ML070780033
| ML070780033 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 01/24/2007 |
| From: | Babineau G Yankee Atomic Electric Co |
| To: | John Hickman, Youngblood T NRC/FSME |
| References | |
| OOL-08 | |
| Download: ML070780033 (97) | |
Text
LJohn Hickman-RE: Yankee Rowe FSSR OOL-08-03 Information Page-1 From:
"Greg Babineau" <Babineau@yankeerowe.com>
To:
<thy@nrc.gov>, <jbh@nrc.gov>
Date:
01/24/2007 8:56:15 AM
Subject:
RE: Yankee Rowe FSSR OOL-08-03 Information
- Tom, We scanned the two documents and burned them to a CD. They will be going out via fedex today, addressed to you and John. To avoid any confusion during your review, please note that when these documents were generated in 1998, they were in support of the LTP we were developing to implement a NUREG 5849 FSS. We terminated that project in the 1999 timeframe. Hence the documents refer to assumed GLV's, etc. However, the deposition evaluation and the background measurements performed and evaluated remain valid.
Greg
Original Message -----
From: Alice Carson 1967 @ comcast.net
Sent: Tuesday, January 23, 2007 1:17 PM To: 'Greg Babineau'
Subject:
FW: Yankee Rowe FSSR OOL-08-03 Information I'll call you in a few to discuss the request.
Original Message -----
From: Thomas Youngblood nrc.gov
Sent: Tuesday, January 23, 2007 12:00 PM To: Alice Carson Cc: John Hickman
Subject:
Yankee Rowe FSSR OOL-08-03 Information
- Alice, The final status survey report OOL-08-03 has a Technical Evaluation YA-EVAL-00-002-06 on Sr-90 identified in soil samples, and the evaluation refers to two additional documents that contain information on environmental Sr-90 levels.
Could you provide a copy of the referenced reports: YRC-1 178 and RP 98-72?
I have checked a CD with YNPS Historical Site Assessment, Master Reference List information, and the CD contains similar reports, but not these specific reports.
John Hickman is on sick leave today, but hopefully will be back at work soon.
- Regards, Tom Youngblood Health Physicist US NRC 301-415-5875
I~ohn Hickman - RE: Yankee Rowe FSSR OOL-08-03 Information Pa ge 2I CC:
"'Alice Carson' <acarson1967@comcast.net>
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RE: Yankee Rowe FSSR OOL-08-03 Information 01/24/2007 8:55:40 AM "Greg Babineau" <Babineau@yankeerowe.com>
Babineau@yankeerowe.com Recipients nrc.gov OWGWPOO4.HQGWDOO1 JBH (John Hickman) nrc.gov TWGWPO04.HQGWDOOI THY (Thomas Youngblood) comcast.net acarson1967 CC ('Alice Carson')
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MEMORANDUM To: File Date: June 22, 1998 From: Edward Cumming fF' File: RP 98-72
Subject:
Technical Basis Document for Background Sr-90 in Soil, Rev. 1 Reference
- 1. Memorandum RPG 98-011, Rev. 1, C.B. Martel to E.M. Heath, "Background Strontium-90 Concentration in Soil," dated June 18, 1998.
- 2. Memorandum RPG 98-011, C.B. Martel to E.M. Heath, "Background Strontium-90 Concentration in Soil," dated May 29, 1998.
- 3. Procedure AP-8800, Rev. 2, "Final Status Survey Organization, Training and Technical Basis Documents."
This memorandum, along with the attached DE&S memorandum (Reference 1), constitutes a Technical Basis Document (TBD) for background concentrations of Strontium-90 in soils surrounding the Yankee Nuclear Power Station. The attached DE&S memorandum is a revision to the original DE&S memorandum (Reference 2), and contains corrections to several typographical errors. Preparation and review have been done in accordance with the TBD requirements of Procedure AP-8800 (Reference 3).
cc: FSS TBD File RP File S.Roberts J.Thompson B.Yetter E.Heath G.Babineau K.Heider K.Corbett D.Trudeau S
MEMORANDUM DE&S - BOLTON O
To E. M. Heath Date June 18, 1998 Grolip #
RPG 98-011 Rev. 1 From C. B. Martel W.O.#
00468.00.0004.16.00000 Subject Background Strontium-90 Concentration in Soil I.M.S.#
A13.01.08 RT 07.C02.018 File #
SR90BACI.WPD Reference
- 1.
YRC-1180, "Background Concentrations of Cesium-137 in Soil and Sediment to Support YNPS," 2/98
- 2.
YRC-1 179, "Yankee Rowe Site-Specific Derived Concentration Guideline Values for Residual Radioactivity in Soil," 3/98
- 3.
YAEL Procedure 368, "Determination of Strontium-89, 90'in Environmental Media via Cerenkov Counting," Rev. 4, 7/7/97.
- 4.
YNPS License Termination Plan, Appendix A, "Final JStatus Survey Plan for Site Release," Rev. 1, 5/97
- 5.
NUREG-5849, "Manual for Conducting Radiological Surveys in Support of License Termination," USNRC, 3/92 Purpose and Backqround The purpose of this memo is to present a background concentration value for Strontium-90 in soils related to decormnissioning work at the Yankee Nuclear Power Station (YNPS). This value is specifically for use in support of the Final Status Survey at the YNPS. Like Cesium-137, Strontium-90 is a radionuclide that is present in background, and which was also produced and released to the environment by operations at YNPS. A background value for Cesium-137 is the subject of another report (Reference 1) entitled, "Background,:Concentrations in Soil and Sediment to Support the Yankee Nuclear Power Station Decommissioning Project."
The Strontium-90 value presented is calculated based on guidance in NUREG-5849 and is intended as input to help establish that radioactivity release lirnits are met for any residual radioactive materials remaining on-site after decommissioning.
This regulatory guidance establishes a method to determine values for the background level of a given radionuclide by averaging results of sample analyses and establishing with 95% certainty, that the calculated background level for a radionuclide is correct.
0
Heath, E.
June 18, 1998 Page 2 The number of samples required to provide a valid average value is determined by a statistical procedure. For a given number of samples collected, a mean radio'nuclide concentration value is valid if the 95% upper level bound of variations in individual analyses results are less than 10%
of the Guideline Value (GLV) used for Final Status Survey.
Methodolo 4
Soil samples that were analyzed for Strontium-90 were selected fromfi those previously collected and analyzed for Cesium-137, as described in Reference 1. The rationale for the location from which the soil samples were obtained, the method used to collect the! soil, and its preparation for analysis, is presented in Reference 1. Strontium analyses were peiformed on 30 soil samples selected from four background reference locations. Selection was~fmade to assure that samples were representative of each background area.
For Strontium analyses the process for soil sample preparation was different from that done for samples analyzed for Cesium-137. Aliquots of soil were taken from those samples which had been dried and homogenized by the Duke Engineering & Services Laboratory for the Cesium-137 analyses. The aliquots of soil were processed and an'alyzed accordifig to Reference 3. The 95%
upper level bound on the average concentration was calculated as described in Section 5.2.3 of Reference 4, using Equation 5-4.
Results and Conclusions Results of the analyse. are presented in the attached Table. 'The average Strontium-90 concentration for the 30 samples is 0.274 + 0.310 pCi/gm. The.GLV for Strontium-90 that will be applied to the Final Status Survey at YNPS is 5.7 pCi/gm (Reference 2). The 95% upper bound on the average concentration is 6.8% of the GLV, which is i'ss than the 10% prescribed by NUREG-5849 (Reference 5) for significance. Therefore, no further soil samples are required to further refine this value since the variations in background are not significant and need not be determined.
Prepared by: C. B. Martel Reviewed b umming evIewdi.* F,. X. Bellini
Heath, E.
June 18, 1998 Page 3 Attachment c:
J. Grant R. Marcello J. Jacobson P. Littlefield D. McCurdy W. Riethle E. Cumming F. Bellini E. Dayotas (EED/SC File)
Vt
N~)
Strontium-90 Concentration Sample No.
TS-01A TS-11A TS-12A TS-14A TS-15A TS-16A TS-20A TS-01 B TS-11B TS-12B TS-15B TS-16B TS-17B TS-18B TS-13B TS-20B TS-11C TS-16C TS-17C TS-14C TS-18C TS-12C TS-13C TS-20C TS-1D TS-1I D TS-13D TS-14D TS-15D TS-1 6D Ave SD 95% level upper bound in Background Solls at YNPS Sr-90 Concentration (pCi/gm) 0.235
-0.09
-0.018 0.31
-0.049 0.244 0.326
-0.18 0.069
-0.02
-0.146 0.188 0.684 0.23
-0.02
-0.002 0.624 0.072
-0.003 0.496 0.857 0.371 0.413 0.464 0.952 0.75 0.649 0.173 0.148 0.506 0.274 0.310 0.390
Main 17 Att. A 38 QA Record?
App. A 33 Total 88 Yes V No DUKE ENGINEERING & SERVICES ENVIRONMENTAL HEALTH & SAFETY TITLE Radionucli, PAGE I OF 88 PAGES NO N02.0-1. OA4/ N102,.O3.03 TYPE 07.C16.004/
00468.00. 01"4..17. 00000
.O./P.O.
NO.
- /CALCULATION FOR de Soil %Cor cit-tations Surroundinq, YNPS Gas~eous Release's cduring.Plant 'Operation PLANT Yankee Nuclear Power Station CALCULATION NUMBER YRC-1178 (Nonsa fetý'-Related).
PREPARED ý.BY.
DATE REVIEWED-By/
DATE.,
APPROVED :.BY/
- DATE REVIIEW 'LEVEL AsS,I GNED"
ýORIGINAL 4.tA~
REVISION 1 1
REVIS.I ON. 2 REVISION 3
.1 Level of Review Required:
1 = Review in Detail 2 - General Review for Reasonableness 3 = Review Not Required KEYWORDS Meteorology, Atmospheric Depos'iticin, Dose Assessment, AEOLUWS-ý2-,
Req Guide 1.109.-
-Computer Codes;: LOTUS 1-2-3, rev.5, Quattro Pro, v.6.0 y
ON a "
29'rk AIJ
'11, ReiOh::
YjA: EED-0 I Revi s~i.on-1:0 R12/32
YRC-l 178, REV. 0 Page 2 Table of Contents I Calculation :Objective...
3 II Method of Solution 4
III Inputs q -ud Assumptions...............................
5 IV Calculation and Analysis......
.6 A. Estimation of 1960-1971 Release Distribution 7
B. Decay Equation 7
C. Decay Calculation Application D. Application of Atmospheric Deposition Factor........
8 E. Soil Concentration.
. 9 V. Results and Conclusio ns..................10 VI. List of References.................
12 VII. List of Attachments 1,3.
VIII Review Sheet...............................
14 Appendix A., Spreadsheet Printouts..................
17
- 1. Selected N uclide Properties............................................
A-I
- 2. Gaseous Release Summary:& Soil Concentrations.
A-2
- 3. Estimated Annual:Undecayed Releasd-"1,960 through 1971.....................
A-3
- 4. Reported Annual Undeiyed Releases-4972:through 1992.
A-75
- 5. Estimated Annual Decayed Releases-l1960 through 1971...................
A-8
'.6 Reported, Annual DecayeReleases-1972 through 1992......
0.....-l0
- 7. Detail of Annual Releases-1972 throu*u 1975......
A-13
- 8. Detail of Annual Releases-1976 through 1980.
A........
7........
A-17
- 9. Detail of Annual ReleaseIs-1981 throughl985..............
..A22
- 10. Detail'of Annual Releases-l986 throug 1990.....
A-27 H1. Detail of Annual'Releases-1991 throuh 199".2-..........
..A32
YRC-1178, REV. 0
___Page
.3.
I Calculation Objective The objective of this calculation is to calculate the maximum soil concentrations of radionuclides deposited off-site as the result of gaseous releases from the Yanked Nuclear Power Station (YNPS) during its period of operation, 1960 through 1992' This information was requested by Service Request 98-00, dated 0 1/08/98. This information is necessary to support the "non-impacted area" classification, as described in Revision 0 of the YNPS Final Status Survey Plan. This calculation is intended to evaluate the data from all recorded radioactive gaseous releases from the plant.
TI
YRC-l 178, REV. 0
_4 II Method of Solution The method of solution is to: 1) detcrmine the radlionuclide distribution and quantity, released as a gaseous effluent, during each year from 1960 through 1991; 2) decay each annual release, by individual radionuclide, to 01/01198; 3) apply a conservative atmospheric deposition factor (D/Q value) to each particulate radionuclide released to determine the surface concentration of each radionuclide; and 4) apply proper regulatory guidance to determine a maximum soil concentration for each particulate radionuclide.
Although the distribution and quantity of all reported radionuclides are calculated herein, only the particulates are considered as candidates for deposition. The strictly gaseous effluents like Krypton, Xenon, and Argon are dispersed in the atmosphere without deposition potential, and largely have half-lives measured in days (or less), with the exception of KR-85. The three isotopes of Iodine, while particulate in form, all have half-lives less than 8 days, and are of no significance for long term deposition.
Tritium activity released as Hydrogen gas, or as. water. vapor, would not have any potential to concentrate in the soil. Carbon 14 is listed as beingsreleased is the gaseous state. It most likely existed as carbon dioxide when released and also has no potential to concentrate in the soil.
YRC-l 178,. REV. 0
_Page 5
III Inputs and Assumptions The source of information on gaseous releases is contained in the Semi-annual Effluent Reports commencing in 1972. The individual radionuclides are listed as Fission Gases, lodines, Particulates, Tritium, and unidentified. The data is tabulated, by quarter in each report, for both continuous and batch releases. This data was directly transcribed by others to Lotus spreadsheets. The annual summing, without regard to decay, was performed in the spreadsheet for the period.
Prior to 1972, gaseous release data was reported, for the prior year, in the January Monthly Operating Report for the next year. The early data was reported as "gross beta-gamma" curies or millicuries. In order to estimate annual releases by radionuclide, for these early years, a previous EPA study was used (Ref 1). This study consisted of a sampling and analysis program at the plant in the years 1968 through 1970. The study analyzed for 10 gases and 6 particulates in gaseous discharges. The quantity and distribution reported by the EPA was assumed to represent the best data available. The annual releases reported by Yankee for the years 1969 and 1970 were averaged and compared to the value the EPA estimated was released. The EPA distribution fractions were calculated and applied to the Yankee reported release total ratioed to the EPA release total to estimate the annual release of the radionuclides reported by the EPA. This methodology was applied to the gaseous release data for the years 1960 through 1971. The first reported release of Tritium was in the March, 1965 Monthly Operating Report, when instrumentation capable of detection tritium became available. Estimates for previous years, 1960 through 1964, were assumed to be the same as reported in 1965.
The annual releases were assumed to occur on the last day of the year and decayed to the beginning of 1998. Thus, for 1960, decay commenced in 1961 and ended at the end of 1987; a total of 37 years As a check of data transfer correctness, the releases as reported in monthly and semiannual reports for each fourth year, commencing with 1960 and ending with 1988 was compared with the values transcribed to the spreadsheets. No transcription errors were detected. As another check, the results were manually scanned after the calculations were performed to see if any data seemed to be anomalous. In the case of CS-I 37, it was noted that 84% of the undecayed activity reported to be released between 1972 and 1992 was released during the second quarter of 1982. Typical Cesium ratios are 3:1 Cs-137 to Cs-134. The Semiannual Report for that period was re-checked and it was found the reported value for April, 1982 for gaseous Cs-137 was 1.50e' and the reported value for May, 1982 was 8.1 le". One might expect the Cs-137 value to be in the range of 2.3e6, rather than 2.3eo, for the quarter While this quarterly total is suspect, it is assumed to be correct, lacking any other information. In another instance, it was noted that in the third quarter of 1973, 9.54e6 Ci of Ag-i I10m was reported as being released. On the surface, this value appears about a factor of 100 too high. In both cases, assuming the higher values do not affect the final conclusions of this calculation.
As an aside, it was noted in the February, 1964 Monthly Operating Report, that the incinerator was shutdown pending a review of elevated activity detected in the discharge filter. No record was found in which the incinerator was ever restarted. It can be assumed from this that any releases from the incinerator were minor with respect to the other gaseous releases documented in this calculation.
4:!
YRC-1 178, REV. 0 Page 6 IV Calculation and Analysis Table I DATA FROMEPA REPORT'"
NUCUDF.
EPA.EST. RELEASE PERCENT OF TOTAL FISSION GASES KR.-9 33.0¢00 6V 72%
KR 45m 2,0c-02 041%
KR-87 2.0e-02 0.41W KR-S8 3.0e.02.
4.90%
-XFI 33 1.0e-o1 2.060/6 XE-I 3 5 2.0e-01 4.11%
XE-135m 2.4c-01 4.90%
XE-138 Ie-01 17.406%
XV.Al:33m 1.0-O 006%
.AR-.41 4.0e-O1
,8.23%
C-14 3.0c-01 TOTAL 4.9c+00.
100.00%
IODINES I. 131
- 3i0.04 100.00%,
1-133 0.00%
1-135 000%
'TOTAL 3.0c-0'4 100.00%
.-PARTICULATES
- sR-89.-
oe-5 7.40%
R-90-,
37.02%:
CS-341 C137
- 2. *.
04%
cO-60 2e0 37,02%
- MNq-S4 I.0.0
,IS:Sl%
TOTAL
- 5;4"4 99.90%
H-3 1.3e+ 1,01
YRC H a78,REV.7 Page 7 A. Estimation of 1960-1971 Release Distribution The data in the Table I was extracted directly from section 3.3.8 of an EPA report', and represents the "best estimate" of radionucide distribution for the period up through 1971.
B. Decay Equation The general equation for
ýWhere:
A= Activity at timet Q0 =Activity attimee zero
= decay constant, where *: i'sfl 2-. divided by half-life, in. years, and A t is decay time in years
YRC-lI 178, REV. 0 I P, age 8 C. Decay Calculation Application For this calculation, Q0 is the activity of the specific radionuclide at the end of the year in which it was released. Time, t, is January 1, 199g. Each radionuclide in each year of release is decayed to January 1. 1998, using the lambda values from Appendix A, Item.l. and the number of years from the release year to 1998. For example, 1.17e-08 curie of Co-60 was released in 1960, thus, the quantity remaining on 01/01/98 is:
Qof 1.17e-08 decay time (years)f37 (1961 through 1997)
X, for Co-60 = 1.318e-0I Qt = 1.17e-08 e"l-3k'OX37)
Q, = 1.736e-10 curies The spreadsheets are set up to: 1) perform quarterly summations to determine annual releases, by radionuclide; 2) decay each annual released radionuclide to January 1, 1998; and, 3) sum each decayed quantity to determine the total activity over the 37 year operating period, by radionuclide.
D. Application of Atmospheric Deposition Factor A long term average atmospheric deposition factor (D/Q) has been calculated by others and is indicated in Section VII as Attachment A to this calculation. The details for determining the appropriateness of this factor can be found in this Attachment A. This deposition factor is applied to the decay corrected released activity to determine the maximum remaining deposition on an area extending 100-200 m beyond the owner controlled area. The units on D/Q is: 1I/m 2. The maximum long term average deposition factor, from Attachment A is:
D/Q=8.79e-08 1/nW The desired result is individual radionuclide surface distribution, in units of:
pCi/m2. Thus multiplying the historical released activity, (decay corrected to Jan 1, 1998), in units of pCi, by D/Q gives the desired result. Unit conversion from curie to picocurie is: (Ci) (le+12) =
picocurie Therefore; Surface Conc.(Co-60 from 1960) = 1.73e-10 Ci*le+12*8.79e-08 1/m2 = 1.53e-05 pCi/mr2
YRC-1 178, REV. 0 Page19 E. Soil Concentration Guidance on calculating voiume concentration from surface concentration is provided in Regulatory Guide 1. 109 (Ref. 2). Table E-15 defines the effective surface density of the soil as 240 kg/rn2 The assumption provided is that this represents a 15 cm deep plow layer. It is assumed that the deposited activity is captured and retained withini-a-5 cm depth. This is considered conservative for this application, given that this deposition occurred over a thirty year period, with snow and rain serving to further disperse the activity. Dividing surface concentration (pCi/rm) by 240 kg/mn results in estimated soil concentrations of residual radioactivity from past plant gaseous releases (pCi/kg) rent;ni,;na thp ivanmnla nfr'e.AA
- fha eimmatkn ^fall thi annival a*Aenuim rAPA.cPC iArOPA tn January 1, 1998 is: 3.5803-04 Ci. Multiplying the result by 8.79e-08 (D/Q), and Ie+12 ( pCiICi) gives a surface concentration of 3.147e+01 pCiim2.Dividing by 240 kg/r 2 provides the estimated soil concentration of Co-60 of 1.311 e-01 pCi/kg
YRC-i 178, REV. 0 Page 1 0 V. Results and Conclusions In the Summary Table, below are listed the total releases, decayed to January 1,1998. In this summary table, if the decayed activity was less than Ix e7", it was not listed. In the case ofKr-85, C-14 and H3.
The releases are assumed to be in gaseous form and would not be deposited on the ground surface The complete results are listed in Appendix A, Item Z, Of all the radionuclides listed as having been released in the gaseous effluent, six particulates have the potential to be present, as of January, 1998, in concentrations greater than 10 " pCi/Kg. These are: Sr-90, Cs-134, Cs-137, Co-60, Mn-54, and Sb-125. Three of these are calculated to be present in the range of 10 "' pCi/Kg. Even these calculated concentrations are several'orders of magnitude below the current levels of detection and are masked by natural occurring radionuclides.
The YNPS Final Status Survey Plan defines "non-impacted areas" as areas of YNPS property outside of the "unaffected area" that have not been impacted by plant operations. The "unaffected area" essentially extends from the "affected area" (which is centered around the vapor container) to a 20-meter wide buffer zone outside of the owner controlled area fence. (See Attachment A, for details and references).
This calculation demonstrates that, under conservative assumptions of atmospheric deposition, no area exists outside the "affected area" would be expected to have detectable residual radioactivity from past plant routine (licensed) gaseous effluents.
YRC--! 178, REV. 0 Page I I Table 2 SlJMMARY TABLE OF SOIL ACIrMTY RESULTING FROM GASEOUS RELEASES NUCLIDE DECAYED ACT SURFACE CONC SOIL CONC (Ci)
(pCi/m ))
.(:pCitkg)
FISSION GASES KR-85 3,626e401 1-135
<1 e-l PARTICULATES
- SR-89
<Ic-J0 SR-90 7.0()C-04 61.153c-,{0 i 2:504c1 CS 134 L343c-06 I.soe-0 I 4.9 18c-04 CS-1 37 2.763t-04:
2,429e+01, 101 2eo:.
BIA/LA-1,40
<Ic-JO 0 ZN-65
<lc-10-....
CO-58
<le-10 CO,-60 1.580c-04 3.147e+O0
.. 311cHO0 FE-59
<Ie-JO CR-51
<ie-JO I
ZRJNB-95.
.lco
-0 CE-1,41
<le CE-I144
.1*14i.09 SB1-124
<Ic-10 MN54
.2371 c-08 2084e-03 8'682c.o6
ýAG-' 10m
<1c-t1 SE-75
<IclO MO-99
<I - 10 RU-103:
<I-IO SB-125 5.020c-07 4.4 ll3c-02 839c-O4 TE-132
<I-JO
Y-RC-1 178, REV. 0 Page 1.2 VI. List of References
.1. "RD-7 1-1 RADIOLOGICAL SURVEILLANCE STUDIES AT A PRESSURIZED WATER NUCLEAR POWER REACTOR", U. S. Environmental Protection Agency, National Environmental Research Center, Cincinnati, Ohio, August, 1971
- 2. "Regulatory Guide 1.109, CALCULATION OF ANNUAL I*OSES TO MAN FROM ROUTINE RELEASES OF REACTOR EFFLUENTS FOR THE PURPOSE OF EVALUATING COMPLIANCE WITH 10 CFR PART50, APPENDIX I, rev I", U.S. Nuclear Regulatory Commission, October, 1977.
- 3. Spreadsheet Data Files The following files contain the data used in this calculation. Lotus 1-2-3 rev.5 and Quattro Pro rev. 6 use these files interchangeably
- 1. YRGASEF.WB2
- 2. g71-75.wk3
- 3. g76-80.wk3
- 4. ggl-85.wk3
- 5. g86-90.wk3
- 6. g91-92.wk3 7 DECAY. wk3
)
YRC-1 178, REV. 0
- Page 1,3 VII. List of Attachments
- 1. Attachment A., Calculation of Atmospheric Deposition Factors
YR'C-l 178, REV. 0 Page'14 VIII Review Sheet
( SiL,4.
tf r,-'"
NONNI&
?~ I0 REVIEW FORM CALCULATION NO:
YM
-1// m TITLE:
?0.440KAMA.ýr&
Sgj./-C;-b(t te.44?/AiV.a4 REVISION NO:
RESOLUTION I
COMMENTS
-r A.144 4 eP
~
4 21See-A7*tA,.sat]4 Coments Provided By:
- I'#II Reviewer
/
Date Resolutions By:
.5..
-43 l
Preparp t Date" Concur with Resolutions-:
D*at41e Reviewer
/
ate e Page
/
Of a
Form: YA-EED-700.2 Revision :
0
.e v; ej F6 R --t DATGE:
P A'GE N0.
A 2
3 4
S 6
7 8
9 10 II 12 13 14 IS 16 17 li 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 3S 36 37 3'
39 40 41 42 43.
44 45 47 48 49 SO SI tdrsedn Ca ko, Uljfý Dcca 8920
_a__re__
_(y_--_)--
0i.1318_
_D_
_,_psiion _:___E08
) -l rot. Co-60
___r_.
0 1_
,__1
________o__:C..60 I :Dccaycd.
1998;deca ed '998 dcce.Ycd N_______._
Ymt decay undccaycd to 1998 sirfac& Act, Vol. conc.
i Year i)
Mrlcsscd C1.
(al) il/m.
1960 37:
1;1,7&,08 8,92E-1I
- 7.7848-,06
- 317"'*$:b
-19%1.
36 3.68E408 3__E-_._
____OS:
- 1. f-r7:
1962
.35 421E404 4:18E406.3.67E-001
,I.3E3 1963 34 1143E-04:
- 1.62E-06 !
'1.42E-01 5.93,-04
- 1964, 33 1.988-05 2.56E-07 J2.25E-02 9.37E-05 1965 32 2.02-05 3.688-47 3.24E-02 1:351304 1966 31 4.37M,05 7.68,1107.
-fi&75E-02 I 2.81-04 1967 30 4:.,48.0 8.59E-07:
7.5SE;02 3.15-"04 1968
- 29.
1125.-O
- 2;73E-07 2,40-02:
T.00.04) 1969 2
84.006-05
- 2.001106
<1.76E.601 7131 E-04
.1970 27; 3.202-04 9A1&-06 8101E-01 3.34.,03 1971 26 2.38M-04 7.73", 06.".
6.806-01 2:83E-03 1972 25' 102E-04 3.78E406 -'.3.32E L38&031 1973 24 1.83E44 7.74E-06
_" 6.808-01 2.83E-03 1974 23 2.18M03 1.;0511w04 1-9.2,E+00 3.858-02 1,975..
22:
3322-03 A.72-04 N'13111401 6.219202 1976 21 9442E-06 5.938-07
- -*,.21FA2X 2.17-*44 1977 20 2.20E-07 1.5-*O8 L.39E203 5.77E-06 1978 19 2.42E05 1.98E-6 1.74E410 7124E-04 1979.
18 2.208-05
'2.05E-06.
LSOE-1 7.51E-04 1980ý 17 1.18-O.
.216E-06
- 1.1013-01 4.60E-04 1983 16 1.06E20-1:29E-06 IM 3E-.
, 4.718E2-04 1982 I'
1.75E,06 2A42E107
'2.13E02
" 8.886-05
.1983 W4 5,87E.06, 9.27E407 "BA.SE-o2 3A40E-04 1984 13, Oo0E+00 0.0013+W 0.1OOE+00 O.OOE+00 1985.
12 41391346 903 -07ý
?M.94E-02 3.3 1&.44 1986 II 9.65E-06
- .226-06-6 1.99 1
8.-29
.44' 1987 10T 935E-06 2:50E606-1,i..2:20E&4[
91E7044 1988W 9
6.989M06 2.13E606.
ýý"J187E401:
7.81E-04 1989 8
3.202-05 L.IttE-05 9.0.2-01 4.08E-03 1990
- 7.
1.83E45 7.27E.-06
-: 6.398-0:
2.66E-.03 1991 6 *
.81E-06
4.0 01-06
3.51E-01:
1.46E-03 1992 5
7.516E-06 3
- 89 -06 3:426-01
.l42E-03
- Totals, 7.12E-03 3MSE04
.. ;.315SE+Ot 1.31E-01I (a)
(ci)
.(Cl)
)*
weas~wk3 CAM NO.
Ac AI
- 4. 3t 1w1 Z S>,ria c-it iAI*1v'+),1
.- qE-t
YRC 1178, 0EV0 Page 1:7 App*ndix A.. Spreadsheet Printouts
- 1. Selected Nuclide Properties
- 2. Gaseous Release Summary & Soil Concentrations
- 3. Estimated Annual Undecayed Releases-1960 through 1971
- 4. Reported Annual Undecayed Releases-1972 through 1992
- 5. Estimated Annual Decayed Releases-1960 through 1971
- 6. Reported Annual Decayed Releases-1972 through 1992
- 7. Detail of Annual Releases-1972 through 1975
- 8. Detail of Annual Releases-1976 through 1980
- 9. Detail of Annual Releases-1981 through 1985
- 10. Detail of Annual Releases-1986 through 1990
- 11. Detail of Annual Releases-1991 through 1992 (YRGASEF.WB2, SH. G)
(YRGASEF.WB2, SH. F)
(YRGASEF.WB2, SH. B)
(YRGASEF.WB2, SH. C)
(YRGASEF.WB2,. SH. D)
(YRGASF.WB2, SH. E)
(G71-75.WK3)
(G76-80.WK3)
(GS1-85.WK3)
(G86-90.WK3)
(G91-92.WK3)
A YR04 178 TaRe, A I I I
. 'i 4AI Auacbni~iit A YRC-1 178, Page Al u~sIuw.winUSUUSUUinUinUwUUWSWinUSU.
ATTACHMENT A Calculadon of Atmospheric Deposition Factors I-Prepared ýby:
ReRBdby h1~
Reviewed br. ý:Q M
Attachindrit Aý Y4R'C-1118, Pago A2 Attachment A YRC-1 178. Page A2 Calculation of Atmospheric Deposition Factors 1.0 CALCULATION OBJECTIVE Generate an atmospheric deposition factor (D/Q value) which can be used to estimate the maximum possible concentrations of radionudlide contaminants in the soil surrounding YNPS based on primary vent stack releases from plant start-up to present. This effort pertains to information required to support the "non-impacted area" dassification as deseaibed in Rev. 0 of the YNPS Final Status Survey Plan (Reference 1).
The YNPS Final Status Survey Plan defines "non-impacted areas" as areas of YNPS property outside of the "unaffected area" that have not been impacted by plant operations.0) The "unaffected area" essentially extends from the "affected area" (which is centered around the vapor container) to a 20-meter wide buffer zone outside of the owner controlled area fence@) as shown in Exhibit A-1.
Note that this D/Q calculation differs from previous calculations of atmospheric dispersion factors for YNPS (e.g., YRC-437, YRC-501, and YRC-830) in that the previous calculitions were concerned with identifying the highest atmospheric dispersion factors which occurred beyond the site boundary (which extends 450-2400m downwind; see Exhibit A-3) whereas this calculation is concerned with identifying the highest atmospheric dispersion factors which occurred beyond the owner controlled area (which extends 100-200m downwind; see Exhibit A-1).
, Sction 4.1.2 of Reference 1.
(OSection 4.2 of Reference 1.
Prepared by:..R8Hfa
, Jr-Reviewed by:
AttachineritA YR-C-1,178', PageA.
2.0.
MIETHOD-OFTSOLUTTION The required atmospheric deposition factor (D/Q value) was calculated using the DE&S computer code AEOLUS2 (Reference 2). AEOLUS2 is approved for use in non-safety calculations per YA-REG-200. The use of AEOLUS2 is appropriate for this application since it was developed to fulfill the RG 1. 111 (Reference 3) criteria for estimating atmospheric transport and dispersion for routine releases from nuclear power facilities. There are currently no open software problem reports applicable to AEOLUS2.
The current set of atmospheric dispersion factors in the ODCM were calculated in YRC-501 (Reference 4). In order to account for wind channeling effects through the valley, the ODCM atmospheric dispersion factors were determined assuming seven downwind sectors (SSE clockwise through WNW) formed the valley. If a particular receptor location was in one of these valley sectors, the contribution from the other six valley sectors was also included. The effective valley width was assumed to be twice the width of a 22.5 sector. Consequently, the SSE clockwise through WNW sector dispersion factors were added together and divided by two. This "valley model" was applied for distances greater than 500 m from the stack where valley effects were assumed to cause channeling (see Exhibit A-2).
For the purposes of this analysis, the primary area of interest lies within the YNPS site boundary where stack-high terrain is generally encountered downwind in the "non-impacted area" before reaching the site boundary (as shown in Exhibit A-3). As such, it was decided for this analysis to run AEOLUS2 as a straight-line trajectory model and not account for wind channeling effects.
Receptors were placed downwind at increments of 100 m in each sector starting at 100 m until a terrain height exceeding the maximum effective plume height of 120.8 m was encountered.(-)
AEOLUS2 was executed using five years of YNPS on-site meteorological data, from January 1987 through December 199 1.('0 The meteorological data base was obtained by merging the Software Control Library files YRMET87, YRMET88, YRMET89, YRMET90, and YRMET9l.
(°Tihe maximum effective plume height h1, (relase height h, plus plume rise hF, expressed in meten above plant grade) occurs with a maximum plume rise which happens during unstable conditions with lighi winds. Maximum plume rise can be predicted utilizing the following equation (Equation 4.40 of the AEOLUS2 Technical Manual) assuming a primary vent stack exit velocity w. of 10.5 m/sec (representing 20,000 cfm being exhausted through a diameter stack d of 1.07 m) and a 0.447 n/sec (1 mvh) wind snmd hp, - 3 (wju) d - 3 (10.5/0.447) 1.07 - 75.4 m Consequently, the predict&4 m
.fit-a.w-4ve plume height above plant grade i.w hS +b,
- mAqA,
+ 75,A 170 9 Pre d
fe Rrare.r h
aprbsenii h ltfv a
ant opration.
Prepared by:.RBff ý J~r.
Reviewed rby:
ý
ŽŽ-
Attach~merit A
,YRC.I1.I78, Pagke.A4 3,0.
UTS.AND ASSUNMTIONS The following issumptions were used ih executing AEOLUS2 for this analysis:
Sector average D/Q values (which are applicable to long-term releases) were generated.
S MAll releases were assumed to occur through the prinmay vent stack. This release pathway was modeled as a RG 1. 111 (Reference 3) mix-mode release since the primary vent stack release height is at the height of'the adjacent vapor container. A normal stack exit flow rate of 20,000 cfm (indicative of the operation of one stack fan) was assumed for the determination of plume entrainment and plume rise.
In accordance with guidance from the XOQDOQ User's Manual (Reference 7), lower level wind data were provided as input. These data were used "as is" to disperse the ground-mode portion of the plume and were extrapolated up to the PVS release height for evaluating plume entrainment effects and for determining plume rise and dispersion for the elevated-mode portion of the plume.
Upper level wind direction data were provided to the code to determine -lume transport.
The lower level wind direction sensor is often affected by localized nocturnal drainage flowing down the east and south slopes of the river valley within the plant vicinity.
Consequently, the upper level wind direction measurements are generally considered to be more represetative of general flow conditions within the valley.
The RG 1.111 depletion/deposition model was used to determine the D/Q values. Wet depletion/deposition and decay-in-transit effects were not considered.
Specific plant and receptor data input requirements for AEOLUS2 are listed in Attachment B to Reference 2. A listing of the inputs used is provided in Exhibit A-4; most of the inputs were derived from YRC-830 (Reference 5). An actual listing of the input deck is provided as part of the output listing provided in Exhibit A-6.
Prepared by: RB HIf y.Jr.
A Reviewed by:
Z22M L
A-ttA6ibdnt k Y-RC-I 178,,PA9q A5, 4.0 CALCULATION/ANALYSIS A partial listing of the AEOLUS2 output which includes all relevant program iinputs and outputs is provided in Exhift A-6.
iPage84,Ofthe*A Lus outut showsththhighest calculated D/Q value is 8.79E8 1/r2, locatedat:5*
- downwind in theS SWýtor(Noteit'ilthighest offsite, value calcuated ýin YC-50 1fr, u se in the Y NPSODM-C 1si 2E-8 I/m2, located at the site boundary 800o4n SSE,
- '* *,:!(,.* *
.L,*
- 4!**
Prepaed by
£ilf~,Y~J~rS~~J) eviewd by:
Ij,)
Prepared by: R8 Jr. @ý Reviewed by:
Attachment A YRC-1 178, Page A6 5.0 RESULTS/CONCLUSION An appropriate atmospheric depositior facýor(*D*- u) f'or use in ting the maximum posible concentrations of radionuclide coniiil in the"non-pa a"
surrounding YNPS is 8.79E-8 1/mn.
Prepared by:
Redb:
Reviewed by.
-,TD 44W-
YRCLA:1en8A YRC-1ý A7 60 REFERENCES I.
YAEC-1933, "Final Status Survey Plan for Site Release," Rev. 0.
2.L*_, YNSD Calculation YC-329, "Computer Code Documentation Package, AEOLUS-2, Mod 6," Rev. 0.
- 3.
US NucleardRegulatory Commission, "Methods for Estimating Atmospheric Transport andtDispersion of Gaseous Effluents in Routine Releases from Light-,Water-Cooled Reactors," Regulatory Guide 1.111, Rev. 1, July 1977.
- 4.
YNSD Calculation YRC-501, "Rowe ODCM Dose Conversion Factors," Rev. 0.
- 5.
YNSD Calculation YRC-830, "Yankee Nuclear Power Station ODCM Atmospheric Dispersion/Deposition Factors," Rev. 1.
- 6.
YNSD Calculation YRC-678, "Yankee Rowe Terra Datam" Rev. 0.
- 7.
JF Sagendorf Yr Go, and WF Sandusky,'XOQDOQ,Computer Prog f for. the Meteorological Evaluation of Routine Effluent RelessatNuclear Power Stations,"
NUREGICR-2919, Pacific Northwest Laboratory, September 1982.
Prepared by: RB i&ar.
(y R
d Reviewed by:
.Attachment A
YRC.-I 18Page AE YNPIS Final Status Survy Plan I Lor-tion nf U naffpefM' ~and Non-i.4pq('tPd A-r9*ot
.VNP.*--A, STA SURVEY, PLA REVISION,,
7)
.AFFECTED
- ARFA, I,)
.vIstT1'cZffTtI.
f~
1' FIGURE 2-3 Prepared by: RB Hfarvey. Jr.
Reviewed by:
J. D-2.i4
Attachment A EXHIBIT A-2 YNPS Site Topographic Map YRC-1 178, Pae A9 Prepared by: RB Har-ey......Reviewed by:_......
Preparedby: RWHarvey.-Alip)
W.L.,
EXHIBY!r A-3 YNPS Site Boundary YRC-1 178, Pge AIO YA Preped by: B RMew by:
- -2? *'
Reviewed by:
T nA L
Attachment A YRC LiSts of Piant and Receptotor.Inputs to AEOLUS2(V)
Run Title YNPS NON-IMPACT AREA DIQ VALUES Program Control Options
,- 1$78, Pge Al.1 Imt Line I TITLE In~ l~ine 2 KPRINT KTP7 KMN KCF KWEXP KGX KSIG KVORS KDEPL KRAIN NWSIN 0
Set printout control option to short printout I
Set the control option for transferring informauut, to tape7 to sector average CHI/Q and D/Q values 0
Set meander control option to exclude plume meander consideration in the plume centerline C SSet control option for Woreu*
r r correction to no correction I
Set wind speed n
p1i'f/n control option to use the built-in extrapolation coefficients from XOQDOQ 0
Set the gamma CHI/Q control option to bypass this calculation 1
ýeS the model selectiondbontroi option for the dispersion coefficients to the EimutisIKomicekinioel, in XOQDOQ 0
Set the seabreeze/valley model option selection to open terrain analysis 0
Set the depletion model control option to the RG 1.111 depletion and deposition curves 0
Set the wet deposition control option to not evaluate wet deposition effects 12 Set the number ofvwkdped groups to twelve
("The plant and receptor data input miulrr fmts for AEOLUS2 are listed in Atachment B to RefvmCC 2. Most of the inputs listled h wr derived from YRC-830 (Rcfrn 3).
Prepared by: RB Har Jr.
Reviewed by-yh
Attachmen't.A
)MC-17,agA2 EXHIBITI A-4 NEG 0
Set the number of gamma energy groups in the user-specified spectrum to zero INTERM
{
Leave the duration of intermittent releases blank IPCT
{
Leave the hourly value exceedance probability forzinternittent releases blank NMONTH 60 Set the number of monthlyrsec.dsin thermet data base. which will be analyzed to60( y'e'ars)~
'nput Lne* Set 3 d
Group D "fiitins Input Line Set 3A WSLIM(2) 0.42 WSLIM(3)
WSLIM(4)
WSLIM(5 WSLIM(6)
WSLIJv7)
WSLIM(8)
WSLIM(9) 0.92 1.59 3.37 5.61 8.29 10.97 14.10 Set the upper wind speed in the first wind speed group to 0.42 m/sec (This is the minimum wind speed acceptable as a valid observation and corresponds to an assumed anemometer/wind vane starting speed of 0.95 mph)
Set the upper wind speed in the second wind speed group to 0.92 m/sec Set the upper wind speed in the thirdwind speed group to 1.59 m/see Set the upper wind speed in the fourth wind speed group to 3.37 m/sec Set the upper wind d n the fifth wind speed group to 5.61 m/sec Set the upper wind -speedfn the sixth wind speed group to 8.29 ni/sec Set the upper wind speed in the' seVenthwnd. speed group to 10.97 m/sec Setth upe wndspee in. th
- ht ind speed group4 o~4 10
~/sec InMu Lne Set 3B WSLIM(10) 17.23 Set the upper WSLiM(1 1) 20.81 Set the upper Prepared by: MifnnJr. 0
',in the ninth wind speed group to 17.23 m/sec Iin the tenth wind speed group to 20.81 m/sec Reviewed by:.
Attachment A YRC-1 178. Paste A13 Attachment A YC17.Pg 1
EXHIBT A-4 WSLIM(12) 24.38 WSLIM(13) 40.23 Input Line 4 Set the upper wind speed in the eleventh wind speed group to 24.38 ni/sec.
Set the upper wind speed in the twelfth wind speed group to 40.23 m/sec (This corresponds to the maximum wind speed acceptable as a valid observation, 90 mph)
Wind Speed Extrapolation Data Omit this input line since the AEOLUS-2 built-in extrapolation coefficients will be used Input Line 5 Release Point Data HREL 45.41 Set the height of release to the primary vent stack height of 45.41 m above plant grade (0.Olm higher than the adjacent building height to ensure a mix-mode release)
HBLD BAREA DIAMTR VFLOW QH Lt Line 6 45.4 Set the height of the building adjacent to the release point causing the building wake effects to theyvapor container height of 45.4 m above plant grade 1575.
Set the cross-sectional area of the building adjacent to the release point causing building wake effects to the vapor container cross-sectional area of 1575 e2 1.07 Set the effluent vent effective internal diameter to the primary vent stack diameter of 1.07 in 20000.
Set the effluent vent flow rate to the primary vent stack flow rate of 20,000 cfln
- 0.
Set the stack effluent heat content to zero to ignore buoyant plume rise General Site D 950.
Set the annual average height of the inversion layer to the YNPS annual mixing layer height of 9510,m.
950.
Set the maximum allowed plume centerline height to the annual average inversion layer height of 95 m HFMX I
Prepared by:
a
- r.
R b
Reiwdby:
Y
Attachment A YRC-1 178. Paste A14 Attachmenti A
Y.RC...1.8. P A14 EXHIBIT A-4 THLFNG THLFNG SCAVCF(1)
SCAVCF(2)
JMt Lines 7-0.
0.
Set the noble gas half-life for decay-in-transit analysis to zero (e.g., do not consider decay-in-transit)
Set the iodine half-life for decay-in-transit analysis to zero (e.g., do not consider decay-in-transit)
{) }
Leave the first coefficient in the rainfall scavenging rate equation blank (e.g., do not consider wet deposition)
(
Leave the second coefficient in the rainfall scavenging rate equation blank (e.g., do not consider wet deposition)
)Gamma Ener*v Snectra Data Gamma Enerav Sneam Dat Omit these input lines since gamma CH/Q values will not be generated ho Lne Set I0 Deposition Velogit/Atosperic Wftbli Correlation*
Omit these input lines since the RG 1.111 depletion and deposition curves are used to generate the deposition factors Input Line 1I Meteorolog*cal Data Innut Fonrat (4F2.0,F3.1,16XF3.0,6XF4.1,28X,2F3.2)
Format for input of year, month, day, hour, lower wind speed data, upper wind direction data, delta-temperature data, precipitation data, and solar radiation data In Line 12 Meteorologcal Daft Sol LIM ID(1)
ID(2)
ID(3)
ID(4)
ID(S) 1 2
3 4
6 Seque nce~n un
,equenc enuber of!
Squ nmber ofd'a Sequence' nbr of!I Sequence niumbeýr of data in EMT Prepared by: RB HMMM'Lrý Reviewed by:.:11*2
Attachmenit A YRC-1179, ý'Plage Al 5 EXHIBIT A-4 ID(6) 5 Sequence numberof wind speed:data in M ID(7) 7 Sequence number of delta-temperature data in IMT ID(8) 9' Sequence number of solar radiation data in IMT ID(9) 8 Sequence number of precipitation data in IMT KPRMET 12 Set the printout control option for the hourly meteorological data to print the first 12 hourly meteorological data records in each month KP1UFD I
In~ Line 13 WDMAX 540.
WSMAX 90.
Set the printout control option for the joint frequency distributions to include the distributions in the printout Meteorological Data Base Entrics Set the maximum wind direction value acceptable as a valid observation to 540 (values of 999 in the data base indicate missing data)
Set the maximum wind speed value acceptable as a valid observation to 90 mph (values of 99.9 in the data base indicate missing data)
DTMAX
- 15.
Set the maximum delta-temperature value acceptable as a valid observation to 150F (values of 999.9 in the data base indicate missing data)
SUNMAX 2.0 Set the maximum solar radiation value acceptable as a valid observation to 2.0 langley/min (values of 9.99 in the data base indicate missing data)
Set the maximum precipitation value acceptable as a valid observation to 5.0 inches (values of 9.99 in the data base indicate missing data)
Meteorooýe i*.*Dattr. -Converýor. Factorl RAINMX 5.0 In Line14 WSCONV 0.447 Set the conversion factorto convert the data base wind speed data from mph to n/sec w
.,d4 DTCONV 0.556 Set the conversion facto-to convert, thedata base delta-temperature data from mph to vsec tc 0.44?
Prepa"e by:~I~ sr Revee by:
A Reviewed by:
-U-0 M/
Attachment A YRC-1l78,Pg A16 0XH=,IT A-4 SUNCON
- 1.
Set the conversion factor to convert the data base solar radiation data from langleyfmrin to ca/cmO-min to 1.0 (langley = cal/cm2)
RAJNCV 25.4 Set the conversion factor to convert the data base precipitation data from inches to mm to 25.4 WSCALM 0.21 Set the wind speed assigned to calms to 0.21 m/sec, one-half the assumed anemometer/wind speed starting speed of 0.42 m/sec (0.95 mph)
WSHITE
- 10.
Set the height'o,4of ewid speed measurement to 10 m above plant grade DH
- 50.
Set the delta-emperature, senst separation on the meteorological tower to 50 m (197 ft -33 ft - 164 ft - 50 m)
WDVAR 888.
Set the variable wind direction identifier to 888 (not used)
LWputnes 15-19 MD Omit these input lines since the seabreeze model option is not being executed I"Dut Lines 20-21 Valiy Data Omit these input fines since the valley model option is not being executed bo Ln 2 Sat of Reaegor Dec TITL START OF RECEPTOR DECK Input Line Set 23-xx ReWtorData I
The remaininsihput lines which provide receptor dataare fisted in Exhibit A-3 Innut Line 23A-xxA Reepftor Distances
+.
DIST Provide receptor distances (m meters) for each sector starting at 100 m and imcreasging in100 m increments until the terrain height in all sectors exceedas 115 m RIDENT Set the receptor identifier to the downwind distance Prepared by: PHaMx&ý.
Reviewed by: --Tt? ba
Attachment A ExIBTA-4 YRC-1 178, Page6Al7 Input Line 23B-xxB ISCT IKPRT IVALOC HTERN RCF VWJTH VSLOPB VDIST DESCR 0
0 0.
0.
0.
(}
- i Receptor Data List'iech downn dsector until the tenrain height for that sector exce6ds 1!5 I Set the printout contro1*ption to suppress the printout for all receptors Set the valley location j-tifier for all receptors to indicate that each receptor is in open terrain Set the receptor terrn heit to the maximum terrain height between the release point and the receptor as listed in YRC-678 (Reference 6)
Set the recirculation correction factors for all receptors to zero Set the valley width for ll receptors to zero Set the valley slope, for alireceptors to zero Leave the receptor distance along the valley blank for all receptors Set the receptor identifier to the receptor's downwind distance and sector Prepared by. AR f0BJ1~
Revewe Jr.~Jk Reviewed by-Zatm-
Ata~chment A YRC-1_178 Page A18 EXHIBIT A-5
- Receptor Data DIST' lOM 100.
loom MSc' N
WNW NW NNW N
NNE NE E
.:.ii¸KP T, IVAWOC HTERN 1RCF 0
0.00 0.
0 0.00 0.
0 12.19 0.
0 18.29 0.
0 18.29 0.
0 18.29 0.
0 6.10 0.
0 12.19 :0.
0 24.38 0.
o 24.38 0.
0 0.00 0.
0 12.19 0.
0 0.00 0.
0 0.00 0.
0 0.00 0.
0 0.00 0.
0 0.00 0.
0 0.00 0.
0 12.19 0.
0 18.29 0.
0 1S.29 0.
0 18.29 0.
0 12.19 0.
0 18.29 0.
0 36.58 0.
0 42.67 0.
0 42.67 0.
VWDTH VSLOPE VDIST
- DSCR IOOMN 100MNNE IOOMNE 1OOMENE 100M E 100MESE I00MSE OOM SSE l00M S looM SSW lOO0MWSW 100MW 1O0MWNW 100MNW 100MNNW 200MN 200MNNE 200MNE 200MEME 200MB 200MESE 20OM SE 200M SSR 200M S 20OMSSW 200M SW 200.
200M Prpared by:
RebM Reviewed by: -,102
ýDIST
- RIDENT, ISCT WSW W
WNW NW NNW 300.
300M N
NNE NE E
WNW NW NNW 400.
400M N
NNE NE B
E ESE SB KPRT 1.0
'0
- 0,
.0
- 0 "0!
0 0o 0
"0
!0; 0'0 O0
'9 0VALOC 0
0
%0 0
- 0
.0.
.0 0
o*0 0
0',
0
- 0 "0.
Attahment A HTERN
ýRC NVWMDt 12.19 0
0.
00 '.
0.: o,
- o:"::
0." ::..
A000 0
0 00Ooz0
'0',.
0 001. :
0i:,.
0.00
- 0.
0..
6.10.,0.
0.0 18.29, 0
0.
-18.29 "OA 0-18.29 9
Q 30.48
- 0.
0.
2.67.
- 0.
O..*I'll 48.77:0 0.
- 60.96
- 0.
0..
60:.906
- 0.
0.
24.38~0 0.00' 0.
0.,
0.00
- 0.
0.
0.00
- 0.
0.il 30As
- 0.
0.
36.58
- 0.
0' 30.48
- 0.
0 36.58
- 0.
0 48.77 0.
7315S
- 0.
0.'
VSLOOE VOIST DESCR 200M WSW 200MW 200M WNW 200MNW 200MNNW 300MN 30OMNNE 30OMNE 300M ENE 300ME 300M ESE 30OMSE 300MSSE 300MS 300M SSW 30OM SW 300MWSW 300MW 300M WNW 300MNW 30OM NNW 400MN 400MNNB 400M NE 400MENE 400ME 460M ESE 400MSB
- 0. ""
YRC-1 1781 PMe A19 Prpcp"~ by:
RUwim Rvee b:
~
h Reiewed by: ZM WL
_Attachment A.
EXHIBT A-5
-YRGi;8agA2 DIST RIDENT 500.
soOM ISCT KPRT IVAU)C HThN
- RCF
-179.25 0.
SSW 91.44 -0.
SW-9.44 0.
Wsw-2438 0.
W0.00 0.
W-VNWý 0.00 0.
NW 6.10 0.
tNNW 0.00 0.
N 0.00 0.
- NNE, 48.77 0.
~14E48.77 0.
"ENE 60.96 0.
S.73.115 10.
~ESE73.15
- 0.
SE 103.63 0.
SSE 1s.o 0.
S 9121.92 0.
SSW.
128.02 0.
, _WSW, 24.38 ~0.
W0 0.00 0.
vjWNWý 0
.12.19-: 0.
~NW, 0
30A,. 0.
NNW 0
12.19 0.
0 0.00 0.
ANW 0
67.06~~0 14.50 73.15 0
VW1DTH VSWAPE
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VVIDT.H VSLOPE VDIS" DESCR 600MMENE 600ME 600M ESE 600M SE G00M SSE E0M SW 600M WSW 600MW 600MWNW 600MNW 600MNNW 700MN 700MNNE 700MNE 700MENE 700M WSW 700MW 700MWNW 700MNW 700MNNW S00MN S00MNNE S0OMNE 0OM sw 800MW 300MNNW 900MN 900MNNE 0
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00 doo00DN s00N 4.2053-09 1.1055-08 2.4893-01 1.7539-03 7.7983-09 5.2793-09 8.7163-09 1.3303-08 4.3273-08 5.1163-08 1.2363-01 1.5763-09 9.1303-10 1.0221-09 1.4073-09 2.2753-09 3.4163-09 1.2441-08 2.3593-00 2.1943-08 1.0903-01 6.1841-09 9.1623-09 1.?703-01 S.7811-01 2.6303-08 1.3661-09 7.729R-10 9.5593-10 1.5523-09 2.0143-09 2.9181-09 1.2903-08 2.3853-00 2.2982-0S 1.3321-03 8.0143-09 9.3132-09 1.3343-oS
.0003.00
.0003.00 2.0113-08
- 1. 219-09
- 9. 0505-10 1.8863-09 2.670Z-09 2.2232-09 7001
- 2. 5443-09 1.2302-08 2.4263-08 2.1113-04
.0003.00
.0003.00
.0003.00
.000..00 S0003.00 0003.00
.0003.00 1.093-09 1.4573-09 4.5743-09 5.1248-09 3.1573-09 s00n 2.5443-09 1.543-08 2.3563-08
.000+.00
.0003#00
.0003*00
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.0009.00
.0003+00 4.5343-09 2.0118.0249-09
.0003.00
. ~.030
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.0003+00 0002+00
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'5%
00 "ii.qi3O0 O ANALYSTS #If##
DECAY jA.
7-E I
7767 7C F~ -j'K, a FI
-AZi 13 14 77W
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1.
412 133 1.46 36;:,"*ii',ý
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XR4N XE4-36in, XEA138 XE%13*n AR.37 1.135 PART)OJLTE S;R-SI SR90-CS-i34 ftM.A.146 TTE-13t4 W3-24 HALF LIFE LAMBA (YRS) 1.07.E*01 447E.0 5.019E.04 1.3B16E03 i.445E.04 4797E.03 1183E.04 2.178&03 1.443E.32 4.6046,01 1.04W6-03 6.6336*02 2.955E.05 2.322E#04 2.710G05 2.1571.04 6.I66E-03 1.120E42 9.582E.02 7.233E600 2.06E-04 3.320E*03 537064-3 1.2106.04 3274E-02 2.1176E01
&3.08 2.060E*04 2.207E.02 1141E601 2,37X6-03 2.921E*02 7.643E.04 9.069E*02 1.391E.01 4,964E*00 2.6906-01 2.300E-02 2.000&00 3*e3=,,0 1020C-01 2.295E.02 4.569E.03 1.SI*0+62 1672E.01 1.0 E095.0 1.9*5E.01 3546*5.0 525215-00 1.3166.0 1.232E.01
&020C00 7.611E-02 9107E.*00 1.730.01 18665-00 1006".-2 7,783&.00 7.7*
6
.1I902E1 1.648.01 4206*00 19279E.01 1.001E.*0 1296E.01 2.103E+00 7.596.03 9.123E*01 1.090E.01 0.36E1600 2.7JOEO00 2.53.01 169660 7.19*M 1.2335.01 5.622902 two wie uw'A o.7e.yr 4.40 IV 2.70 fr 527 di 9.16 tv 1.70 oM 14.20 m 2.26 di 35.00do 1.83 hr 11.96 dai.
17.70 innl A00 da~
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&.26 yr 27.60 df 65.50 do 32.53 ft 264.40 di SM20do.
3100 da 25&009 120L40 di, 7100 twy QZ3 ~r~.
'fiuQUM L SKt 0t
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_____GASEOU I&RELEAS SSE-UMMARY 11" 7 S,0L'CONCENTRA
~jfON JSI.
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'24 XE.71 35 00006.00 aooxE.0 26 XE-138 00006.-00 0-OnOD0 26 XE=-133m 4.850.29 0'00060 27 AR37 78996.20 0.006t,00 28 AR.41 O-OOOE00 OiE.MM*06 29 C-14 5,§S096!0 2.017E+00
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- 38-AA-35 0.0006.08 60OtXE4.0 G~.00E; 000,ob06.0
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IM.26 1.539M4
~75.261 364 1962
- -44, Cs-14 135.0 0
- OE#00~35 1107E4O1 1296.0 45
-C&+/-137 3.427E-05 6.720E.07 VW3494E.63,071E.0 128bb 2____
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-47, ZN 212156.09 00006.-00 2 2156409 1.9476.,04 ~ 160 40 005 1553E.13 OODDE001 1tS563t.1 \\l.656.6 7*.11
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- 1931E.35 '3 455E.W i14406.32 62 ZR-N&995 4.730E.20 0.DE08.
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.28 C-i4d 30-01 176-05 5526.05 6316-01 2,4156-01 2.97E-02 315E-02 2 9 X E.
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W WI YRC-1178. REV. 0 Pap A-4UE ESTIMATED ANNUAL RELEASES (UNDECAYED CURIES)
! TOM bdimad 196.97 16 99 1970 61.72%
6.06E,01
.721-01 1.t7E-01 1.20=*00 4.80E300 041%
4.57E.03 4.4MG-1.25E.03 8 00E0 3,20E402 0.41C 4.5716M 4 4814603 1.25E.0 8 00E-03 120E-02 Q.00% 6.Ua-03": 672E-0 1.67E-03 1.20E.02 4.80E-02 2.08%
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REF(.,RTED ANNUAL RELEASES (UNDECAYED CURIES) 12' 131 RAD ONuCLIDE 1972 187-3 194 875ý17 97 1976
'.14 165 I.'FISSION GASE 17 KR4S 16.8E00 2 55E.01 1.4E00 2.71E*00 7.49E-02 1.30E*00 7.56E*00 K13.1456.03 1..525.01
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3 7.11E-04 1.676,03 2.55E.05 4.4E-05
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AR-37 2.17E10 4.13E.101 598101 1261.01I L50-.0 1.23E101 3.77.00 570E-01 27 AR-41 121E0 919E.01 1.331.0 113E+00 1711.00 2.43E0 ISI&100 3.61E-01 23 C-4 2.6-E01 1.501.01 4.71.01 1.241W00 4.31E-01
.101+00 1.53-00 6.&56101 23 XE-131M 121E*00 1.05E+M0 1.16.00 2.341E4 9.01E00
.t.TE*01 1.35E+01 4.26.00 30 Rb-G 0001.00 000100
.000100.0E01 0.001E00 000.0E0 31 32 UNIDENTFI 33 34
- 1. ooicES 36 11131 1.79-0E4 IL32-06 1.6-0E4 2.3E.04 100E-03 6.21E-03
.63E.04 1.09E1O4 36 1-133 7.45105M 4.61E405 4.116-05 1.2415-0 2.991
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1.2601-7 1.021-06 I.62146 1.96E-07 2.721506 4.21E-08 43 CS-134 4.02-06 3.04E-06 7.911E.07 7.511-07
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.0006E+0 0.0006.00 1.266E-47 00006.00 4.5195.29 0.0006.+00 O.0E00E+
0.0006.00 00505.00O M0006.00 1966 11 2.212E*00 O.OOE00 0.0005.00 GkOMC-OD 2.453E-228 O.0006E00 00006.00 0.0006.00 00006.00 1.0066-,
(00006.00 4.2515+00 O.0000E+0 4.431E.155 0.0005.0 8.kO7*
6.725607 0.000500 0.00600 1.260E.12 1.10E-22 0.0*+005 0.0006.00 0.000E.00 2.731E-27 0.0005E00 0000.E00 1722E-27 0.000.E00 0000.E00 0.000.E00 0000.E00 O.00.E00 0.000.E00 0.000-+00 SR-89 SR-90, CS-134 CS-137 a8LA140 ZN-65 CO-58 00-6 FE59S CR-51
- ZRNB-9 CE-141 CE-144 SB-124 MW454 AG-1 10M, SE-75 MOM-9 RU-103 SB-125 TF-132 4.954E+00 2.39RE-02 3.305E-01 2.295E-02 1.510E+02 1.039EC00 15466.00 1.316-01 16266.00 01075000
&1666-+00 7.763E.00 19&025C.01 4.2066.00 166.*01+0 2.103E-+00 9.123E601 12616.00 2.83E.01 7.7O0601
.I-3 1622.02 1.2995.00 s.166E651 0.D00E0 C0006.00 0005.00 O +000050 G0.0E0 0.C00
.ROAWSPA, SIt. LP 2
I REV. 0 Pboe A.12 YEAR 1967 19m6 Ym to 1998 10 9
Nuc*i<e Lambcla KR-85
.440E.02 2.193E.00 I0 8eE*00 KR-85M 1.361E*03 O.000.E00 0000*W00 KR-8W 4.797E.03 0.=0+2.00 0000.E-00 KR46 2.178E*03 0.000E400 000E*00 Ii-133 4.604E.01 1.4442--207 65902.18 XE.135 6.633E202 OOOE*.00 O.O000E00 XE-'135m 2.322E#04 0.0002.0 a0.00020 XE-138 2.567E+04
.000E.00 a0E+00 XE.133m 1.120E+02 0.000E+00 0.000E+00 AR-37 7.2232.00 6100242 4.5992-22 AR-41 3.320E.03 0.000E+.00 G000200 C-14 1.210E-04 41112E00 1.096E200 XE-13in 2.117.+01 0.00200 0.0002+00 RSM8 2.061E+04 0.0002.00 0.0002.00 87
- 91.
1992..
1972-92 TOTAL 6
5 DECAYED TO 01 i01*
1.131 3.141E201 6.314E-142 2.735E.126 1.133 2.921E+02 0.000E200 0.000E200 1-135 9.06*E202 O.000.E00 0.000E+00 S-9 4.964E.00 Q00002.0 0.0002400
,SR-90 2.3W-6.2 7.45S 2.1032M6 CS-14 3+36$E-01 7.728246 7.234*.4 CS.137 2,295E-, M 0.000E*0 0.000-.00 IA-LA-140 1.5102.02 (0.0002.0 0.000240 ZN-5 1 0302.00 0.0E2+.00 0.0002&00 CO-58 3 546E-00 3.722-21 9.626-20 CO-60 i-3182.01 a00002400 0.0002.00 FE 59 56262.00 3.001242 0.0C0020 CR-51 9107E+00 5.5M34 o.O000.0 ZR-NB-95
$.8002.00 6.6012-25 Q000E02.0 CE-141 7.783200 0.0002.0 0.0002.0 CE.144 o.902EV 0.0002.0 o.000200 88124 4,206E400 9.80M-2 0.000240 td4-54
$ 0692.01 0.000240 0.0002.0 S2-75 2.1032400 a00002.0 0.0002.0 140-99 0.1232.01 0.000240 0.0DC-0020 RU-103 63612.00 0.0002.0 0.0WE0020 88-12 2.539E.01 0.0002.0 0.000240 TE-132 T7.902.01 0.0002.0 0.0002400 7.1192E01 1386E.01 1.252E*00 0.00000 3.448E.01 00002E00 0.000E+00
.000E*00
.000E*00 0.000.E00 0.00.E*00
.000E*00 0.0002E00 O0000*00 0.000.E00 0.0002.00 0.000E20 0.000E*00 0.000E400 0.0004E00 3.275C-108 2.104E-145 2.219E-124 0.00E+00 2.219E-124 000.E*00 O0.0002.0 0E.000.000.00E200 0000E200
.00E.00 0.000E00 O0.0000E# O.000.0.X 0.000E2.O0 0,0002E00 0.000E200 0.0002400 0.000E+00 0,000E20 0.000200 000E2+00 4.050E-293 0.0002400 4.850E-293 32--2" 6.666-22 7.922-20 0.000E+00 7.t
-20 0.000E#00 0.000.E00
.0004E*00.000.EO0 0.0002400 1.963E-41 26S90 1 &.794E-1 0.000C00 5909E.01
.0002E.00 0.000E+00
.0004E00 0.0002C00 5.294E.157
.000 0.000 200
.00E.0000 0.0000E00 0.000 00E 6.095E-115 3.M6E-101 3.476247 0.000E+00 3.476E287 0.000E+00 O..000.00 0
O.00C-00 0.0002.0 0.00+00 0.000E200 0X000E+00 0.000E2,.00.000E*00 O.000E.0O 3.79S-26 G0C.0000 O.0002400 0.000E240 1795E-26 5.1014E07
- 3171E-7 U000200 0.0002.00 1.136E-04 2.410E.07 1.640E-7 7.06E24 3.621E-2 3,535246 6.00GE-07 9.027E.07 0.000E.00 O.000.E00 3,427E-05 a0.00000 0.000E,0 O.O0E*000 0-000E00
- 000C02 1.276249 0.326E210 0.0E+00 0.0*- 00o.
2.215.09 1.531E-17 10302.16
.06E-15 1.499*-13 1.563E-13 4.0071E7 1.212E4 0.0a.0E+o o.002.00 2.951E.04 6&47252-3.607E-24 O.000E.00 0.000O00 4,454E-24 1.368-37 3.917E-345 0O0E+0 0 0.0M&00 3 931E-35 4.73-20 0.OE.00 0.000400 0.0002.00 4.7302-20 1.274E3 0.000200 C0.0CW00 O0000400 1.274E-33 5.6144E9 M.0002E.0 0C.0E20 0.0000 5,614E-9 2.01*3,0 4.78W2-19 2292E-19 0.00400 7.279E.19 31,84-100.0002.00 0.0002.00 0.000O400 4.26DE-10 m0.00.0*
000000 0.00200 0.00 0
&067E.15 C0.002 0.0OC-200 O0L0C-00 0.0002400
&0621-26 00.00E' 0.*00040 OO0.00 E
O0.000E20 Q00GE000 0.0001100 a0100E*00 00200EO 0.0002EO0 5.5311-42 0.0002.00 0.002.00 0o.
200- 0L.00024C00 5.934E-0.000 0 0.000EO0 0.000E+00
.0002400 Q0.o0002.
0.0002.00 O.O020 0L.O000.0 O0.00-+W0 1.051E-01 Ths.WAI&U mE. Ls PC 1K3 5.622E.02 0.000E+00 0.000E00
Asl A
+
K fL
'M N
0 P
11 :
Yankee Atomlc Electdrc*Co.
I IYRC 1178. REV. 0 2 TOTAL GASEOUS ELEASES P~re~________jeowA;13 I
7
~
~
ITotal Adt 8
RAIONU~iDE1972
__Total All j.Iby-gr2-29 I.
lFISSION GASES.'
3 4
-Releasýes Ci Ci 9 R4 845-02 IAE-02 7.OOE-03, '1'59E+06 1
t6E-o1 10 KR8M____0.O-4 2OEý-03 3.OOE-03, 5-45E,0 1111 KR-87__
`112 K<R-88' 4ME-03 4.00E4031__
13
)XE-1 33,__
3.38E-O01 6.68E-01 2.33E+00L '7.84E+OOQ 1.12E4+0 141,1' XE-I 35 1___
.23Eý02, 7.11 E-02.
M.OE-1
- 1. 1 MEOO 1.94E+O00____
1, XE-1315M 1%8 XE-138,--
IT XE-I 33M 17.70E-03 6..OOE-01. 4. 1 OE-02' 5AM7-02 I8 AR-37 3,21 E-01 4.65E+00 5.OOE-03 1.51 E+0O 8.49E+OO 19 AR-41 3.35E-02 7.93E-01 7.50E-01 5.20E-02 I,16315+00___-
20 C -14 4.93E-01 1.47E-03 3.OOE-031 4.81 E701,
- 9. Q1, 21 XE-131M 22 Rb-81ZZ 26 11I. IODINES 21 1-131
- 4.
-5' 1,.73E-04 2IE0
~28 1-133
'29 1-135 31 111. PARTICULATES 32 33 SR-89____
34 SR-90 I_
______Q
_1_
E_06 6.00E-G61 35 CS-134 36 CS-I137 0___
O-8
-2OE-06 37 BA-LA-140
~38 ZN-85N 39 CO-58
.8.OOE-O6 2,50E-05 3.30E-05 40 CO-80
.2.50E-05 7.70E-05 I1.02E-04 41 F E -5 9'1____
1.OOE-06 1.OOE..06 42 CR-5I1___
43 ZR-NB-95 44
~CE-141 45
~CE-144 46 SB-124 47
.. MN-54.
9.OOE-08 3.1 OE-05 4.OOE-05 48' AG-1I OM
__3._
3OOE-06 8MOE-O6 l;IOE-05ý so~
$1 RU-I 03 62 SB-125 53 TE-1 32__
~54 UNIDENTIFIED 8A6 H3 2.66E+06 1 65.0
.0E-04 4-.52E+OOl 8.83E+00 7
AR Q
R 7Y7]ý 1", T T
U
-v x
-V W
- i I Ynnkee AtnmIe~ EI~r.C~n YRC 11l:178.REV: 0 T',2 "TOT AL GASEOUS RELESES-'
R s"
E L EA.
n S..
Total ACtL.
i_:_
4 Release Ci Ci....u...
,..-., * *Tots:1973 To al All'.
- y. rou ILTIS8iON'GASES 1
\\
23 4
'.R lea6ses,. Cij"
- Gi*:
'8 9
iKR85 1.__..
81E-02 4.63E-02 1,::,91E-Ol, 1.55E&60t1_._.
10
.KR-85M 4.49E-02 3,24E-02 7148E-02
".52E-01
.11' KR-8 "12 KR-88 2.41E02
.06E-02 2,3E-02" 7,84E.2" t3..
.X"E-133; 1i.17E+01 1.38E+01 L07E100 3.34E,01
.14.XE3351 286E.O0 2.71E+O.9.501
.52E,00 1 5..,
XE;135M 1
.6 4, 147.
XE-33M
.90E02 55.91,E02..
781E02
'18 4 AR-37..
35E
-03,.4E--E02 4,33E 02 6.60E*02 1
AR-41
____2.45E+O06 5' 1 E71 30115+06
- 20'.,
- C '4.: :.
1....
ICE1.34E-02
- 3. E-03 1i8Ez1 i.95E-0 2-1 XE-131M
.- 50E-03.488E6-02 1.498E02
.41E-02......
24 UNIDENTIFIED-.
25T 26
- 11. IODINES
- 27 ""
.311 43E04
.24IE03 7.11 E-04 2.69E-03 28~
E-043 t2__
',',03-
-l-_
-32f
'29 35 1
":.33. ::*:.: SR -89.
3
.24E07.
1 s54&E06
- 35s, C-68341 4.OOE-08 36 C-X3;___
,I.'O[E-06 5:90E-07 I.9E-'06 3.55E-06 37 A-LA-I 40
,38, N____
OEO
-06 I.
E-06 39 CO-.58 200E-06 4.OOE-+06 5.1.0EO
.:A60E-*07, 6.97E-06
'40 CO-60
- .1 E-05 9.30E-05 1.56EO5, iý5 29EE05L 1.83E-04 41 FE-591 42 CR-51--
-4 R N
-9 4
CE-141i 4
CE-144-
~
~
46' SB.ý124:'-_
4M 7.00E 06 *2.10E-05,.2.59E-06,,7.i E-06 3.78E-05,
- 48.
AG-1IlOM-
-. 0~8 50-6 54EO 1.0-0 03E7'04
-49,,
SE-TS 1 -GI.OE-08 1.00E 06~
2.GOE-06
,6~ MO-99 H-.
'51.
RU-I 03-i 52 SB-125 53_
'TE8,132__
54:*
- _U7INIDENTIFIED
',".AL.. '
,ZIII 5,00E+00 2-.23E+00
.9:20E-6f0 2.*4,E-O1r
.8:39E+00
A-53
,A, Z
A B
I.ý
.. *',AD AE I
AF I
AG I
AH Z
-Yantkee!Atomic Electric Co'.
I YRC 1178.,REV. 0
-Pihe*A-IS
.1 (ril L71-75.Wk3 t~~~~~
7 I.FISSIONIGASE 1
'2 3
4 Rlae i
C 9
KR85"___36E0 8;97E-O 1A'51 T&EOfl 3-84E,02 1.48E,+00 106 KR'85M
.9.0-04, 4.76E'-4 4.2E0
.2-2_.50E 02 11 KR-;87
, 9.90E 01' t.OE-Mf3 1.59E-0' 12, KR-88 I.80E4 i'80E-0*ý4 15.8E-02
.906E702.
8.888,02.
13
ýXE-1 33,
-66E0O.47E+O01'2 7.'73E-01T 2.1E+,0O 6',07E 0i 14 XE-,135,
_____21;E-01 1 tO3EZ'01 129E' 11S46 15
ýXE-135M I.
.88E-4.4.30&-04
&4SE-044__
1S XE-1 38' I.'64'E,04:
3.7 Ei04 5.41E-04, 17
'XEI-133M
-.I.04E-02
- 2.74E-062 3.785402____
18 AR 37-6.ýIBE-'03 4'2SE4-1 "-0E0 1.8E0 5.01 E,0~1 19
_ A 41______
3.6E~O
'3E02' 68 0E-1
-1.76-O 8.50OE T.
- 20.
R-41i 3 7.78E-
ý03
';38-l35E0' 2.76EO
- 7-0 21 ~ ~
~
~
~
~
6
'01,
.5-3~t4~2 207-2____
231'
'24,
'UNIDENTIFIED
'26:
11' IODINES
'27
.1-131 1 O-05 <588E"-' 4-5 1'E-05 tw60-0&
'7.I1E-0 28, 1-133 3.03E-5
.2.92E--5 2.8E0 2.8E64 29 1135 4,.,38E-5 3.40E-0 3.84E4 3067
`6380 3111 III. PARTIJCU L'TS___
32:1
~7 f77 34:
__3.78E-08 3.0O&0E-8 6.0-5 6.1E 35' CS-1 34 8.70E-07~ 1.4ME08 460E0 1_373 E-0 X3:
CS-1 37 3E-630E0 2E-7.4E7 1.1 E05, 37 B3E-06 ;40E-`06'.
6-
-AO I IS&
39~'
iO5
____1.94E-08
-8.'O0E045 3E041.9E0 z4E0
- 40.
Clo-e
'2.57E-~05
'2.0IE-O3
'9.16E.051 ý44:5E-05 6 8-3___
41~
E F59=
42 CR-51
'5 E-04
,.bE-4 43__
ZR-NB-95, k
3,I0OE-07, 8:8E-07 118-6_
S~~CE 144%-ý
-~__
46, SB-~124-8.'-
70E-081 3.20E 07 4.07E-07
'A47 MN-54'-
2.77E-06
ý-2.95E-04 8.60E-051 12M3E-05 4.08E7:04 48' AG-110M
-2.6Q&Or5
'i,.-20EO 0E-06
-49>'
S-5 s0 MO-99
'52 SBE125' 53'
>TE-1 32'.-
54
'UNIDENTIFIEED I 144E-06] 1.18E-06 2;62E-06.
E0 66 2.87E01, -1' 36E~4,O0 I.84E+'003 1.56E841 3.84E40
IAlI All AJ_:
ýYankee Atb'mic'Electric Co...
~777 YRC..
1178. REV..
-4
ý2
ý.CONTINUOUS GASEOUS.RELEASES'(tCurks-b)-.--.
Ra__
ge-6
'1175:t
- Total. All ygr p
,7j.:FISSIONl GASES 1_1~3_
- 3.
4,
RlaeCi{Ci 94 R8
.2.205102 1.97E,'02
-'08E.-03 A.78E-r'02.
1, KR-85M 1'60Eý.02
&3.50-O 45E2
.54E0 1.0E0j J
11 KR487 I.E-223E-23.42E&021I.1E-02 83E-M&
- 12.
KR-88 2
E-02 "'&.3.08402 :6.66E-02 I 48Eý-02 1:.55 1
13,,
'XE-i 33 2)0OEt00 5.OE*O0.3.72E+00 I
,ý.,29E+OO 1.2 E'O1' 14 E1 35'.:
-ý
.50-01, 6.OOErOf 6.67&-01 13E0
.5+0___
15Iýi XE-135M' S-Z iIOE-0417,40E-01 611E-01Y93~0
.5+0____
'1"'XE-i I8 U.
1.10&E02 4,34E-02Z 'l.5E-ý03:
';81'E-02 17 XE-133M 2.iE-O72~ ~6.80E-'02 5.46IE-2 31,9&E-02, 1.7,6E 20 C-1A45 7.0-035.0E-O3 I.24&-05 1 N6EI0 1:.56E-0 21~~0 XE-91 4___
__31_
22; b-8 6.5OE02.~I.0E-'1
.02-01 8.4E02, 4
-:01" 24 UNDETIIE 2T5 I.- IODNES 16.73E,63 1;1jE 27 1-31 580E-5i'20El01' 1.145-0 4.6E-0
'7E02 8
113 ____
..8.0E-02 j 2.20E-04l 4.05En-04T 0.2E-5 84E 29'113 "29EQ 75E0
.6~6 t7-4 34 SR9
.0-04 0-847E0 22E0
.8-7____
35 CS-i34.80E 4.72E-061
- 8,42E 04 40 CO80__05_
.80710 4.0-0 IE405 4.188E166 t3EZ 3 A3 R-B9 7-0.'
.03E 64
-.4iE-0 SBý C-12
'W0.
2.6E0
.Ei570105'1.9E-a5 a59'E-03 471 MN-5 84E01OO-512E05 9j 1A2EEZ04 I.92E&04____
~42 CR-751
-1.8~'2 2E-06 9.289E-04
- 9.. 012E-IN 431 ZRU-10 7'7
,'10E 42 SB-125 53:
TIC-132 4T JH-3
143-1"'
5-4E01 1.-04E-051,627E¶.04 1;.9E.-04
~
jq~3-A A
B C
D IE 172 fn*kee"e' Atomic ElectricCo 1
L. ;::j 171 Total Continuous 4 Batch Releases(Cnies)
LXK~i H
A-178 66A-i 7 f
~174,`
__1._____
(tiWeG76-80.WVK3, S~
~176~
f
~176~ ____1___
9761 T
MUtlI TotWA~t:1 177T k FISSION "GASES i
2~
3
~
~
~
~
ib~oi 179 KR-851-1,36E-03 2.46E;102 3.31 E-02 1.58E-02 7.49E-.02,____
180 MO-8M 9M0OE-O3 5.80OE 02L 9.37E-02
ý937E-02 0256.1' __
11 K-7____437Th-035bE~2A1E0-.37-E-02 1.6615-0Y, 182 KR~8 122E02 i.25-iC2E41 :13E0~3E-01 183& XEi3
"'E0
~5400 8,96E4:00 ~6153E0 4I+1____
184' X-3 1.38E--61 5,27E601. 1~4E0 12E 01 L AE0 18AX.354 1.36E-01 1.19E-01' 3.86E-01 "5.59E-01
.1.Z21E+0 18Z&.13 2.46IE-03 8`62E-03 9.:8 3E- -
04, A.38E-02
-2.S9E4-02 188
..37 873-2'15-TS O1 8.04E-03
'-2681-42 4834-61__
189 AR4-Al 065IEi2 5428-40Z 15.6E-0, J9;27&E-02
- .W!E-01 190
'1.2E0 1:1EOt 1,'4.06E-03 25.60E-0.3 1:2E0 19tX-13M____
3.47E-02
'3.47E-02___
119 Rb-881
_-49E02
.15 01
- 5.
-01' 4.9,4E-01~ 1.25E4-00____
193. -
194 VNIDENTI FIED___
f-95
.1E0 196 11I. 1IODINES 197 1-131 1
____i0E0 3-51.4-6I.29E-05 Z55E-05 198 1-1331 1.24E-05 620E506, 4-.35E,061 2.58E405 4.84E-05
~199, 1-1354
______35E&05
- B03E-.06 (3',7AS3E0 2i97E-05 64~26,05 2 0 1 I. PARTICUL1ATES 202:
~____
203 SR-89 204 1SR-gO Z
~
83&~08 L, '21 IE-08 1205 CS71 34U___
4.266-,071 :.3'20E-08
- .`58E-L07~
206 C-137
- 7-0 T.OE&07.
'2l-58E-07 4"M664-7 207
`BA..tA4,,40'-'
208.
Z.
4-6 209 0O-58
'6.47E-07 3.1OE4!07L 6.14E,!07 2.47E-07 1.82E-06 210
_co-6o 3.OE-06 1.84E;06 i4.31 E-06 1-.93E-07 9i44E-08 211 FE-591ZI1 9.410 g~E-:08
- 1. 18E-06' 4.19E-07 1187E-06 1/42112;
-,:CR-51 7.78E-07:
-213ý7
- xZR-.NB-95 45E0' I
4:54Eý0 214 TCE-141 S215
'CE-l 44
~216>
~SB-124 8.35E-08 9,1-3E-08 14.75E-07
~217~<
MN~54162E-08
___'-~5.10&-07,
ý- 5A46E-07 7218 "-L :L<,AG-110M 38E071 1709E08-
~ 5E
~921 9>
E7 7I K 220O,-
ý,W 0-~9 9 221'1/4 RU-103____
222 SB-125
-. 223'.~ :UNIDENTIFIED ----
~225~
~______ _______
1.75E-05, 226-3 j-S.5.7E -02j ý4`74IE-O 01 926E!01l "5.63IE-0,1 20E0
A J
I K
I L
M N
0 P
Q R
172 Yankee Atomic Electric Co YRC-1178 173 Total Continuous + Batch Reles_ (Cties Page A-18 174 Mre G76-80.WK3 175 176 1977 Total All Total Act 177 I. FISSION GASES 1
2 3
4 Releases Cib group 178 IZ 1__
Cl 179 KR-85 8.28E-02 1.03E+00 1.46E-02 1.75E-01 1.30E÷00 180 KR-85M 1.33E-01 1.09E-01 1.03E-01 7.01E-01 1.05E+00 181 KR-87 7.47E-02 9.51E-02 6.16E-02 2.79E-01 5.10E-01 182 KR-88 I.83E-01 1.41E-01 1.48E-01 9.26E-01 1.40E+00 183 XE-133 1.08E+01 1.87E.+01 6.01E+00 6.25E+01 9.78E+01 184 XE-135 1.84E+00 1.41E+00 1.54E+00 8.90E+00 1.37E+01 115 XE-135M 8.37E-01 5.44E-01 1.09E+00 2.20E+00, 4.67E÷00 186 XE-138 8.64E-03 2.405-02 1.15E-03 2.43E-02 5.81E-02_
187 XE-133M 1.83E-01 1.07E-01 126E-01 1.01E+00 1.43E+00:
188 AR-37 7.055-02 8.54E-01 2.66E-03 1.35E-02 9.41E-01 189 AR-41 1.78E-01 2.15E-01 2.89E-02 6.44E-02 4.86E-01 190 C-14 3.74E-03 2.28E-01 1.86E-03 5.85E-03 2.39E-01 191 XE-131M 9.03E-02 1.20E-01 3.17E-02 3.78E-01 6.20E-01 192 Rb-88
.3.24E-01 3.60E-01 6.84E-01 193 194 UNIDENTIFIED 195 1
1.25E+02 196 II. IODINES 197 1-131 2.21E-06 2.60E-05 2.12E-05 "4.94E-05 198 1-133 2.29E-05 4.445-05 6.73E-05 199 1-135 2.62E-05 2.85E-05 5.47E-05 200 1.71E-04 201 III. PARTICULATES 202 203 SR-89
" 1.5_E-0 204 SR-g0 1.56E-08
-1.5E-08 205 CS-134
-_-_1.15E-07 1.15E-07 206 CS-137 2.18E-07 1.43E-07 2.19E-07 1.32E-07 7.12E-07 207 BA-LA-I 40 208 ZN-65..
209 CO-58 2.79E-07 2.79E-07 210 CO-60 2.20E-07 2.20E-07i 211 FE-51 1.55E-07 1.81E-07 3.36E-07 212 CR-51 213 ZR-NB-g5 "2
2.18E-07 2.18E-07 214 CE-141 2
0-7 2.16E-07 215 CE-144 7.98E-07 7.98E-07 216 88-124 217 MN-54 218 AG-110M 1.72E-07 2.03E-07 3.75E-07 219 8E-7 z
220 MO-99 221 RU-103 222 S-125 223
~_
224 UNIDENTIFIED 225 1
3.28E-06 226 1"4-3 1.55E+00 2.145-01 4.91E-01 1.01E+00 3"27E+]
0
AS'7 I....................
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S
.1 T
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~U I., V WI X
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I Total Cohtin*ous + Batch Rblea ses (C ui:.as)
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G,68-OWK3 3
R*
.ea.ses Ci by I
1[*.
77 I
i.: FISSION:GASES 1
14786 F.
- CV I
IODINES 1__131 7.SOE-05 1.711 1-133 1011__
1-135__
31.79E-05 1.341 PARTICULA~
__777 i 11
~
1-I:3E-07 1.85 8.16E-07 1.08 2.38E-06 8* 75 140.1
-ý~70-,6E-0&1 F5.3
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L*i RA8 AU
- AD:
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,AF AG, AH' At'.
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lies Toa otnou ac elae Cre YRC-11,78
'Pagie'A,2O0
~iZ4Zll~F7T I1
~
i~~eG&8F-~
-7,,
'I. FISSIONZGASE5Sý Z-3 e
e9s Al
- KR-95 5.24E,;a2T;11t4E+OO 7.38&,02 ~3.72E-01
.6E+O____
KR,-85M 2.5SIE-01 5.8!E-01 >5.50&01' ~3.10E-01 i'.'60E+O KIR447
____1.5 14;97E-01 4.29E-01 2.'77E-01 1.:368+6o____
K88____3.49E-,O1 '94SE-01
>7:36E-01',
4.97E-0O1
.,2.52E40O XE13 402*O 13015-O
~4.4IE O t
'-1lI2E+Oil 1.17E+02 XE4135%
_______3.'14E+O
.8.58E+OO0 -8 53E4.O0
'527E+00,
.65E+64
,XE-i5M!
1.8EO fl'ý&6.8E.OO.7.54E+O.
5.81 E+00 2.21E+01 XEI 8_____3.49E,,02 2.42E-01 3:'15E-01, -ý I.56E-01 7.48E-61 XEJ133W 4.61 E-01 3'.67E-01 7.58E-01 2.78E-01 1.86E4+00 AR-37, 1.61 E+00 5i.69E-02 3.79E-'Oi 1.25E-01 2.17E+00 AR 41 7.36E7011, ~2M3E7O1 2.36E!Ol -1.00E+00
~2.21E4tOG
<C 1.4`.
TSM4___7:7E01 lV.ý32E401 6.17E;02, 1~4,E,701 2.8E
-X E 1 M
____2.28E+O 3.8-O 1.79E01 4.3El 13.2IE+OO_____
UNIDENTIFIED__
- I.B2F+02
_ 1.40E-04 2.5E;O8 3.11E4051 SE l1E0*
.:48E-0 3ý54E:O
.-M 3ELO5 A:7o B.
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3.1'E-105: '53.51E-5 1.28E4O5
.-51'E-O6 1.'03E-04'____
3.'54E-0,4:
ýULATES I.5.3E.;07
.7E'0
.2
-7 4.2-6 ___
5.39E-0 311E06
-I.29E-05 2:20E-05_____
3.4E'.7 3.49E-07
- +
4
---II t~~-Xh1777I....I____
7'~fl~fl5.
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1-
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- R*;4i*ITR VRC:-i 178 13 Total Continuous Batci Releases.(Cues..
Page A21 1
M (f ',G76-60W 3)
I*L _________1 1980 Total-All A
TotalA*ct "177 IL FISSIONGASES:
2 4
Release.s b-r.Ou.
- 178, Ci 179,
A.KR-85 1
&51E-021 9.28E-03 1.19E+00
,.22E-02 l.23E+00 180.
".A,.
1W80 KR85MR.
1.21zE-0..
.__6,:24E-.41`
- 7 45E-0 181 KR-47.
1-.09E 4 6 l
-6;2E4r:
-7.112-0_...
182 KR-88 I,.722-01 1.09E+00 1.26E+00' 183 XE-133 0_
.1E+01 2.38E-05+
221E+0, 3`22E501 184 XE-135 22,1E00 I :08E+01.30E+01i_
18-5 XE-i 35M
,!.-48E+00 I
1.60E+01 185E+01__
186 XE-1,38 4.79E-02 3318E-01 M3.6E-01 187 XE-1,33M 11342&021-.
813E-021 V.47&-02,____
1188J.
AR-37 44_i_-J35,3321 8`I:8E-0i -
'6.2E-03 7333E-02 E413E-01 1,.
AR41
'2_:.E0E 7109E'0p 4
9.U19-01' 190; A
,14 136E;-02 232-E02 -.liOE-01 5*31E-03 "5OE-01
,* 191 XE
........,, 01.
84.87&-05
- 3.36E-01 1.........
1192 rRb88]
E-.
3 16' 19 3 2" 194 UNiDENTIFiED_
195 J____
70E0
-196 II.O IO IES I___
- 17 1-131 E.57E.
6 6.32&065 198
-133.
2E-19,9 1-.135 K-200 6432E-051 K201 Ill. -PARTIC-ULATE S
-- 202"_
203' SR
....506EB408 I 74E07: i -.1 7
-08 3:04E-07 204
205' CS-I34 "___6407E507 5.27E;07 1.91E06.3l.04&E06 C206 137 7.78E-07 7.12E-,07 499E&06, 6.48E--06 '
_207 BA-LA-1'0,-
-'-208
!ZW6Ný8_
i-:209 5
1
-0 7 -78E0 3.08E07 1.28E28 0-606 210 Q0,,80
____1.412-0 1.68-;06 8.75E-.06 1.18E45!
,211 FE-9____
~212, M~fR 51__
1213
-ZR-NB-95,
-14 CE 141, 215ý
-CE1444--
216~ -S137124
-~217
____1.09E-06 1.83E.;06 5;385Eý06 8.28E-06+
218 2AG-Ib0M
- 219,
, SE751
- 220
~ MO99.----
i.221ý L RU'03 e-.
.222 SB-I 25,____
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... 40E2.06 I.*4i0-06
-223 224 UNIDENTIFIED
- ;226'
....... H-3 7.0~-~"1 3.30E-011 180E 201 2.3*4E-01 1.47E+00....
A A
I B
I> C
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.I 171 Y7ankee-Atomi*El-ctric Cok..
1178 REV. 0 172 Toital Continuous. + Batch,Releases: (C.o. As_
Page'A22.
174' I I II Total Act 1*i75 981 Tbtal -All.
yg ouP t 176 J.FISSION123GAtES'--. 1 3-.
- 4.
Releases Ci Cij 1778:
__85_
18 R-85ý 2.90f..-02 2.70E-01 6.22E+01 1.23E402.
6.53E+0o
- 179, KR-5M'
___6.;95E-01 1.53E-01 2.80E,;01 3.1A5&'01f 1.I.44E+00-__
- 180, KIR87, -
___40 A E-01+ 1i.50E,01
-2.78E;0"l 1.4E' 1
1.,+l
ý'f52E+ý06 181
- XKR188, 20E+00 *2159E-O l'
5.473E.0t 5..54E-0f 2*.48E+O0__
1'82.
X 1:33!.....
.280E+012! i*3.l5E+01
.5 1 S
-0 1'.22E+
,~ ~
~
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-9E 59E
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1983 XE-135, 1.21 E+01 It3.88Eon, '6-95E+00I 7:0SE+06 2."'90E401 XE-135M ~
~
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- 1.
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',4~2E00 9.10E+00 1123E+41' 4.55EO____
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5,E-~0 1.2.1 E001 :2 26E-01 4.61 E-01 I.OE*00.
XE-ia 33m
.42E-1` 4.49E-01l
'I"
.92E-02 8.810OE-0Q ARý-37
____-.~1
~.0:15.25Et-02..4:82E-02
.9E-0 AR-41.......
-6.E59E-041 A
108E-01 365E-01
.2OE-01 I
.33E+00 0C44 1.26E-02! 8:3E-02 3-565E-01
- 562E03, 4.71E
.01 X&E I 31M W._"
6-79E-02 5.91 E-0!
224N E.I*1
- 294E-01 1.18E+00........
UNIDENTIFIE
..E....
-1 OAODINE'Sr 1-;131, 6.03E&05 ":49En05 2Ai1E-05 2.18E-06.
1',*.68E
.04t 1-133 I ~89E-06 4.,42E4,61 61E05____
145--
- 7E05:-
7.76E-05 Ill111.
PARTICULATES 4.29-07 7.03E-07 1.1tOE-"07
-12E06____
- 6-7 07 7
-I 028-06,____
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8;5.1 E-07 "0
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3.53E-06 2.44E;06. t63E&066
-I.6E0
- 3~97E-O7 1 97E'O 5.80E-06 58E0
-95 2:63E-07 2.19Eý07!____
67307 24E0 8E 8.61 &-07. ~9.61E06____
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5 10368BE06 9.23EZ-07
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I YRC-1 178. REV. V 172 Total Continuous + Batch Releases(ues i
PageA "174 Total Ac
- 171
.176 7-1 17!
181 i :181 8.
- FISSION GASES K
1i
',1982:Ii
'Total All by ro
- 2*
.... I
,4.
Releases
_ _ Ci_
S.1.
.1.
1: 67.F'O2 I 82E:-02 I.4*92E-01
":3:62E,,0.1 5:89EM01 KR-8 1... 67I21E.
4'2-0 124 9
XKR-5M 4.485-01:,.6.04E6 7.2 E2-0:1 f8E.-02 1.85E4;00
- 0)
"KR-`87 5..04E-01,6.39*01 9.57E-01
'5.97E-021[
2e, 6E+00 1
KR-88 7.. 78E;0* '12+E00
.140+00 `11.3E-01 13.41EO0 Q 2
XE-133 1.76E201 1.702E+01
- 1. 72E+01: 1.72E+00' 5E.352+01 :
xE-135 06E+00 1.22E+01 1.24E+01 1:.56E+00 3.52E+01 4
XE-135M
.1.55E*+01
.,77E2+01 ý 1.08E401, 2.88E00 4i69E+01 5
XE4138 7.28E-01
.1068+00 %2.38E+00 3.23E-O3W 4.17E+00 6' :
XE-i 33M J877E0 2 3 9E5D 8
-072-01 9.27E2-D01:
7 AR737
.16E402, *l37E-01
."68E-*1 4.96E-02" 8 262-01 8
AR-41 3.746041
-6.4-3E0*-1,07E+00 4.23E0,2 2*43E2+00 C-1 4 8
142E+00, 8.82E'02 1.24E+00 0
'XE31M 9.19E604'1 1."33E+00, 6.41E-02 2.40E02, 2.34E;00 3.
UNIDENTIFIED 4
1.___.
1,55E+02 5-:II. :IODINES*
- 6.
1 2.44E204 31:94E-05
.283E-m0 7
-'133 4.99E-05
-:31, 4499E`05_
-3 1
.7...05...1.
- 78. 2-tBE05 3_5___E __
3`.5j2&04' 0 :II1 PARTICULATES, 12:t
+
SR-89 1.28E-05, *
- ,1.2.2-0...__'2E_0 3
,SR0_,,
1*,S4E-G6
'8.16E'08 1.622-06 4 `
CS-134 7.51E07, 75.512E07-5:
.2:31204 1.69E-07:
2.312-04S 6
"BA-.A140
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CO-58 3.96.,06 2.39E-06 6.352E-06 9
COý60 1720 1720 0
E-59
.i
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`
- 1. 69'E06 i
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9.49E..
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- SB-124 6".
M54-8.32E-07 :967E-07 :,190E06
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MO-99 2-.1003-
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7-H-3
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I.-
S I
U. "I V IRY C1,t78, REV.
Yankee Atomic Electc Co.
I.
I I I I II IUIII Total Continuous +- ;Batch Release.s (Cun as' Pa.ie A-24
- 4
- ,T'. tai; 'Ct'.
1983 b___Ttal-,All b yqroup I. F.ISSION GASES:
- 1 2:
-,"r
=
4 Releases Ci Ci
."i
.R 616
- ,C i.*::
KR-85 1
i25E-02: 1 j30E-O1 6,'58E-0I-1.'78E-01
.179E-'0i KR405M 9Q72E-01 1:32E+00 2.37E+00 3.60E+O0 8.26Ei00
`1
.KR-87 812E-0 11"*,E00,
'253E+/-00.4i26E400 -.
- 79EO00,
-.R-88 1.5E+00
.2:1,3E+0' 3*9E+00 6.18E,00 3.038E+01" 3.E XE61133':
3654E8+01 6.98E+0*. *29E402 132E8+02 4t66E+02 XE-*135.,
- 1.66E+01 280Et0l r 4.50E01 5.75IE*01 1.47E+02 XE JI35M 72.61 E+0901* TI3M2E
`1.51E+I 08
ý.'8E01: 2.01 E02 XE138i "1.56E05 a
6Z08EI01. -2.'1194E+00ý
-46E4O00' 7.33E+00 XE4133M
- 322E-01 9t62E6-0,1
.4167E54.00 239E+02
.3E00 AR437 5.58E-02
-1 06E+00 5.2.4E+, 00: 1 48,ý-01
.50E+00_
AR-41
..... 2.31E01 1.81E-01 5.0E-01
""7+93E-01
- .11E,00.....
. 14.-..
__5.39E-03 f104E.01 :2.44E;01774E-02 2
.43EE-01.__.._._
- ,.XE-i311M
_ : 3..1OE-02 2.O2*IE-0*1
!8.7*8E+0 9.01E+00____
UNIDENTIFIED" 1' IODINES E
1 131 75E-5ý
- 2;49E-04 2:60E-O3 ".91E-04 3.09E-03 1-i331, _:
ý8152E.05
- ,.38E&-
';8.62E6'404
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- 1.
i:*24E-03*
1-135 i
1.1t8E04 I' 321E-O4
.150E3'3
.13E"04 2,05E-03.......
_ _:_6.
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Ill. PARTICULATES SR-89 2:
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- E17,
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~FE-54 A__
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- =2 24E 0,7 '*2 57E 086.*'6 03E -07 4,'i:
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,71, " IYankee;Atomic Electric CO.,
L -
172,*T~otal Continuous + Batch Releases, (Cutes YRCý- 1178 REV. 0 Page'A -25 173:
[
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174
-Tbtal dt
- 175, T.
.6C
,-,otAl TO I. FISSION GASES j1 2
3 4
ReleaSes Ci 177
- -1,78,
- 2.34E*00.1oi2E00 1.38E+00 7.32E-02 1
792E+O0 "1,79 KR-85M
,i5.24E*00
'9,38E-014'481E+O0
.5693E+0 01.79E+0I M80 KR-87 1 '6.02E+O01 76E06E 3:53E400', 6'*50E+0
,1*8E 1,
1 181 "
KR88 9.33E+,00.',i35E500 5.105'.E0O I.0 11E+tOl 2.68E+01 182 XEZ-133 3.3IE+02 156E402' 24E 021 1.1,6E02 2 1.09E03-183' A XE035
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9.'37E+0.
2:29E+01 :85E+0,1
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-184*
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9.87E01'i 2-.,1S*01E C.63'4E0t1 I E311E+,1 2.57E+02 185
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1 9 2 U N I DE N T IFFIE D 194,
1.74E 0.3 2195 ILI IODINESI___
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- 1. IE-04,Z..223EiO4
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- 1580E-56 E044 13*02E-6 4
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199
____9.72E-03;
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- .i-202
SRz89 OE*0 07 SOT.
8.`:81 E-07t -1.1lE,0 I,25E-O&5_.
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2.54E08
-265E-06 2.72E.7
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I34 27E-0: ;:2.~E-0i :-6.35E-07*
8.'3: 1Er8'72Eý05,
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C -137 1.19E0
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- 92E-05 1
9-ý53E 5r' 206" B A;LIA-140r r 7.93E.`06 79E06.
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9.54E-07 2.27E-07 IZ 8E-
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216 MN-54 2.13E-06 9.29E-07 4'.17E-06 '.275E,06 :9.,98E-0-6
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- 7. OSEfl I fAF1lf 143 TNE____ 4_____
¶gF0ll JA'fll 4-0 45F:+fl
4qGq
ý,,AK I
- 11. AM I
AN.
- AR AS
-t
-I.-
- YankeeAtomic Electric*.C0Co:
YRC-11,78. :REV. 0 j1.TotdI'Corhtinuousý- +BW tiReIea~seds,(ci63s).YI
~
PgA2 I
(f-Ge81 -85.WK3V FSSONGASES 1
1'985ý y____1i*__
oa
~___
___TdtaI-Allbif
.....2.
3
- i.
K Releases Ci
'Ci 178 KR-8S ME-02
.1-1 A.2E0
- 1.
OE*.1 1.13EtOlt 179
%R8M6;81,Eo 0U7.12E0Ol ~44,1E+00 146E+O0 1.998E+ of 180 KR-7 8:8E40
- .30E-1400 2OE+O
.137EO
- 1. 98E+01I 181' KXR-8 05e 601" I A2E+0,1 ý6i9E+O
--2.-.67E -,00 3.13E+O
~182, XE-133 2.-72IE4+0 2.50E+02:,-l $7E4,,21 241 E+01 9:.38E+02____
183:
.XE-i 35, T____
56E5+0: 7.88E+ 1', 4.42E0
- 74E10O,
- 2.E+02 184 XE9t-i-35M 02E+01, 6.1+1 AE01 2,.03E+O1.
1.9E-02___
I 85 XE-I: 38 5.38E+0O, 4.59E+OO 3',l.,44E+0' I.33IE40O *,
I ý.47E+/-01-_____
XE-I 3M.5.37E+0
.8+O.38
+04.24E+00 1,9; +1 1T AR-37
.690 3,
0E0 19O1 35E0 377OO____
189 1, 498E0 1.86E-`2 ~ 8E'02-1.4,E4*00 1.53E+`00____
19EmI 31W 7.'28E+'0O 4.60E400 3.42E02 "I.54E400 I'M3E+0 191 Rb 8____________
192 7.. UNIDENTIFFIED' W-19s I O IE 19,6 IA1S1 J,-______
.1 4E-091I 4;'65E'06 659E-0 66E04'____
1 9 71 - 3 3 6.,2 0 E -ý O 'S
'.2 0 E - 5 b7 198 115
____--23E0
.5-6____
199 T27E 04 200' "1I1 PARTICULATES,_________
201 IZIZi 202
'%SR-8 203 SR-SO
-08t
.l-0~____
204' C-3 4."19S'.O06 4.1 9EO& ____
205 S~17
.3E-07 1.24E&V 2'.62E,0, 206
'BA-,LA-140
.48E,07
-44E0 207 WN65______
- 208, CO-58%
-32E08
-.2; E`0 r8 209 O
1 64 0
'17.02E-07 I.80Er06 41,95-6____
210+
__1_
~211 CR-5I1
'~-
212
~ZR-NB-95 5.-44E-08 5.44E-08
- x213,
-"C&141+
~~
- --214+
CE-144 2.70EW0
~1'.92E-07 4 462E-,07'___
7-~21-97
-SB-124
'216 +
____I2.25E 07 1~.04E 07 4.63E-08 3.76E-071,____
p217 AGA IIOM 218~h-
.SE-7$_
S219.
-MG-99____
~220'-;
RU7103 22 SBI 125 r____
222 IIE-1 32 223 E 5____
..24~
f
ý
ý r I -ý
ý + -
--.--- 4 -. 1-1.1-i -
.1 i
'I,
I
ý4. -ý 11 226 UNIDENTIFIED II 227:.75E+O,001 1,.33E+'00,
'8.07E-OI 1j 1.28E+00 G
.6E0O
1"06 Yankbee AtomnicElectric CO.-:._____yŽ17~E.0 107 Total C ortiiiou + Batd, R6eleasestCt.=
'Pae-2 105 (file G86-90.WK3 109 Total Act
.110 I RADIONUCLIDE 1r8 Total All by p
ill It FISS**N. GASES.12
.3
.4 Releases Ci di.
11 3 KR8:____49E0 0+03.93E-OZ 4.66E-02 2.84E+'00' 8.g7Fo1 I4 9AF-O'1.
1-71 F+nO.I..13,9E4.00 4A9QE00 KR-8-7 30E-,01
-4.76E-44 1-5E01;.6E+-00
-315E+~06 KR-8 1'38E+00 "823E0 1 9E0 63E0
.~E0 XE133 ~~
~
-O `Y3+11 0E0 7`3 5+0,1-k586+O 6.9E+02 XE-35
.42E+01 -114EA+-0¶,t.60
~2,21 E4011 7.3EJ
.XE-i,35M 1
l.36E+0i1 I 86EO'.i 3.90E+01 2.37E+01 93E XE-i138
___2.17E-01
'8.06,E42, 4.48E-Ot 68.80E-,01 1.43E+06' XE-I 33M 1.47E+00 I.62EiýO0 9.25E-1'. 25E4+00 5.2-78+O0',
AR-37 1.33E-02 5.26E-01 1.68E-02 1A.'3E-102 5 701E-O1 AR__Al 2.98E OSI0EZ'02 Iý,.03E-01
-1fS7E-O1 3461Et1.
________ 131M8E
- 1. 1 56E*VO 9.06E-01 I 2E00' 4f26E+ 0.
_________5.11E+02 1-3 1.07E,061 868E1051 1.18E-04 14.88E-,06 1.80EJ04]____
~L 1-______
3.8E.6 102EO52.91 E-05t 5j210 4&1E0S ]__r VI Si E,O
.1
__________.5E-8
-1.iE06
- 1. 1.4Et-ý06, 3.3-ft, 27E4061 4.89E-08 1.168E706 I.2E6
-"A 2".51E--06 A.,E08 i0EO8
,1.6-4,0
~
~
~
~
_ýý3 8rf l*
A' S
SS I
l~
SS£
- Il oz r--Lmt 4A1
'r; I. I On-u Z.
6r-I--
_____ 95E-09 7.95E-09 1.I36&-07 4.7-7iý7 72 90E 08 7.09ET07..____
9'~83E-01.
9.83E-09 C
129E-05' 8.4-0 522E*.-00T-2.S8E+'00 1, 50E+001 fiM0E+01'
7K1
~
M 0
p Q
fRi 106 YankeeAtomic !Electic Co..'
YRC-, 178 REV..0 1,07 Total -Cohtinuo6us +Bat~cfiReleases-qries:-)
10
~-
~fili G86'90WK4 110_
'RADIONUCLlDE 1987 Totalil bý
- Atb, Il 1 I.FISSIONGASES 1:
- 2,:.3 4
Releases~i Ci 113 448OE42 7*44E4+
2.09E4-02 ;'.,ý36E-02 !.-7.2E+00 114
-!KR-85M
___-J1.67E~O
&5-1' &68~8-41 8.0-2E-O`
28~0 115 KR*
,166E 00 7.68E'01 1.51 E-of -849E-O 3199E+00 116 KR-68 3`,47 -:E+00 1.:59E+.0O 1.54E+00 1.58E+00 8.....8.+00.
117 "
XE-i33' 5.56E+01 8.-94E+0 4.06E4 3.48E+01 2]-20E+02 11 V XE-135
.2i04E+01 1,.31E01 1.52E+01 1.:3E+01 23EO 119:.
X*E-135M i
- 2.f6E401 689Et00 jt 16E,_01 1.85E+01 631E+011...
120.,,.".XE.138 1.00E*~00 *4.56E0
'-O'*
4;83E&01
..26E-1'6 2.47EO"'
121 XE-i 33M3
- l 1'30E400 L-83E400 i 8.68E&01 '463E-01 4`26E+00 122 AR-37
'.72E-02 7:3E501 3*i338E 02?
'2:55E-02
":.20EOI 123
,AR-41 3.76E-01 1.61E'O1.
4.62E-01T.3.35E-01
-1.33!E+00
.;125":
X.
9 E
-r30E+00
-360E-03 U2.3E-03
.I :32E+100'32E00
.'12.
"::1~A o.11.*0292E400 5.21E-01.;
728E60 1
- .2E+00 -_ : ____
126 M NIDENTIFIED
____---38E0 127
-02__
128 11-IODINES 129 1-131 3.65E-08 2.86E-06 2.1 OE1
- 05. 4.25E-06 :2.891E05 130-1-133 1.63E-05, 63E45
,131, 1
132 133 ** IL PARTICULATES
~134 SR-89 135
~SR-90 136
'CS-134, 4
.ioE07 336E07 9175E-08
.04E0E07 9.48E0, T',__.
1-37' 4CS...:*8
-75E-07 3 81:E'07 4.05E-07
ý5.75E-07
.2.' E
_6_"
-v133-BA'L -4
~139.
2N-6~*-
~
'140~
CO-58
_~
141
'CO-60 2.83E-06 2,43E&06 2.0E06E 2.03E-:6 9ý35E&08 4
'143
- -;,CR-51 7;~ 8-14E,08
.8.14E-08
- ý2R-NB-95.
19E08 1 1ý99E-08 145 1CE-141 4.15E08-4.15E.08 146L CE-i1__
147 SB-124_____
.3/4-148 WMN-54
____1.01E-07
!5.75E- 08 2E-08
-1.E-7__
8
.18 E
0
~149
-AG-1-IOM__
151. 'v13 152 "SB-125 1655 1_____._
{..2-
-1H
-..0 8 42E;...'..
I 4E4-00 4.+
-48E+00
r 1
. I' i
r i
.X, :.
y.,
Z I
PA il.
I YRC-.1178 :REV. 0 VRC-Ij 7A'."REV.!,O (file 6861:9WK31 vU v
.RADIONUCLIDE.
1 Total All
"-byr**aio6y up.I
- FISSIONGASES 1
2.23 4-Releases.
"ci
-KR 85 2.96E-02 3.74E-02 2.89E-02 4ý01E+0O 4.102+00 KRM.85M..
59E601
&6iIE-O1 6.12E&01 1.04E-01 1.94E20 KR487!,
1AiSE2-01 5.58&-01
ý 5.10*-01
ý.9.34E&02 1.68E+600 KR-88:
_1.2.022E+00 I:..09E+00
- 1.83-O't 3.51E+00 XE-33..
,147 Z0
'2:38E2*0*1, 2i27,i 2,61E01
.02E202 StXE135.
1.1,6E1 011 1'30E+011 1.17E+01 12`65E*,0', -3.89E+01r XE-135M
'1.61,O110::68E01, 13.i15E*01
- 314E, 4.7 15E+
-XE138 1.48E-01 335E 2
-65E01 1.095E-02 8.08: 1 j`
XE&-133M 4.89E-01 7.25E41V
-86.12E-01 :2.46E-01t 2.07E+00 AR-37 4.92E-02 6:01E4021 9,16E-02 5.10E-01 7.11 E-01 AR*.
7
.2.02E-01
- 268E.:01 *C,3.33E3 Oi 5558E-02 8.59EE. -
C. 14."..
- I.*.0E,03 7.71
-E03 '5&M05E 13 6.22E-4O 6.41,EV01
- XE-131WýM_
3-91E-.
.5.80E-0.1 O6E55E-03 1:.19E01 1.10E+001 U N ID E N T*
IF IE D t
ý, I I I -
I:..
"2.05E202 II IODINES' 11131
]
1-,*:*~
l*13 31* :::::: :::::::: :: : ::,,. :.
S5.'04E-05 C616".06
+.135]
-a
- 6165E.05
-4
_2'61 E-08 4.13E-07 3.1 140 1.09E-06 1.
- i:: -. :"-
- -:-= -
L,'0 I 4.7:4 TE-07 1 `i~-352E4071. ';50 E5 6
- 3.30E-,;06
'9" 76E-07" 6.98E-
..... : :,!,,.: 7 : :....
H73z
.4, A. _
D CT ADý
ýAf AG A
Al
- AJý 106
.YannkeeAtomicid.Electric Co.
111
_ YRC-11i8 REV 0 Y
____B"
______ses es j
107 Total Continuous+.B atchRelea i(fie I-9O...
Lk...,
109 To.....
110 jADIONUC'LIDEý
'd18 TtlAl ygoup ill L.FISSION GASES 1___~ 2'
- 3.
Releases C
- 112,
- 113 1
'KR.5 3*3*E-
- -031 4.22&-03 O
1.04E+06O'
'.,58E-o03 105E+OO 14;.j KR 85M' ".02&012E-0.
- 373E.-0*i 4,98E-01 1.1.9E*00
- 15 KR-87
,1;27E01*
.250E-O 3.76E-050*15
+ISE-Ol
- 31E400. "_.....
116 XKR-88 214E 1 4.24E-01 I 7.18E-01i 7.17E-i01 207E+00, 117 -
XE-433 22EOOE00 I20 2.17E+01 1.54E+01' 4-E46E+-O1 118
- XE-135.
2:86E+00 1 5.20Et0O 7.54E+00 1i.09E+0i 2.65E+01
- 19: :
XE135Mi 4.4E00 7.58E400, +1.00E+ý01 18E+O1 4'09E+61 120--':
-,XE4138:
5AI2E02 1.:67E4O1 1*71*El0 3.36E-01,,', 7.28E401 r :121.:
- XE-133M
°..
3.2E*02 i: 08E* V 4.47E-01 4~04E*
4 7E 08E-O1 122.
A3J 1,8E.02
3.1 7E'02
1.34E-01 :6.99E-03 -.. 8E-0i
_T-__
123.
- AR41, 2409,E-01 3.24E;.O.
2.74E 01 l2.78E-01
.2E+00 124 BE E
2.04E-*Cl 1.52E-03 2.0EE-O1 126 XE-131M 3
1.74E* o l.,24E1 A0.85E,021:97E-0.
126 UNIDENTIFIED,
~
127 I; iE IL
___0E 3.
1___
2___
... E.
128
'11. IODIN.
129 1-:131 4.17E*07 8.56E058 1.29E-06 1,73E-05 130 1-133
=__=..
=
8.20E-06 "820E-06 131
.17135 6.30E-1071' 6.301E407
,..;133..
fil
- .ARTICULATE_
13
-8 77'.
13 RR
&0-89-5.6E,071
.06E-07 135 lSR-90 7.86E-0:
I 00 7.86E.0g 136 t'CS-1l34.77
&.1:8607 6.807___
7-137---
CS-137,:
1'10E.06
- 6. 81 E-07 150EM06 [-286E-071 :3.57E-06ý
- 138,
-BA-LA-140
- 9. 62E;61,-,,4
_9,62B4,071 139
-6L751 140 A Oý8
.7~06 1325E0 1:8O.06'-:2E0 141 14.20E.06.
6.94.E-06, 4, 66 142 l.'1E08-
'S15E,06 143 CR-S
____3AE06
-1 1.90E4,5 73201E-07i
.8.0 144
.ZR-NB-95 1
38E0
~2.22E-.06
. 2:1E0ý~
60E
-1459 CE.I4 I"
J_ " t821E-07 398E-07, 4.93E-08 "127E06,
146 CE-144.
1..40E--086-
.40E-06 147 B~12~
~
-6.70E-06 2.53E-07
~6.GSEm06 148
,MN-54 3.38E-06 5.60E-08
~4.26E-06 5.64E-07 8.26E-06 149 AG-110M~
2;'51 E-07 2.51E-07 r____
150 MO-99, 1161,: -`,RU-i 03 534-0
~2.21 E-06 1.274ETý06 13 TE-.132 154 UNIDENTIFIED-___
166
- 1E 0O 22E*M0 1.78Eý=06 1,.3E+001 6.648+001 155
-.I3
- ,..'*:,,.,* i* ________!:*=:
________:.:::*:::*i~;
- !i' ___-_____;','
________::::!:L:,:,
938E 05:
.:.:i:
lAtfý V
- r.
C AK, I
AL I
AM AWN AOQ AP 1, AQý AR I:: AS L
~-
-~
4---
-4
- 4.
1-Yankee Atomic Electdc'ýC....
YRC-17k'8 REV.-0.
".,Total Contii-fi u*, 4:Bat-ch*Releass*IGunes)1 :" :!::i::!..,, :,:,'*!.,.:,
I __......_
'.4:P ie:;II7'. :
iiii fileG8&-90.K T.tal Act RA'DIONUCLIDE
.1990 Total All b'Y"'-groupj_'
I. FISSION GASES 2
4 Reass C
" :::KR-85
- 1,;26E-02 2:10E+O0 1:82E*O0 118E 00 5.12E+00 R,,5M 4:02E-01 4.80E-Q1
,.21E-,.I0E+00
, KR-87' _____ :
_ -*4'76E-01I 5*582E&Q1 I
1.65E;01,I 122E+0O KR-881.46&O
~.0E0 0.5-O12.12E+ý001
,XE-133'"
.42EO1 2:07E+ 01.2.25E.00
.i:48E+00 "ý3;86E*0i J
- ."XE-i 35,,
75E+00 1..030
-" 3.26E4+06,233E3'0+.1 XE 135M..
- 1.70E+01. -1.61E+01 5.70E+60 &388E+01 XE-138 4,90E-0f 7-86E-01 8.64E-03 1.28E+00 XE-l33M 1'.T4&E02 3.075E-01 3.637E-02 4.20E-01 AR-37
_____245E-02
-2~71E02J 9%90E 03 1.56E-021
-71E-02' ARA1 22E41' 2Z38E'0j____
.3-01 Of -WE01, C-14 2~~~52E-03:;'&59&~01i
-161E01<.5-I-.7E0 XE-1 31M 4.47E-02 213-1269E-02 4,.'E-'03T,2:89E-01 UNIETIFIED
___I---_
=!::
r' 4.15E4+02 II. IODINES 31:I
- I 1.10&-04!
7 I3E0 1-.1351
":J'.*i:,::':::
- ii :g..,. ;:-
779F -
1.46E!04-E -:
9,63E-
` 2.16E-07
-4 4.
1.75EIOT:
.07~ 1.94E-066 1.06E-06 407 1.34E-06
- 05 I :l.83E,05
,3.05E 4.83E-0T7
.07:
1.90E-.07
-06 2:93E zI~ +/-zz 001
14Ya~n'ke" Atomý"lad L
YR C ý178.,EY.
2E lZ TO al Continuous+ atcn;Nel eases((,.;lnes Pge-3.
1773 flG1
- K3)~
"174.
-1 TotalAct 175 1 4991
{TotrAl'Ibygou.
-.:176 jI. FISSION.GASES V
2 3
4 Releases,
Ci 17i KR85 9~5O:5'.16-l 1.16E-62,69EO 7.48E+OO 170-K M ----
4:602E40'f
.97E-606
.1.
E-O 4.8f8E-ý02W 1.;848E+
1.80 KR.87
._,,68 m.76E*01
.I.T07E-Ol
,6*O9E-Oi
,:50E-02 1.64E4O0 I81 KR-6 88:....
" :846EO1' IKj.'12E+0
.I31E+0O 9:36E602 lt3437E_00____
182.
"XE-133 1-.42E4;01: 5'15E01 253E01 292.01 1.20E+02' 1:83 XE-1359,.752+00 6201 1.12+01 1.117E I +GO.
3..37E+01 184 XE-135M 1.702+01!
1.0i0E41
,1'27E+0 9
173E-O1 4.08E-01 185 XE-1:38....
..90E-O1 2.80E
.'67E.-.1' 31.7.95,02 *7.232-01 v
7*:1'86.*
XE-i33M""
1.i148-02 :.1*02E+,0 4-696E-01 4.07E`01; 2.142E00 187 AR-37.
'1:i185E-021.22E-01 Z.12-02 1.;78E-01 3.140E-01i S188
- AR-4i
.2.21E-01.
.23E-01 I.85E-01"
.123E-2.5.41-01"
- 189:1 J
"j",.,
.87Z,031 3.85Eý0l _232E403 '1.'35E*00 1:.742E+00, "
.190
,XE.131M 4E-4027 4.07E-01 *7.84E.02 4'750E0Qi 980-01.
193 UNIDENTIFIED 7
1...4 2.15E+021 195ý'ýý Al. IODINESi_____
196 3-131`
3484E068
_ý'38E-05 2.67E-06 2.036-05
'19SIT7
-1433 4.2. -7 1
2.4'
- 198 1-35 1
.597E-08' 1.43E-06.
!::19 1i 4.62E*05 200".: IIl. PARTICUIATES*
201 202
.SR 0-2031 R9 I~
204 j C-1r3,4---
205 CSi 37 702E-08
.9-07 1
..... 54E-08 2.49E607 S5.32Ez07 20'6 BA-LA-140
-207 -
ZN-6w
'2089 C600-5
- 8.1&0 i.i209:.
c..~0' 3..*:
00E.006,,2. 39E406 'f.*07E-06 2.'355-06, 8 210~'
FE-59j7____
J:211
,CR-S_
_E,-
7 212a RN 9
,2132 C-4 214 4*"
'0-1 44
~215 SB-124.
21
.MN-54 2.09E-08 09-08.
- ~27I~.
AG IIOM
....2 -18(:.i!*::i*:*SE-75 219" MO-99 7220 RU-1 03"
>SB -125 2
T E 13 7'223 F6___
'224,_
2265 UIDENTIFIED
-0__
__225_0
- 6,2E_0 226 93206:
~22V A-1
.8E+00.1 4ll9E+060 1"3-3E+00 2, 2500. 6-25+006.____
A J
K L
M
.171 Yankee Atomic-Electic 172 Total Continuous + Batch Releases
-173 1 -
I N
0 P--
R
._ __YRC-1 178, REV. 0
'(nI G91 -92 wK3)
- 174, ITotal Act
+
I 4
175
,,I I
176,t. IFISSION: GASES,
177 1*
1992 3
4 Total All lby group AReleases Ci 4
-,:4 1178 KR;85
'18 118 9
KR-85M II 0
KR-87
- I KR488 2
XE-133 3
XE-135......
4 XE.135M
.i.s.-m S
XE-133M 17
" :AR'-37
-"+"**
A9
-C44
'0 ": XE-131.M,
- 13.
UNIDENTIFIED"'..
11. IDINES
_9
""0:OOE+00 10
,IlI. PARTICULATES I17
_1_3
-ASR,89_
- 13.
)4'
-CS-134:
-,-÷ 15; CS6-37 3,18E-08 '.04E-07 223E-08':
3.67E;08 1 95E-07_
Il
- BA-LAAI 40:
17 ZN 6,_
- 19.
CO. 0
-4.26E'06 1.76E-0B 1 3E-06.-3A63E-07,75 IE-06_
12 N;R-B-95r_
[3
-'C&141 14"." ::
C.. ",I i7 :
.,-132
!3 T
-55 UNIDENTIFIED W'3
____1.16E+00 8S5EO&O5 91E-132EO
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