ML19331E275
| ML19331E275 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 09/04/1980 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19331E271 | List: |
| References | |
| NUDOCS 8009090540 | |
| Download: ML19331E275 (50) | |
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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL i
REPORT l
RADIOLOGICAL IMPACT ON MAN f
FOR I
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JANUARY - JUNE. 1.93 l
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VERMONT YANKEE NUCLEAR POWER STATION r
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009 090 u
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TABLE OF CONTENTS P,, age _
1.0 INTRODUCTION
1 2.0 METEOROLOGICAL DATA...........................................
2 3.0 RADI0 ACTIVITY RELEASES........................................
3 1
3.1 -Liquid Releases..........................................
3 3.2 Gaseous Releases.........................................
3 4.0 DOSE ASSESSMENT...............................................
4 i
4.1 Organ Doses to Individuals from Receiving-Water Exposure Pathways........................................
4 4.2 Individual Whole-Body and Skin Doses from Noble Caseous Effluents........................................
4 4.3 Organ Doses to Individuals from Radioactive Iodine and Particula tes in Gaseous Ef fluents.................... 7 4.4 Whole-Body Doses in Unrestricted Areas from Direct Radiation.........................................
9 4.5 Whole-Body Doses to the General. Population from all Receiv ing Wa te r Rela ted Pa thways.........................
10 4.6 Doses to the General Population and Average Individual within Fifty hiles from Gaseous Effluents................
10 RE F E RE NC E S.........................................................
12 FIGURES............................................................
13
-TABLES.............................................................
15 APPENDIX A - SUPPLEMENTAL INFORMATION..............................
Al
a I'
LIST OF TABLES Table No.
Title LA Gaseous Effluents - Summation of all Releases 1B Gaseous Effluents - Elevated Releases 1C Gaseous Effluents - Routine Grcund Level Releases ID Gaseous Effluents - Non-Routine Releases 2A Liquid Effluents - Summation of all Releases
.3 Sulid Waste and Irradiated Fuel Shipments 4-A to 4-H Vermont Yaa'~
'oint Frequency Distribution Janue'
- _on, 1980 5-A to 5-H Vermont Yankee Joint Frequency Distribution April - June, 1980 6
Quarterly Average X/Q and D/Q Values for Selected Receptors 7
Summary of Radiological Impact on Man s
D
~
-111-
VERMONT YANKEE EFFLUENT-AND WASTE DISPOSAL SEMI-ANNUAL REPORT RADIOLOGICAL IMPACT ON MAN JANUARY - JUNE, 1980
1.0 INTRODUCTION
Using actual measured effluent and meteorological data for the first half of 1980, this report estimates potential doses from radioactive effluents that could af fect individuals and the general population near the Vermont Yankee Nuclear Power Station. Tables 1 through 3 list the recorded radioactive effluents and solid waste for this semi-annual period.
Tables 4 and 5 report the cumulative j oint frequency distribution of wind speed, wind direction, and atmospheric stability observed during the first half of 1980. Figures lA and 1B summarize wind speed and direction in a wind rose. Table 6 lists the calculated X/Q and D/Q values at different points of interest based on the meteorological record presented in Tables 4 and 5 for both quarters. Table 7 summarizes the potential radiological dose commitments to individuals and the general population surrounding the plant. Supplemental information concerning the plant's regulatory release limits and the methods used in measuring released radioactivity is given in' Appendix A.
All estimates of potential dose for the first half of 1980 were
~within the dose obj ectives set forth in Appendix I to 10CFR50. This was accomplished while the plant: realized net capacity factors (design MWe) of 91.08 percent and 90.97 percent for the first and second quarters, respectively.
[
2.0 METEOROLOGICAL DATA Meteorological data was collected during this reporting period from the site's 300 foot meteorology tower located approximately 2200 feet northwest of the reactor building, and about 1,400 feet from the plant stack.
The 300 foot tower is approximately the same height as the arimary plant stack (94 meters) and is designed to meet the requirements of Regulatory Guide 1.23 for meteorological monitoring.
Implementation of the Central Meteorological System (CMS) was completed during the month of May, 1978. Combined data recoverability for the first and second quarters was 98.7 percent and 100 percent respectively.
X/Q and D/Q values were derived for all receptor points from the i
site meteorological record for each quarter using a straight-line airflow model. All dispersion and air concentration factors have been calculated employing appropriate source configuration considerations, as described in Regulatory Guide 1.111(1) plus a source depletion model as described in Meteorology and Atomic Energy (1968),(2) and deposition velocities as given by Pelletier' and.Zimbrick(3). Changes in terrain elevations in the site environment were also factored into meteorological models. A full description of the methods used to evaluate air dispersion phenomenon at the plant site is given in Vermont Yankee's 10CFR Part 50, Appendix I
-evaluation (4).
e 3.0 RADIOACTIVITY RELEASES 3.1 Liquid Releases There were no liquid releases of radioactivity from the plant during this semi-annual period.
3.2 Gaseous Releases All gaseous effluent recorded for the first half of the year are listed in Tables lA through ID.
All gaseous effluents were recorded ac continuous in nature, and were released to the environment via the 94 meter stack located approximately 875 feet north of the Reactor Building. As indicated in Table 1A, all gaseous effluents were well within the plants operating Technical Specification for gaseous releases of radioactivity.
In addition, there were no unplanned or non-routine releases of radioactivity in gaseous ef fluents during this reporting period.
O 4.0 DOSE ASSESSMENT-Following the guidance of NUREG-0473(7), nuclides in particulate form which were not detected above the lower limit of detection, (LLD) have been reported as "less than" the'LLD and have not been included in the dose calculations. However, the release rate of noble gases from the plant stack, af ter treatment of the gas stream from the air ej ector through the augmented off gas system, is so low that no noble gases are detectable above the LLD.
Therefore, as a conservative approach, it has been assumed for dose
- alculational purposes that the principal noble gases measured in the of f-gas mix at the air ej ector are present at the LLD level determined for the plant stack.
4.1 Organ Doses to Individuals from Receiving-Water Exposure Pathways There were no routine or accidental liquid releases from Vermont Yankee during the first half of 1980. As a result, no receiving water exposure pathways could contribute to any whole-body or organ doses to individuals in unrestricted areas.
4.2 Individual Whole-Body and Skin Doses from Noble Gaseous Effluents Based on the method of sector averaging discussed in " Meteorology and Atomic Energy - 1968", and utilizing the site meteorological data 4
recorded for this reporting period, the point of maximum off-site ground level air concentration of radioactive materials in gaseous effluents was determined'for each quarter. Terrain height in the vicinity of the ef fluent stack was taken into account in calculating these ef fluent ground level concentrations. For the first half of 1980, the point of maximum ground
level air concentration was determined to be approximately 2400m WNW of the plant stack. The undepleted X/Q's at this location were calculated to be 4.1 x 10-7 sec/m3 and 8.7 x 10-7 sec/m3 for first and second quarters of the year, respectively.
Whole-body and skin doses were calculated at these off-site points as a reault of noble gas releases occurring in both quarters. The methodology applied to the dose calculations is consistent with that of Regulatory Guide 1.109(5) for an elevated release point. Dose conversion factors for noble gases and daughters were taken from Table B-1 of this Regulatory Guide. For the beta contribution to the skin dose, a semi-infinite cloud model was used. The whole-body gamma dose was eva1.uated using a fini':e cloud sector average model with Gaussian activity distribution in the vertical plane. The gamma radiation received at a point of interest from a differential volume of the cloud is calculated. The radiation is then integrated over the entire cloud, taking iato account of the geometry of the cloud. variation in concentration, attenuation by the interactica of photons wich matter in the path between source and the receptor point, and scattering of radiation from material outside the direct path to the point of interest. An attenuation factor of 0.7 is also applied to the dose calculations to account for the dose reduction due to shielding which would be provided by a residential structure. No additional credit is taken-for decay of radionuclides in transit to the receptor point.
For the first quarter, the-skin and whole-body doses from exposure to noble gases at the point of maximum ground level air concentration were calculated to be 0.055 mrem and 0.022 mrem, respectively. For the noble gaseous ef fluent during the second quarter, the skin and whole-body doses,
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. be 0.11 area and 'O.045._sem, respectively.
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.si ent and site boundary whole-J
- body and skin doses have been ' calculated due to noble gaseous effluents 1
-from the plant stack during-the reporting period. The maximum whole-body and skin site bou~ndary doses (both' approximately 0.08 arem) 'for. the first
. quarter of 1980 occurred in the S sector, 0.24 miles from the stack.- The i
1second quarter maximum whole-body and skin' site boundary doses (both approximately 0.08 ares) occurred ~ in the S sector 0.24 miles from the stack.
I j
LIn the first quarter, the maximum skin and whole-body dose to the j
nearest' resident (both approximately 0.056 area) in any direction vss
' determined to be in the s sector. 0.33 miles from the plant stack. As a E
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result of the second quarter meteorolor,y and noble gas effluents, the maximum j
whole-body and skin dose' to the nearest resident (both approximately. 0.06 arem) in any sector occurred to the resident 0.33 miles south of the plant
~ s tack'.
i The resultant doses due to noble gas effluents 'for the maximum site 4.
. boundary location, maximum nearest r'esident, and point of maximum ground level air concentration are tabulated in Table 7.
All doses are conservative in that they assume 100 percent occupancy at each point Whole-body doses c consider thel gamma radiation received from the effluent plume overhead.
DI The' skin' doses considers both the beta and gamma contributions-at the receptor point'. All doses-from noble gaseous effluents are well below the.
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dose criteria offl0CFR50, Appendix I.
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4.3 Organ Doses to Individuals' from Radioactive Iodine and Particulates in Gaseous Effluents The -critical pathway of internal exposure to. radioactive iodine t'
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.and particulates, includl. g tritium, 'resulting from gaseous effluents for the - third quarter 'is through the grass-milk pathway.. It.is-assumed that milk animals 'are' free to graze on open pasture during the second quarter l
with no supplemental feeding. This assumption is conservative since most i
of the milk animals inventoried in the site vicinity are fed stored feed throughout the entire year with only limited grazing allowed during the growing season.
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During the winter months of the year, the dose commitment through the'ailk pathway and fresh vegetable ingestion is insignificant. The maximum i
l length of annual growing season is approximately six months long in this 4'
t part of New England. ' Therefore, the milk pathway and vegetable ingestion 9
- doses for the first quarter are the result of activity deposited on feed
- and vegetables grown 'during the growing season and allowed' to decay while held in storage. _ As a result, the critical pathway of-exposure for radioactive iodine and particulates during the first quarter is through inhalation.
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'As a result at the milk cnd fresh vegetable pathways, the maximum.
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' dose for_ the :second quart'er from gaseous releases of' radioactive iodine 4'
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and _ particulates.was determined.to occur at -a farm 1.9 miles WNW of the
' plant. The critical organ was an infant. thyroid with' a calculated dose of 0.07 ares. For the first quarter, with inhalation being 'the prin 'iple
= pathway of exposure, - the maximum organ dose was at a farm.SSE 3.5 miles.
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.14:e critica11 organ was a child's' thyroid with a calcu1ated dose of 0.0021
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ares. The pathways of ' exposure which were assumed to exist during the second-quarter at this. farm-include ground. plane exposure, inhalation, fresh'home i
. grown vegetables and cow's milk. The; pathways of exposure considered at the farm during the first quarter include continuous ground plane exposure, inhalation and. contributions from stored ' vegetables and milk.
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Table 7 shows the maximum calculated quarterly organ dose due to the combination of exposures.from all pathways which have been identified t.
i at the farm. Table 7 also shows the calculated organ doses to the highest exposed nearby resident, and potential organ doses to individuals if-assumed standing at the highest ground level air concentration point on che site 4
l boundary for the entire six-month reporting period. The site bounctry. doses 4'
~ include -only exposure from inhalation, and direct. radiation from the ground plane. The nearest resident is assumed to have a vegetable garden duting
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. 'the growing 'sess'on which' contributes to his or her ingestion dose.
I For
- all ground plane exposures,' the activity is-assumed to accumulate on the ground for.15 years.at the. rate equivalent to that observed during each -
. quarter. This. is 'a simplified method of approximating the. average deposition I.
over.the life of the plant. - The calculated dose from direct exposure to 1
activity on the ground thus represents the dose an individual would see
+
in. each ' quart'er if ' the plant had been operating-15 years. This approach j
-is very conservative, but shows the relative impact the plant would.have
. on the dose commitment over its operating life 11f the releases were to 4.
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. continue at, the' levels recorded during this reporting period.
4 1
The. critical. organ, for -the.second quarter.for the nearest resident
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with the most_ exposure was the Lbone,;and for the maximum site boundary
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location, was calculated in both quarters to be a child's thyroid. For the nearest residet.ts, in the first quarter, each organ considered was exposed to 0.0013 meem and for the second quarter, the bone dose was 0.00027 area (both at SSE 1.3 miles).
4.4 Whole-Lody Doses in Unrestricted Areas from Direct Radiation The maj or source of direct radiation (including sky shine) from the station is due to N-16 decay in the turbine building. Because of the orientation of the turbine building on the site, and the shielding effects of the adj acent reactor building, only the seven westerly sectors (SSW -
NNW) see any significant direct radiation.
High pressure ionization chamber (HPIC) measurements have been made
- n the plant area in order to estimate the direct radiation from the station.
The chamber was located at a point along the west site boundary which has been determined to receive the maximum direct radiation from the plant.
Using measurements of dose rate made while the plant operated at different power levels, from shutdown to 100 percent, the total integrated dose from direct radiation over each three month period was determined by considering the quarterly gross megawatts generated. Field measurements of exposure, in units of Roentgen, where modified by multiplying by 0.6 to obtain whole body du, equivalents, in units of rem, in accordance with recommendations of HASL report 305(6) for radiation fields resulting from N-16 photons.
Estimates of the population exposure from direct radiation during the tx;: ' and second quarters have been made out to two miles. Beyond two miles, tne dose from 'the turbine building is negligible. As a result, the
)
estimated population dose for each of the tro quarters respectively was
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approximately 1.9 x'10-2 and 1.9 x 10-2 person-rem, for a total population of about 351 persons. The estimated direct -radiation dose at the maximum site boundary location wasapproximately 3.4 mrem for the first quarter of 1980, and 3.5 mrem for the second. These hypothetical individual doses assume a 100 percent occupancy factor, taking no credit for the shielding effect of.any-residential structure. Taole 7 summarizes these results.
4.5 Whole-Body Doses to the General Population from all Receiving Water Related Pathways f'
There'were no routine or accidental liquid releases from Vermont Yarkee during the first half of 1980. As a result, no receiving water exposure pathways could contribute to any population dose.
4.6 Doses to the General Population and Average Individual Within Fif ty Miles from Gaseous Effluents Using site meteorological data in Tables 4 and 5, quarterly average X/Q values were determined for each sector-formed by placing radial rings from the plant at distances of one, two, three, four, five, ten, twenty, thirty, forty and fif ty miles, and their intersection with radial lines drawn to form each of the sixteen principal compass direct *ons.
For noble gases, whole-body and skin doses were calculated for each sector and
. multiplied by the estimated population within each sector to determine the sector person-rem. No credit for decay in transit of activity was assumed.
For the approximately 1.1 x 106 people within fifty miles of the Plant, the first and second quarter whole-body doses from noble gas cloud
- exposure were estimated to be 0.77 person-rem and 0.92 person-rem,..-
'a respectiv ely. For the same two quarters, the average individual whole-body doses were 6.7 x 10-4 mrem and 8.0 x 10-4 mrem, respectively. The skin doses for the two quarters were 1.5 person-rem and 1.7 person-rem, respectively, and the average individual skin dose was 1.3 x 10-3 and 1.5 x 10-3 mrem, respectively.
Table 7 also indicates the population whole-body and thyroid dose commitments from radioactive iodine and particulates (including tritium) released from the plant in gaseous waste. The pathways of exposure which have been considered for the 50 mile population include inhalation, ingestion of vegetables, milk and meat produced within 50 miles, and the direct exposure to activity deposited on the ground plane. The total whole-body and thyroid dose commitments for the first quarter were calculated to be 2.3 x 10-2 person-rem and 2.5 x 10-2 person-rem respectively. For the second quarter, these doses were 6.6 x 10-3 person-rem and 0.13 person-rem respectiv ely.
G,
REFERENCES l... Regulatory Guide 1.111, " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-
. Wnter-Cooled Reactors", U.S. Nuclear Regulatory Commission, Of fice of Stendards Development, March 1976.
4 2.
Meteorology and AtomicL Energy,1968, Section 3-3.2.2, " Cloud Depletion",
pg. 204. U. S. Atomic Energy Commission, July 1968.
3.
C. A. Pelletier, and J. D. Zimbrick, "Kinctics of Environmental Radioiodine Transport Through the Milk-Food Chain", Environmental Surveillance in the Vicinity of Nuclear Facilities, Charles D. Thomas Publishers, Springfield, Illinois,1970.
4.
" Supplemental Information.for the Purposes of Evaluation of 10CFR Part 50, Appendix I", Vermont Yankee Nuclear Power Corporation, June 2, 1976.
5.
Regulatory Guide 1 109, " Calculation of Annual Doses to Man From Routine Release of Reactor Effluents for the Purpose of Evaluating Compliance-with 10CFR Part 50, Appendix I", U. S. Nuclear Regulatory Commission, Office of Standards Development, Revision 1, October 1977.
6.
W. M. Lowder, P. D. Raf t, and G. dePlanque Burke, " Determination of N-16 Gamma Radiation Fields at BWR Nuclear Power Stations", Health and Safety Laboratory, Energy Research & Development Administration,
~ Report No. 305, May 1976.
7.
NUREG-0473, " Radiological Effluent Technical Specifications for BWR's",
Revision 2, July 1979; Table 4.11-1, notation f.
1 4 -
-.e Figure IA: Vermont Yankee January-March 1980 Upper Level Wind Rose 1
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TABLE 1A VERMONT YANKEE EF LQENT'AND WASTE DISPOSAL SEMI ANNUAL REPORT t'
' JANUARY - JUNE 1980 j
GASEOUS EFFULENTS.- SUMMATION OF ALLLRELEASES L.-
l-l Unit Quarter Quarter Est. Total i.
1 2
Error, %
. A.. ' Fission & activation gases 1.
Total release Ci 7.89E2 8.45f2 1.0 E2 2.
Average-release rate.for period uCi/see 1.01E2 1.08E2 l
3.
Percent of technical specification limil 1.27E-1 1.19E-1 l
B.
Iodines i
_1.
Total iodine - 131-Ci 6.64E-4 3.81E-3 25.0 El-
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Average release rate for period uci/sec 8.45E-5 4.85E-4'
_3.-Percent of technical specification'11mit 1.76E-2 1.01E-1 L
I C.
Particulates i
1.
Particulates.with half-lives Ci 2.03E-3 8.88E-4 5.0 El 2.
Averaee re1. ease rate for oeriod uC1/sec 2.58E-4 1.12E-4
[
- 3. Percent - of technical' soecification limit 8.05E-2 1.50E-2 l.
4 Gross aloha radioactivity Ci 8.45E-8 7.82E-8 D.
Tritium 1.
Total release Ci 3.74E0 3.23E0' 25.0 El j
2.
Average' release rate for period uCi/sec 4.76E-1 4.10E-1 l ;.
- 3. Percent of technical. specification limit N.A.
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TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY - JUNE 1980 GASEOUS EFFLUENTS - ELEVATED RELEASE CONTINUOUS MODE BATCH MODE *2 Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1. Fission gases
- 1
- 1 krypton-85 Ci E
E E
E krypton-85m Ci 4.78E0 1.16El E
E krypton-87 Ci 1.52El 1.93E1 E
E krypton-88 Ci 1.32El 2.41El E
E xenon-133 Ci 7.71El 1.43E2 E
E xenon-135 Ci 2.34El 4.38E1 E
E xenon-135m C1 1.21E2 1.20E2 E
E xenon-138 Ci 5.43E2 4.84E2 E
E Others (specify)
Ci E
E E
E Ci E
E E
E Ci E
g E
E unidentified Ci E
E E
E Total for period Ci 7.98E2 8.45E2 E
E
- 2. Iodines iodine-131 Ci 6.64E-4 3.81E-3 F
1 e
iodine-133 Ci 2.30E-3 2.91F-1 F
r i.odine-135 Ci
< 4.67E-2
< 5.14E-3 E
E Total for period Ci 2.97E-3 6.72E-3 E
E
- 3. Particulates 1
strontium-89 Ci 1.73E-5 8.88E-5 r
E strontium-90 Ci 1.72E-6 9.36E-7 E
E cesium-134 Ci 7.88E-6 2.18E-5 E
E cesium-137 Ci 1.09E-4 7.85E-5 E
E
)
barium-lanthanum-140 Ci 7.38E-5 2.33E-4 E
E cobalt-60 Ci 1.82E-3 3.37E-4 E
E zine-65 Ci
< 3.01E-4 4.89E-5 E
E mancanese-54 Ci
< l.12E-4 7.94E-5 E
E unidentified Ci E
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- 1 - Kr85 not detected in offgas mix - Limit of detectability = 6.97 x 10-7 uC1/cc
- 2 - No batch releases mode for this period t.
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TABLE IC VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT.- 1980 JANUARY - JUNE' GASEOUS EFFLUENTS - ROUTINE GROUND LEVEL RELEASES *
'
- There were no routine measured ground level continuous, or batch mode, gaseous effluent releases during the reporting period.
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. TABLE ID VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL' REPORT - 1980
-i JA11UARY JUNE' GASEOUS EFFLUENTS - NON-ROUTINE RELEASES *
- There were no non-routine or accidental gaseous effluents releases during the. reporting period.
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TABLE 2A-VERMONT YANKEE ~
EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1980
. JANUARY - JUNE
' LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES
- i 1-
.
- There.were no liquid effluent releases during the reporting period.
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l TABLE 2B VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1980 JANUARY - JUNE LIQUID EFFLUENTS
- There were no liquid effluent releases during the reporting period.
s TABLE 3 EFFLUENT AND WASTE DISPOSAL SE!!IANNUAL REPORT JANUARY - JUNE 1980 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel)
- 1. Type of waste Unit 6-month Est. Total Period Error, %
- a. Spent resins, filter sludges, evaporator m3 9.85E+1 bottoms, etc.
Ci 7.38E+2
- 7.5 El
- b. Dry compressible waste, contaminated m3 1.44E+2 eoulp, etc.
C1 1.79E+1 7.5 El
- . Irradiated components, control m3 0.0 E0 rods, etc.
Ci 00EO
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0.0 E0 m
- d. Other (describe)
Ci 0.0 79
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- 2. Estimate of mejor nuclide composition (by type of waste)
Unit 6 month Unit 6 month a.1131 1.55E-1 La140 7.22E-2 Csl34 2.69E+1 Na
- 1.05E-2 4
Csl37 5.05E+1 Bal40 7.27E-4 Co30 1.18E0 Cel41 1.89E-3 Mn5*
1.25E0 I 133 2.17E-3
. Zn65 5.70E0 Zr95 3.25E-3 Cobu 1.41E+1 Mn56 2.94E-3
- b. Cs1>*
2.31E+1 Mn54 2.45E0 Cs137 4.08E+1 Zno5 8.38E0 CoS8 9.80E-1 Co60 2.43E+1 C.
E d.
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- 3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 29 Truck Barnwell, S.C.
Richland, WA B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments.
Mode of Transportation Destination None l
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. 29 7.9 F T hlND D AT A STAGILIIV CLASS E CLASS FREQUENCf IPERCENI) a 31.02 WIND DIRECTION FNOW SPEE0(MPH)
N NNE NE ENE E
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o TABLE 5-D VERMUNI VANMEE APN=JUN 1980 JOINI PREQUENCY DISTRIBUTION (UPPER LEVEL) 29170 FI hlNO DATA OIA0ltilY CL400 D CLA00 FREuufNCY (PERCENTI e 41.e4 klND DIRECTION FROM SPEED (MPN)
N NNE NE ENE E
GSM SP M8m nNa NW NNm VN8L 101AL CALM 0
0 0
0 0
0 0
0 e
o 0
0 0
0 0
0 0
o 1
(1) 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 n.00 0.00 0.00 0.00 0.00 (2) 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 3.00 0.00 0.00 0.00 a.co C=3 10 8
6 81 30 17 15 9
6 4
2 5
7 2
e 18 0
gle (t) 3.10 08 66 1.22 1.10 1.00 3.66 99 66
.C#
22 55 77 22 44 1.55 0.00 38.36 (2)
.e6 3F 27 50 46 70 69 48 2F 30 99 23 32 09 18 64 0.00 5.95 e*7 20 12 le 11 Il 12 27 35 19 6
6 0
6 e
to 50 0
239 (1) 2.28 1.33 1.10 1.22 8.22 1.33 2.98 3.0F 2.10 66 66 0.00 66
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.e6 2.29 0.00 10.oa 8-82 22 23 12 6
7 11 12 es 28 5
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268 (1) 2.43 2.58 1.33 66 7F t.22 1.33 e.86 2.32 55 46 1.22 1.55 3.09 1.22 3.87 0.00 29.61 (2) 1.08 8.45 55 2F 32 50 55 2.08 96 23 21 50 64 1.28 50 1.60 0.00 12.27 I5-In 15 3
0 1
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4 12 33 3
5 3
le 3e 87 34 e
185 (l) 8.66 35 0.00 31 11 66
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i ALL SPEEDS 78 87 28 29 29 46 59 los el 18 19 Po se TF 58 176 0
905 (1) 7 e5 5.19 3.09 3.20 3.20 5.08 6.52 11.38 8.95 1.99 2.10 2.25 4.86 8.58 6.el 19.e5 0.00 100.00 (2) 3,25 2.15 1.28 1.33 1.33 2.88 2.70 e.72 1.71 82 87 92 2.91 1,53 2.66 8.06 0.00 et.se (1)ePERCENT OF ALL GOOO OuStavat{UNO FUM INIS PAG (
(2)eP(hCENT OF ALL GOOD URSE Rv4' lONS FOW THIS PERIOD Cs CALM (=IND SPfl0 LE SS IHAN HN (WUAL TH 60 MPN) )
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i TABLE 6 VERMONT YANKEE QUARTERLY AVERACE X/Q, D/Q AND GAMMA X/Q VALUES FOR SELECTED RECEPTORS January - June' CEi POINT OF INTEREST FIRST QUARTER SECOND QUARTER
'A.
Maximura of fsite ground Location:
WNW ~ 2415myters 2415nyters Location:
WNW Icvel air concentration X/Q (undepleted)*:
4.059 x 10 X/Q (undepleted):
6.701'x 10
~7
~7 location X/Q (depleted)*:
4.040 x 10 X/Q (depleted):
8.670 x'10
-10
~9 D/Q**:
8.776 x 10 D/Q:
1.632 x 10
~7
~7 Gamma X/Q:*
1.632 x 10 Camma X/Q:
3.453 x 10 B.
For whole body and skin-dores from noble gases
- 1) Haximum site boundary Location:
S 0.24milgs Location:
S 0.24milgs location X/Q (undepicted):
1.585 x 10 X/Q (undepleted):
5.265 x 10
~9 X/Q (depleted):
1.585 x 10 X/Q (depleted):
5.264 x 10~9 4
-11 D/Q:
1.173 x 10 D/Q:
2.831 x 10
-7
~7 Gamma X/Q:
5.579 :: 10 Gamma X/Q:
6.437 x 10
- 2) Maximum nearest Location:
S 0.33milgs Location:
S 0.33milgs residence X/Q (undepleted):
6.424 x 10 X/Q (undepleted):
1.062 x 10
~9 X/Q (depleted):
6.423 x 10 X/Q (depleted):
'1.061 x 10-8
-II
-11 D/Q:
4.327 x 10 D/Q:
5.246 x 10
-7
~7 Gamma X/Q:
4.097 x 10 Gamma X/Q:
4.724 x 10 C.
For organ doses from i
lodine and particulates in gaseous effluents.
i
- 1) Maximum farm location Location:
SSE 3.5 mi Location:
2.365x10}es 6.390x10}es WNW 1.9 mi X/Q (undepleted):
X/Q (undepleted):
~7
~7 X/Q (depleted):
2.311 x 10 X/O (depleted):
6.330 x 10
~9
~9 D/Q:
1.290 x 10 L/Q:
1.170 x 10 Gamma X/Q:
1.488 x 10-7 Gamma X/Q:
2.689 x 10~7
-3S-
q d
TABLE 6 (continued)
POINT OF INTEREST FIRST QUARTER-SECOND QUARTER
^
. 2). Maximum nearest residence Location:
SSE't.3mi}es Location:
'SSE 1.3miges X/Q (undepleted):
1.100 x 10 X/Q (undepleted):
8.000.x-10
~
~7
-8 X/Q (depleted):
1.097 x 10 X/Q (depleted):
7.978 x 10
-10
-10 D/Q:
8.784 x 10 D/Q:
.5.672 x 10
-7
~7 Gamma X/Q:
4.097 x 10 Gamma X/Q:
-2.573 x 10
'3)
Maximum site, boundary Location:
SSE 0.53afles 0.53agles-Location:
SSE location X/Q (undepleted):
3.127 x 10 X/Q (undepleted):
-4.705 x 10
-8
-8 X/Q (depleted):
3.124 x 10 X/Q (depleted):
4.699 x 10
-10
-10 D/Q:
2.673 x 10 D/0:
3.880 x'10
~7
~7 Gamma X/Q:
4.713 x 10 Gamma X/Q:
5.055 x 10 3
6' Depleted and undepletedX/Qs and Gamma X/Q are in units of sec./m Delta (D/Q) in units of.1/m r
i 8 days:
1.6 x 103 MPCa Ci/sec.
d.
Liquid effluents:
1 x 10-7 pCi/ml (HTO:
3 x 10-3 pC1/ml, dissolved Noble gases:
4 x 10-5 pCi/ml). isotopic limits are found in 10CFR20 App. B, Table II, Column 2.
2.
Maximum Permissible Concentrations Provided below are the MPC's used in determining allowable release rates or concentrations.
-a.
Fission and activation gases: No MPC limits b.
Particulates, half-lives >8 days: See 10CFR20, App. B, Table II, Column 1 d.
Liquid effluents: -See 10CFR20, App. B, Table II, Column 2.
3.
Average Energy Provided below are the average energy (E) of the radionuclide mixture in releases of fission and activation gasses, if applicabJe.
a.
Average gamma energy:
1st Quarter 0.998 Mev/ Dis.
2nd Quarter 0.888 MeV/ Dis.
b.
Average beta energy:
Not Applicable.
Al
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4.
Measurements and Approximations of Total Radioactivity Provided below are the methods used to measure or approximate the total radioactivity in ef fluents and the methods used to determine radionuclide composition.
a.
Fission and Activation Gases Daily samples are drawn at the discharge of the Air Ej ector.
Isotopic breakdown.of the releases are determined from these samples. A logarithmic cnart of the stack gas monitor is read daily to determine the gross release rate. At the very low release rates normally encountered during operation with the Augmented Off Gas system the error of release rates may be approximately
+ 100%.
b.
Iodines Continuous isokinetic samples are drawn from the plant stack through a particulate filter and charcoal cartridge. The fi:ters and cartridge are removed weekly (if releases are less than 4%
of the Tech Spec limit), or daily (if they are greater than 4%
of the limit), and are analyzed for radioiodine 131, 132, 133, 134, and 135. The iodines found on the filter are added to those on the charcoal cartridge. The error involved in these steps may be approximately +50%.
c.
Particulates The particulate filters described in b. above are also counted for particulate radioactivity. The error involved in this sample is also approximately +50%.
d.
Liquid Effluents Radioactive liquid effluents released from the facility are continuously monitored. Measurements are also made on a representative sample of each batch of radioactive liquid effluents released. For each batch, station records are retained of the total activity (mci) released, concentration (uC1/ml) of gross radioactivity, volume (liters), and approximate total quantity of water (liters) used to dilute the liquid ef fluent prior to release to the Connecticut River.
Each batch of radioactive liquid effluent released is analyzed for gross gamma and gamma isotopic radioactivity. A monthly proportional composite sample, comprising an aliquot of each batch released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to
. gamma spectroscopy.
-A2
o.
1 1
' There were no liquid releases during the reporting period.
5.
Batch Releases a.
Liquid There were no routine liquid batch releases during the reporting pe riod.
b.-
Gaseous There were no routine gaseous batch releases during the reporting-
. pe riod.
6.
' Abnormal Releases a.
Liquid There were no non-routine liquid releases during the reporting period.
b.
Gaseous There were no non-routine gaseous releases during the reporting pe riod.
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