13.41E403 l3.41E403 13.41E+03 13.41E+03 l5.41E+03 l lNo 24 l1.02E+04 11.02E+04 l1.02E+04 l1,02E+04 l1.02E+04 ll.00E+04 11.02E404 I JP-32 l1.32E+06 l7.71E404 l5.01E+04 l ND l ND l ND 18.64E+04 l lCr 51 1 ND l ND l1.00E+02 15.95E+01 12.26E+01 11.44E+01 l3.32t*03 l lHn 54 l ND 13.96E+04 l6.30E+03 l ND 19.64E+03 l1.40E+06 l7.74t+04 l lMn-56 l ND l1.24E+00 11.83E-01 l ND l1.30E400 l9.44E+03 12.00E404 l lTe 55 l2.46E+04 l1.70E+04 13.94E+03 l ND l ND 17.21E404 16.0'.E+03 l lTe 59 ll.16E+04 12.76E+04 11.06E404 l ND l ND l1.02E406 11.60E+05 l lCo 57 l ND l6.92E+02 16.71E+02 l Nb l ND l3.70E+05 13.14E+04 l lCo 58 l ND l1.5EE+03 l2.07E+03 l ND l ND 19.2BE+05 11.06E405 l
) lCo 60 l ND 11.15E+04 l1.4BE+04 l ND l ND l5.97E406 12.B$E+05 l lNi-63 l4,32E+05 13.14E+04 l1.4$E+04 l ND l ND l1.76E+05 l1.34E+04 l lNi-65 11.54E400 l2.10E 01 19.12E 02 l ND l ND l5.60E+03 l1.23E+04 l lCu 64 l ND 11.46E+00 16.15E 01 1 ND 14.62E+00 l6.76E+03 14.90E+04 l lZn 65 13.24E+04 11.03E+05 l4.66E+04 l ND 16.90E+04 16.64E+05 15.34E+04 l lZn 69 13.36E-02 l6.51E 02 14.52E 03 l ND l4.22E 02 l9.20E+02 l1.63E+01 l lBr-82 l ND l ND 11.35E+04 l ND l ND l ND ll.04E+04 l lBr 83 l ND l ND l2.41E+02 l ND l ND l ND 12.32E+02 l lBr-84 i ND l ND l3.13E402 l ND l ND l ND 11.64E 03 l lBr-85 l ND l ND l1.26E+01 l ND l ND 1 ND 10.00E+00 l lRb 66 l ND l1.35E+05 15.90E+04 l ND l ND l ND ll.66E+04 l lRb 8B l ND 13.670+02 l1.93E+02 l ND l ND l ND 13.44E 09 l lRb 89 l ND l2.56E+02 l1.70E+02 l ND l ND l ND l0.00E+00 l lSr 89 13.04E+05 l ND l6.72E+03 l ND l ND l1.40E+06 13.50E+05 l lSr 90 19.92E+07 l ND l6.10E+06 l ND l ND l9.60E406 17.22E+05 l lSr 91 16.19E+01 l ND 12.50E+00 l ND l ND 13.65E+04 11.91E+05 l lSr 92 l6.74E+00 l ND 12.91E 01 l ND l ND l1.65E+04 14.30E+04 1 lY-90 12.09E+03 i ND l5.61E+01 l hD l ND l1.70E+05 l5.06E+05 l h
64 -
APA 22 01003 j Rev. 1 i
[
J TABLE 5 (Contd.)
ADULT PATWAY DOSE TACTORS (R g) TOR RADIONUCLIDES OTi!ER T)(AN NOBLE GASES i
- Inhalation Pathway (mrem /yr) per (pC1/m')
l' l... l l l Total l l l l l
-lNuclidel Bonc Liver
! i Body l Thyroid l Kidney _ l Lung. l GI LLI l LY 91m l2.61E 01 l ND l1.02E 02 l ND l ND l1.92E+03 l1.33E+00 l LY 91 l4.62E+05 l ND 11.24E+04 l ND l ND l1.70t+06 13.85E+05 l I
Y 92- l1.03E+01 l ND 13.02E 01 l ND l ND l1.57E+04 17.35E+04 l Y 93 19.44E+01 l ND l2.61E+00 l ND l ND l4.85E+04 l4.22E+05 l lZr 95 lL 07E+05 13.44E+04 12.33E+04 l ND 15.42E+04 11 77E406 l1.50E+05 l .
lZr 97 19.68E+01-11.96E+01 l9.04E+00 l ND l2.97E+01 l7.87E+04 l5.23E+05 l-lNb 95 11.41E+04 l7.82E+03 l4.21E+03 l ND l7,74E+03 l5.0$E+05 11.04E+05 l .
4
' lMo*99- l ND l1.21E+02 12.30E+01 l ND [2.91E+02 l9.12E404 l2.48E405 l lTc 99m 11.03E 03-l2.91E 03 !3.70E 02 l 'ND [4.42E 02 l7.64E+02 l4.16E403 l
[ l7c 101 14.18E 05 l6.02E 05 l5.907. 04 l ND l1.08E 03 l3.99E+02 l0.00E+00 l l lRu 103 l1.53E+03 l ND l6.58E+02 l ND l5.83E+03 15.0$E+05 l1.10E405 l i lRu 205 17.90E 01'l- ND 13.11E 01 l -ND l1.02E+00 l1.10E+04 l4.82E404 l
- / -1Ru 106 6.91E404-l ND l8.72E+03 ND ll.34t+05 l9.36E+06 19.12E+05 l
- lAg 110m 1.08E+04 l1.00E404 l5.94E+03 ND l1.97E+04 l4.63E+06 l3,02E+05 l p lCd 109 ND l3.67E+05 l1.31E+04 1- ND l3.57E+05 (6.83E+05-l5.62E+04 l lSn 113'; 5.72E+04 12.18E+03 l4.39E403 11.24E403 i ND l9.44E+05 11.16E+05 l
-lSb 124 13.12E404 l5.89E+02 11.24E+04 l7.55E+01 l ND l2.48E+06 l4.06E405 l llSbe125 15.34E+04 15.95E+02 ll.26E+04 l5.40E+01 l ND l1.74E+06 l1.01E+05 l
.lTe 125ml3.42E+03 11.58E+03 .4.67E402 l1.05E+03 l1.24E+04 l3.14E+05 l7.06E+04 l
. 17e*127ml1.26E+04 15.77E+03 1.57E+03 13.29E+03 14.58E+04 l9.60E+05 l1.50E+05 l l 'lTe 127 l1.40E400 l6.42E 01 l3.10E 01 ll.06E+00 l5.10E+00 l6.51E+03 l5.74E+04 l ,
lTo 129ml9.76E+03-l4,67E+03 l1.58E+03 l3.44E+03 3.66E+04 l1.16E+06 l3.83E+05 l
-lTe 129 l4.98E 02 12.39E 02 l1.24E 02 l3.90E 02- 1.87E 01 h l.94E+03 l1.57E+02 l lTe 131ml6.99E+01 j4.36E+01 l2.90E+01 .5.50E+01 l3.09E+02 ' 1.46E+05'l 5.56E+05 l lTe 131 l1,11E 02 l5,95E 03:l3.59E 03- 9.36E 03 l4.37E 02 1,39E+03 1.84E+01 l'
- lYe 132 l2.60E+02 12'15E+02'l1.62E+02 . !1.90E+02 l1.46E+03 :2.88E+05 5.10E+05'l 11 130 l4.58E403 l1.34E+04'l5.28E403 l1.14E+06 l2.09E+04 l ND L7.69E+03 l l1131 l2.52E+04 13.58E+04-l2.05E+04 l1.19E407 l6.13E+04 l ND 6.28E+03 l1 132 -l1.16E+03 l3.26E403 l1.16E+03 ll.14E+05-l5.18E+03 l ND 4.06E402
-l1 133 l$ 64E+03 11.48E+04 l4.52E+03 12;15E406 l2.58E+04 l ND l8.88E+03 ,
]! 134 - l6.44E402 l1.73E+03 l6.15E+02-l2.98E+04 l2.75E+03 l ND l1,01E+00
]
65 -
l
,-...#,.,..%, L.' a , ..._._._,.,..__.~_mm_m__m ,.m ,_ ,.,,e-,.._m,,,m,r,.m,.,,..-,,m.,me m.,.,-_,,,_.,-,-... v-,~m#,r**'-+
APA 22 01003 Rev. 1
} TABLE 5 (contd.)
ADULT PATINAY DOSE TACTORS (Rg) TOR RADIONUCLIDES OT}lER T}{AN NOBLE GA$ES
) Inhalation Pathway 4 (mrem /yr) per (VCi/m')
l l l 1 Total l l l l l lNuclidel Bone l Liver l Body l Thyroid _1 Kidney 1 Lunc l GT LLI 1 lI-135 l2.66E403 l6.98E+03 12.57E+03 14.48E+05 l1.11E404 l ND 15.25E+03 l lCs 134 13.73E+05 16.46E+05 17.26E+05 l ND l2.67E+05 l9.76E+04 l1.04E+04 l lCs 136 13.90E404 l1.46E+05 l1.10E+05 l ND lB.56E+04 l1.20E404 l1.17E404 l lCs 137 l4.76E405 16,21E+05 14.26E405 l ND l2.22E+05 l7.52E+04 l8.40E+03 l lCs 138 l3.31E+02-l6.21E+02 l3.24E+02 l ND l4.60E+02 l4.86E+01 l1,66E 03 l lBa 139 l9.36E 01 16.66E-04 12.74E 02 l ND l6.22E 04 l3.76t+03 18.96E+02 l lBa 140 l3.90E+04 l4.90E+01 l 2.57E403 l ND l1.67E+01 l1.27E+06 12.18E+05 l lEa 141 l1.00E 01 l7.53E-05 3.36E-03 l ND l7.00E 05 l1.94E+03 l1.16E 07 l lBa 112 12.63E 02 l2.70E-05 1.66E 03 l ND l2.29E 05 l1.19E+03 l0.00E400 l lLa 90 l3.44E+02 l1.74E+02 14.5BE+01 l ND l ND l1.36E+05 l4.58E+05 l lLa 142 l6.63E 01 l3.10E 01 17.72E 02 l ND l ND l6.33E403 12.11E+03 l lCe 141 l1.99E+04 11.35E+04 l1.53E+03 l ND 16.26t+03 l3.62E+05 11.20E+05 l
) lCc 143 11.66E+02 l1.38E+02 11.53E+Cl l ND l6.06E+01 l7.98E404 l2.26E+05 l lCo 144 l3.43E+06 l1.43E+06 11.64E+0S l ND 18.4EE+05 17.76E'06 l6.16E+05 l lPr 143 l9236E+03 13.75E+03 l4.64E+02 l ND l2.16E403 l2.61E+05 l2.00E+05 l lPr 144 l3.01E 02 l1,25E 02 l1.53E 03 i ND l7.05E 03 l1.02E+03 12.15E 08 l lNd 147 l5.27E+03 If.10E+03 l3.65E+03 l ND l3.56E403 l2.21E+05 11.73E+05 l
' ltu 154 l5.92E+06 l7.28E+05 l5.18E+05 i ND l3.49E+06 l4.67E+06 l2.72E+05 l lHf 161 l1.41E+04 l6.62E+04 l6.32E+03 l ND l1,4BE+04 l6.65E+05 l1.39E+05 l lW-187 l6.4BE+00 17.06E+00 12.46E+00 l ND l ND l2.90E+04 11.55E+05 l lNp 239 l2.30E+02 12.26E+01 l1.24E+01 l ND l7.00E+01 l3.76E+04 11.19E+05 l l
)
66.
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l l l l 10181 l l l l l 1Nnotyp4l goua l I'TAa2 l gopA l 1yA2orp l xipuai. l gnuJ l DI ITI I lI ICS !0'003+00 10'003+00 i0'003+00 10'003+00 10'003+00 l NQ !0'003+00 1 105 IC1 19'f43+09 li'793+06 li'393+06 l NG li'091'+09 lI' 993+09 l U ' 413+04 l los tC9 lI'303+04 li'493+04 lC'133+0.I l NQ l3'9S3+04 lC'9C3+09 if'103+09 l 108 IC4 19'413+09 lt'163+06 14'913+09 l NQ 11'013+09 lt'C73+09 lC'Ct3+04 I
)08 159-10'003+00 10'003+00 10'003+00 l NQ 10'003+00 10'003+00 i0'003+00 l lga IC6 10'003+00 10'003+00 l0'003+00 l
~ NQ 10'003+00 10'003+00 10'003+00 l
, +
189 t70 lC'943+04'lC'913+01 lt*993+09 l NG li'CC3+01 13'043+01 lf'613+04 l
-lav tit 10'003+00 10'003+00 10'003+00 l NO 0'003+00 10'003+00 10'003+00 l lO'003+00 10'003+00 I NO 0'003+00 10'003+00 !0'003+00 l lge ll'u t40.ttt.10'003+OOLII'943 lC'tt3 03 03 11'653 0( l NC I NC l NO . lI'C43+0C l '
lI'U tyC : 0'003+00 ]0'003+00 10'003+00 l NQ l NQ l .NQ 10'003+00 l 100 111 t'103+01 16*163+0C 1'093+0C l NQ l v'113+0C l NQ lC'9C3+04 l
(
100-11( 3'013-03 li'163+01 t'913 OC l NQ 9'S13 0C l NQ lS'773+0Z l 1 100 t11 t'193+09 19*063+05 4'933+01 l NG C'9t3+05 l NQ 11'6C3+09 I ldJ tyC l C' t03+01 l9'103+0C ~lt*013e0C l NQ 11'953+0C l NU l6'i93+04 l dJ t11 l0'003+00 lO'003+00 IO'003+00 l NG l0'003+00 l NU l0'003+00-l NP t74 14'043+0( 19't43+0C 11'963+0C l NQ 11-443+0C NU lC*633+04 l 13n t51 19'0:3+09 l6'993+05 14'0(3+05.l .NQ 11 ' .t t3+09
' NU ll't73+09 l 1HJ 19t'lC'013+09 lt*193+04 lt*C53+09 l NG lC't73+09 l NC lI'993+tO
.IM-t94 1Z'043-03 li'4C3 OC 19'053 0C l NQ l NQ l NU 19*943+00 lNdgC6lE'9C30113'56303li'1C303l NQ 19*043 03 l NG li*C03+0C 1 d
j q
94 -
1
l APA ZZ 01003 Rev. 1 i
} TABLE $ (Contd. )
ADULT PATlNAY DOSE TACTORS (R g) TOR RADIONUCLlDES OTHER T)lAN NOBLE GASES Grass Cow Fk Pathway (m8 mrem /yr) >..er (vCA/sec)
I l l l Total l l l l l lb'uclide l Eone I Liver i Body l Thyroid l Kidney l Lung i GI LLI I ,
lH 3 l ND 17.63E+02 l7.63E+02 17.63E+02 l7.63E+02 17.63E402 l7.63E+02 l lBe 7 11.63E+03 l3.72E403 11.81E+03 l ND 13.93E+03 l ND l6.45E+05 l lC 14 12.63E+08 l5.27E+07 l5.27E+07 15.27E+07 15.27E407 15.27E+07 15.27E+07 l lNa 24 12.44E+06 l2.44E+06 l2.44E406 l2.44E+06 l2.44E+06 12.44E+06 l2.44E+06 l lP 32 l1.71E+10 l1.06E+09 16.61E+08 l ND l ND l ND l1.92E+09 l lCr 51 l ND l ND l2.86E+04 l1.71E404 16.30E+03 13.79E+04 l7.19E+06 l lMn 54 l ND 18.42E+06 l1.61E+06 l ND l2.50E+06 l ND l2.58E407-l lMn 56 l ND 14.20E 03 l7.45E 04 l !TO 15.33E 03 l ND l1.34E 01 l lTe 55 12.51E+07 l1.74E+07 14.0$E+06 l ND l ND l9.68t+06 19.96E+06 l lTe 59 12.97E+07 l6.98E407 l2.68E+07 l ND l ND l1.95E+07 12.33E+0B l Co 57 ND ll.2EE+06 12.13E+06 l ND l ND l ND l3.25E+07 l Co 58 ND l4.72E+06 l1.06E+07 l- ND l ND l ND {9.56E+07 l lCo 60 'ND 11.64E+07 l3.62E407 l ND l ND l ND l3.08E+08 lNi 63 16.73E+09 l4.76E408 12.26E+08 l ND l ND l ND l9.73E+07 lN1-65 l3.71E 01 14.82E 02 12.20E 02 l ND l ND l ND ll.22E+00 l lCu 64 . ND l2.39E+04 l1.12E+04 l ND 16.01E+04 i ND l2.03E+06 l lZn-65 1.37E+09 l4.37E+09 l1.97E+09 l ND l2.92E409 i ND l2.75E+09 l lZn 69 l0.00E+00 l0.00E+09 l0.00E+00 l ND l0.00E+00 l ND l0.00E+00 l lBr 82= l ND l .ND l3.23E+07 l ND l ND l ND 13.71E+07 l l lBr-83 l ND l ND l9.75E-02 l ND l ND l ND l1.40E-01 l lBr 84 l- ND l ND l0.00E+00 l ND l ND l ND l0.00E+00 l lBr-85 l ND l ND l0.00E+00 l ND l ND l .ND 10.00E+00 l lRb-86 l ND 12.60E+09 l1.21E+09 l ND l ND l ND l5,12E+08 l lRb-88' l ND 10.00E+00 l0.00E+00 l . ND l ND l ND 10.'J0E+00 l
- lRb-89 l ND l0.00E+00 10.00E+00 l ND l ND l ND 10.00E+00 l lSr 89 11.45E+09 l ND l4.17E<07 i ND. l ND l ND l2.33E+08 l
. lSr 90 l4.68E+10.l ND l1.15E+10 l ND .I ND l ND 11.35E+09 l lSr-91 l2.90E+04 i ND l1.17E+03 l ND l ND l ND l1.38E+05 l lSr 92 14.90E 01 l ND l2.12E-02 l ND l- ND l ND l9.71r+00 l lY 90 l7.09E+01 l' ND l1.90E+00 l ND l ND l ND l7.52E+05 l l
L 68 -
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APA ZZ 01003 l Rev. 1
) TABLE 5 (Contd. ) l ADULT PATWAY DOSE TACTORS g (R ) TOR W10EM OMR W NOM GASES Grass Cow Milk Pathway (m' mrem /yr) per (1C1/sec) l l l l Total l l l f l ,~
lNucifdel Bone i Liver l Body i Thyroid l Ridney l Lunr. I GI LLI l lY 91m l0,00E+00-l ND l0.00E+00 l ND l ND l ND l0.00E+00 l lY 91 l8.59E+03 l ND 12.3CI+02 l ND l ND l ND l4.73E+06 l lY 92 15.59E 05-l ND 11.63E 06 l ND l ND l ND l9.80E 01 l lY-93 l2.24E 01 l~ ND 16.18E 03 l ND l ND l ND l7.09E+03 l l2r 95: 19.44E+02 l3.03t+02 12.05E+02 1 ND 14.75E+02 l ND 19.59E+05 l lZr 97. 14.34E 01-l8.75E 02 14.00E 02 l ND ll.32E 01 l ND l2.71E404 l lNb 95 l8.26E+04 l4.59E404 l2.47E+04 l ND l4.54E+04 l ND l2.79E+06 l lMo 99 l ND l2.48E407 l4.72E+06 l ND 15.61E+07 l ND l5.74E+07 l lTc 99m 13.33E+00 19.40E+00 l1.20E+02 l ND l1.43E+02 l4.61E+00 l5.56E403 l-lTc 101 l0.00E+00 l0.00E+00 l0.00E+00 l ND 10.00E+00 10.00E+00 l0.00E+00 l-lRu 103 11.02E+03 l ND 14.39E+02 l ND 3.89E+03 l ND 1.19E+05 l ,
g ~lRu 105 18.58E 04 l ND l3.39E 04 l ND 1.11E 02 l ND 5.25E 01-
/ lRu 106 l2.04E404 l ND l2.58E+03-j ND l3.94E+04 l ND 11.32E+06 lAg 110ml5.82E+07 l5.39E+07 13.20E+07 l ND l1.06E+08 l ND l2.20E+10 lCd 109 l _ ND l1.13E+06 13.95E+04 l _ ND ll.08E+06 l ND l1.14E407 ISn 113 l1.34E+08 l3.81E406 17.73E+06 l2.18E+06 l ND ! ND 14.02E+08 l lSb 124 l2.57E+07 l4.86E+05 l1,02E407 l6.24E+04 l
-ND l2 00E+07 l7.31E+08 l
-lSb 125 l2.04E+07-l2.28E+05 14.87E+06 l2.08E+04 l ND l1.58E+07 l2.25E+08 l ,
lTe'-125ml1.63E+07--l5.90E+06 12.18E+06 l4.90E+06 16.63E+07-l ND 16.51E+07'l lTe 127ml4.58E+07-l1.64E+07 15.58E+06 l1.17E+07 l1.86E+08 ND 11.54E+08 l lTe 127 16.54E+02 l2.35E+02 l1.41E+02 l4.84E+02-l2.66t+03 ND l5.16E+04 l lTe-129ml6.02E+07 l2.25E+07 19.53E+06 12.07E+07 l2.51E+08 i ND l3.03E+08 l
-lTn 129 12.84E 10 11.07E*10 l0.00E+00 l2.18E-10 l1.19E 09 i ND l2.15E 10 l-lTe-131ml3.61E+05 l1.77E+05 11.47E+05 l2.80E+05 ll,79E+06-l ND- l 1. 755'% 7 _l iTe 131 10.00E+00 l0.00E+00-l0.00E+00 l0.00E+00 l0.00E+00 1 ND l0.00b00 l
- lTe 132 l2.40E+06 ll .55E+06 - l1.46E+06 li.72E+06 ' li .50E+07 l ND l7.35E+07-l - r lI 130~ l4.21E+05 l1.24E+06 l4.91E+05 l1,05E+08 l1.94E+06 l ND ll.07E+06 l 11 131 l2.97E+08-l4.2SE+08 l2.43E+08 l1.39E+11 l7.28E+08-l ND ll.12E+08 l
- II 132 11.65E-01 l4.42E-01.-l1.55E 01 11.55E+01 l7.04E-01-l ND 18 30E 02 l l
lI-133 l3.88E+06 16,75E+06 l2.06E+06 19.92E+08--ll.18E+07 l -ND l6.07E+06 l
.lI 134- l0.00E+00 10.00E+00 l0.00E+00 l0.00E+00 [0.00E+00 l ND l0.00E+00 l
{ ,
i
APA EZa01003 Rev. 1 TABLE S (Contd d
)
ADULT PATHk'AY DOSE TACTORS (Rg ) TOR RADIONUCLIDES OTHER THAN NOBLE GASES Grass Cow Hilk Pathway (m' mrem /yr) per (uC1/sec) l l l l l Total l l l l l l$clidel Bonc 1 Liver 1 Body l Thyroid i Kidney i Lung l G1 LLI i lI-135 11.29E+04 13.37E+04'll.25T.+04 l2.23E+06 l5.41E+04 l ND l3.81E+04 l lCs+A34 15.65E+09 l1.35E410 l1.10E+10 l ND l4.35L+09 11.45E+09 l2.35E+08 l lCs 136 12.63E+08 l1.04E+09 l7.48E+08 l ND 15.79E+08 17.93E+07 11.'9'&06 l lCs-137 l7.38E+09 l1.01E+10 l6.61E+09 l ND 13.43E+09 l1.14E+09 i &OB l lCs 138 10.00E+00 10.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+0 ' +00 l lBa 139 l4.44E 08 l0.00E+00 11.30E-09 i ND l0.00E+00 l0.00E+00 ,, 5 08 l lBa 140 l2.69E+07 l3.38E+04 11.76E+06 l ND ll.15E+04 l1.93E+04 15.54E+07 l lBa 141 10.00E+00 10.00E+00 l0.00E+00 l ND l0.00E+00 10.00E+00 10.00E+00 l lBa-142 l0.00E+00 10.00E400 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l lLa 140 l4.51E+00 l2,28E+00 16 ^1E 01 l ND l ND l ND l),67E+05 l lLa 142 l1.87E-11 l8.49E-12 12.12E 12 l ND l ND l ND 16.20E*06 l lCe 141 l .85E+03 l3.28E+03 l3.72E+02 l ND l1.52E+03 l ND l1.25E+07-l
) lCo 143 l4.16E+01 l3.08E+04 13.40E+00 l ND ll.35E+01 l ND l1.15E+06 l lCe 144 l 3.58E+05 - l1.50E+05 11.92E+04 l ND 18.87E+04 l ND l1.21E48 l lPr 143 l1.58E+02 l6.34E+01 l7.83E+00 l ND l3.66E+01 l ND l6.92E+05 l lPr 144 l0.00E+00 10.00E+00 l0.00E+00 l ND l0.00E+00 l ND l0.00E+00 l lNd 147 l9.42E+01 l1.09E+02 l6.51E+00 l ND 16.36E+01 ! ND lf.23E+05 l lEu 154 12.37E+04 12.91E+03 l2.07t+03 l ND l1,39E+04 l ND l2.11E+06 l lHf 181-ll.42E+02 l6.91E+02 16.41E+01 l ND l1.49E+02-l ND l7.87E+05 lV-187 l6.52E+03 l5.45E+03 l1.91E+03 l ND l ND l ND 11.78E+06 lNp-239 l3.69E+00 13.62E 01 12.00E 01 l ND l1.13E+00 l ND 17.43E+04 l l
- _ . _ . _ _ _ . _ _ _ . _ _ . -_ ~
F APA EE 01003 Rev. 1
) E BLE $ (Contd.)
ADULT PAT)NAY DOSE FACTORS (R )g FOR RAD 10NUCL1 DES OTilER T) TAN NOBLE GASES Grass Goat Milk Pathway (m' mrem /yr) per (VCi/sec) l l l l Total l l l l l lNuclidel Bone l Liver i Body l Thyroid i Kidney l_ Lung i GI LLI l l11 3 l ND l1,56E+03 l1.'56E403 l1.56E+03 l1.56E+03 l1.56E+03 l1.56E403 lBe 7 11.96E+02 l4.47E402 12.17E+02 l ND l4,72E+02 l ND l7.74E+04 10 14 l2.64E408 l$.27E407 l5.27E+07 15.27t+07 15.27E407 l5.27E+07 15.27E407 lNa 24 l2.93E+05 l2.93E+05 l2.93E+05 12.93E+05 l2.93E+05 12.93E+05 l2.93E+05 l
! lP 32 12.05E+10 ll.18t+09 l7.94E+08 l ND l ND l ND l2.31E+09 l l
E lCr 51 ND -l ND l l3.43E+03 12.05E+03 17.56E+02 l4.5bE+03 18.63E+05 l lMn 54 l ND l1.01E406 l1.93E+05 l- ND 1.01E+05 l ND l3.10E+06 l lMn-56 l _ ND 15.04E 04 l8.94E 05 l ND 16.40E 04 l ND l1.61E 02 l lFe 55 l3.27E+05 12.26E+05 5.26E+04 l ND l ND l1.26E+05 l1.30E+05 l lTe 59 l3.87E405 l9.08E405 5.48E+05 l ND l ND l2.54E+05 l3.03E+06 l l
lCo 57 l ND l1.54E+05 l2.56E+05 l ND l ND l ND l3.90E+06 '
, lCo 58 l ND l5.66E+05 11.27E+06 l ND l ND l ND li.15E407 ,
lCo-60 I ND l1.97E+06 l4.35E+06 l ND l ND l ND 13.70E+07 1 l -lN1 63 8.08E+08 l5.60E407 l2.71E+07 l ND l ND l ND l1.17E407 l
-lN1 65 .4.46E 02 l5.79E 03 l2.64E 03 l ND l ND l ND l1.47E 01 l
~
lCu 64 l ND l2.66E+03 ll.25E+03 l ND 16.71E+03 l NP l2.27E+05 l
/ lZn 65 l1.65E+08 l5.24E+08 12.37E+0B l ND .13.51E403 l ND l3.30E+08 l lZn 69 _ l 0.0K+00 l0. 00E+00 l0.00E400 l ND l0.00E+00 l ND 10.00E+00 l >
lBr 82 l ND. l ND l3.88E+06 l ND l ND l ND l4.45E+0e l lBr 83 l ND- l ND l1.17E 02 l ND l ND l ND ll.69E 02 l lBr 84 -l -ND l ND l0.00E+00 l ND l ND l ND 10.00E+00 l lBr 85 l ND l ND l0.00E+00 l ND ND l ND l0.00E+00-l lRb-86 l -ND 13.12E+08 l1.45E+08 l ND ND l ND l6.15E+07 l-lRb 88 l ND l0.00E+00 l0.00E+00 l ND -1 ND l ND' l0.00E+00 l lRb 89 l ND 10.00E400-l0.00E+00 l ND l _ND l ND l0.00E+00 l ISr 89 l3.05E+09 l ND l8.75E+07 l ND l ND l ND I4.89E+08 l
'lSr 90 l9.84E+10 l ND l2.41E+10 l ND l _ND l ND 12.84E+09 l
-lSr-91 16.09E+04 l ND l2.46E+03 l ND l ND l ND l2.90E405 l lSr 92 l1.03E+00l ND l4.45E 02 l ND l ND l ND , 12.04E+01 l lY 90 -l8.51E+00 l -ND l2.28E-01 l ND l ND l ND l9.03E+04 l-
-)
71 -
e APA ZE 01003 ,
. Rev. 1 I l
i
- 1 i
) TABLE 5 (Contd.)
1 j' ADULT PATWAY DOSE TACTORS (Rg) FOR RADwNUCLIDES OTHER THAN NOBLE GASES t
l_ Orass Goat Milk I'athway (m' mrem /yr) per (pC1/sec) l l l l Total l l l l l lNue11del Bone i Eiver i Body l Thyroid l l'idney 1 1.ung I 01 LLI i 1 lY 91m l0.'00E+00 l ND l0.00E400 l ND l ND I 'ND 10.00E400 l
. lY 91 l1.03E+03 L ND l2.76E401 l ND l ND -1 ND 15.66E+05 l
. lY 92 -l6.72E 06 l ND 11.96E 07 l ND l ND ND (1.18E-01 l 1 lY 93 l2.69E 02 ND l7.42E 04 l ND l ND ND l8.52E+02 l l l2r*D5 l1.13E+02 .3.63E+01 l2.46E+01 l ND 15.70E+01 l ND l1.15E+05 l
- lZr+97 l5.21E 02 l1.0$E 02 l4.60E 03 l ND l1.59E 02 ND 13.2SE403 lNb 95 l9.92E+03 15.52E+03 l2.97E+03-l ND 5.45t+03 ND 13.35E+07 r lMo 99 l ND l2.9BE+06 l5.66E+05 i ND 6.74E+06 ND l6.90E406 ,
lTc 99m l3.99E 01 11.13E+00 l1.44E+01 l ND l1.71E+01 L5.53E 01 l6.66E+02 lTc.101_l0,00E+00 10.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E400 l0.00E+00 ,
IRu 103 l1.22E+02 l -ND l5.27E+01 l ND :4.67E+02 l ND l1.43E+04 l 1- lRu 105 l1.03E 04 l' ND l4.07E 05 l ND 1.33E 03 l ND l(.31E 02 l l _/ lRu 106 l2.45E+03 i ND l3.10E+02 l ND 4.73E+03 l ND ll.59E+05 l l As 110ml6.99E+06 l6.47E+06 l3.64E+06 l ND l1.27E+07 l ND l2.64E+09 l LCd 109 i ND l1.36E+05-l4.74E+03 l ND l1.30'+05 i ND l1.37E+06 l
- l$n 113 l1.61E+07-14.58E+05-l9.26E+05 l2.62E+05 l ND l ND 14.83E+07 l l
l$b 124 13.09E+06 15.84E+04 11.23E+06 l7.50E+03 l ND l2.41E+06 l8.76E+07 l lSb 125 l2,46E+06 12.74E+04 15.64E+05 l2.50E+03 l ND l1.89E+06 l2.70E+07 l ,
! lTe125ml1.96E+06 l7.09E+05 12.62E+05 j5.69E+05 l7.96E+06 i ND l7.81E+06 l l lTo 127ml5.50E+06 l1.97E+06 16.70E+05 l1.41E+06 12.23E+07 ND l1.64E+07 l lTe 127 l7.65E+01-l2.62E+01 11.70E+01 l5.82E+01 l3.20E+02 ,
ND 16.19E+03 l lTe 129ml7.?3E406 12.70E+06 11.14E+06 12.46E+06 13.02E+07 l ND l3.64E+07 l L ITe 129 l0.00E+00 10.00E+00_l0.00E+00 l0.00E+00 l1.43E 10 l ND 10=00E+00 l
' lTe 131ml4.34E+04 l2.12E+ M l1.77E+04 13.36E+04 12.15E+05 l ND l2.11E+06 l L
- lTe 131 l0.00E+00 l0.000 10.00E+00 10.00E+00_10.00E+00 1 ND 10.00E+00 l lTe 132_'l2.89E+05 11.67_ l1.75E+05 l2.06E+05 l1.60E+06 l ND 18.83E+06 l 1 130 15.0$E+05 l1.49E+06 15.66E+05 11.20E+0B l 2.32E+06 'l ND 11.26E+06 l 1 131 l3.56E+08 l5.09E+08-l2.92E+06'll.67E+11 16,72E+08 l ND l1.34E+08 l
!I 132 11.98E 01 l$ 29E 01 l1.85E 01 l1.65E+01 l8 43E-01 l ND l9.95E 02 l I 133 14.65E+06 18.09E+06 l2.47E+06 -l1.19E+09 l1.41E+07 l ND l7.27E+06 l 11 134 -l0.00E+00-10.00E+00 10.00E+00_l1.15E 10 10.00E+00 l- ND l0.00E+00 l
- h I. 72 -
- :...,4 . . - . - - , - . . . . . . .----m-.,--.~.. a...-- ~, , . . - - , . . , , , , - , - . - - , _ _ , , _
m,..._-
APAoZZo01003 Rev. 1 TABLE 5 (Contd.)
s ADULT PAhWAY DOSE FACTORS g (R ) FOR RADIONUCLIDES OTHER.THAN NOBL Grass Goat-Milk Pathway (m mrem /yr) per (pCf/sec) 8 l l l l Total l l l l l lNuclidel Bone l Liver l Body l_ Thyroid i Kidney l Lung l GI-LLI l lI-135 l1.54E+04 l4.04E+04 l1.49E+04 l2,67FrC6 l6.48E+04 l ND 14.57E+04 l lCs 134 l1.70E+10 l/ .04E+10 l3.30E+10 l NC -l1.31E+1C l4.34E+09 l7.07E+08 l lCs-136 l7.91E+0B l3.12E+09 l2.25E+09 . 'ND l1.74E+09 l2.38E+08 l3.55E+08 l lCs-137 l2.22E+10 l3.03E+10 11.99E+10 l ND l1,03Ed10 l3.42E+09 15.87E+08 l lCs-138-l0.00E+00-10.00E+00 l0.00E+00 l ND 10.0664 30 l0.00E+00 l0.00E+00 l lBa-139 l5.34E-09 l3.08E-12 l1.56E-10 l ND l3.55E l'i l2.16E-12 l9 46E-00 l lBa-140 l3.23E+06 l4.06E+03-l2.12E+05 l ND l1.38E+03 12.32E+03 l0.65E+06 l lBa-141 10.00E+00 l0.00E+00 l0.00E+00 ( ND l0.00E+00 10.00E+00 l0.00E+00 l lBa 142-l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l' lLa-140 l5.42E-01 l2.73E-01 l7.22E-02 l ND ND l ND l2.01E+04 lLa-142 l0.00E+00 l0.00E+00 l0.00E+00 l ND , ND l ND l7.45E 09 j 4 lCe-141 l5.82E+02 13.94E+02 l4.46E+01 l ND ll.83E+02 l ND 11.50E+06 l
)' ' !Ce-143 l4.99E+00 l3.69E+03 l4.09E-01 l ND l1.63E+00 l ND l1.38E+05 l lCe 11;. l4.30E+04 l1.80E+04 l2.31E+03 l ND l1,07E+04 l ND ll.45E407 l lPr-143 l1.90E+01 l7.61E+00 19.40E-01 l ND l4.39E+00 l ND l8.31E+04 l lPr-144 l0.00E+00 l0.00E+00 10.00E+00 l ND l0.00E+00 1 ND l0.00E+00 l
-lNd-147 l1.13E+01 11.31E+01 l7.82E-01 l ND- l7.64E+00 l ND l6.28E+04 l lEu 154 l2.84E+03 13.49E+02 12.49E+02 l ND' .ll.67E+03 l ND l2.53E+05 l
-lHf-181 11.71E+01 l8.31E+01-l7,70E+00 l ND 11.79E+01 l ND l9.46E+04-l l k'- 187 l7.83E+02 16.54E+02 l2.29E+02 l ND l ND l ND J2.14E+05 l
'llip-239 l4,43E-01 14.35E-02 l2.40E-02 l ND l1.36E-01 l ND l8.93E+03-l.
L L
l j
73 -
I APA 32-01003 I Rev. 1 TABLE 5 (Contd.)
ADULT PAT}NAY DOSE TACTORS (Rg) FOR RADIONUCLIDES OTi!ER TliAN NOBLE GASES -
Vegetation Pathway (m8 mrem /yr) per (pC1/sec) l~' .
l l l Total l l l l l lNuc11 del Bone 1 Liver 'l Body i Thyroid i Kidney l Lung l GI-LLI l l }{-3 'l ND l2.26E+03 l2.26E+03 12.26E+03 l2.26E+03 12.26E+03 l2.26E+03 l lBe 7 l9.24E+04 l2.11E+05 11.03E+05 i ND l2.23E+05 l_ ND 13.66E+07 l 10-14 l2.28E+08 l4.55E+07 l4.55E+07 14.55E+07 14.55E+07 14.55E+07 l4.55E^07 l lNa-24 l2.69E+05 l2.69E+05 12.69E+05 12.69E+05 12.69E+05 12.69E+05 l2,69E+05 lP-32 l1.40E+09 l8.74E+07 l5.43E+07 i ND l ND l ND l1,58E+08
';.'rs. l ND l ND 14.64E+04 12.78E+04 l1.02E+04 16.16E+04 ll.17E+0? l lMn 24 l ND l3.13E+08 l5 97E+07 l ND l9.31E+07 l ND l9.59E+08 l lMn 56- l ND l1.60E+01 12.84E+00 l- ND l2.03E+01 1 ND - .l5.10E+02 l lFe-55 l2.10E+08 11.45E+08 l3.38E+07 i ND l ND l8.08E+07 l8.31E+07'l lFe -11.26E+08 l2.96E+08 l1.14E+08 l ND l ND l8.28E+07 l9.88E+0B l 100-57 l ND l1.17E+07'l1.95E+07 l ND l ND l ND l2.97E+08 l-y .lCo-58 l ND .l3.07E+07 l6.89E+07 l ND -l ND l ND l6.23E+08 l
) lCo-60 l ND ' l1.67E+08 l3.69E+08 l ND l ND l ND l3.14E+09.l lNi l1.04E+10 17.21E+08 '13,49E+0B l
- ND l ND 1 -ND l1.50E+08 l lNi-65 l6.16E+01 l8.00E+00 l3.65E+00 l ND l ND l ND l2.03E+02 l lCu-64 l ND l9.20E+03 l4.32E+03 l ND l2.32E+04 l ND l7.84E+05 l lZn-65 13,17E+08 l1,01E+09 l4,56E+08 l ND 16.75E+08 l ND 16.36E+08 l lZn-69' 15.52*;-06 l1.05E-05 .l7.34E-07 l ND 16,85E-06 l ND l1.59E-06 l lBre82 'ND- l ND. -l1.50E+06'l ND l ND l ND 11.72E+06 l
_-l B r-8 l 3ND. l l ND l3.11E+00 l ND l' ND i ND l4.48E+00 l lBr-844 l- ND l ND l0.00E+00 l ND l ND ND l0.00E+00 l lBr-85 l ND _l ND 10.00E+00 l ND l ND ND_ [0.00E+00 l
-lRb-86 l ND' l2.19E+08'll.02E+08 l ND l ND i ND ll4.33E+07 l lRb-88~ l. ND l0.00E+00 l0.00E+00 l ND l ND l ND l0.00E+00-l l Rb'-89 ll. ND- l0.00E+00 l0.00E+00 l ~ND l ND l ND l0.00E+00 l
-lSr-89. l9.97E+09 l ND- l2.86E+08 l ND l ND l ND l1'.60E+09 l' lSr-90 16.05E+11-l ND l1.48E+11 1 ND l ND l ND l1.75E+10 l
-lSr 91 l3.05E+05 l ND ll.23E+04 l ND l ND l- ND l1.45E+06 l lSr-92 -l4.27E+02 l: ND ll.85E+01 l ND l ND l ND l8.46E+03.l-lY-90_ l1.33E+04Jl ND l3.57E+02 l ND l ND l ND. l1.43E+08 l s-
APA ZZ 01003 Rev. I l
.[ TABLE 5 (Contd.)
ADULT PATINAY DOSE TACTORS (Rg) TOR RADIONUCLIDES OTHER THAN NOBLE GASES Vegetation Pathway (m8 mrom/yr) per (pC1/sec) l l l l Total l l l l -l lNuclidel Bone i Liver l Body l Thyroid l Midney l Lung i GI-LLI 1 lY-91m l5.24E 09 l ND -l2.03E 10 l ND l ND l ND l1.54E-08 l
'lY-91 l5.11E+06 l ND l1.37E+05 l ND l ND l ND l2.81E+09 l lY-92 l9.16E-01 l ND l2.6bE 02 l ND l ND l ND. l1.60E+04 l lY-93 11.70E+02 l ND l4.68E+00 l ND l ND l ND l5.38E+06 l lZr 95 11.17E46 13.77E+05 12.55E+05 l ND l5.91E+05 l ND ll.19E+09 l lZr-97 l3,37E+02 l6.81E+01 l3.11E+01 l ND ll.03E+02 l. ND l2.11E+07 l lNb-95 l1.42E+05 l7.92E+04 l4.26E+04 l ND l7.83E+04 l ND l4.81E+08 l lHo-99 l0.00E+00 l6.15E+06 l1.17E+06 l ND l1.39E+07 l NO l1.43E+07 l lTc 99m l3.10E+00 l8.77E+00.'ll.12E+02 l ND l1.33E+02 l4.30E+00 15.19E+03 l ,
lTc-101.l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l0.00E+00 l0.00E+00 l lRu 103 l4.77E+06 l ND l2.06E+06 l ND l1.82E+07 l ND l5.57E+08 l j- '
lRu-105 l5.39E+01 l ND l2.13E+01 l ND 16,97E+02 l ND l3.30E+04 l
/ . l Ru-106 l1.93E+08 l ND l2.44C+07 l ND l3.72E+08 l ND 1.25E+10 l
-lAg-110ml1,05E+07 l9.75E+06 l5.79E+06 l ND l1.92E+07 l ND 3.98E+09 l lCd-109 10.00E+00 l8.36E+07-12.92E+06 l ND 18.00E+07 l ND. 8.43E408 l
.lSn-113 l4.16E+0B l1.18E+07 l2.40E+07 l6.75E+06 l ND l ND l1.25E+09 l lSb-124 l1.04E+08 .l1.96E+06 l4.11E+07 l2.51E+05 l ND l8.07E+07.l2.94E+09 l lSb-125 l1.37E+08 l4.53E+06 l3.2SE+07 l1.39E+05 l ND ll.05E+08 l1.50E+09 l lTo .
nl9.66E+07 13.50E+07 l1.29E+07 l2.90E+07 l3.93E+08 l ND l3.E6E+08 l l7 el3.49E+0B l1.25E+08 l4.26E+07 l8.92E+07 l1.42E+09 l ND l1.17E+09 l
- t. '. 1 15.66E+03 l2.03E+03 l1.23E+03 l4.20E+03 l2.31E+04 l ~ ND l4.47E+05 l l
lTe-129ml2.51E+08 l9.38E+07 l3.9BE+07 l8.64E+07 l1.05E+09 l ND l1.27E+09 l
, lTe-129 l7.65E-04 12.87E-04 l1.86E-04 l5.87E-04 l3.22E-03 l ND l5.77E 04 l lTe-131ml9,12E+05 l4.4eE+05 13.72E+05 17.07E+05 14. 9E+06 l ND l4.43E+07 l
.lTe-131 l0.00E+00 10.00E+00 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l lTe-132 l4.30E+06 l2.78E+06 l2.61E+06 l3.07E+06-12.68E+07 l ND l1.32E+08 l-l -lI-130 l3.93E+05 l1.16E+06 l4.57E+05 l9.81E+07 l1.81E+06 l ND l9.97E+05 l lI-131 -18.0BE+07-l1.16E+08 le.62E+07 l3.79E+10-l1.98E+08 l ND l3.03E+07 l l1-132 l5.77E+01 l1.54E+02 l5.40E+01 15.40E+03 l2.46E+02 l ND l2.90E+01 l lI-133 .l2.09E+06 l3.63E+06 l1.11E+06 l5.33E+08-l6.33E+06 l ND l3'.26E+06 l lI-134 19.69E-05 l2.63E-04 l9.42E-05 l4.56E-03 l4.19E 04 l ND l2.30E-07 l j.
- 75 -
n = e v
APA ZZ-0100?.
Rev. 1 TABII 5 (Contd. )
ADULT PATHWAY DOSE TACTORS (R g ) FOR RADIONUCLIDES OTHER THAN NOBII GASES Vegetation Patbway (m' mrem /yr) per (pC1/sec) l l l l Total l l l l l l@elfdel Bone l Liver l Body 1 Thyroid 1 Kidney l Lung i GI-LLI l 11-135 13.90E404 ll.02E+05 13.77E+04 16.74E+06 l1.64E+05 i ND 11.15E+05 l lCs-134 l4.67E+09 l1.11E+10 l9,08E+09 l ND l3,59E+09 l1,19E+09 l1,94E+08 l lCs-136 l4.27E+07 l1.69E+0B 11.21E+08 l ND l9.38E+07 11.29E+07 l1.91E407 l lCs-137 l6.36E+09 18,70E+09 l5,70E+09 l ND l2.95E+09 19.81E+08 l1,68E+08 l lCs-138 l0,00E+00 l0.00E+00 l0,00E+00 l ND 10.00E400 l0.00E+00 l0.00E+00 l lBa 139 12,86E-02 l2,04E 05 18.39E-04 l ND l1.91E-05 11.16E 05 15.08E 02 l lBa-140 11.29E+08 l1.61E+05 18.42E+06 l ND l5,49E+04 l9.24E+04 l2,65E+08 l lBa-141 l0.00E+00 l0.00E+00 l0.00E+00 l ND 10.00E+00 l0.00E+00 10,00E+00 l lBa-142 10.00E+00 l0.00E+00 10.00E+00 l ND l0.00E+00 10,00E+00 l0,00E+00 l lLa 140 ll,98E+03 l9.97E+02 l2.63E+02 l ND l ND l ND 17.32E+07 l lLa-142 l2.03E-04 19.21E-05 12.29E 05 l ND l ND l ND 16.72E-01 l lCc 141 ll,97E+05 l1,33E+05 l1.51E+04 l ND 16.19E+04 l ND 15,10E+08 l
) lCo-143 l9,98E+02 17.38E+05 l8.17E+01 l ND 13,25E+02 l ND l2.76E+07 l lCc-144 l3,29E+07 l1.3BE+07 ll,77E+06 l ND 18,16E+06 l ND l1.11E+10 l lPr-143 l6,26E+04 l2,51E+04 l3.10E+03 l ND l1.45E+04 l ND l2,74E+08 l lPr-144 l0.00E+00 l0.00E+00 l0.00E+00 l ND l0.00E+00 l ND l0.00E+00 l lNd-147 l3.33E+04 13.85E+04 l2,31E+03 l ND l2.25E+04 l ND ll 85E+08 l leu-154 l4,85E+07 l5.97E+06 14.25E+06 l ND 12.86E+07 l ND l4.32E+09 l lHf-181 l1.40E+05 l6.82E+05 l6.32E+04 l ND ll.47E+05 l ND 17.76E+08 l lW-187 l3.80E+04 13.18E+04 l1.11E+04 l ND l ND l ND l1,04E+07 l lNp 239 l1,43E+03 11 41E+02 l7.76E+01 l ND l4,39E+02 l ND- l2.89E+07 l b
APA-ZZ-01003 Rev, 1
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3.6 Gaseous Radwaste Treatment System 41862 3.6.1 REC 9.9.1.1 4160 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE 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, from each unit, to areas at and beyond the SITE BOUNDARY would exceed:
- 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 an Individual 3.6,2 . Description of the Gaseous Radwaste Treatment System The gaseous radwaste treatment system and the ventilation exhaust system are available for use whenever gaseous effluents require treatment prior to being released to the environment. The I
gaseous radwaste treatment system is designed to-
. allow for the retention.of all gaseous fission products to be discharged from the reactor coolant _ system. The retention system consists of eight (8) waste gas decay tanks, six (6) for use during normal operations and two (2) for use during shutdown conditions. Normally, waste gases will be retained for at least 60 days prior to discharge. These systems will provide reasonable assurance that the releases of radioactive materials.in gaseous effluents will _
be kept ALARA.
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1 APA-ZZ-01003 Rev. 1
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3.6.3 Operability of the Gaseous Radwaste Treatment System The OPERABILITY of the gaseous radwaste treatment system ensures this system will be available for use when gases require treatment prior to their release to the environment. OPERABILITY is demonstrated through compliance with Sections 9.6.1.1, 9.7.1.1, and 9.8.1.1. _;
Projected doses (gamma air, beta air, and organ !
dose) due to gaseous effluents at or bevond the SITE BOUNDARY are determined each 31 cays by dividing the cumulative annual total by the number of elapsed months.
4.0 DOSE AND DOSE COMMITMENT FROM URANIUM FUEL CYCLE SOURCES 41864- 4.1 REC Section 9.10.1.1 4160 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC due to -
releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to
) less than or equal to 25 mrem to the_ total body or any organ, except the thyroid, which shall be t limited to less than or equal to 75 mrem.
4.2 Calculation of Dose and Dose Commitment from Uranium Fuel Cycle Sources The annual dose or dose commitment to a MEMBER OF u THE PUBLIC for Uranium Fuel Cycle Sources is
! determined as:
l a) Dose to the total body and internal organs due ,
to gamma ray exposure from submersion in a ?
m cloud of radioactive noble gases, ground plane
? exposure, and direct radiation from the Unit and outside storage tanks; l
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APA-ZZ-01003 Rev. 1
) b) Dose to the skin due to beta radiation from submersion in a cloud of radioactive noble gases, and grcund plane exposure; c) Thyroid dose due to inhalation and ingestion of radiciodines; and d) Organ dose due to inhalation and ingestion of radioactive material.
It is assumed that total body dose from sources of gamma radiation irradiates internal body organs at the same numerical rate. (Ref. 11.12.5)
The dose from gaseous effluents is considered to be the summation of the dose at the individual's residence and the dose to the individual from activities within the SITE BOUNDARY.
Since the doses via liquid releases are very conservatively evaluated, there is reasonable assurance that no real individual will receive a significant dose frcm radioactive liquid release pathways. Therefore, only doses to individuals via airborne pathways and doses resulting from
- direct radiation are considered in determining
) compliance to 40 CFR 190. (Ref. 11.12,3)
It should be noted that there are no other Uranium Fuel Cycle Sources within 8km of the Callaway Plant.
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APA-ZZ-01003 Rev. 1 4.2.1 Identification of the MEMBER OF THE PUBLIC The MEMBER OF THE PUBLIC is considered to be a real individual, including all persons not occupationally associated with the Callaway Plant, but who may use portions of the plant site for recreational or other purposes not associated with the plant. (Ref. 11.4 and 11.8.10.)
Accordingly, it is necessary to characterize.this individual with respect to his utilization of areas both within and at or beyond the SITE BOUNDARY and identify, as far as possible, major assumptions which cculd be reevaluated if necessary to demonstrate continued compliance with 40 CFR 190 through the use of more realistic
-assumptions. (Ref. 11.12.3 and 11.12.4)
The evaluation of Total Dose from the Uranium Fuel Cycle should consider the dose to two Critical Receptors: a) The Nearest Resident, and b) The Critical Receptor withir. the SITE BOUNDARY.
4.2.2 Total Dose to the Nearest Resident The_ dose to the Nearest Resident is due to plume
'] exposure from noble gases, ground plane exposure, and inhalation and ingestion pathways. It is conservatively assumed that each ingestion pathway (meat, milk, and vegetation) exists at the location of the Nearest Resident.
It is assumed that direct radiation dose from operation of the Unit and outside storage tanks,. ,
and dose from gaseous effluents'due to activities !
within the SITE BOUNDARY, is negligible for the Nearest Resident. The total Dose from the Uranium Fuel Cycle to the Nearest Resident is criculated using the methodology discussed in Section 3, using concurrent meteorological data for the location of the Nearest Resident with the highest value of X/Q.
80 - )
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APA-ZZ-01003 Rev. 1 The location of the Nearest Resident in each meteorological sector is determined from the Annual Land Use Census conducted-in accordance with the Requirements of-Section-9.12.1.1.
4.2.3 Total Dose to the Critical Receptor Within the SITE BOUNDARY The Union Electric Company has entered into an agreement with the State of Missouri Department of Conservation for management of the residual 1 lands surrounding the Callaway Plant, including some areas within the SITE BOUNDARY. Under the terms of this agreement, certain areas have been opened to the public for low intensity recreational uses (hunting, hiking, sightseeing, etc.) but recreational use is excluded in an area immediately surrounding the plant site (Refer to Figure 4.1). Much of the residual lands within the SITE BOUNDARY are leased to area farmers by the Department of Conservation to provide income to support management and development costs.
Activities conducted under these leases are primarily comprised of farming (animal feed),
grazing, and forestry. (Ref 11.7.2, 11.7.3, 11.13, 11.13.1).
J Based on the utilization of areas within the SITE BOUNDARY, it is reasonable to assume that the critical receptor within the SITE BOUNDARY is a farmer, and that his dose from activities within the-SITE BOUNDARY is due to exposure incurred while conducting his farming activities. The
, current tenant has estimated that he spends l approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year working in this l
L area (Ref 11.5.5)~. Occupancy of areas within the SITE' BOUNDARY is assumed to be averaged'over a period of one year.
Any reevaluation of assumptions should include a reevaluation of the occupancy period.at the locations of real exposure (e.g. a real individual would not_ simultaneously exist at each point of maximum exposure).
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APA-ZZ-01003 Rev. 1 4.2.3.1 Total Dose to the Farmer from Gaseous Effluents The Total Dose to the farmer from gaseous effluents is calculated using the methodology discussed in Section 3, utilir.ing concurrent meteorological data at the farmer's residence and historical meteorlogical data from Table 10 for activities within the SITE BOUNDARY. These dispersion parameters were calculated by assuming that the farmer's time is equally distributed over the areas farmed within the SITE BOUNDARY, and already have the total occupancy of 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> / year factored into their value (Ref.
11.5.6).
The residence of the current tenant is located at a distance of 3830 meters in the SE sector. No meat or milk animals or vegetable gardens were identified by the 1987 Land Use Census for this location, therefore, the gaseous effluents dose at the farmer's res4.dence is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.
It is assumed that food ingestion pathways do not
}
exist within the SITE BOUNDARY, therefore the gaseous effluents dose within the SITE BOUNDARY is due to plume exposure from Noble Gases and the ground plane and inhalation pathways.
4.2.3.2 Total Dose from Direct Radiation 4.2.3.2.1 Direct Radiation Dose from Outside Storage Tanks The Refueling Water Storage Tank (RWST) has the highest potential for receiving significant amounts of radioactive materials, and constitutes the only potentially significant source of direct radi'ation dose from outside storage tanks to a MEMBER OF THE PUBLIC. (Ref. 11.6.14, 11.6.15, 11.6.16, and 11.6.17.)
)
APA-ZZ-01003 Rev. 1 Direct radiation dose from the RWST ta a MEMBER ;
OF THE PUBLIC is determined at the nearest point '
of the owner Controlled Area fence which is not obscured by significant plant structures. This has been-determined to be 450 meters from the RWST. ,
The RWST is a right circular cylinder approximately 12 meters in diameter, 14 meters in height with a capacity of approximately 1,514,000 liters. (Ref.-11.6.17.) The walls are of type 304 stainless steel and have an average thickness t of .87 cm. (Ref. 11.14.1.)
The direct radiation dose from the RWST is calculated based on the tank's average isotopic content and the parameters discussed above, considering buildup and attenuation within the volume nource. Appropriate methodology for calculating the dose rate from a volume source is given-in TID-7004, " Reactor Shielding resign- i Manual" (Ref. 11.17). The computer program ISOSHLD (Ref. 11.18, 11.19, 11.20) will normally ^
be utilized to perform this calculation.
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i-
APA-32-OlOO3 R iv . - 1
'4.2.3.2.2 Direct Radiation Dose from the Reactor The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC has been determined to be 7E-2 mrads/ calendar year, based on a point source of primary coolant N-16 in the-steam generators. This-source term was then projected onto the inside surface of the containment dome, taking credit for shielding provided by the containment dome and for distance attenuation.
No credit was allowed for shielding by other structures or components, .The number of gammas per second was generated and then converted to a dose rate at the given distance by use of ANSI /ANS-6.6.1, " Calculation and Measurement of Direct and Scattered Gamma Radiation from LWR Nuclear Power Plant 1979", which considers attenuation and buildup in air. The final value is based on one unit operating at 100% Power.
The distance was determined to be 367 meters, which is approximately the closest point of_the boundary of the Owner Controlled Area fence which
=is not obscurred by significant plant structures.
(Ref. 11.14.3.)
)' The maximum direct radiation dose from the Unit to a MEMBER OF THE PUBLIC due to activities-within'the SITE BOUNDARY is thus approximately 9E-3.mrads per_ year, assuming a maximum occupancy
-of-1100 hours per year.
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APA-23-01003-Rev. 1
, -41835. 5.0 RADIOLOGICAL ENVIRONMENTAL MONITORING 3535 41866' 5,1 REC Section 9.11.1.1 The radiological environmental monitorAng program shall be conducted as specified in Table 9.11-A.
5.2 Description of the Radiological Environmental 1
Monitoring Program -
'The Radiological Environmental Monitoring Program is intended to act as a background data base for preoperation and to supplement the radiological effluent release monitoring program during plant operation. Radiation exposure to the public from the various specific pathways ~and direct radiation can be adequately evaluated by this program. .
Some deviations'from the sampling frequency may ;
be necessary due to seasonal unavailability, '
hazardous conditions, or other legitimate bases.
Efforts are=made to obtain all required. samples within time frame outlines. Any deviation (s) in C sampling frequency or location is documented in ,
l the Annual Radiological Environmental Operating 1 Report.
The Environmental samples are collected and analyzed at the frequency outlined in Table 6.
. Reporting 11evels'and' lower limits of detection (LLD) are given in Tables-7 and 8.
l l
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1
APA-ZZ-OlOO3 Rev, - l' i :
/
Airborne, waterbore, and ingestion samples collected under the monitoring program are analyzed by an independent, third-party laboratory. This laboratory is required to participate in the Environmental Protection Agency's (EPA) Environmental Radioactivity Laboratory Intercomparison Studies (Crosscheck)
Program or an equivalent program. Participation includes all of the determinations (sample medium ;
- radionuclide combination) that at. offered by the EPA and.that are also included in the monitoring program.
5.3 Performance Testing of Environmental Thermoluminescence Dosimeters-Thermoluminescence De'tectors-(TLD's) used in the Environmental Monitoring Program are tested'for accuracy and precision to-demonstrate compliance with Regulatory Guide 4.13. (Ref. 11.16).
Energy dependence.is tested at several energios between 30 kev and-3MeV corresponding to-the approximate energies of the predominant Noble Gases (80,-160, 200 kev), Cs-137 (662 kev), Co-60
')
(1225 kev), and at least one energy less than 80 kev. Other testing is' performed relative 7to either Cs-137 or Co-60.
-)
t.
APA-ZZ-01003 Rev. 1 TAlllE 6
- ADIOt0GICAt ENVIRONMENTAL m MONITORING PROGRAM l
NUMfifR OT RTf'ptSENTATIVE SAMPLES. SAMPLING AND TYPE AMD TREQUENCY l t APGS!'4E PAlifWiY Or.ANALYSfS ANDfon SAMPIE AND SAMPLE LOCAiIONS COLLECTtON FRESUINC_Y 40 routine monitoring stations either At least once per 92 days Camma Dose
- 1. Di rect Radiatiort with two or more dosimeters or with one l instrument for meastering and recording dose rate continuously, placed as foilows- \
An inner ring of sixteen stations, one in each meteorological sector in the general area or ttie SITE HOUNDARY.
Station location Code Sector e,i t.c De3c r i p t ion O 's A O.3 Miles last or llwy O and CC _ Junction, Callaway 1.9 mi. @ 349' N flectric Coop. Utility Pole No. 18872 47 8 County Road 8:48, 0.9 Miles South or Ivy 0, Ca s taway 0.9 mi. # 17' NME Electric Coop. Ut3lity Pole No. 28151 48 C County Road br48, 1.5 Miles South or sfwy 0, Plant 0. r4 mi. @ 45' NE 5ecurity Area sign Post 05 D P ri ma ry Me teo ro l og i ca l Tower 1.3 mi. @ 78' ENE 49 E Courit y Road 448, Callaway Electric Coop Utility 1.7 mi. # 98' E Pole No. Or,959. Reform Wildtife Management Parking Area 52 F Light Pole Near East Plant Security Tence 0.4 mi . # 11fs* ESC 51 C tocated in tt.e "Y" or the abarwiored Ra i l road spur, 0.7 mi. @ 137' SE northwest or sludge lagoon 50 ff County ftoad 459, 3.3 Miles North or etwy 94, Caffaway 0.9 mi. # 163' SSE Liect ric Coop. Utility Pole No. 35086 07 J Cotenty Road 459, 2.6 Mi les North or tuy 9rs, Ca l laway 1.3 mi. @ 181' S Elcetric Coop. Utility role No. 35091 37 K County Road 459, 0,9 He les Scotti or Itwy CC, Ca t laway 0.7 mi. 4 202' SSV Electric Coop. Utility Pole Nc. 3*,'077 43 L County Road 459, 0.7 Miles South or INy CC, Callaway 0.5 mi. @ 230' SV Electric Coop Utility Pole No. 35073 bis I liighway CC, 1.0 Miles South of County Road 450, 1.7 mi. @ 257' WSW Callaway Electric Coop. Utility role No. 18769 06 N County ftoad F28, 1.2 Miles West or stwy CC, Callaway 3
2.0 ms. @ 277' W Electric Coop. Utility Pole No. 18609
\
.. .4 APA-ZZ-01003 Rev. 1 hetM 9 1ABL L6_{_QontipuedJ RADIOLOGICAL [NVIRONMENTAE MONI TORING l'ROGRAM Station Code Sector Site Description LocaJion 45 P County Road 428, 0.1 Miles West or ifwy CC, Callaway 1.0 mi. @ 290' WNW Llectric Coop. Utility Pale No. 18580 03 0 0.1 liiles West or liwy CC on Gravel Foad 0.8 Miles 1.3 mi. 0 306' NW South Hwy 0, Castaway Electric Coop. Utility Pole No. 18559 46 R Nortis-East side or ifwy CC and Cotenty Road br:6 1.5 mi e 333' NNW Intersection Callaway Electric Coop.
l Utility role No. 28242 An outer ring or sextcen stations, one in each meteorological sector in the 6-to 8-3.m ra neje t' rom the site.
36 A Cotenty Road 155. 0.8 M3les South or County Road 132, S.2 mi. O 7' fl Caffaway Electric Coop. Utility Pole No. 19137 21 0 Cotenty Road 155, 1.9 miles nortle or ifwy 0, Callaway 4.0 mi 4 23' NNE E lect ri- Coop. Uti l i ty Pole Ito. 19100 C Ifighway D, 0.4 Miles North or liwy M, Callaway 4.8 mi. p 47' NE 20 Electric Coop. Utility Pole No. 12830 ;
l 18 D liighway 0, 0.4 tiiles Soteth of Ifwy 0, Callaway 3.8 mi O 63' ENE E lect ric Coop. Utility Pole No. 12952 1
County Road 4053 O.3 Miles East or llwy D, Kin 9dom 4.0 mi. p 89' E !
17 E Telephone Company Pole No. 3X 12 I ts I South-fast Side of ttwy 9rs and liwy D trtersection 5.0 mi @ 121' ESE Callaway Electric Coop. Utility role No. Il97 3 G 11 C City of Portland, Callaway Electric Coop. Utility 4.8 mi. O 139' SE Pole No. 12112 10 il liighway 9fs, 1.8 Miles East of County Road is59 4.0 mi. 0 157' SSE Callaway Electric Coop. Utility Pole No. 12182 09 J Mnrth-West Side or ;lwy 9fs and County Road fs59 3.7 mi. # 183* S Jtenc t i on, Callaway Electric Coop. tit i l i ty Pole No. 067583 30 K West Side of County Road rais7 at the Junction 12.6 mi. O 208' SSW witis Cotenty Road is63, Kingdom Telephone Company Pole No. 2K1 42 L County Road is's 7, 2.6 Miles North ol~ Cotrnty Road 163, 8 Is.4 mi. # 233' SW Callaway Electric Coop. Utility Pole No. 06326 i
bra-ZZ-01003 Me, -
hv. 1 -
t.
lABLE 6 (ContinuedJ RADIOLOGICA LENVIRONMENTAL MONITORING PROGRAM
~ Station' i Code pee g - . Site Description. Location 32 ' M liigtrway W. 0.6 Miles West or Cotenty Road 4887, 5.84 mi.'O 251' WSW
' Ca l laway Cloct ric Coop. Utility Pole No. 27031 41 N fligway AD, 2.8 Miles East or ifwy C, Callaway Is.8 mi. Q 279' W Electric Coop. Ut3lity. Pole No. 18239 iso .P North-East Side or Cotenty Road 112 and Itwy 0 83. 2 m i , @ 29ta' WNW Jttnction Ca l laway Electric Coop. Utility Pole No. 06326 39 Q County. Road 112, 0.7 Miles East or County Road 111 5.83 mi. 6 315' NW Catlaway Electric Coop. Utility Pole No. 17516 38 R County Road 133, 1.5 Miles South or ftwy I;U 8.8 4 mi. G 337' NNW Catlaway EleIctric Coop. Utitity Pote No. 37708 8 Eight Stations to be placed in s;pecia l interest areas such as poptstation centers, nearlsy residences, scitoo l s, and in l' or 2 areas to serve as control
. stations.
33 N City of Itams Prairie, South-East of the Itwy C 7.83 ei. 0 273* W and Itwy AD Jeanction .
31 L C i t y o r f"o ka ne, Callaway Eicctric Coop. Utility 7.4 mi. Q 218' SW PoIe No. U6039 26 E lown or Americus, Cattaway Electric Coop. Utility 12.1 mi. 9 82' E Pole No. 11159 27 T- 10wn or Blurrton, Callaway Electric Cot & . Utility 9.",mi. @ 110' ESE Pole No. 11739 6 35 R City or Toledo, Caitaway Efectric Coop. Uti8ity 5.8 mi. @ 372' 4 NfN Pole No. 176S?
23 8 Ci ty o r Yuca ta n, Caffavay Electric Coop. Utility 6.8 mi. 6 16' NNE Poie No. 12670 11 C ' Ci ty 4.f' Portland, Ca l t away Electric Coop. Utility it . 8 m i . G 139' SE Pole No. 12112 20 C City or Readsviile, CaIlaway Etectric Coop. UtiIity '*.8 mi. O ra7' NE Pole No. 12830
'3ft P North-East Side or Itwy C and County Road 408 9. 7 m i . @ 293* W!N
.(P-Control) Junction
~ . - _ _ . - _ _ _ _._ .__________
AFA-Z2-01003-J Rev. 1 "s... 'W- 'Q.
TABLE 6 iContinued1' ItADIOLOGICAI. ENVIRONMENMt,._HONI TORING ' PitOGRAM Station
. Code Site Description
}cctor. Location Ol' Q l'ighway 7, 0.8 Miles East or Business 54,.Callaway 11.0 mi. 0 312' NW (Q-Control) Electric Coop. Ut3lity I' ole No; 2154fa
- 2. Airborne Radiciodine C5nistefi
'Radioindine and Sampics from'five locations' Continuous' operations or Analyze it least Pa rt icul a tes samplet wi tti sample once per 7 days co l lec t
- on a s requ i red for 6-131 ,
by dust loading, but at least.onte per 7 days.
Three samples from close to tite three SI TE 13OUNDAftY locatiens, l'a rticulate Sample;_
in. di f ferent' sectors, of the feigliest calculated annua l ave rage Analyze for gross g round level D/Q. beta radioactivity
> 2Fs hours following filter change. Perform gamma isotopic analysis' on those samples for which the gross beta activity is >10 times the yearly mean or control samples. Perform gamma isotopic analysis
- on compcsite samples .-
(by location) at least once per 92 days.
'A1 'O Prima ry Neteorological lower 1.3 mi. @ 78* ENE '
t A8 B-
~
County Road 4t:8, 1.0 Miles South or liwy 0 0.8 mi @ 2f4' NNE B3 A 0.3. Miles East or liwy 0 and ifwy CC Junction 1.9 mi @ 37:9' N one sample from the community witt, the highest D/Q. a A9 R Community or fterorm 1.7 mi. @ 338' NfW i
-i b
. . ,. y z u. L' -
.7 -
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.APA-ZZ-01003 Rev. 1
.%,. -V +p.
~
1 TABLE 6 fContinued)
RADIOLOGICALENVIRONMENTAL MONI TORING PROGRAM -
Station Code Sector Site Description ' Location One sample ' f rom a control location,' as -
l'or example 15-30. km distant and in the least prevalent wind direction.
A7 Q .. 11a C. rtley Ta rie 9.5 mi.'.@ 312' NW
~t.
- 3. Waterborne
- a. Su r face
- One sample. upstream Composite samplef Camma isotopic' analysis 8
- over a period of each sample.
or less than or Tritium analysis of equa* to.31 days, composite sample-i at least once per 92 days.
So l . 11 ' 88: reet upstream of discharge, north bank is.8 mi . 6 Ifsta' SE One sample downstream 502 G '1.1 miles downstream or discha rge,' north bank '5.2 mi. O 133' SE-
- b. Drinking.' One'sampfe of each.. Composi te -sample over - t-131 analysis on one to three or the 2-week period when each composite when nea rest water supplies 1-131 analysis is the dose calculated within 10 miles'downstrea, performed, monthly for the comstmption
- that could be affected by- composite othervice. of the water is i ts discharge. . greater than 1 mrem per year. Composite for gross beta
/One sample from a control- and gamma isotopic location. analysis conthly.
Composite for..
tritium analysis quarterly.
k ~
As the re a re no d ri nk i ng wa te r intakes within 10 miles devnstream of the discharge point, the drinking water pattway is currently not included as part or the Callaway Plant Radiological Environmental Moni toring Prngram. Shnuld future water intakes be constructed within 10 river miles downstream of the discharge point, then the program will be revised to include this
-pathway, f ( fle r. 11. 6. 6 )
- c. Sediment One sample f rom downstream - Semiannually Camma isotopic from area with existing or .
analysis (d)
ShoreIine _potentiaI recreationai vafue, semiannua!ly.
-C G ' 1.0 river mile downst ream or discharge, north bank 5.1 mi. @ 135' SE '
-l APA-ZZ-01003
- 'Rev..1 us %i. W Tohti f_Lcontin.idi
~ RAD I OL OCl CAL ENV I RONME N T Al. _!T*d i TOR I NG PROGRAM Station Code Sectoj Site Description' t.oca t ion -
ts . Ingestion
-a. Mith Samples fros milking animals Semimunthfy when Gamma isotopic 8 and 5 in titree loca t ion wi thin - anima ls are on t-131 analysis 5 km distance tiaving the .
pastesre, monthly at seminenthly vben highest dose potentiat9 Other times.
animals are on 4 i' there a re none, tfien one' pasttsre; inonthly at sample.From miIking animals ~ other ti nes, in eacts of' three areas between 5 to 8'km distant-where dnset. a re ca lcte l a ted to tie greater ttian 1 mrem per yea r _
i e Dtte to a lack of milk ' animals visich satisfy these regirements,' the milk pthvay is etstrently~
not incitaded as a pa r t ' o r the Ca l l away Plant Rad io log ica l Envir e ntal M itering P mg ram.
Should the Anntial Land (fse Censtrs identify the existence of milking ansmats in locat ions which sa t i s f"y these reqts i rements, then the p rog ram vi l t he' revised to incitude this pathway.
- b. fish One sample or .eacti Sample in season, or Camma isotopic commerciaffy and . semiannyla t ly if they analysis 8 on ,
recreatinnally important a re not . seasona l . N ibse portions. [
species in vicinity of' '
plant discharge area. ,
Station de -
. C_9 Sector LSite Desc h tion Loca_ tion l
C. G 1.0 river mile downstream or discharge, north bank 5.1 mi. @ 135' SE One sample of same species in a rea s not inrI(senced by piant discharge.
A 11 0.6 river miles 12pstream or discharge, north bank 4.9 mi. O 154' SSE i
i i
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APM ZE-01003 g
,.. M ""-
(ABLE 6 (Continued) .l RAD 1OLOG1 CAL ENV8RONMENi AL MOttiiORING PROGRAF 4..
Station CM ?
Sector ' Site Description o Location
- c. food Products One sample or'esch At t ime ' o r ha rves t (h) Gamma isotopic principat. class of analysis 8 on products f rom any a rea edible port ion.
that is irrigated hy-water in which I4 quid plant wastes have been
' discharged.
As there are no areas irrigated by water in which Iiquid plant vastes have been discharged w i th i n 50 r i ve r m i l es downs t ream o r the d i scha rge po i nt , this sample type is not currently included as part or.the Catlaway Plant Radiological Envi ronmenta l Monitoring f'rogram. Should futstre irrigation water intakes be constrtscted within 10 river miles downstream of the discha rge point, then the program will be revised to i1ctode'this sample type. (Rer. 11.7.ts and.11.T.3)
Samples or three Monthly vten ava l table Camma' isotopic 8 and dirrerent kinds or - t-131 analysis, broad lear vegata tion g rown nea res t each of two dirrerent orrsite locations or highest predicted annual average grnund-level D/Q ir milk saepling'is not performed.
Station Code Sec_fg Site' Description Location V6 R tiecker's Farn T.8 mi. e 3 %
- ft'sW V7 A Mechan's f arm 1.8 mi. @ 356' N One sample or each of Monthly when avaitable Gamma Isotopic 4 simi tar broad scar .. analysis.
Vegeta tion grown 15 to 30 km distant in the feast prevalent wind direction (if milk-sampling is not performed).
Staticn Code Sector Site Descrip3 ion Location v3 t. Beazley's f a rs 15.0 mi. @ 227' SW
+ A >
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- - , - r- %- .-- ,q -
9 7#
f APA-ZZ-01003 REv. 1
%r n w
TAP.tE 6 (continued)
TAflE fiOTATtON (a) Devia t ions a re permi t ted from the regtvired sampling schedule if speci Pens are unohta inable due to haya rdous conditions, seasonal uttava i l ab i l i ty, ma l func t iort of atttoma t ic saspp l itig equipment , anff e t tm hemarie r legitimate reasons.
to complete If spec i mens a re surtobta inah t e due to sampl i ng entsi pment ma f f unctAll i ons, eve ry ef fofrom deviations r t shathe l l sampling schedoel shalf corrective action prior to the crid of the next samp f irig period. is recognized that, at times, it tea y tre stocumentert in the Anntra l Radiological [nvironmental Ope ra t i ng Repor t . l' not be possible or practical to continue to obtain samples of' the media of choice at the most desi red loca tion or time. .en these instances, sui ta b l e a l te rtia t i ve med i a arwt locations may be chosen for the pa rt icu l a r pa tfuay in qtres t ion and appropriate sashst ittitions inade wi thin 30 days in the Radiologica l invironmental f4oni toring I'rogram.
Identify the cause of the uravailability of samples for that pathway and identify the new tocation(s) for obtainisig replacement samples in the next Semi-Annstal Radioactive Ef fiteent Release Report and aise inctode in the report a complete and legibic copy of' the ent i re ODCf4, including the revis?d figure (s) and table - *8ecting the new l oca t iovi( s ) .
(b)
One or mo re i n s t rtimen t s , sitch as a pressurized ion chamber, for measuring and recording dose rate cont inienus ty may be used in place of, or in addition to, integra t ing dosimete rs. f or the ptsrpose of this table, a tite r mo t on i nescen t. <*os i me te r (ItD) is considered to te one phosphor; two or trore phosphors in a packet are corisider ed as two or more dosis'teters. Film hadges shallTnot be used as dosimeters for measuring direct he neembe r o f d i rec t rad i a t i on son i to r i ng s ta t i ons may be radiation the 40 stations is not an absoltete number.e.g., at an ocean site, some sectors wiff be ove r wa te r so that reduced according to geog raphica l limitations; the number of efosimeters may he reduced accordingly. The frequency of analysis or readout for TLD systems Vilf depend upon tite 'cteristics of the specific system used and should be selected to obtain optimum dose irtf or ma t ion wi t! . mat fading.
If it is not p ra c t ica l to establish control (c) itre pterpose of' this sa:ftp l e is to obtain backgrosend information.
locations in accord 1nce with the distance and wind direction criteria, other sites that provide valid background data may be substititted.
(d) Camma isotopic analysis is defined as the i den t i f i ca t i on a nd quan t i f i ca t i on o f g amma-em i t t i ng radionuclides that may be attributab te to the efrtuents from the facility.
The (e) The " upstream" sampfe sitalt be taken at a distance tmyond significant influence of tie discharge.
" downstream" sample shall be taken in an a rea beyond, but near the mixing zone, (f) t ai this p rog ra m, constant volume sample aliquots are collected at short time i nterva i s ( e.g. , monthf y) .
(g) The dose shall De calculated for the mawimum organ and age group, us i ng the me t hodo l ogy a nd pa ramet e rs i n the ODCf4 If ha rves t occurs more than once a year, sampling shatt be perfor1sted during each discrete harvest. If harvest occters cont nuously, sampling shall tee monthly. Attention shatI be paid to including samples of tuberous and (h) root fnod products.
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. w 'w =a =
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< Ck Oe- O n =
g om .
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g C0 0 =
6e & w O Ca U U 6 .D O m M L hm M += 6. L L a <o- : o w e w !
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- = .
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- = 0. 3
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e= 2 C
- N e Q wQ 6 na L n 3w C L w
4 *
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- p. *=
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h d ,w
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- =
- Ch C C e mm *S 4 L 6 f D @ D ~ **
- N D =
I e
h =
' "e't .t s t 6 = 1 I e J' M 0 0 C C 4 == m e 't' L M e I ** E 6 Q Q L Q Q c 0 C l 8C N C 6
- ___5_______.____.________._ , .
l'
APA-ZZ-01003
.Rev. 1
,_ W "v i TABL{_3 MAXtMUM VALUES TOR THE LOWJR LIMITS OF DETECT 10MLLD_]",*,
I l
I Water Ai rborne Particulate : Tish . Milk food Product Sediment I l Analysis ' (pCi/1) or Cases (pt,i/m3) (pCi/kg), vet.. (pCi/3) (pCi/kg, wet) _ (pCi/Kg, dry) l I
Icross Beta 4 'l
.u t . I l-I ...11 - 3 I
2000 * -1 I .
'l I re-54 15 130 I l
I I Fe-59 .30 260 I I
- 1. co-58,60- **- i 130 I I
I I Z r- ta b-95 15 ** I I
I l l-131 1(d) .07, 1 60 I I
I l Cs-134 15 .05 130 15 60 150 I I
Cs-137 18 I I .06 150 18 80 180 l i I I na-La-140 15 ** 15** I f or sterface wa ter samples, a va lue of' 3000 pC3/ 8 i s tesed.
- Total activity, parent plus daughter activity.
t i
2 4
- fe 4 e
4 b
- ~ s'v~~. .-
APA-ZZ-01003 l Rev. 1
.i TABLE 8 (CONTINUED)
TABLE NOTATION .
(a) The LLD is defined for purposes of compliance with the Radioactive Effluent Controls as.the smallest concentration of radioactive muterial in a sample that will yield a net count, above system background, that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system (which may include radiochemical separation):
i LLD = 4.66 S b
1 E*V' 2.22 'Y
- exp (-lat)
Where:
LLD = The lower li'ait of detection as defined
)
?
above (as picoeurie.per unit mass or volume)
Sb.= The standard deviation of the background counting rate or of the counting rate of a
-blank sample as appropriate (as counts per minute).
E= The counting efficiency (as counts.per disintegration).
V =- 'The sample size-(in units of mass or y volume),
- 2.22-= The number of' disintegrations perLminute per picoeurie.
Y= The fractional radiochemical yield (when applicable).
L )
L L
i t _ _ -
APA-ZZ-01003 Rev. 1
- L= -The radioactive decay constant for~the >
particular radionuclide and, at = the; elapsed time between sample collection (or end of the smaple collection period) and time of counting (for environmental samples, not. plant effluent samples).
Typical values of E, V, Y and at shall be used in the calculations.
It should be recognized that the LLD is defined -
-as a-aj priori (before the fact) limit representing the capability of a measurement system and not as an a;posteriori (after the fact) limit for a particular measurement.
Analyses are performed in such a manner that the stated LLDs are achieved under routine conditions. Occassionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumsta aes.may render these LLDs_unachievable. In su h cases, the contributing factors shalt be identified and described in the Annual Radiological EnvironmentalLOperating Report.
~}
(b) 'This list does not mean that only these nuclides are to be considered. Other peaks that are identifiable, together with those Eof the=above nuclides, shall also be 3 analyzed-and reported in the Annual :
Radiological ~ Environmental-Operating =
Report. 4 E (c) Required i detection. capabilities for-thermoluminescent dosimeters used for environmental measurements shall be in-accordance with the recommendations of p Regulatory Guide 4.13, Revision 1, July -
I 1977 (Refer'to Section 5.3) .
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APA-ZZ-01003 l Rev. 1
) 6.0 DETERMINATION OF ANNUAL AVERAGE AND SHORT TERM R MOSFHERIC DISFERSION PARAMETERS 6.1 Atmospheric Dispersion Parameters The values presented in Table 9 and Table 10 were determined through the analysis of on-site meteorological data collected during the three year period of May 4, 1973 to May 5, 1975 and March 16, 1978 to March 16, 1979.
6.1.1 Long-Term Dispersion Estimates The variable trajectory plume segment atmospheric transport model MESODIF-II (NURE0/CR-0523) and the straight-line Gaussian dispersion model XOQD0Q (NUREG/CR2919) were used for determination of the long-term atmospheric dispersion parameters. A more detailed discussion of the methodology and data utilized to calculate these parameters can be f^und elsewhere (Ref. 11.6.12).
The Unit Vent and Radwaste Building Vent releases are at elevatio"o 66.5 meters and 20 meters above grade, respecti" ' y. Both release points are within the building wake of the structures on which they are located, and the Unit Vent is equipped with a rain cover which effectively eliminates the possibility of the exit velocity exceeding five times the horizontal wind speed.
All gaseous releases are thus concidered to be ground-level releases, and therefore no mixed mode or elevated release dispersion parameters were determined. (Ref. 11.5.2)
- 105 -
I
_ _ _ _ _. . .-. . . _ _ . _ _ . . _ _ _ _ _ _ _ _ _ _ . - . . - . _ . . . ~ _ _ . _ _ _ . . _ _ _ . _ . _ _ _ _ . _ . . -
APA-32-03003 Rev. I s
)
6.1.2 Determination of Lono-Term Dispersion Estimates for Special Receptor Locations Calculations utilizing the PUFF model were performed for 22 standard dictances to obtain the desired dispersion parameters. Dispersion parameters at the SITE BOUNDARY and at special receptor locations were estimated by. logarithmic interpolation according to (Ref. 11.6.13):
MeX (6.1) 3 (d)B dy Where
- B= In (X2 /X 1 )/In (d 2/d 3).
X,X2 3 = Atmospheric concentrations at distances d y and d , respectively, from the source 2
3 (in C1/m ).
The distances d 3
and d 2 were r. elected -such that d) <d<d2 '
6.1.3 - Short Term Dispersion Estimates Airborne releases are classified as short term if they are less than or equal to 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> during a calendar year and not more than'150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> in_any quarter. Short term dispersion estimates are determined by multiplying the appropriate long
! term dispersion estimate by a correction factor (Ref. 11.9.1 and 11.15.1):
Fa . (T,/T,)6 .(6.2)
L l 106 -
)
1 i
g
,e-- . , , e._my e-n..,.%,_ - - -
, , , . . ,--r.; g ,y , - , , + .#-
w -v %..-,-e.. g
APA-0Z-01003 l Ret 1 l
) Where:
Tg = The total number of hours of the short term release.
T, = The total number of hours in the data collection period from which the long term diffusion estimate was determined (Refer to Section 6.1).
Values of the slope factor (S), are presented in TABLE 11.
Short term diepersion estimates are applicable to short term releases which are not sufficiently random in both time of day and duration (e.g.,
the short term release periods are not dependent solely on atmospheric conditions or time of day) to be represented by the annual average dispersion conditions. (Ref. 11.8.11.)
6.1.3.1 The Determination of the Slope Factor (S).
The general approach employed by subroutine PURGE of XOQD00 (Ref. 11.15.1) was utili ed to produce
.J values of the slope of the (X/Q) curves (Slope Factor (S)) for both the Radwaste Building Vent and the Unit Vent, However, instead of using approximation procedures to produce the 15 precentile (X/Q) values, the 15 percentile (X/Q) value for each release and at each location was determined by ranking all the 1-hour (X/Q))
values for that release and at the location in descending order. The (X/Q)y value which corresponded to the 15 percentile of all the calculated (X/Q) values within a sector was extracted for use in the intermittent release (X/Q) calculation.
107 -
1 l
1
APA- Z-01003 Rev. 1
) The intermittent release (X/Q) curve was constructed using the calculated 1-hour 15 percentile (X/Q)3 and its corresponding annual average (X/Q),. A graphic representation, of how the computational procedure works is illustrated by rigure 4.8 of reference 11.15.1. The straight line connecting these points represents (X/Q)g values for intermittent releases, ranging in duration from one (1) hour to 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br />. The slope (S) of the curve is expressed as:
1 l
-log ( (X/0)3/(X/0),1 (6.3)
S=
log (Ta/T )
3 or
-(100-(X/0)3 - log (X/0),1= (6,4)
S=
log Ta - log T y
/
)' 6.2 Atmospheric Dispersien Parameters for Farming Areas Within 7he SITE BOUNDARY The dispersion parameters for farming areas within the SITE BOUNDARY are intended for a
~
narrow scope application: That of calculating the dose to the current tennant farmer from gaseous ;
effluents while he conducts-farming activities l within the SITE BOUNDARY.
l.
i s
l !
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)-
_ _ - _ . . . . . . _~ _ ~ , .. _ - _ , ,_- - . , . - _ - _ . _ , _ . _
- . .-. -..- .-. .-_.~.-.. -.- - .- - - - _- -.- - . - _ -
APA-0Z-01003 Rev. 1
) For the purpose of these calculations, it was assumed that all of the farmer's time, approximately 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> per year, is spent on croplands within the SITE BOUNDARY, and that his time is divided evenly over all of the croplands.
Fractional acreage / time - weighted dispersion parameters were calculated for each plot as <
described in reference 11.5.6. The weighted '
dispersion parameters for each plot were then summed (according to type) in order to produce a composite value of the dispersion parameters.
The dispersion parameters presented in Tablas 9 &
10 therefore represent the distributed activities '
of the farmer within the SITE BOUNDARY and his estimated occupancy period.
h i
- 109 -
l }
l l
APA-2Z-01003--
Rev. 1 w
j'_
TABEEJ 11191,(ST ANNUAL. AVERAGE ATMOSPHERIC DISPERSIOM l'ARAMETERS (s)
- RADWASTE UUt(_OING VENT DISTANCE- .
. . X/0 ' 'X/Q l- EOCAIION'Lbj SECTOR -[ME_i_ERS): X.LQ . Decayed /Undepleted . Decayed /Denteted DLQ l
j (sec/m3)- (sec/m3) (sec/m3) (m 2)
StTE HOUNDARY'- 'NW ?200 1.30-6' 1aE-6 1.1I-6 4.3E-9 4 Nearest Cow (c)' WSW 2172 5.7E 5.7E-7 4.9E-7 1.6E-9
- Nearest Coat (c) WSW 2172- -5.7E-7 5.7E-T 4.9E-7 1.6E-9 s.
Stearest Heat Animal (d) NNW. 286Fs 8.7E-T- .S.7E-7 7.2C-7 2.6E-9 G1carest Ventable (c) j' carden nNW . 286tt 3.7E-T 8. 7E- T - 7.2E-T 2.6E-9
^
f;carest Residersce(c) NW 2864 8.7E-7 8. 7E-7 7.2C-7 2.6E-9 i- Tarming Areas Witftin N/A ft/A 2.9E-7 2.9E-7 2.6E-7 1.IE-9
, site tunnedary (c)(c) 4
-(a) - Va ttees given a re from TSAR Tab te 2.3-874 i
(Is) . Data from 1988 Eand Use Census
.(c) values derived f rom FSAR 1abic 2.3-81 using the methodology presented in Eqtration (6. 8 )
( Ref'.' 11.5.6)
(d) Itve nearest meat animat is assumed to exist at the tocation or tke nearest resident.
,(c) These valtscs were derived for a narrow scope application. Extresee caution should be exercised wtven determining their suitability for use in other applications.
1 j Bevi lding Strape Pa rseeter (C) = 0.5 (Rer. 11.5.3 )
4 1.
Vertical fleight of It3 9 h est Adjecent Building (V) = 19.96 meters (Ref. 11.5.3) i-1 1
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i l :i i auI srb d nL . T sb aoa )A Tt na s fti C (t eT n . Ac i du s T
o S R es re T eA t v eb
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1 R t t t i ar r 1 ave r a
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APA-02-01003 Rev. 1
) TABLE 11 SHORT TERM DISPERSION PARAMETERS (a) (c)
Slope Factor (S)
Location (b) Sector Distance Unit Vent Radwaste (meters) Building Vent Site Boundary S 1300 .328 .320 Nearest Cow NW 5053 .263 .266 Nearest Goat NW 5053 263 .266 Nearest Meat NNW 2736 .262 .268 Animal Nearest Vegetable NNW 2865 264 .268 Garden Nearest Residence NNW 2865 .264 .268
+
1 (a) Reference 11.5.3 (b) Data from 1987 Land Use Census (c) Recirculation Factor = 1.0
- 112 -
I
APA-ZE-01003 I Rev. 1
%s.s7 m .
TABEE 12 ArrttCAff0M Of' AIMOSPHERIC DISPERSION ?ARAFETERS DIsrTRSIOM CONTROtt f MG CO N TR0t tlfv'.
00C?9 REFEFENCE I'ARAP"E Y ER AGE GROUF LOCAllOM DOSE PAfffWAY X/0, decayed /undepleted -- Site Boundary Noble Gas, tieta Air 3.5.2.1 F2.26 day hairfire)
X/Q, deca yed /emdep le ted -- Si te Botenda ry Moble Cas, Garuna Air 3.5.?.1 (2.26 day hatriffe}
Y/O. decayed /tedepleted -- Site notmda cy l Noble Gas, Total nody 3.4.1 & 3.5.1.1 (2.26 day hatriire) l l
X/Q. dec ayed/imdar t e ted - Si t e Ftoemda ry roobie Cas, skin 3.4.2 & 3.5.1.1 (2.26 day hairiife)
Ground P f arw= Degesition 3.5.2.2 D/Q -- Nea mst Residert 3.5.2.2 X/Q, decayed / depleted ChiId Nearest Resident inhalation
( 6 day !?a l f t i re )
D/Q* ChiId Nearest Resident Ve<te t a t. i nn 3.5.2.2 D/Q* ChiId Nearest Fesident MiIk 3.5.?.2 D/Q* Chiid f4ea res t Fesident ficat 3.5.2.2
- T o r 14- 3 a nd C- 1 fs, Y/Q, decayed / depleted is used instead of D/O (Reference 11.11.1).
-113-
- M
APA-20-01003 hev. 1 7.0 REPORTING REQUIREMENTS 7.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.
The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysir of trends of the results of the radiological er.vironmental surveillance activities for the report period, including a comparison with preoperational studies, with operational controls and with previous envaronmental surveillance reports, and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of Land Use Censuces required by Section 9.32.
j The Annual Radiological Environmental operating Reports shall include the results of analysis of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the Table and Figures in the ODOM, as well as summarized the tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data chall be submitted as soon as possible in a supplementary report.
- 114 -
1
APA ZZ 01003 !
Rev. 1 i
The reports shall also-include the following a !
summary description of the radiological ;
environmental monitoring program; at least two legible maps
- covering all sampling locations keyed to a table giving distances and directions ,
from the centerline of one reactor; the results of licensee participation in the Interlaboratory i Comparison Program and the corrective action i being taken if the specified program is not being performed as required by Section 9.13.1; reasons -'
for not conducting the Radiological Environmental Monitoring Program as required by Section 9.11.1 and discussion of all deviations from the sampling schedule of Table 9.11-A, discussion of :
T environmental' sample measurements that exceed the -i reporting levels of Table 9.11-B, but are not the ;
result of the plant effluents, pursuant to a Section 9.11.1; and discussion of-all analyses in l which the LLD required by Table 9.11-C was-not ,
achievable.
1
- I L
r
.* One mapfohall: cover stations near the SITE BOUNDARY;fa second
. shall11nclude the more distant stations.
-115-
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ATA-02 01003 Rev. "
)
7.2 SEMI A!1t?UAL RADIOACTIVE EFFLUE!!T RELEME REPORT Routine Semiannual Radioactive Effluent Release Reports covering the operation of the unit during the previous 6 months of eperation shall be submitted within 60 daye after January 1 and July 1 of each year. The period of the firct report shall begin with the date of initial criticality.
The Semiannual Radioactive Effluent Release Reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and keleases of Radioactive Materials in Liquid and Gasecus Effluente from Light-Water-Cooled Nuclear Power Plante, " Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereof. For solid wastes, the format for Table 3 in Appendix B chall be supplemented with three additional categories:
clace of solid waste (as defined by 10 CFR Part 60), type of centainer (e.g., LSA, Type A, Type
, B, Large Quantity), and SOLIDIFICATION agent or
) absorbent (e.g., cement, urea formaldehyde).
-116-
AFA-22-01003 Rev. 1
)
The Semiannual Radioactive Effluent Release
' Report to be submitted within 60 days after January I of each year shall include an annual o summary of hourly meteorological data collected over the previous year. This annual summary may be either in the form of an hour-by-hour listing on magnetic tape of wind speed, wind direction, atmospheric stability, and precipitation (if measured), or in the form of joint frequency i distributions of wind speed, wind direction, and U atmospheric stability *, This same-report shall include an assestment of the radiation doses due to the radioactive liquid and gaseous effluents released from the unit or station during the previous calendar year. This same report shall also include an assessment of the radiation doses from radioactive liquid and gaseous effluents to MEMBERS OF THE FUBLIC due to their activities inside the SITE BOUNDARY (Technical Specifications, Figures 5.1-3 and 5.1-4) during 4
the report period using-historical average 3
atmospheric conditions. All assumptions used in making these assessments, i.e.,. specific activity, exposure time and location, shall be included in these reports. The meteorological
-} conditions concurrent with the time of release of
..- radioactive materials in gaseous effluents, as determined by sampling frequency and measurement, L
- shall be used-for determining the. gaseous pathway doses. The assessment of radiation doses shall
- be performed in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
1 l
In lieu of submission with the Semiannual Radioactive Effluent Release Report, Union Electric has the option of retaining this summary of required meteorologica1Jdata on site in.a_ file that-shall be provided "
to the NRC-upon-request.
-117-j.
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APA-ZZ-OlOO3 Rev. 1
} The Semiannual Radioactive Effluent Release Report to be submitted within 60 days after January 1 of each year shall alr.o include an assessment of radiation doses to the likely most exposed MEMBER OF THE PUBLIC from Reactor releases and other nearby uranium fuel cycle sources, including doses from primary effluent pathways and direct radiation, for the previous calendar year to show conformance with 40 CFR Part 190, " Environmental Radiation Protection Standards for Nuclear Power operation."
Acceptable methods for calculating the dose contribution from liquid and gaseous effluents are given in Regulatory Guide 1.109, Rev. 1, October 1977.
The Semiannual Radioactive Effluent Release Reports shall include a list and description of unplanned releases from the site to UNRESTRICTED AREAS of radioactive materials in gaseous and liquid effluents made during the reporting period.
The Semiannual Radioactive Effluent Release Reports shall include any major changee made 4
) during the reporting period to any Liquid or Caseous Treatment Systems, pursuant to Section 10.1. It shall also include a listing of new locatione for dose calculations and/or environmental monitoring identified by the Land Use Census pursuant te Section 9.12.1.
The Semiannual Radioactive Effluent Release Reports shall also include the following information: An explanation as to why the inoperability of liqu;d or gaseous effluent monitoring instrumentation was not corrected within the time specified in Section 9.1.1 or 9.2.1, respectively; and description of the events leading to liquid holdup tanks or gas storage tanks exceeding the limits of Technical Specification 3.11.1.4 or 3.11.2.6, respectively.
-118-i
APA-20-01003 Rev. 1
)
L 2815 The Semiannual Radioactive Effluent Release Reports shall also include as a part of or submitted concurrent with, a complete and legible copy of all revisions of the ODOM that occurred during the reporting period pursuant to Specification 6.14.2.
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-119-l
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APA=tt-01003 Rev. 1
.) 0.0 IMPLEMENTAT!ON OF ODCM METHODOLOGY
!' The ODOM provides the mathematical relationships used to implement the Radioactive Effluent Controls.
For routine effluent release-and dose assessment, computer codes are utilized to implement the ODCM methodologies. These codes have been evaluated by a. qualified independent reviewer to ensure that they produce results consistent with the methodologies presented in the ODCM. (Ref.
11.5.4.)
l 1
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-120-I
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APA-00-01003 Rev. 1
) 9.0 RADICACTIVE ErrLUENT CONTROLS _(REC)
NOTE 1. The terms in this section that appear in CAPITALI2ED TYPE are defined in Technical Specifications.
- 2. All frequency notations are per Table 1.1 of Technical Specifications.
9.O.1 Compliance with the Controls contained in the succeeding Controls is required during the OPERATIONAL MODES or other conditions specified therein; except that upon failure to meet the Control, the associated ACT' requiremento shall be met.
9.0.2 Noncompliance with a Cor 11 exist when the rnquirements of the Con', astociated ACTION requirements are not met the specified time intervals. If the Co .. . is restored prior to expiration of the cpecified une intervals, completion of the ACTION requirements $s nc, required.
N 9.0.3 haen a Control is not met, exv b a provided in I the associated ACTION requirements, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ACTION enall be initiated to place the unit in a MODE in which the Control oes not apply by placing it, as applicable, '. n :
- a. At least HOT STANDBY within the next 6 hourc,
- b. At least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and
- c. At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Control. Exceptions to these requirements are stated in the individual Controls.
This Control is not applicable in MODE 5 or 6.
I
-121
- ._. _ ___. _ ..~._ - .._. _ ____. _ _ - ._ _._._ ._
AlA-ZZ-Divus kei. 1
?
) 9.0.4 Entry into an OPERATIONAL MODE or other specified -
condition shall not be made unless the conditions '
for the Control are met without reliance on provisions contained in the ACTION requirements.
This provision shall not prevent passage through or to OPERATIONAL MODES ais remaired to comply
' with ACTION requirements. Ex eptions to these -
requirements are stated in the individual '
2 Controls.
9,0.5 Operability of equipment included in Section 9.0 must be tracked in the Equipment Out-of-Service !
Log (EOSL) as per ODP-ZZ-00002, Equipment Status :
Control, P
-?
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1 APA-22-01003 :
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9.1 RADI_0ACT!YE LIQUID _ EFFLUENT MONITORINp INSTRUMENTATION ,
41838 9.1.1 Controls
- 9.1.3.1 The radioactive liquid effluent monitoring
_ instrumentation channels shown in Table 9.1-A shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 9.3.1.1 are not exceeded. The Alarm / Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the OFFSITE DOSE CALCULATION MANUAL (ODCM).
APPLICABILITY: At all times. >
ACTIONi
- a. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above control, immediately suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel incperable.- '
- b. With less than the minimum number of radissetive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shv.n in Table 9.1-A. Restore the inoperable instrumentation to OPERABLE :
. status within the time specified in the r ACTION, or explain in the next Semiannual Radioactive Effluent Release Report, pursuant to Section 7.2, why this anoperability was not corrected-within the time specified.
- c. The provisions of Sections 9.0.3 and 9.0.4
' are not applicable.
L - 41839 9.1.2 Surveillance Requirements =
9 1.2.1 Each radioactive liquid effluent monitoring-instrumentation. channel shall be demonstrated OPERABLE by;the performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG '
CHANNEL OPERATIONAL TEST at the frequencies shown in Table 9.1-B.
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41840 9.1.3 Bases 9.1.3.1 Radioactive Liquid Effluent Monitoring ;
Instrumentation l
- The radioactive liquid effluent instrumentation
-is provided to monitor and control, as applicable, the releases of radioactive materials ,
in liquid effluents during actual or potential releases of liquid effluents. The Alarm / Trip Setpoints for these instruments shall be calculated and adjusted in accordance with the methodology and parameters in the ODOM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation le consistent with the requirements of General Design Criteril 60, 63, and 64 of Appendix A to 10 CFR Part 50, i
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- : r Table _9.1-A (Continueql '
ACTION STATEMENTS ACTION 31 - With the number of channels OPERABLE less'than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway i may continue for up to 14 days provided that
= prior to initiating a releases
- a. At least two independent samples are analyzed ,
in accordance with Section 9.3,2.1, and
- b. At least two technically qualified mesnbers of the facility staff Andependently verify the.
release rate calculations and discharge line "
valving, t
otherwise, suspend release of radioactive 1
- effluenta via this pathw'ay.
ACTION 32 - With the number of channels OPERABLE Lese than required by the Minimum Channels OPERABLE ;
requirement, effluent releases via this_ pathway j
may continue for up to 30 days provided grab samples are analyzed for principal gamma emitters ,
and I-332 at a lower limit of detection as specified in Table 9,3-A:
- a. At least once,per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the epecific
-metivity of the secondary coolant.is greater. -1 than 0.01 lat-crocurin/ gram DOSE EQUIVALENT
~1-131, or )
b.-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 specifie ;
activity of the secondary coolant isL less than -
or equal to 0.02 microcurie / gram DOSE
- EQUIVALENT.I-151.-
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APA-02-01003 hev. 1
) Dble 9,j-A (Contiyaed) i ACTItM STATEMElpis ACTIO!4 33 - With the number of channelb OFERABLE Less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may contirne for up to 30 days provided that prior to initiating a release
- a. At least two independent samplos are ana ' yr.ed in accordance with Section 9.3.2.1, and
- b. At least two technically qualif.ied membe 1 of the f acility r,tMf independently verify the release rate caiculations and discharge line valving.
Otherwise, suspend releaca of radicartive effluente vis this pathway. -
1 ACTION 34 - With the number of cht.nnels OPERABLE less than -
required by the Minimum Channels OPERABLE requirement, effluent rblesses via this pathway j
may contin'.ne for up to 30 days providec! the flow rate is estAmated et least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases. 'tump performance curves generrated in plat e may be used to estimate flow.
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TABLE 9.1 B (Continuedl TABLE NOTATIONS 41841 (1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or b, circuit failure (alarm only), or
- c. Instrument indicates a downscale fai)are (alarm only), or d, Instrument controls not set in operate mode (alarm only).
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) standards certified by the
) National Bureau of Standards (NBS) or using standards that have been obtained from suppliere that participate in measurement assurance activities with NES. These standards shall permit calibrating the system over its intended range of energy, measurement range, and establish monitor response to a solid calibration source.
For subsequent CHANNEL CALIBRATION, NBS traceable standard (gas, liquid, or solid) may be used; or a gas, liquid, or solio source that has been calibrated by relating it to equipment that was previously (within 30 days) calibrated by the same geometry and type of source standard traceable to NBS, (3) CHANNEL CHECK shall consist of verifying indication of flow during periods of release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> on days on which continuous, periodic, or batch releases are made.
-129-l
APA-ZZ-01003 Rev. 1
. 1 l'
9.2 RADIOACTIVE GASEOUS EFFLU2NT MONITORING INSTRUMENTATION 41872 9.2.1 Controls 9.2.1.1 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 9.2-A shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Section 9.6.1.1 and Technical Specification 3.11.2.5 are not exceeded. The Alarm / Trip Setpoints of these channels meeting Section 9.6.1.1 shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.
APPLICABILITY: As shown in Table 9.2-A.
ACTION:
- a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the-affected channel, or declare the channel
} Anoperable.
- b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 9.2-A. Restore the inoperable instrumentation to OPERABLE status ;
within the time apecified in the' ACTION,_or
- expitin in the next Semiannual Radioactive-Effluent Release Report, pursuant to Technical Specification 6.9.1.7, why this inoperability-was not corrected within the-time specified.
- c. The provisions of Sections 9.O.3 and 9.O.4 are not applicable.
-41843 9.2.2 Surveillance Recuirements 9.2.2.1 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST at the freque!.cies shown in Table 9.2-B.
-130-l I
APA-ZZ-01003 Rev. I
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9.2.3 Bases 41844 9.2.3.1 Radioactive Gaseous Effluent Monitoring Instrumentation The radioactive gaseous offluent instrumentation it provided to monitor and centrol, as applicable, the releases of radioactive materla10 in gaseous effluents during actual or potential valeases of gaseous effluents. The Alarm / Trip 4etpoints for these instruments shall be calculateo and adjusted in accordance with the methodology and parameters in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR Part 50. The sensitivity of any noble gas activity monitor used to show compliance with the gaseous effluent release requirements of Section 9.7.1,1 shall be such that concentrations as low as 1 x 10 ' pC1/cc are measurable.
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APA-ZZ-OlOO3 Rev. 1 l
I ) TABLE 9.2-A (Continuedl l TABLE NOTATIONS At all times.
ACTION STATEMENTS ACTION 38 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the contents af the tank (s) may be released to the environment for up to 14 days provided that prior to initiating the release: ,
- a. At least two independent samples of the tank's contents are analyzed, and
- b. At least two technically qualified members of tne facility staff independently verify the release rate calculations and discharge valvo lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
I ACTION 39 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated based on fan status and operau.ng curves or .
actual measurements at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samplas 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 radioactivity within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l _ACTIO. 41 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE l requirement, PUROINO of radioactive effluents via j this pathway may continue for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With j both channels inoperable, immediately suspend PUROING of radioactive effluents via this pathway.
-133- '
APA-22-01003 Rev. 1
~
TABLE 9.2-A'(Continued)
TABLE NOTATIONS ACTION 43 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via the affected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 9.6-A.
ACTION 45 - Flow rate for this system shall be based on f an status and operating curves or actual measurements.
<-5 h
1 1
i
-134-
A PA-Z.Z-0100 3 Rey, i TABLE 9,f-B RADIOACTIVE GASEOUS EIFEUINT MONITORING INSTRUMENTATION SURV QLLANCE REQUIREMENTS ANALOG CilANNFL MODES FOR WillCll SOURCE CilANNIL OPERAiIOflAL SURVEILLANCE CliANNfL TEST IS RE MIRED I NSIlttifil til C1lECK CHECK CA(IBRATION I. tin i t Vent System Holste Gas Activity Monitor D M R(3) Q(2) a.
l'rovid irig Ala rm (GI-ItE-?1 )
k N.A. N.A. N.A.
- b. lodine Sampler W N.A. N.A. N.A.
- c. Pa rticola te Sampler N.A. N.A. R( is ) Q
- d. Tlow Rate D N.A. R Q
- e. Stimp l e r f l ow Ita te flon i to r
?. Containment Purge System
- a. Nob i c Ca s Ac t i v i ty Morr i to r -
Provid ing Ala rm arid Automatic
- termination of Release O P R(3) Q(1]
(CT-RE-22, CI-RE-33)
W N.A. N.A. M.A.
- b. todine Sampler W N.A. N.A. N.A.
- c. Particulate Sampler I
- f N.A. R(1s ) N.A.
- d. I low fla te N.A.
N.A. R N.A.
- c. Sampler i Iow Ra te Moni tor D
- 3. Radwaste Dtailding Vent System l
- a. Noble Gas Act ivi ty Moni tor - D, P M, P R(3) O(i) l Providing Alarm and Automatic Termina tion of Release (Gil-RL-lO)
- W N.A. N.A. N.A.
- h. t od i ne Sa mp l e r W N.A. N.A. N.A.
- c. Particula te Sampler N.A. R( 's ) N.A.
- d. Flow Rate fi . A.
N.A. R N.A.
- c. Sampler I low Rate f4oni tor D
-135-
APA-ZZ-01003 Rev. 1 1
-) TABLE 9.2-B (Continued)
TABLE NOTATIONS 41845
- At all times.
(1) The ANALOG CHANNEL OPERATIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur as appropriate if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm / Trip Setpoint (isolation and alarm), or
- b. Circuit failure (alarm only), or
- c. Instrument indicates a downscale failure (alarm only), or
- d. Instrument controls not set in operate mode (alarm only).
4 (2) The ANALOG CHANNEL OPERATIONAL TEST shall also l demonstrate that control room alarm annunciation occurs if any of the following conditions exists:
- a. Instrument indicates measured levels above the Alarm Setpoint, or
- b. Circuit failure, or
- c. Instrument indicates a downscale failure, or
- d. Instrument controls not set in operate mode.
-136-
. . . .-- ~ --- . -- - . .- ..
APA-ZZ-01003 Rev. -1 TABLE-9.2-B (Continued)
TABLE' NOTATIONS (3) The: initial CHANNEL CALIBRATION shall be performed using one or more of the reference (gas or liquid and solid) 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 NES. These standards shall-permit calibrating the system over its' intended ;
range of energy, measurement range,.and establish :
. monitor response to a solid calibration source.
For subsequent CHANNEL CALIBRATION, NBS traceable standard (gas, liquid, or solid) may be used; or a; gas, liquid, or solid source that has been--
calibrated by relating it to equipment that was previously (within 30 days) by the same geometry and type of source traceable to NBS.
(4) If flow rate is determined.by exhaust; fan status-and. fan performance curves, the following
. surveillance operations shall be performed at-
, least once per 18 months:
- -[ a. The specific vent flows by direct measurement, or-
- b. late differential pressure across the exhaust fan and vent flow established by the fan's
" flow- AP," curve , or
.c. The fan motor horsepower measured and vent-flow-established.by.the fan's
" flow-horsepower" curve.
l.
L g
-137-
APA-ZZ-01003 Rev. 1
) 2881 9.3 LIQUID EFFLUENTS CONCENTRATION 41846 9.3.1 Controls 4160 9.3.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (see Technical Specification's Figure 5.1-4) 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:
- a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the concentration to within the above limits, i
"j b. The provisions of Sections 9.O.3 and 9,0.4 are not applicable.
41847 9.3.2 Surveillance Requirements 2895 9.3.2.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table 9.3-A.
9.3.2.2 The results of the radioactivity analysis shall be used in accordance with the methodology and parameters in the ODOM to assure that the concentrations at the point of release are maintained within the limits of Section 9.3.1.1.
i
-138-l
APA-ZZ-01003 Rev. 1 9.3.3 Bases 9.3.3.1 This section is provided to ensure that the '
concentration of radioactive materials' released in liquid waste 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 assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within: (1) the Section II.A design objectives of Appendix I, 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 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 in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2.
9,3.3.2. The required detection capabili+1es for
.* radioactive materials in liquid saste samploc are I tabulated in terms of the lower limits of detection (LLDs). Detailed discussionuof the LLD,.and other detection limits can be found in HASL1 Procedures Manual, HASL-3OO (revised-annually), Currie, L. A., " Limits for Qualitative "r Detection. and Quantitative Determination -
Application to Radiochemistry", bnal _ Chem. 40, 586-93 (1968), and'Hartwell, J. K., " Detection Limits-for Radicanalytical Counting Techr.iques",
Atlantic Richfield Hanford Company Report ARM-SA-215 (June 1975),
i l -139-o i.
APA ZZ-01003 Rev. 1 TAkLE 9.3 A RAD 10 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGR_Ajj
~
l l l l l LOWER LIMIT l l l l MINIMUM l l OF DETECTION l l LIQUID RELEASE l SAMPLING l ANALYSIS l TYPE OF ACTIVITY l (LLD)(I) l l TYPE j FREQUENCY l FREQUENCY I ANALYSIS l (VCigl) l 1 l l 1 l l l 1. Batch Waste l P l P l l l l Release lEach Batch leach Batch l Principal Gamma l 5x10 l l Tanks ( ) l l l Emitters (3) l l l l l l l l l l l l I 131 1 1x10 l l a. Weste l l l l l l Monitor l l l l l l Tank l P 1 M l Dissolved and l 1x10' l l lone Batch /Ml lEntrained Gases I l l l l l(Gamma Emitters) l l l b, Secondary l l 1 l l l Liquid l l l l l l Waste l P l M l H-3 l 1x10' l l Monitor lEach Batch l Composite j l l l Tank l l l Gross Alpha l 1x10' I l l l I I l
, l c. Discharge l P l Q lSr-89, Sr-90 l 3x10'b l 8 l Monitor lEach Batch lCompositeb)l Fe-55 l 1x10 l l Tank l l I l l 1 l l l l l 2. Continuous l l W l Principal Gamma 1 5x10' l l Releases ($) IDaily(6) lCompcsite IEmitters( ) l l l l Grab Samplel l l l l l l l I-131 l 1x10 l l Steam l t i I l l Generator [ l l l l l Blowdown l M l M lDissc1ved and I 1x10' l l l Grab Sample l l Entrained Gases l l l l l l(Gamma Emitters) l l
\ l l I l l l l l M lH3 l 1x10' l l l Daily ) IComposite )l 1 _l l l Grab Samplel l Gross Alpha l 1x10' l l l l I l l l l lSr-89, Sr-90 -6 l Q l 5x10 g l Daily )
l l Composite )l l l l l Grab Samplel -6 lFe 55 l 1x10 l l ! l I l
- I t. 0 -
APA-ZZ-01003 Rev. ?
TABLE 9.3-A (Continued)
)
TABLE NOTATIONS (1) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separaticn:
LLD = 4.66 a b E*V* 2. 22 x 10'
- Y ' exp (-lot)
Where:
LLD = the "a priori" lower limit of detection (microcuries per unit mass of volume),
s the standard deviation of the background b
counting rate or of the counting rate of a
, blank sample as appropriate (counts per
- minute),
-)
E = the counting efficiency (counts per disintegration),
V = the sample si e (units of mass or volume),
2.22 x 10' = the number of disintegrations per minute per microcurie, Y = the fractional radiochemical yield, when applicable, 1 = the radioactive decay constant for the particular radionuclide (s 2), and at = the elapsed time between the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
)
-141-
APA-ZZ-01003 Rev. 1 i
TABLE 9.3-A (Continued) .
) TABLE NOTATIONS 41848 It should be recognized that the LLD is defined as a 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.
(2) 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 the ODCM to assure representative sampling.
(3) The principal gamma em.cters for which the LLD control applies include the following radionuclides: Mn-54, Fc-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144.
This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Seminannual Radioactive Effluent Release Report pursuant to Technical
)
Specification 6.9.1.7, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
(4) A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids released.
Prior to analysis, all samples taken for the composite shall be thoroughly mixed in order for the composite samples to be representative of the effluent release.
(5) A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g., from a volume of a system that has an input flow during the continuous release.
)
-142-
APA-ZZ-01003 Rev. 1 TABLE 9.3-A (Continued _)
I "AbLE NOTATIONS I
(6)- Samples shall be taken at the initiation of I
e f f '. v e n t f l % and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafte. While the release is c: curring. To be rerresentative of the liquid effluent, the sample vo'.ume shall be proportioned to the effluent stream discharge volume. T1 ratio of sample volume to effluent discharge volume shall be maintained constant for all samples taken for the composite sample.
)
I
-143-
APA-ZZ-01003 l Rev. 1 l
) 9.4 DOSE 41849- 9.4.1 Controls 4160 9.4.1.1 The dose or dose t;mmitmen* +o a MEMBER OF THE PUBLIC from radioactive mat ..als in liquid effluents released, from each unit, to UNRESTRICTED AREAS (see Technical Specification's Figure 5.1-4) shall be limited:
- a. During any calendar quarter to less than or equal to 1.5 mrems to the whole body and to less than or equal to 5 mrems to any organ, and
- b. During any caler 'ar year to less than or equal to 3 mrems to the whole body and to less than or equal to 10 mreme 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 identifies the cause(s) for exceeding the .'imit(s) and defines the corrective actient that have been taken to reduce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits. This Special Report shall also include: (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Clean Drinking Water Act.*
- b. The provisions of Sections 9.O.3 and 9.O.4 are not applicable.
- The requirements of ACTION a.(1) and (2) are applicable only if drinking water supply is taken from the receiving water body within J 3 miles of the plant discharge. In the case of river-sited plants this is 3 miles downstream only.
-144-
APA-ZZ-01003 l
Rev. 1 l
) 9.4.2 Surveillance Requirements 9.4.2.1 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
41850 9.4.3 Bases 9.4.3.1 This section is provided to implement the requirements of Sections II.A, III.A and IV.A of Appendix I, 10 CFR Part 50. The Limiting Condition for Operation implements the guides set forth in Section II.A of Appendix I. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents to UNRESTRICTED AREAS will be kept "as low as is reasonably achievable". Also, for 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 drinking water that are in excess of the requirements of 40 CFR part 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section III.A of Appendix I which specify that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due te the actual release rates of radi'oactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
Revision 1, October 1977 and Regulatory Guide 1.113, " Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I", April 1977.
)
-145- )
1
APA-ZZ-01003 Rev. 1 l
l
)
9.5 LIQUID RADWASTE TREATMENT SYSTEM 41851 9.5.1 Controls 4160 9.5.1.1 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, from each unic, to UNRESTRICTED AREAS (see Technical Specification's Figure 5.1-4) would exceed 0.06 mrem to the whole body or 0.2 mrom to any organ in a 31 day period.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive liquid waste being diccharged without treatment and in excess of the above limits and any portion of the Liquid Padwaste 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 includes the following information:
1
- 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 action (s) taken to prevent a recurrence,
- b. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41852 9.5.2 Surveillance Requirements 9.5.2.1 Doses due to liquid releases from each unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being fully utilized.
}
-146-
APA-ZZ-01003 Rev. 1
- )--
9.5.2.2 The installed Liquid'Radwaste Treatment System shall be considered OPERABLE by meeting Sections 9.3.1.1-and 9.4.1.1.
9.5.3 Bases 9.5.3 1 The OPERABILITY of the Liquid Radwaste Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the envir'onment.
The requirement that-the appropriate portions of this system be used when specified provides essurance that the releases of redsonctive materials in liquid effluents will be kept "as low as is reasonabley achievable". This sectd.on
' implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60-of Appendix A to 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 Radwacto: Treatment. System were specified as a suitable fraction of the dose design objectives set forth in Section.11.A of Appendix I, 10 CFR-Part 50,.for liquid effluents.-
-147-
. ..- . .. -- . . - - - - -.~ -- , -~.
-APA-32-01003 Rev. 1
^
)I 9.6 GASEOUS EFFLUENTS DOSE RATE
- 41853- 9.6.1 Controls-4160- 9 . 6 . l .1, The dore, rate due to-radioactive materials released in gaseous effluents from the site to areas. at and beyond the SITE BOUNDARY (see Technical Specification's Figure 5.1-3) shall be limited to the following
- a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than i or equal to 3000 mrems/yr to the skin, and i
- b. For Iodine-131 and 133, for tritium, and for all radionuclides in particulate form with
-half-lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
APPLICABILITY: At all times.
l ACTION:
)
- a. With the dose rate (s) exceeding the above !
limits, immediately restore the release rate to.within the above limit (s),
..[
- b. The provisions of Sectionn 9.0.3 and 9.0.4 are not. applicable.
418541 9.6.2 Surveillance Recuirements :
9.6.2.1 The dose rate due to noble gases-in gaseous effluents shall be determined to be-within the
.above, limits in accordance wi-th.the methodology L and parameters 'irr the LODCM.-
9.6.2.2 t The dose rate due to Iodine-131 and 133, tritium, and all, radionuclides:in particulate-form with half-lives-greater than 8 days in gaseous effluents shall be determined to be within the above-limits in accordance with the methodology L and-parameters in the ODCM by obtaining representative samples and performing analyses in-accordance with the sampling and analysis program g specified in-Table 9.6-A.
n l
F L
-148-
APA-ZZ-01003 Rev. 1
) 9.6.3 Bases 41855 9.6.3.1 This section 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 en 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 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 usually be sufficiently low to compensate for any increase in the atmospheric diffusion factor above that for the SITE BOUNDARY. Examples of calculations for such MEMBERS OF THE PUBLIC, with the appropriate occupancy factors, shall be given in the ODCM.
A The specified release rate limits restrict, at
'7 all tines, the corresponding gamma and beta dose rates above background to a MEMBER OF THE PUBLIC at or beyond SITE BOUNDARY to less than or equal to 500 mrems/ year to the whole body or to less than or equal to 3000 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 mrems/ year.
9.6 3.2 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.7 rLimits for Qualitative Detection and Quantitative Determination -
Application to Radiochemistry", Anal. Chem. 40, 586-93 (1968), and Hartwell, J. K., " Detection Limitt for Radioanalytical Counting Techniques",
Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
_b
-149-
- 1 v k' .Q APA-Z7-01003 Rev. i l T. AB_EJ,1,$f 3 RADIOACTIVE CASEOL,' ttASTE SAMPLING AND ANALYSIS PROGRAM
- l l l lHINIMUM i i
i t_ObrER t_ I M I I 03' I I SAMPl. I NG . lANALYStS' }- TYPE Of' l DETECTI0ft (LLD). (')l.
ICASEOUS RELEASE" TYPE 1 'l!PdquENCY if ftlQUENCY IACYtVITY ANALYSIS' I (IJCi/m t ) ll l El P. I P- l. . (2) l [
1 II. Waste Cas Decay- ,) Each tank .
l Tank 1 Grab Sample l Each Tank IPrincipal Camma Emitters i 1x10 l l-l
{ l-1 l P 1 P .
I i l
- I . I (3) I (3) I . . . (2) 1 -4 I
- 12. Containment ? urge leach PURCE Ifach PURCE- JPrincipal Camma Emitters I 1x10 I I ,
.(3)
. Icrab ! 1- 1 -
1 -6 I I or vent Isampt_e i H - lit-3 f oxidel i 1x10- 1 I I (3),(4) i
- 13. unit vent IM 1 (3) (2) 1 -4 1 i_M Irrincipat camma Emitters I 1x10- I I Icrab. Sample I (4) i -6 1 I ,
1 1 1M I!!-3Jox ide l i 1x10 I !
I I (5) I 1 (2) ( -8 I t i ts . Spent Itse l Building. I M 1 M ~ j Principal -Camma Emitters 1 1x10 l I Exhatest l Crab Sample I (5) l. l -6 l '
l l M l I 1 IH-3 foxidel- l 1xto i l 'l (2) 1 -4
- 15. Radwaste Building i M i irrincipal Gamma Emitters I 1x10 5
I I vent Icrab Sample M
- 1. - i i i 1
- 16. All fie l ea se . Types
- 1. . (6) (a) l (7) i 1 -12 1 Icontinuous I- V 18-131 J 1x10' I i as listed inI.,' I : lCha rcoa l l I . -10 I i
I 2., 3.. 4., and l l Sample 11-13J [ 1x10 I
- 5. above (6) (8) I I I (1) 1 (?! I -11 I i 'lContinuous ' i W IPrincipal Catmna faitters l I-I 1x10 l l Particulate ! I I I i Isample j i l i I (6) (8) i M i I -11 I I Icontinuous IComposite ! cross Alpha i 1x10 l 1 I c l Pa rt icu la te i ! i I i LSimp ie I 1 1 I i - (6) (8) i Q l 1 -11 i
1
! l Continuous IComposite Isr-89, Sr-90 l -1x10 .I I I Irarticulate i l 1 !
I I Isample I l ! -
I I
-150-i 6
h f , ._.. .,m._,. #- s +.
em .c- ---.,F + + -' W i = '~-9 *r * -- * ' ' " - ~ ' " " ' ' ' " - '*
APA-ZZ-01003-Rev. 1 TABLE 9.6-A (Continued) '
)
TABLE NOTATIONS (Continued)
-(1) The LLD is defined, for purposes of these controls, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" cignal.
For a particular measurement system, which may include radiochemical separation:
4,66 s LLD = b E
- V + 2. 22 x 10' + Y + exp (-lat)
Where:
LLD = the "a priori" lower limit of detection (microcuries per unit mass of volume),
sb = the standard deviation of the background counting rate or of the counting rate of a j
blank sample as appropriate (counts per minute),
E = the counting efficiency (counts per disintegration),
V = the sample sice (units of mass or volume),
2.22 x 10' = the number of disintegrations per minute per microcurie,
~
Y = the fractional radiochemical yield, when applicable, 1 = the radioactive decay constant for the particular-radionuclide'(s 3), and at = the elapsed time-between'the midpoint of sample collection and the time of counting (s).
Typical values of E, V, Y, and at should be used in the calculation.
l l l 1
-151-l
p APA-ZZ-01003-Rev. 1 TABLE 9.6-A (Continued)
I ~
TABLE NOTATIONS (Continued) 41857 It should be recognized that the LLD is defined as a.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.
'2)
, The principal gamma emitters for which the LLD specification applies include the following radionuclides:- Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 in noble gas releases and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, I-131, Cs-134, Cs-137, Ce-141, and Ce-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 Report pursuant to Section 7.2, in the format outlined in Regulatory Guide 1.21, Appendix B, Revision 1, June 1974.
i' (3) Sampling and analysis shall also be performed
/- following shutdown, startup, or a THERMAL POWER change exceeding 15% of RATED THERMAL POWER within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
(4) Tritium grab samples shall be taken and analysed 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.
.(5) . Tritium grab samples shall be taken and analyzed at least once per 71 days from the ventilation exhaust from the spent fuel pool area, whenever-
-spent fuel is in the spent fuel pool.: Grab:
samples need to be taken only when spent fuel is
- -in the_ spent fuel pool.
(6) The ratio of the sample' flow rate to.the sampled stream flow rate shall be known for the time I
period covered by each dose or dose rate calculation made in accordance with Sections 9.6.1.1, 9.7.1.1, and 9.8.1.1.
1
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APA-ZZ-01003 Rev. 1 TABLE 9.6-A (Continued 1-
-[ TABLE NOTATIONS (Continued)
(7) Samples 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.
For unit vent, sempiing 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 y following each shur.down, STARTUP or THERMAL POWER change exceeding 15% of RATED THERMAL POWER within a 1-hour period 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. -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 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 reactor coolant has not increased more than a factor of 3, and (2) the moble gat monitor shows that effluent activity
- has not increased more than a f actor of- 3.
(8) Continuous sampling of the spent fuel building exhaust.needs.to be-performed only when spent '
fuel is in the spent fuel pool.
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Rev. 1 I
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9.7 DOSE - l'OSLE GASES 41858 9.7~.1 Control _s
-4160 9.7.1.1 The atr dose due to noble gases released in -
gaseous effluents, from each unit, to aroap at and beyond tlp SITE BOUNDARY (see Technical Specification's Figut'e 5.1-3) shall be 1Amited to
+he following:
- a. During any caler.dar quarter: Less than or equal to 5 mrada for gamma radiation and lees than or equal to 10 mrada for beta radiation, and b, During any calendar year: Less than o* equal to 10 mrade for gamma radiation and less than or equal to 20 mrads for beta radi6 tion.
APPLICABILITY: At all timese ACTION:
a.'With the calculated air doce from radioactive noble gases in gasecus effluetne exceeding any
.l 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) fer exceeding the limit (s) and defines the corrective actions that have'been taken to reduce the releaees and the proposed L
corrective actions to be taken to assure that subsequent releases will be in compliance with l~ the.above limits,
- b. The provisiens of Sections 9.0.3 and 9.0.4 are not applicable.
L L 41859 9.7.2 Surveillance Recuiremente-9.7.2.1 Cumulative dose contributions for the current calendar quarter and curront calendar year for noble gases shall be determined in accordance with the methodology and parameters in the ODCM at least once por 31 days.
]
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n APA-ZZ-01003 Rev. 1 i 9.7.3- Bases 9.7-.3.1 Thid=section is provided to implement th e -
requirements of Sections II .B, III.*., and IV.A cf Appendix I, 10 CFR Part 50. Tha L2miting Conditions for Operation implements t bs guides-set forth in Section II.B of Appendix 1. The >
ACTION statements provide the required operating floaibility and at the same time implenunt the guideo set forth in Suction IV.A of Appendix I to assure that the releanes of radioactive material in gaseous effluents to UNREST 3ICTED AREAS will be kept "as low as in reasonably achievable".
1he Surveillance Requi.?cmente imp}ement the requirements in Section III.h of Appendix I that conformance with the guides of Appendix I be shown Oy calculation 41 procedures based on models D
and. data such that the actual exposure of a L NEMBER OF THE PUBLIC through appropriate pacl vays is unlikely to be substantially uaderestimated.
The dose calculatt.on meth>delogy .nd parameters established in the ODCM .fe r calculating .the deset due to the actual release raten of radioactive noble gaoes in gaseous effluents are consistent with the methodology provided in Reguintory
}
Guide 1.101, C siculation of Annual Doses to Man from Routine Keieases of Reactor Effluents for the Purpose ,of . Evaluating Compliance wi .h 10 CFR Part 50, Appendix.I", Revision 1, October 1977 and Regulator) Guide 1.111, " Methods for Estinating Atmoepheric Transport and Dispernion of-: Gaseous Effluents.in Routine-Releases from Light-Water Cooled Reactors", Revision 1, July 1977. The-0DCM equations provided for .
determining the' air doses.at and beyond the SITE D BOUNDARY;are based upon tho historical average "
atmospheric conditions.
l.
i
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APA-ZZ-01003 Rev. 1
) 0.8 DOSE IODINE-131 AND 133, TRITIUM, AND RADIOACTIVE MATERIAL IN PARTICULATE FORM 41860 9.8.1 C,introls 4160 9.6.1.1 The done to a MEMBER OF THE PUBLIC from Iodine-131 and 133, tritium, and all radionuelides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SPlE BOUNDARY (see Technical Specification's Figure 5.1-3) shall be limited to the fol]owing:
- a. During any calendar quarter- Las* O sn br
, equal to 7. 5 mre3 e to any Sr.,an, anu i
- b. During any calendur year: Less than or equa]
to 15 mrems to any organ.
APPLICABIBITY: /t 0,'l timer..
If ] 2N: I
- a. . ::s : h tho calculated dose from the release of ladine 'il and > G, tritjum, anG radionuclid*~
j in particu_ ate Iorm with ialf-lives gret,tt.-
than 0 days, in gaseous effluents exceeding ,
any of the above limits, prepare snd submit to the Commission within 30 days, pursuant to Technic al Specifict. tion 6. 9.2, a 'Special Report that idantifies the cause(s) for exceeding the limits and defines the corrective actions that have been taken to recluce the releases and the proposed corrective actions to be taken to assure that subsequent releases will be in compliance with the above limits.
b, The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41861 9.6.2 Su/veillance Recuirements ,
9.6,2.'l Cumulative dose contributions for the current calendar quarter and current calendar year for Iodine-131 and 133, tritium, and radionuclides in particulate form with half-lives greater than 0 days shall be determined in accordance with the methodology and parameters in the ODCM at least once per 31 days.
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APA-E"-01003 Rev. 1
)
9.8.3 Base e 9.8.3.1 This section is provided to implement the requirements of Sections II.C, III.A, and IV.A of Appendix I, 10 CFR Fa:t 50. The Limiting Conditions for Operation are the guides set forth in Section II.C of Appendix I. The ACTION statements provide the required operating flexibaAity and at the same time implement the guides cet forth in Section IV.A of Appendix I to assure that the releases of radioactive mater.a1 in gaseous effluents to UNRESTRICTED AREAS will be kept "ac low as is reasonably achievable .
The Surveillance Requiroments implement in Section III.A of Appendix I that conformsuce with the guides of Appendix I be shown by celculational procedures based on models and data such that the actual exposure of a MEMBER OF THE PUBLIC threugh appropriate pathways is unlikely to be substanticily underestimated. The doce calculation methodology and parameters established in the ODOM 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 bones to Man 110m Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", Revision 1, October A977 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 also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for Iodine-131 and 133, t ri tium , and radionucl. es 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 dSvelopment of these calculations weret (1) is.dividual inhalation of airborne radionuclides, (2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, (3) desposition of radionuclides onto grassy hreas where milk animals and meat-producing animals grace with consumption of the milk and meat by man, and (4) deposition on the ground with subsequent exposure of man.
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APA-ZZ-01003 Rev. 1
) 9.9 GASEOUS RADWASTE_ TREATMENT SYSTEM 41862 9.9.1 Centrols 4160 9.9.1.1 The VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEM shall be OPERABLE and appropriate portions of these systems shall be used to reduce releases of radioactivity when the projected doser in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SITE BOUNDARY (see Figure Technical Specification's 5.1-3) would exceed
- a. .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.
APPLICABILITY: At all times.
ACTION:
- a. With radioactive gaseous waste being j discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days, pursuant to Technical Specification 6.".2, a special Report that includes the following information
/ 1. 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 action (s) taken to preveat a recurrence,
- b. The provisions of Sections 9.0.3 and 9.O.4 are not ecplicable.
)
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I APA-ZZ-01003 Rev. 1
)
9.9.2 q Eurveillance Recuirements 41863 9.9.2.1 Doces due to gaseous releases from each unit 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 the ODOM when Gaseous Radwaste Treatment Systems are not being fully utill:ed.
9.9.2.2 The installed VENTILATION EXHAUST TREATMENT SYSTEM and the WASTE GAS HOLDUP SYSTEMS shall be considered OPERABLE by meeting Sections 9.6.1.1 and 9.7.1.1 or 9.8.1.1.
9.9.3 Bases 9.9.3.1 The OFERAEILITY of the WASTE GAS HOLDUP SYSTEM and the VENTILATION EXHAUST TREATMENT SYSTEM ensures that the systems will be available for use whenever gaseous effluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used, when specified, provides reasonable assurance that the releases of radioactive materials in gaaeous effluents will l
be kept "as low as is reasonably achievable".
This control implemente the requiremente of 10 CFR Part 50.36a, G.vural 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 Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents.
l t
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!.PA-2Z-01003 Rev. 1
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9.10 TOTAL Dose 41864 9.10.1 Controls 9.10.1.1 The annual (calendar year) dose or dose commitment **> any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the whole body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.
APPLICABILITY: At all times, s
1
-leo-
APA ZZ-01003 Rev. 1 ACTION:
- a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Section 9.4.1.la., 9.4.1.Ib, 9.7.1.la., .
9.7.1.1b., 9.8.1.la., or 9.8.1.Ib.,
calculations should be made including direct radiation contributions from the units and from outside storage tanks to determine whether the above limits of Section 9.10.1.1 4
have been exceeded. If such is the case, >
prepare and' submit =to the Commission within 30 days, pursuant to Technical Specification 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 i includes the schedule for achieving conformance with the above limite. This Special Report, as defined in 10 CFR 20.40Sc, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct
-} radiation, for the calendar year that includes the release (s) covered by=this report. It '
shall also describe levels of radiation and concentrations of radioactive material involved,.and the cause of the exposure levels or concentrations. If the estimated dose (s) exceeds the'above limits, and if the release condition resulting in violation of 40-CFR
'Part 190 has not already been corrected, the Special Report shall include a request for a variance in accordance with the prov.isions 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.-
b.:The1 provisions of. Sections 9.0.3 and 9.0.4 are
-not applicalbe.
L
.i
- 161-
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l t, AFA-02-01003 Rev. 1 41865 .9.10.2 surveillance Recuirements -
9.10.2.1 Cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with Sections 9.4.2.1, 9.7.2.1 and 9.8.2.1, and in accordance with the methodology and parameters in the ODCM.
9.10.2.2 Cumulative dose contributicts from direct radiation from the units and from radwaste ctorage tanks shall be determined in accordance with the methodology and parameters in the ODCM.
This requirement is applicable only under ,
conditions set forth in ACTION a. of Section 9.10.1.1 s
1." ,
w
-162- _
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APA-ZZ-01003 Rev. I 1
)
9.10.3 Bases 9.10.3.1 This section 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 control requiren the preparation and submittal of a Special Report whenever the calculated doses due to releases of radioactivity and the radiation from uranium fuel cycle sources exceed 25 mrems to the whole 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 MEMELR OF THE PUBLIC will exceed the dose limits of 40 CFR Part 190 if the individual reactors remain within twice the dose design objectives of Appendix 1, and if direct radiation doses from the reactor units and from 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 te within the 40 CFR Part 190 limAts. For the purposes of the Special Report, it may be ascumed that the dose commitment to the MEMBER OF THE
) PUBLIC from other uranium fuel cycle sources da negligible, with the exception that dose contribution 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 conditions res'lting 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. 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 Sections 9.3.1.1 and 9.6.1.1. An individual ic not considered a MEMBER OF THE PUBLIC during any period in which he/she is engaged in carrying out any operation that is part of the nuclear fuel cycle.
I
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APA-ZZ-01003 Rev. 1
) 9.11 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 41866 9.11.1 Controls 9.11.1.1 The Radiological Environment Monitoring Program shall be conducted as specified in Table 9.11-A.
APPLICABILITY: At all times.
ACTION:
- a. With the Radiological Environmental Monitoring Program not being conducted as specified in Table 9.4-A, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Section 7.1, a description of the reasor.s f or not conducting the program as required and the plans for pre.'/enting a recurrence, h
-164-
APA-22-01003 Rev a i
b b. With the level of radioactivity as the result of plant effluents in an environmental sampling medium at a specified location i exceeding the reporting levels of Table 9.11-A 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 7HE PUBLIC is less than the calendar year ,
limits of Sections 9.4.1.1, 9.7.1.1, or-
- 9. 8.1.1. - When more than one of the radiocuelides in Table 9.11-B are-detected in t the sampling medium, this report chall be -i submitted ifi i
concentration (3) concentration (2) reporting level (1) . + reporting level (2) +
...? 1.0 When radienuclides other than those in Table'9.11-B are detected and are the result of plant effluents, this report.shall be i
) submitted if'the potential annual dose
- to A ,
/ MEMBER OF THE-PUBLIC from all radionuelides is '
4 equal to or greater than the calendar year limits of Sections 9.4.1.1, 9.7.1.1 or i
- 9. 8.1.1. . This report is not required if the measured level of radioactivity was not the result of plant effluente; however, in such an event, the condition'shall be reported and described in the Annual Radiological Environmental Operating Report, required by .
Section 7.1. !
1-3 L*The methodology and' parameters used to estimate the potential ~ annual j1 dose to aLMEMEER OF THE PUBLIC shall be indicated in this report.
-165-u c"
- l. _ - -
. _ . _ _ m__ m_._ _ _ . . _ .
1 APA-0"-01003 Rev. 1 l
l
)
- c. With milk or fresh leafy vegetable camples unavailable from one or more of the sample locations required by the Table 9.11-A, identify specific locations for obtaining replacement samples and add them within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. *
- The specific locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Technical Specification 6.14, submit as part of, or concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible copy of the entire ODCM, including the revised figure (s) and table reflecting the new location (s) with supporting information identifying the cause of the unavailability of camples and justifying the selection of new location (s) for obtaining samples.
- d. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
41867 9.11.2 surveillance Recuirements
}
9.11.2.1 The radiological environmental nonitoring samples shall be collected pursuant to Tacle 9.11-A from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 9.11-A and the detection capabilities required by Table 9.11-c.
9.11.3 Bases 9.11.3.1 The Radiological Enviornmental Monitoring Program required by this section provides representative measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposures of MEMBERS OF THE PUBLIC resulting from the station operation.
This monitoring program implementsSection IV.B.2 of Appendix I to 10 CFR Part 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and the
- Excluding short term or temporary unavailability.
-166-
APA-32-01003 Rev. 1 modeling of the environmental exposure pathways.
Guidance for this monitoring program is provided by the Radiological Assessment Branch Technical Position on Environmental Monitoring, Revision 1, November 1979. The initially specified monitoring program will be effective for at least the first 3 years of commercial operation.
L Folicwing this period, program changes may be it.itiated based en operational experience.
The requirca detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).
The LLDs' required by Table 9.11-C are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability of a -
~
measurement system and not as an a posteriori (after the fact) limit for a-particular measurement.
Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures
, Manual, H.ASL-300 (revised annually),
-J Currie, L. A., " Limits for Qualitative Detection and Quantitative Determination - Application to 'i Radiochemistry",' Anal. Chem, 40, 586-93 (1986),
and Eartwell, J. K., " Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975).
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W 'v APA-ZZ-Of003 Rev. 1 i
I TABLE 7.11-A[Contimsed) i W 80 TOG?CAtJfp*fRONMENTAE_ MOfttf0 RING IPOCRAM 4
tiffMBER Of ItfITESENI AT t VE EXIMtfRT PAfifwAY . SAMPt ES. Afs0 SAMrstNG AND . TYPE AND FRICUENCY
_. ANU/OM SAM _r.lk - SAMPt[ LOCAT OftS(')' COLLECf1 Oft tREQU( q Of AMALYSIS l ?. .Aieborne I
i Radioindine arod ' Samples from five locatioets; Contimeons sampler Radipiedina Cannistar:
, ' Pa rt icis t a tes operation with sample t-131 analysis weekty.
Ihree sampfes from c*ose to the at sect ion weekly, or tk M S9 IL DOUffDARY tocatiens, more frem mntty if
- j. in d (ferent sectors, of' the revoired by dtest Partietslate Sampler:
, highest ca tetstated armtral loading. Gross beta radios ctivity average ground levet-D/Q. anafysis fottowieg fi 9 ter chartge: ( * ) and 2 One sample frwe the vicinity g asm** isotapic r nalysis(S)
- 1. or a crmarmity havice the highest or covosita- (b
' _ ca lcul a ted ametra l average location) quarterty.
9rmmd ievei D/Q.
- one sampie From a centroI
! .. tocation, as for ewample 15 to
, '30 km (10 to 20 mite) distant a and in the seast prevalent vind i direction.(3) i j 3. Wa tert >o rne
- a. Surrace(6)' '
One sample upstream. Cocposite sample over cama isotopic anatysis(5)
, One sample downstreats. 1-anntit per3M(F). mo-eth l y. Composite for tritiers analysis of i composite sampIe (by locatice.) quarterly.
1 2
- b. Drinkirsg One sasipte of' cach of one to Crwaros i t e s.emple I-131 analysis cet each j three of' the nearest water over ?-weet period (7) c wposite when the dose
! steppt ies within 10 mi tes ~ when 8-131 .tretysis calculated for the coetsump-1 downstream that contd be is performmf, memthey tion of' the water is l' affected by its discharge. composite ot%fVise. greater than 1 mrate twr
! ye= r. ( * ) Campesite for gross beta and l One sample from a coritrnt gasera isotopic analyses (S)
).
j t oca tion. w=?nt h ly. Cov osite for tritiene anstysis quarterly.
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-169-l
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4 APA-II-01003
- s. Rev. 1 1
4 j- i T ABLE 9.11- A(_ Cont i moed_)
l RADIOt0G8 cat...IftYtRONMEf4TAL 790?4 TcnIttG rRoc*:AM i
- j. ItVMBER Of
. RT PRESE9E t AT IVE.
E XPOStJHf PAltfWAY SAMPt.[5 At3D SAMet.lftG AP:D TYt'E AftD FPECUE14CY
__^?jU/1MLT*AFTPt_L._ . SAMPtJ_, t_0_CAi 8 CftSt ' )
_ COtMCi8 Oft iftEQUEMCY OF AftAt.YSI5 j 3. Wa tertervie "( Cont intsed )
i l d. Sediment one sample from downstream Semianmaa l ty. Canta Isotepic analysis (5) trne s.rea with existing er potential semiannera l ty.
- shore t ine tinna4 vaive.
t 98 Innestion
- a. Milk. Szeptes from eithing animals Semiennthly when Cao'=tz lostoric(5) arwt 1-131 in three locations within animals are on analysis semiennthly when 5 km (3 mile) distatice.having pasture, innnthly animals are on pasttere; J the highest <1cse potentia 8 at etter t imes. monthly at othser times,
- j.
- tr-there are nnne, then, one j s. apple from milking animals in j- each of three areas between 5 j tn 3 km (3 to $ mile) distant i
1 where doses are-catentated to tm greater than 1 mrem per
{ yr. ( * ) .'
, One sample trne miikirig animals
! at a control location. 1$ to 3ft km ( 1:1 to ,O mile) distant and in the least prevalent wind l direction.
i i
- b. Tish One sample or eat;h commercially Sample in season, or Gaema isotopic analysis (S) aswf recreatinnai ty important semiarwmaI ty if' they en edible portions, i species in vicinity of" plant are er seasonal.
! discharge' area.
1
{ One sample or same species in j- areas not irertisented by plant o i scha rge.
- c. food one' sample or each prineipat At time or Cames isotopic anztysest5) 4 reinsucts c ass or rood pros. cts f rom ha rvest ( * )( " ) . on edible portion.
any area that is irrigated by water in which ligesid plant 3 wastes have beers discharged.
4 i
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APA-22-01003 l Rev. 1 l
l TABLE 9.31-A (Continued) R TABLE _ NOTATIONS j 41868 (1) Specific parameters of distance and direction sector from the centerline of one unit, and additional description where pertinent, shall be provided for each and every sample location in
- . Table 9.11-A in a table and figure (s) in the ODCM. Deviatione are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling 41 equipment, and other legitimate reasons. If specimens are unobtainable due to samp1'ng c 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 pursuant to Section 7.1. It is recognized that, .at times, it may not be possible or practicuble.to continue to obtain samples of the media of choice at'the most desired location or
... time. In these instances suitable specific
} -alternative media and locations may be chosen for the particular pathway in question and 4 appropriate substitutions made within 30 days in '
the Radiological Environmental Monitoring Program '
given in the ODCM. Pursuant to'-Technical .
Specification 6.14, submit as part of, or
' concurrent with,.the.next Semiannual Radioactive
-Effluent' Release Report a complete and legible '
copy of the entire ODCM including the revised figure (s) and table reflecting the new location (s) with supporting information ;
- identifying the cause of the unavailability of samples for that pathway and justifying the.
selection of the new location (s) for obtaining samplos.
I'
- I
-172-i I
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APA-ZZ-01003 :
Rev. 1 i
) TABLE 9.11-A (Continued)
TABLE NOTATIONS s
l (2) One or more instruments, such as a pressurized l
2 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. Film badges shall not be used as dosimeters for measuting direct radiation. The 40 stations is not an absolute number. The number of direct radiation monitorirg stations may be reduced according to geographit'l limitations; e . g. , at an ocean site, some sectors will be over water so that the L
number of dosimeters may be reduced accordingly.
, 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 optimum dose information with minimal f ading.
)- (3) 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.
(4)- Airborne: particulate sample filters 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 10 times the yearly mean oficontrol samples, gamma isotopic -
analysis shall be performed'on the individual .
samples.
. (5') Gamma. isotopic analysis means the identification and quantification of gamma-emitting . ,
radionuclides that may be attributable to the 1 effluents'from the facility.
(6)- Th6 " upstream sample" shall be taken at a
~ distance beyond-significant influence of the -
- discharge. The " downstream" sample shall be L taken in an area beyond but near the mixing zone.
-173-1 ygya we-w*- vu y- E43-m.:-weq+-y--W-4 pp'
APA-ZZ-01003 Rev. 1 TABLE 9.il-A (Continued)
.)
TABLE NOTATIONS (7) In this program compocite sample aliquets 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. -
(8) Groundwater 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.
(9) The dose shall be-calculated for the maximum organ and age group, using the methodology and parameters in the ODCM.
(10) If harvest. occurs more than once a year, sampling i 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 food products.
I 1.
-174-
. . _ . - . __ _ - . ~ _ . _ . . - . _ . . . _ _ _ . . _ _ _ _ . _ . . . . _ . . _ . _ _ . _ . . . . _ . _ ._ _ . . _ _ _ _
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APA-ZZ-01003
!.. Rev. 1 4
TA_ftLE 9.11-B i REPOR11MG LEE LS tor RAntoAcity:TV CONctNTRATIONS 174 ENVf ROM *tENTAL SAf4PLES REPORTenc ttvEts WATIR AIRHORNE PAft t tCtJI AIL i15H fit t K FOOD PitODUCIS i ANALYSIS (pCi/C) OR GASES (pCi/ mil (PCi/kg, vet) (pCi/1) (pC3/kg wet)
I 88- 3 70,000*
fin-$Ps 1,000 -
30,000 ie-$9. 400 10.000 4 Co-58 1,000 30,000 Co-(.0 300 10,000 7 r-f4tp-95 400**
8-131 2 0.9 3 100 Cs- t 3's 30 10 1,000 '60 1,000 Cs-137 50 20 2,000 70 2,001 na-ta-IPs0 200** 300**
f or drinkiry water samples. This is 40 CIR Part 141 value. For surf' ace water samples, a value
- of' 30,000 pci/1 may be usett.
Total activity, parent plus dastghter activi ty.
l 1
i -775-t 4
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APA-ZZ-01003 Rev. 1
) TABLE 9.11-C (Continuedl TAELE NOTATIONS 41669 (1) This list does not mean that only these nuclides are to be concidered. Other peaks that are identifiabic, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Repcrt pursuant to Section 7.1.
(2) Required detection capabilities for thermoluminescent dosimetern used for environmental measuremente shall be in accordance with the recommendations of Regulatory Guide 4.13, Revision 1, July 1977.
)
-177-
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . __ _ _ . _ _ . - -- -'m
APA-ZZ-01003 Rev. 1
) TABLE 9.11-C (Continued)
TABLE NOTATIONS (3) The LLD is defined, for purposs* of these controls, as the smallest concentration of radf oactive material in a sample thet will yield a net count, above system background, that will '
be detected with 95% probability with only 5%
probability of falsely concluding that a blank observation represents a "real" signal.
For a particular meacurement system, which may include radiochemical separction:
LLD = 4.66 s b E
- V
- 2. 22
- Y
- exp (-14t)
Where:
LLD = the "a priori" lower limit of detection (microcuries per unit mass or volume),
sb = the standard deviation of the background g counting rate or of the counting rate of a
- blank sampic as appropriate (counts per minute),
E = the counting efficiency (counts per disintegration),
V = the sample sico (units of mass or volume),
2.22 = the number of disintegrations per minute per picocurie,-
Y = the fractional radiochemical yield, when applicable, A = the radioactive decay constant for the particular radionuclide (s 3), and-At = the elapsed time between the sample collection, or end of the cample collection period, and the time of counting.(s).
Typical values of E, V, Y, and At should be used in the calculation.
]
-178-e + v - e m ,-- .wa- -n.. w w w- -~.,,--w+-- e--, , w- w
APA-Z"-01003 Rev. 1 4
)_.
)- TABLE 9.11-C (continued)
TABLE NOTATIONS It should be recogni:ed that the LLD is defined as a a___ priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.
Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine i conditions, occasionally background
~ fluctuations' unavoidable emn11 sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors shall be identified and .,
described in the Annual Radiological
- Environmental Operating Report pursuant to Section 7.1, (4)' LLD for drinking water samples. For surface water. samples, the LLD of gamma isotopic analysis may be used.
J i-I h
6 l;.
J l-I J:
^
-179-
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- n. . - . _ . . ._ _ _ _ _ . _ - - _ . _ . . . . _ , _ . ,c_,._.~._._.__.._____;____._._..,. - - _ -
APAo22-01003 Rev. 1
) 9.12 BAD 10 LOGICAL EINIRONMENTAL MONITORING LAND USE CENSUS 41870 9.12.1 Controls 9,12.1.1- A Land Use Ceneus 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 m' t-(500 ft8 ) producing broad leaf vegetation.
' 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 Section 9.8.2.1, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Section 7.2.
l_
i e
l '.
- Broad: leaf! vegetation campling of at.least-three different kinds of vegetation 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 9.11-A,-Part 4.c, shall be followed, including analysis-j of control samples.
-180-
, _ . . .- -. a . . .-_._;__,__.___,.._. __..._.u.- . .._ _., _ _ _ _ _ , _ ... _ . ... _ ~ _ _ .. - -
1
+
APA-22-01003 t Rev. 1 ;
t
) 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 Section 9.11.1.1, add the new '
location (s) within 30 days to the Radiological Environmental Monitoring Program given in the ODCM. 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 6.14, submit as part of, or
~
concurrent with, the next Semiannual Radioactive Effluent Release Report a complete and legible copy of the entire ODCM,-including the~ revised figure (s) and table (s) reflecting !
the new location (s) with information supporting the change in sampling locations.
- c. The provisions of Sections 9.0.3 and 9.0.4 are not applicable.
43871 9.12.2 Surveillance Recuirements 9.12.2.1 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 i results, such as by a door-to-door survey, aerial surv:y, 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 Section 7.1.
t
-181-L
_m - .. _. - . . _ __ _ _ _ _ __ _ . - __
APA-8Z-01003 Rev. 1 ,
.) 41872 9.12.3 Bases 9.12.3.1 This saction 1s provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are id6ntified and that modifications to -
the Radiological Environinental Monitoring Progrt.m given in the ODOM are made if required by the results of this census. Information that will provide the best recults, such as door-to-door i survey, aerial- survey, or consulting with lot:al-agricultur41 authorities, shall be used. Thte census satisfies the requirements of f Section IV.B.3 of Appendix ! to 10 CFR Part 50.
4 Restricting the census to gardens of greater thhn 50 m8 prcvides assurance tha'c significant exposure pathways via loafy vegetables will be identified and monitored since a garden of this size is the minimum required to' produce the-quantity-(26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a "
child. To deternsine this minimum garden size, the following assumptions were madei (1) 20% of the garden was used for growing broad leaf ,
vegetation (i.e., similar to lettuco and '
cabbage),'and (2)'a vegetation yield of 2 kg/m 8.
l e
d 9
-182-
-.-,:.-, .- -. -.. .... . .... -.. - -... .-.- .-.-. _ _.. -- _ _ --. _ . ..- .--..J
APA-ZZ-01003 Rev. 1
(
)
9.13 RADIOLOGIC,AL ENVIRONMENTAL MONITORING INTERLABohr. TORY COMPARISON' PROGRAM 41873 9.13.1 Conjrols 9 13.1.1 Ana.1 /ses shall be performed on radioactive materials supplied as part of cn In':erleboratory Condarisen Program that has been approved by the Com ission.
APPLICABILITY: At all times.
ACTION:
- a. With analyses not being performed as required above, report the corrective actions taken to o prevent a recurrence to the Commission in the i' Annual Radiological Environmental Operating Report pursuant to Section 7.1.
l
- b. The provisions of Sections 9.0.3 and 9.O.4 are r.c t applicable.
41874 9.1* 2 Surveillance Recuirements j
9.13.2.1 The Interlaboratory Comparison Program shall be described in this procedure. A summary of the results obtained as part of the above re- ired Interlaboratory Comparison Program shall included in the Annual Radiological Environmental Operating Report pursuant to Section 7.1, 9.13.3 Bases 9.13.3.1 The requirement for participation in an approved Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental san'ple 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.
i
-183-l 1
l
i b- >
APA-32-01003 '
- Rev. 1 i
i - .
10.0 ADMINISTRA_T H E CONTROLS 10.1 MAJOR CHANGES ?/O L]' QUID Ah10 GASEOUS RADWASTE TREATMENT j EffssI
'r 10.1.1 L;;6; nee-initinted major changes to the Radwaste Treatment Systems (liquid and gaseous):
- n. Shall be reported to the Commission in the Semiannual Radioact ive Ef fluent Releare Report j for the period in which the evaluation was 1 reviewed by the On-Site Review CommAttee I w" (ORC). The discussion of each change shall I contain: l
- 1) A cummary of the evaluation that led to the determination that the change could be made in accordance with 10 CTR 50.59)
- 2) Sufficient detailed information to totally i support the reason for the change without benefit of additional or supplemental r information; !
- 3) A_ detailed description.of the equipment,
} components and processes involved and the interfaces with other plant systems;
- 4) An evaluation of the change, which shows the predicted releases of radioactive materials in. liquid and gaseous effluents and/or quantity of_ solid waste-that differ
-from~those-previously predicted in the _
License application and amendments thereto; '
- 5) An evaluation of the change,.which shows the expected maximum exposures to a MEMBER OE THE'PUBLIC'in the UNRESTRICTED AREA and to the general population that differ from o thosefpreviously estimated in +he License
- . application and' amendments thereto;
- 6) A comparison of the predicted releases ofL radioactive materials, in liquid and gaseous. effluents and in solid waste,'to o .the actua11 releases-for the period prior-to when the changes are to be made; l
l
- Union Electric.co, may choose to submit the information called for ,
j j_ in this specifi' cation as part of the annual FSAR update.
-284-t
---m., -. . . _.m . . < _ - _ , . . _ . _ . , , . - - . . . . . . _ . . _ , _ - . . . . _ _ . . - . _ . _ , . - , _ _ . . _ _ ~ ._
APA-ZZ-01003 Rev. 1
)
- 7) An estimate of the exposure to plant operating personnel as a result of the change; and
- 8) Documentation of the fact that the change was reviewed and found acceptable by the ORC.
- b. Shall become effective upon review and approcal by the ORC &n in accordance with Technical Specification 6.5.3.1.
10.2 CHANGES TO THE OFPSITE DOSE CALCULATION MANUAL TODCM) 2815 10.2.1 All changes in the ODCM shall be completed pursuant to Technical Specification 6.14.2 and approved at per APA-ZZ-00101, Preparation, Review, Approval And Control Of Procedures.
2815 10.2.1.1 All changes shall be approved by the ORC PRIOR to implementation.
10.2.2 Cross Disciplinary Review for each revision of s the ODCM must include, as a minimum, Health i Physics, Quality Assurance, and Radiological Engineering.
3 2815 :e 2.3 A complete and legible copy of each revision of the'ODCM that became effective during the last semiannual period shall be submitted as a part of, or concurrent with that periods Semiannual i R.11oactive Effluent Release Report pursuant to Teshnical Specification 6.14.2.
h l
-185-
APA-ZZ-01003 Rev. 1
}
11.0 REFERENCES
11.1 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 20; U.S. Government Print _ng Office, Washington, D.C. 20402, 11.2 Title 10, " Energy", Chapter 1, Code of Federal Regulations, Part 50, Appendix I; U.S. Government Printing Office, Washington, D.C. 20402.
11.3 Title 40, " Protection of Environment", Chapter 1, Code of Federal Regulations, Part 190; U.S.
Government Printing Office, Washington, D.C.
20402, 11.4 U.S. Nuclear Regulatory Commission, " Technical Specifications Callaway Plant, Unit NO. 1",
NUREG-1058 (Rev. 1), October 1984.
11.4.1 Section 6.8.1 (2791) 11.4.2 Section 6.8.4f (41834) 11.5 Communications 1 11.5.1 Letter NEO-54, D.W. Capone to S.E. Miltenberger,
/ dated January 5, 1983; Union Electric Company correspondence.
11.5.2 Letter BLUE 1285, "Callaway Annual Average X/Q and D/Q Values", J. H. Smith (Bechtcl Power Corporation), to D. W. Capone (Union Electric Co.), dated February 27, 1984, 11.5.3 Letter BLUE 1232, "Callaway Annual Average X/Q Values and "S" Values", J. H. Smith (Bechtel Power Corporation) to D. W. Capone (Union Elecetric Co.), dated February 9, 1984.
11.5.4 Letter BLUE 1358, "Comparisen of Callaway Plant Offsite Dose Calculations for Routine Effluents",
J.H. Smith (Bechtel Power Corporation) to D.W.
Capone (Union Electric Company), dated March 22, 1984.
11.5.5 Private Communication, H.C. Lindeman & B.F.
Holderness, August 6, 1986 11.5.6 Calculation ZZ-67, " Annual Average Atmospheric Dispersion Parameters", April 1989. I l
-186-e
APA-ZZ-01003 Rev, 1
} 11.6 Union Electric Company Callaway Plant, Unit 1, Final Sniety Analysis Report.
11.6.1 Section 11.5.2.2.3.1 11.6.2 Section 11.5.2.2.3.4 11.6.3 Section 11.5.2.1.2 11.6.4 Section 11.5.2.2.3.2 11.6,5 Section 11.5.2.2.3.3 11.6.6 Section 11.2.3.3.4 11.6.7 Section 11.2.3.4.3 11.6.8 Section 11.5.2.3.3.1 11.6.9 Section 11.5.2.3.3.2 11.6.10 Section 11.5.2.3.2.3 11.6.11 Section 11.5.2.3.2.2 1 11,6.12 Section 2.3.5
)
11.6.13 Section 2.3.5.2.1.2 11.6.14 Section 9.2.6 11.6.15 Section 9.2.7.2.1 11.6.16 Section 6.3.2.2 11.6.17 Table 11.1-6 11.6.18 Table 9.4-6 11.6.19 Table 9.4-C 11.6.20 Table 9.4-11 11.6.21 Table 9.4-12 11.6.22 Table 2.3-68 J
-187-l l
_ _ _ ___ J
APA-22-01003 Rev. 1 e 11.7 Union Electric Company Callaway Plant Environmental Report, Operating License Stage.
11.7.1 Table 2.1-19 11.7.2 Section 2.1.2.3 11.7.3 Section 2.1.3.3.4 11.7.4 Section 5.2.4.1 11.7.5 Table 2.1-19 11.8 U.S. Nuclear Regulatory Commission, " Preparation of Radiological Effluent Technical Specification For Nuclear Power Plants", USNRC NUREG-0133, Washington, D.C. 20555, October 1978.
11.8.1 Pages AA-1 through AA-3 11.8.2 Section 5.3.1.3 11.8.3 Section 4.3
, 11.8.4 Section 5.3.1.5
~1 11.8.5 Secticn 5.1.1 11.8.6 Section 5.1.2 11.8.7 Section 5.2.1 11.8.8 Section 5.2.1.1 11.8.9 Section 5.3.1 11.8.10 Section 3.8 11.8.11 Section 3.3 11.9 U.S. Nuclear Regulatory Commission, "XOQD0Q, Program For the Meterological Evaluation Of l Routine Effluent Releases At Nuclear Power Stations", USNRC NUREG-0324, Washington, D.C.
20555.
11.9.1 Pages 19-20 Subroutine PURGE I
l 1
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APA-ZZ-01003 Rev. I e y 11.10 Regulatory Guide 1.111, " Methods For Estimating ;
Atmospheric Transport Ar.d Dispersion of Gaseous ;
Effluents In. Routine Releases From Light-Water- '
Cooled Reactors", Revision 1, U.S. Nuclear
~ Regulatory Commission, Washington, D.C. 20555, July, 1977.
11.10.1- Section c.1.b i
11.10.2- Figures 7 through 10 11.10.3L Section c.4 11.11 Regulatory Guide 1.109, " Calculation of Annual Doses to Man From Routine Releases Of Reactor Effluents For the Purpose Of Evaluating 1 Compliance With 10 CFR Part 50, Appendix I",
Revision 1, U.S. Nuclear Regulatory Commission, i Washington, D.C. 20555, October 1977.
11.11.1 Appendix C, ?ection 3.a-11.11.2 - Appendix E, Table E-15 11.11.3' Appendix C, Section 1 11.11.4 Appendix E, Table E-11 111.'11.5 _ Appendix E, Table E-9 11,12 U-S. Nuclear Regulatory. Commission, " Methods-for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard (40 CFR Part 190)", USNRC NUREG-0543, Washington, D.C._20555, January 1980.
- 11 12.1 Section I, Page 2 11.-12.2 Section IV, Page 8 #
11.12.3' Section'IV, Page 9 11.12.4 Section III, Page 6 l - 11.12.5 Section III, Page 8 l
)
-189-
=- r e ~ , - mv - r ----- + - - m-
APA-ZZ-01003-Rev. 1 i
,h 11.13 Management Agreement for the Public Use of Lands, Union Electric Company and the State of Missouri Department of Conservation, December 21, 1982.
11.13.1 Exhibit A 11.14 Miscellaneous-References 11.14.1 Drawing Number M-109-0007-06, Revision 5, 12.14.2 -Callaway Plant Annual Environmental Operating Report (updated annually).
11.14.3 UE Safety '.nalysis Calculation 87-001-00.
'11.14.4 Calculation 22-48, " Calculation of Inhalation and f
-Ingestion Dose Commitment Factors for the Adult i and Child", January, 1988.
11.14.5 HPCI 89-02,. " Calculation of ODCM Dose Commitment .,
Factors", March, 1989. '
11.14.6 HPCI 87-04, " Calculation of the Limiting Setpoint for the Containment Purge Exhaust Monitors, GT-RE-22 and GT-RE-33", March, 1987.
. 11.14.7' HPCI 88-10, " Methodology for Calculating the Response of Gross NaI(TR) Monitors to Liquid Effluent Streams", June, 1988. .
11.14.8 Calculation ZZ-57, " Dose Factors for Eu-154",
January, 1989.
11.15 U.S. Nuclear Regulatory Commission, "XOQDOQ:
~ Computer Program for the Meterological Evaluation of Routine Effluent Releases at Nuclear Power Stations", USNRC NUREG/CR-2929, September, 1982,
' Washington, D.C, 20555..
- 11.15.1 Section 4, " Subroutine PURGE", pages 27 and 28.
11.16 Regulatory Guide 4.13, " Performance, Testing, and I procedural specifications for Thermoluminiscence L_ Dosimetry: Environmental Applications i "(Revision 1),. July 1977; USNRC, Washington, D.C. 20555-11.17- TID-7004, " Reactor-Shielding Design Manual",
Rockwell, Theodore, ed; March 1956.
]
-190-
APA-ZZ-01003 Rev. 1 I .
I 11.18 BNWL-236, "ISOSHLD - A computqr code for General Purpose Isotope Shielding Analysis", Engel, R.C.,
Greenberg, J., Hendrichson, M.M.; June 1966, 11.19 BNWL-236, Supplement 1, "ISOSHLD-II: Code Revision to include calculation of Dose Rate from Shielded Bremsotrahlung Sources", Simmons, G.L.,
et al; March 1967, 11.20 BNWL-236, Supplement 2, "A Revised Photon Probability Library for use with ISOSHLD-III",
Mansius, C.A.; April 1969.
11.21 ANSI N13.10-1974, " Specification & Performance of on-Site Instrumentation for Continuously Monitoring Radioactivity in Effluents";
September, 1974, 11.22 Nuclear Regulatory Commission Generic Letter 89-01, " Guidance for the Implementation of Programmatic Controls for RETS in the Administrative Controls Section of Technical Specifications and the Relocation of Procedural Details of Current RETS to the Offsite Dose Calculation Manual or Process Control Program",
January 1989.
11.23 ODP-ZZ-00002, Equipment Status Control.
)
-191-
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