ML19290E948
| ML19290E948 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee  |
| Issue date: | 12/31/1979 |
| From: | VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | |
| Shared Package | |
| ML19290E946 | List: |
| References | |
| NUDOCS 8003170367 | |
| Download: ML19290E948 (53) | |
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EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT RADIOLOGICAL IMPACT ON MAN FOR
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THIRD AND FOURTH QUARTERS, 1979
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VERMONT YANKEE NUCLEAR POWER STATION
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TABLE OF CONTENTS Page
1.0 INTRODUCTION
.................................................. I 2.0 METEOROLOGICAL DATA........................................... 2 3.0 RADIOACTIVITY RELEASES........................................ 3 3.1 Liquid Releases.......................................... 3 3.2 Caseous Releases......................................... 3
- 4.0 DOSE
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ASSESSMENT............................................... 4 4.1 Organ Doses to Individuals from Receivin Exposure Pathways.......................g-Water ................. 4 4.2 Individual Whole-Body and Skin Doses from Noble Caseous Effluents........................................ 6 4.3 Organ Doses to Individuals from Radioactive Iodine .
and Particulates in Caseous Effluents.................... 8 4.4 Whole-Body Doses in Unrestricted Areas from Direct Radiation......................................... 10 4.5 Whole-Body Doses to the General Population from all Receiving Water Related Pathways......................... 11 4.6 Doses to the General Population and Average Individual within Fifty Miles from Caseous Effluents................ 13 REFERENCES......................................................... 15
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TABLES.................e........................................... 16-45 APPENDIX A - SUPPLEMENTAL INFORMATION.............................. Al
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LIST OF TABLES Table No. Title 1A Caseous Effluents - Summation of all Releases 1B Caseous Effluents - Elevated Releases IC Caseous Effluents - Routine Ground Level Releases ID
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Caseous Effluents - Non-Routine Releases 1A Liquid Effluents - Summation of all Releases 3
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Solid Waste and Irradiated Fuel Shipments 4-A to 4-H Vermont Yankee Joint Frequency Distribution July - September, 1979 5-A to 5-H Vermont Yankee Joint Frequency Distribution October - December, 1979 .
6 Quarterly Average X/Q and D/Q Values for -
Selected Receptors 7
Summary of Radiological Impact on Man
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VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT RADIOLOGICAL IMPACT ON MAN JULY - DECEMBER 1979 1.0 INfRODUCTION Using actual measured effluent and meteorological data for the second six months of 1979, this report estimates potential doses from radioactive effluents that could affect individuals and the general population near
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- the Vermont Tankee 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 joint frequency distribution of wind speed, wind direction, and atmospheric stability observed during the second
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half of 1979, while Table 6 lists the calculated I/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.
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All estimates of potential dose for the second six months of 1979 t
were within the dose objectives set forth in Appendix I to 10CFR50. This
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was accomplished while the plant realized net capacity factors (design MWe)
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of 72.5 percent and 60.1 percent for the third and fourth quarters, respectively.
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2.0 METEOROLOGICAL DATA Meteorological data was collected during this reporting period from the site's 300 foot met 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 primary plant stack (94 meters) and is designed to meet the requirements of Regu? r ; iry Guide 1.23 for meteorological sonitoring.
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Implementation of the Central Meteorological System (CMS) was completed during the month of May, 1978. Combined data recoverability for the third and feurth quarters was 88.4 percent and 99.8 percent respect 1vely. ,
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X/Q and D/Q values were derived for all receptor points from the 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
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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
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the plant site is given in Vermont Yankee's 10CFR Part 50, Appendix I I evaluation (4).
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3.0 RADIOACTIVITY RE1. EASES 3.1 Liquid Releases During the semi-annual period, a total of 16 planned and controlled batch releases of liquid radioactivity (totalling less than 2.90 x 10-4 C1) were discharged f rom Vermont Yankee in accordance with the plant's operating Technical Specifications. All liquid effluent recorded for the second half of the year are listed in Tables 2A and 2B. Approximately 484,000 litets
of waste liquid was released to the Connecticut River through the plant's
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- liquid radvaste system. Average river flow for the release periods was approximately 4063 cfs. During the same time period, there were no unplanned or non-routine releases of radioactivity in any liquid effluents.
3.2 Caseous Releases *
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All gaseous effluent recorded for the second half of the year are listed in Tables LA through ID. All gaseous effluents were recorded as continuous in nature, and were released to the environment via the 94 meter stack located approximately 875 feet north of the Reactor Building. As
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indicated in Table 1A, all gaseous effluents were well within the plants
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operating Technical Specification for gaseous re1 eases of radioactivity.
- In addition, there were no unplanned or non-routine releases of radioactivity in gaseous effluents during this reporting period.
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4.0 DOSE ASSESSMENT
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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 ejector through the augmented off-gas system, is so low that no noble gases are detectable above the LLD.
Therefore, as a conservative approach for the noble gas releaser, it has
- been assumed for dose calculational purposes that the principal noble gases
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measured in the off-gas mix at the air ejector are present at the LLD level determined for the plant stack.
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4.1 Organ Doses to Individuals from Receiving-Water Exposure Pathways '.
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During the third quarter 16 separate batches of liquid waste totalling 484,000 liters, were released. The radiological health significance of these releases were evaluated using the liquid pathway model described in NRC Regulatory Guide 1.109(5). Site specific parameters used in applying this dosimetric model to the Vermont Yankee environment have been described and documented in the report (4) submitted to the NRC Office of Nuclear Reactor Regulation in connection with 10CFR50, Appendix I.
The liquid pathway dose analysis for the third quarter was per. formed
. at a point in the Connecticut River just below Vernon Dam 0.5 mile downstream of the plant. Fishing from the shoreline was assumed to be the sole contribution to dose. The ingestion of river water and aquatic invertebrates was not considered since these pathways do not exist along this portion of the Connecticut River or any known downstream location.
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The irrigation of farm land by river water was not taken into account because it has not been observed below the plant. Fishing in Vernon Pond was not considered due to the relatively small fish population and because the shoreline access is largely restricted.
All liquid effluent from the plant was assumed to be homogeneously
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mixed in the volume' of water which passed over the dam during the period of release.
This leads to a conservative estimate of the radionuclide concentrations below the dam since no credit is taken for dilution or deposition in Vernon Pond.
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The average river flow over the das during the time of release in the third quarter was 4063 cfs.
Usage factors for adults, teenagers and children were obtained from Regulatory Guide 1.109, and doses were calculated for whole-body, bone,'.
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kidney, GI-LLI, liver, thyroid and lung. The GI-LLI (gastro-intestinal and lower-large-intestine) was the critical organ for the adult age group with Tritium and Manganese-54 being the principle nuclides contributing to dose.
. As indicated in Table 7, the resulting individual CI-LLI dose commitments due to liquid releases during the third quarter are 4.2 x 10-6
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mrem, 3.0 x 10-6 and 1.8 x 10-6 to the adult, teen and child age groups respectively.
It should also be noted that these doses assume that each individual ingests, in the third quarter, one half of the total annual' intake
. of fish recommended for a maximum individual in Regulatory Guide 1.109.
All calculated doses due to radioactivity in liquid effluent are well below the dose criteria of 10CFR50, Appendix I.
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There were no non-routine liquid releases from Vermont Yankee during
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the reporting period. As a result, no accidental or unplanned liquid effluents in receiving water 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 Caseous Effluents Based on the method of sector averaging discussed in " Meteorology and Atomic Energy - 1968", and utilizing the site meteorological data 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 effluent stack was taken into account in calculating these effluent ground level concentrations. For the third and fourth quarters of 1979, the points of maximum ground level air concentration were determined to be approximately
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WNW at 2400m and NW at 4000m of the plant stack. The undepleted I/Q's at these locations were calculated to be 4.9 x 10-7 sec/m3 and 4.8 x 10-7 sec/m3 for third and fourth quarters of the year, respectively.
Whole-body and skin doses were calculated at these off-site points as a result 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
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Regulatory Guide. For the beta contribution to the skin dose, a semi-
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infinite cloud model was used. The whole-body gamma dose was evaluated using
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a finite cloud sector average model with Gaussian activityd 'istribution 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
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then integrated over the entire cloud, taking into account of the geometry of the cloud, variation in concentration, attenuation by the interaction of photons with 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 third quarter, the skin and whole-body doses from exposure
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to noble gases at the point of maximum ground level air concentration were calculated to be 0.069 mrem and 0.03 mrem, respectively. For the noble gaseous effluent during the fourth quarter, the skin and whole-body doqes at the point of maximum ground level air concentration were calculated to be 0.049 mrem and 0.022 mram, respectively.
In addition, the maximum nearest resident and site boundary whole-body and skin doses have been calculated due to noble gaseous effluents from the plant stack during the reporting period. The maximum whole-body and skin site boundary doses (both approximately 0.1 mrem) for the third quarter of 1979 occurred in the S sector. 0.24 miles from the stack. The
, fourth quarter maximum whole-body and skin site boundary doses (both 0.05 arem) occurred in the N sector 0.25 miles from the stack.
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In the third quarter, the maximum skin and whole-body dose to the nearest resident (both approximately 0.07 mrem) in any direction was determined to be in the S sector, 0.33 mils. xrom the plant stack. As a result of the fourth quarter meteorology and noble gas effluents, the maximum
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whole-body and skin dose to the nearest resident (both 0.03 mrem) in any sector occurred to the resident 0.33 miles south of the plant stack.
The resultant doses due to noble gas effluents for the maximum site boundary location, maximum nearest resident, 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 consider the gamma radiation received from the effluent plume overhead.
The skin doses considers both the beta and gamma contributions at the L
receptor point. All doses from noble gaseous effluents are well below the
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dose criteria of 10CFR50, Appendix I.
4.3 Organ Doses to Individuals from Radioactive Iodine and Particulates in Caseous Effluents
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The critical pathway of internal exposure to radioactive iodine and particulates, including 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 third quarter with no supplemental feeding. This assumption is conservative since most 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.
. During the vinter months of the year, the dose commitment through the milk pathway and fresh vegetable ingestion is insignificant. The maximum length of annual growing season is approximately six months long in this part of New England. Therefore, the milk pathway and vegetable ingestion doses for the fourth quarter are the result of activity deposited on feed u
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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 fourth quarter is through inhalation.
As a result of the milk and fresh vegetable pathways, the maximum dose for the third quarter from gaseous releases of radioactive iodine and particulates was determined to occur at a farm 3.5 miles south-southeast of the plant. The critical organ was an tufant thyroid with a calculated
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---dose of 0.049 mrem. For the fourth quarter, with inhalation being the
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principle pathway of exposure, the maximum organ dose was projected to also be at the same farm. The critical organ was a child's thyroid with a calculated dose of 0.0081 mrem. The pathways of exposure which were assuned to exist during the third quat ter at this farm include ground plane exposure, inhalation, fresh home grown vegetables and cow's milk. The pathways of exposure considered at the farm during the fourth quarter include continuous ground plane exposure, inhalation and contributions from stored vegetables and milk.
e Table 7 shows the maximum calculated quarterly organ dose due to the combination of exposures from all pathways which have been identified
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at the farm. Table 7 also shows the calculated organ doses to the highest exposed nearby res'. dent, and potential organ doses to individuals if a.ssumed
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, standing at the highest ground level air concentration point on the site l boundary for the entire six-month reporting period. The site boundary doses
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include only exposure from inhalation, and direct radiation from the ground plane. The nearest resident is assumed to have a vegetable garden during the growing season which contributes to his or her ingestion dose. For
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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 over the life of the plant. The calculated dose from direct exposure to activity on the ground thus represents the dose an individual would see in each quarter if ,the plant had been operating 15 years. This approach is very conservative, but shows the relative impact the plant would have on the dose consitment over its operating life if the releases were to continue at the levels recorded during this reporting period.
The critical organs for the third and fourth quarters for the nearest resident with the most exposure were the thyroid and bone respectively,
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and for the maximum site boundary location, was calculated in both cases
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to be a child's thyroid. The respective doses at these locations for the-third quarter were 1.7 x 10-3 mrem (SSE 1.3 miles) and 2.1 x 10-4 mrem (SSE 0.53 miles). For the fourth quarter both doses were 4.4 x 10-4 mrem.
4.4 Whole-Body Doses in Unrestricted Areas from Direct Radiation
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The major 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 adjacent reactor building, only the seven westerly sectors (SSW -
NNW) see any significant direct radiation.
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High pressure ionization chamber (HPIC) measurements have been made
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in 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.
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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 dose equivalents, in units of rem, in accordance with recommendations of RASL report 305(6) for radiation fields resulting from N-16 photons.
Estimates of the population exposure from direct radiation during
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. . . the third and fourth quarters have been made out to two miles. Beyond two miles, the dose from the turbine building is negligiole. As a result, the estimated population dose for each of the two quarters respectively was approximately 1.6 x 10-2 and 1.3 x 10-2 person-rem, for a total population of about 351 persons. The estimated direct radiation dose at the maximum, site boundary location was approximately 2.8 mrem for the third quarter of 1979, and 2.3 mrem for the fourth. These hypothetical individual doses assume a 100 percent occupancy factor, taking no credit for the shielding effect of any residential structure. Table 7 summarizes these results.
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4.5 Whole-Body Doses to the General Population from all Receiving Water Related Pathways Using the liquid pathway whole-body dose model discussed in Section 4.1, an estimate of the population dose due to the third quarter liquid
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at the site of the maximum individual (see Section 4.1) was assumed to apply to the entire yield of fish within fifty air miles of the plant. No credit was taken for radionuclide loss by sedimentation or further dilution by
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4 tributaries below Vernon Dam nor for the biological removal and decay of activity in the fish during the time periods when no radioactivity was being discharged from the plant.
A 1975 creel census of the Deerfield River, which is a stocked tributary of the Connecticut River downstream of the plant, reported an annual average catch of 431 fish per river mile in a 28 week season. The average weight of these fish was conservatively estimated to be equivalent to one pound of edible flesh. Assuming that there are 100 downstream river
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miles within 50 miles of the plant, the yearly yield of edible fish mass
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in the Connecticut River may be estimated as:
431 fish / mile x 52 weeks x 1 lb. x 0.453 Kg x 100 miles 28 weeks year fish lb.
- 3.6 x 104 Kg/ year '
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Fishing activity is greater on the Deerfield River than on the Connecticut River because the stocked fish attract more sport fishing activity. If it is assumed that one-half of the annual fish catch is caught and con need in the quarter, the resulting calculation yields a quarterly population dose commitment of 3.5 x 10-3 person-rem for a population made
- up of adults (62.6 percent), teenagers (11.9 percent) and children (23.7 percent).
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4.6
_ Doses to the General Population and Average Individual Within Fif ty Miles from Caseous Effluents Using site meteorological data in Tables 4 and 5, quarterly average I/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 fifty miles, and their intersection with radial lines drawn to form each of the sixteen principal compass directions. For noble gases, whole-body and skin doses were calculated for each sector and
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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 third and fourth quarter whole-body doses from noble gas cloud ~
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exposure were estimated to be 1.3 person-rem and 0.5 person-rem, respectively.
For the same two quarters, the average individual whole-body doses were 1.1 x 10-3 mrem and 4.5 x 10-4 mrem, respectively. The skin doses for the two quarters were 2.1 person-rem and 0.95 person-rem, respectively.
The average individual skin dose was 1.8 x 10-3 and 8.2 x 10-4 mrem for the third and fourth quarters.
Table 7 also indicates the population whole-body and thyroid dose connitments from radioactive iodine and particulates (including tritium) released from the plant in gaseous vaste. 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 andthyroiddosecommitmentsforthethirdquarterverecalcukatedtobe
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l.1 x 10-2 person-rem and 6.3 x 10-2 person-rem respectively. For the fourth quarter, these doses were 9.4 x 10-2 person-rem and 0.11 person-rem respectively.
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REFERENCES
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- 1. Regulatory Guide 1.111. "Hethods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-
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Water-Cooled Reactors", U.S. Nuclear Regulatory Commission, Office of Standards Development, March 1976.
- 2. Meteorology and Atomic Energy, 1968, Section 5-3.2.2, " Cloud Depletion",
pg. 204. U. S. Atomic Energy Commission, July 1968.
- 3. C. A. Pelletier, .and J. D. Zimbrick, " Kinetics of Environmental Radiciodine 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, i
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1976. .
- 5. Regulatory Guide 1.109, " Calculation of Annual Deses 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, Octobtr 1977. ,
- 6. W. M. Lowder, P. D. Raf t, and G. dePlanque Burke, " Determination of.
N-16 Camma 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 Ei'9.'s",
Revision 2, July 1979; Table 4.11-1, notation f.
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TABLE lA VERMONT YANKEE EFFLQENT AND WASTE DISPOSAL SEMI ANNUAL REPORT
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JULY - DECEMBER 1979 CASE 0US EFFULENTS - SUMMATION OF ALL RELEASES
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Unit Quarter Quarter Est. Total 3 4 Error, %
A. Fission & activation gases k-
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1.Totai Eelease"
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- 2. Average release rate for period <7.91E2 <7.78E2 1.0 E2 3.
uCi/sec <1.01E2 <9.89El Percent of technical specification limil % <1.24E-1 <8.47E-2
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B. Iodines
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- 1. Total iodine - 131 Ci 3.16E-3
- 2. Average release rate for period 6.56E-3 5.0 El uCi/sec 4.02E-4 8.34E-3
- 3. Parcent of technical specification limit % 8.37E-2 1.74E-1 C. Particulates
- 1. Particulates with half-lives Ci 1.39E-3
- 2. 1.52E-2 5.0 El i Averaee release rate for oeriod uCi/sec 1. 76E-4 5.25E-4 j 3. Percent of technical specification limit
, 4 Cross alpha radioactivity
% 1.29E-2 8.54E-2 C1 1.71E-7 1.87E-7 D. Tritium
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- 1. Total release Ci 7.60E0 2.56E0 I 5.0
. 2. Average release rate for period E1 I uCi/sec 9.66E-1 3.25E-1
- 3. Percent of technical specification limit % N.A.
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TABLE IB
- EFFLUENT AND WASTE DISPOSAL SEMIANNUAL JULY - DECDiBER 1979 GASEOUS EFFLUENTS - ELEVATED RELEASE
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E CONTINUOUS MODE BATCH MODE *(2)
Nuclides Released t u Unit Quarter 3
Quarter Quarter 3
s 4 Quarter
- 1. Fission gases 3 f
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krypton-85 - ~~
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l krypton-85m Ci - * (l)
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krypton-87 Ci *(1) E
<2.99EO <3.43E0 E kryp ton-88 Ci <1.49El- E Ci <1.05El E [
xenon-133 <1.03El E Ci <8.29E0 E xenon-135 <7.78E1 E _
Ci <2.85E2 E xenon-135m <2.21El <1.60El E E
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xenon-138 Ci <l.30E2 <9.67El E_ _ E
_Ci <5.33E2 Others (specify) ~ Ci- <3.58E2 E _
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E E Ci E E l E E Ci E E unidentified Ci E E E
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i Tota {for period E E E
l Ci E E ]
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<7.91 E2 { <7.78E2
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- 2. Iodines l E <
E t
iodine-131 iodine-133 1
Ci t 3.16E-3 I Ci 6.56E-3 I iodine-135 5.14E-3 E '
E '
u Total for period Ci 2.00E-3 2.62E-3 4.72E-3 E
E 3 Ci i 1.09E-2 E l
1.33E-2 E
- 3. Part.'culates
<
E 1 E 1
-
__
3 st ron tiem-89 ;
i Ci 5.01E-5
\
strontiun30 Ci 5.1BE-4
\
1 cesium-li4 2.18E-6 1.32E-6 E
E
_
cesium-137- Ci 2.54E-4 E Ci 3.91E-4 E
- barium-lanthanum-140 2.15E-4 6.65E-4 E
E cobalt-58 Ci 3.46E-4 E 1.29E-4 _ _ E
_
cobalt-60 _
Ci 2.23E-3 8.39E-4 E
E '
zinc-65 Ci 3.15E-4 E ,' '
E manganese-54 Ci _2.03E-4 8. 32 E--] E L C1 3.04E-3 E cerium-139 2.47E-5 1.71E-4 E E L cerium-134 Ci E j_ 7.60E-6 < 2.83E-5 E Ci i<4.07E-5 i 1.61E-5 t E E
(
- (1) Kr00 j
- (2) No Batch mode es for *** -
releasnot detected in offgas y = 6.79E-7 mix-limit uCi/cc of detecta
-
_, ; . .. _ .-.---
-
,.-7-----, ,__ ,__;___,_,_,
- -
, , . . . . . . . . . , . .
.
.
TABLE IC VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 197 JULY - DECEMBER CASEOUS EFFLUENTS - ROUTINE CROUND LEVEL RELEASES *
. ; -
. - - -
_
- There were no routine measured ground level continous, or batch mode
,
gaseous effluent releases during the reporting period. -
.
J e
.
O e
t
.
.
.
_ _ , ,
... .
, _-
- _ . . _
.
TABLE ID
- VERMONT YANKEE EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT - 1979 JULY - DECEBER GASEOUS EFFLUENTS - NON-ROUTINE RELEASES *
.
- . _ _ _ _
- There were no non-routine or accidental gaseous effluents releases.
during the reporting period.
.
-
,
t
.
8 I
t
.
t o
._. _._. , --
,_;--- -
_
.
. . . . . . - - - _ . - . - _ . . . .
. ... . .
. ... - - . . . - . .
.. . - . . . - -.
'
.
.
TABLE 2A
.
EFFLUEhT AND WASTE DISPOSAL SEMIANNUAL REPORT
- ,
JULY - DECEMBER 1979
!
.
. LIQUID EFFLUENTS - SU5MATION OF ALL RELEASES
!
-
Unit Quarter Quarter 3
Est. Total 4 *1 Error, 't.
A. Fission and activation products
__
'
- 1. Total relecse (not including tritium, gases, alpha)
Ci 2.40E-4
- 2. Average period diluted concentration during 15.0E1 I pCi/ml 7.16E-10
- 3. Percent of applicable limit % s 7.I6E-1 B. Tritium
- 1. Total release
._ Ci 4.04E0
- 2. Average diluted concentration during 5.0El
'
period
- 3. Percent of applicable limit VCi/mi 4.16E-6
,
% 1.38E-1 C. Dissolved and entrained gases
.
- 1. Total release C1 1.06E-1
- 2. Average period diluted concentration during i5.0El
- 3. Percent of applicable limit UCi/ml 1.62E-7
%
"
4.05E-1 D. Gross alpha radioactivity
_
- 1. Total relt ase '
Ci *2 t5.0El
!
E. Volume of waste released (prior to dilution) liters
,
I A1.0 El
.
,
F. Volume of dilution water used during period liters
--
- 1 .
No Liquid Effluents for 4th Quarter 1979 -
- 2 No alpha detected, Minimum sensitivity - <9.00x10~II uci/ml o
.. .. . . .-
_ . . . . . .- -. -. . . . - .
___ __ _
.
TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JULY - DECDGER 1979 LIQUID EFFLUENTS -
5 CONTINUOUS MODE *1 BATCH MODE *2 Nuclide., Released Unit Quarter Quarter Quarter Quarter 3rd 4th 3rd. 4th strontium-89 Ci <4.84E-6 strontium-90 Ci 2.71E-6
, cesium-134 Ci <8.62E-6 cesium-137 C1 <1.08E-5 iodine-131 Ci <6.68E-6 cobalt-58 Ci <1.10E-5 cobalt-60 Ci <1.54E-5 iron-59 Ci <2.58E-5 zine-65 Ci <2.89E-5
,
manganese-54 Ci 5.85E-5 chromium-51 Ci <5.03E-5 zirconium-niobium-95 Ci <2.27E-5 molyb<lenum-99 Ci <2.90E-6 technetium-99m Ci <3.09E-6 barium-Janthanum-140 Ci <3.21E-5 cerium-141 Ci <5.66E-6 9
Other (specify) Ci Ci Ci Ci Ci unidentified Ci i
- Total for period (above) Ci e
<2.90E-4
- ..
xenon-133 Ci 2.92E-2
_
xenon-135 '
Ci 7.64E-2
- 1 No continuous mode releases.
- 2 No 4th Quarter batch releases.
. .
, . . . - . . -
--
_. . _ . _ _
,
.-.------..~.--..--.-. -.
...._
_ . . . _ __
.
TABLE 3 EFFLUENT AND WASTE DISPOSAL SE!!IANNUAL REPORT
- JULY - DECEMBER 1979 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. bOLID h'ASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSA
- 1. Type of waste Unit 6-month Est. Total
' ,
Period Error, % ,
- a. Spent resins, filter sludges, evaporator m3 3.59El bottoms, etc. Ci + 7.5El 7.01E2 -
- b. Dry compressible waste, contaminated m3 1. 72El
, equip, etc. Ci
+ 7.5El
'
1.87E0 -
- c. Irradiated components, control m3 0 rods, etc.
Ci 0 mb 0
- d. Other (describe) Ci 0
.
- 2. Estimate of major nuclide composition (by type of waste)
- a. Ce-141 % 4.69E-2 I.131 % 1.04E-1 Cs-134 % 2.90E+1 Ba-140 % 5.18E-1
.
Cs-137 % 5.llE+1 .Cr-51 % 4.51E-2 Co-58 % 7.31E-1 Zr-95 % 1.27E-2 Mn-54 % 2.67E-1 ' I-134 Zn-65
% 5.71E-3
% 1.21E-1 Mn-56 % 5.50E-3 Co-60 % 1.71E+1 i r,-110 % 1.54E-3
% %
- b. Cs-134 % 2.31E+1 '
Mn-54 %
Cs-137 '
2.45E0
% 4.08E+1 Zn-65 % 8.38E0 Co-58 9.80E-1
' % Co-60 % 2.43E+1
% %
- c. % %
% %
- d. g g
% %
- 3. Solid Waste Dispo'ition s
.
, Number of Shipments Mode of Transportation Destination -
-
9 Truck Chem-Nuclear
,
,-
,
, Barnwell, South Carolina
B. IRRADIATED FUEL SHIPMENTS (Disposition)
Number of Shipments Mode of Transportation
- Destination None
'
a
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. . . . . . . . . . . . . , . . . - . . . ., ,, , ,_ ,, e w ... %!y}{ D h_ 3 h@ f$a .o. ... .NN hmm N.. .-- N.. 4 OO MSG hew Nem FNN mer mee - e e M e e e** ee e 600 u m o e m o e o e N e e > DO em op we 9e er mm NGO m mm MM NN mm OO ,E mm & E J 300 300 000 coo m #G Om OO 333 000 eso esO 3 90 00 OO OL OO e 3 e e e e e e e e e e e e e e > Oo OO OC e o e OO OO OO DO em E OOS ONN emm O 044 mNN Nmm woo One > K E 00 e e ese Wee emm WNN eFF mmm mee e e o e e m o e e e e o e e e o e 00 == ee ee mm mm J OO e NN 3 a DoD emm D e*, mee eSe eGe Dee Omm Wee do OO Mpp err Wem emm mmm mee FOO e e e e e e e e o e o e o e m o e OO mm 3 NN NN wm FF u O a pmm 2 9 2 300 eee epp moe Wee ede wh> 4 e OO ee Nam =OO hem New mM 944 & a e o e e e o e e e e o e e e - e e > O Oe == O NN MM - ==
- WW a e 2 000 moo >>> ese e e se -me m>>
ehh MDP mem eNN w e e e e mer NNN mem OO chh J m e o e e e e e e e e e e e . . . . . . _ , . mm y y .De -. um ee O - . - . ._ 4 W W X eOS ese mOC W < u e GO mm =pp hhh Mew MOO DOO ekh & -h> mm OO DO e e & *
- e e o e e e o e e e e e MMM e e w OO OO E OO == O w &
= 3 000 e>> M y > e eNN mee ese mye con mee d > u 90 NN mee mee mm 90 OO S00 w e e e e e e e e e e e e u 4 De e e e e w w DO NN L O. 3 E J ep O g E too mee ese Neo won wem mem NNN p 3 m a e OO mer med NOO wer E L e e e e e e e s e 99 OO een e m e e e e o e e e e DO == E > 2 NN u' h a Q s u e = m ooO mee ehh === @ D 4 h OO NOC FNN -NN mee ooo mmm w J u e e e e o e OPP - e e DNN mem GO eOO W W w OO == o e o e e e N e o y NN es MM OO 3 e W N se N. e < J G w Oee b w - c o. o m e. e. m. m= = m e n, see se.e , o e .. .m m.--m. . m. N. W. . == ee m. m .Oe . - .. . . e m. N w 4 oO em se J = NN 3 == 3 w S00 emm e@ e Mmm w e e@ mee RO O ewe med mm Nee mem Nee a - e e e e WO 90 err u a e e e e b o e e e e e J em NN ee w- N e e OO u 3 J Me a g wm um E w OOO Nem gw c e m e oO mee meen== mem oneNN eso on op Geo om ees NNN && a w e o e e e e e e o e e o W e oc == -m em og e e e o em 3 J eO NN == e u KK = m emo mee e>> 9c0 000 000 ph e > .t e nt e hn ec 000 eNN = > #E *s c *ts nP P es e e e e e e e e e e o e a = .e e == e o e e og
J eo se se me == mm u
n, w een mem mee noe woo poo me
> = 4 Om Ne* -- en ooo eve se u > OO oO oO uu w * * * *
- e * * * *
- e e e Noe 4 w eO e9 * * ==
w OO en so == ww a em
- a w een om- men eso -em >>
w ee eeO one Neo *za 4 New OO SO en oO eo 2 * * * * * * * * *
- Neo ww m so
- e
- e * * ##
. se ao ao == az
.
- QQ a w 000 ese New WNN mem som one are j m 3 e .
d 2
eO e e N==
e e mer e e mm e e ao e e em om ean ouo 00 m e e o e e 33 7 se ==
We me e NN w u.
W D
.
w a goo see NNN JJ a O em mem ese See em" mFP
-em eenOO eso kmm sa a g e e e e e e ** e e e o Se mme eg
% m e e e o e eO ** NN NN OO ce
> & MM k%
m
, uu
>
d b m gmm mmm ham Nam ema emm MM Q E JmN 3-N tmN saa emm ZZ
& O
- N ==N N=N N=N OmN we g a a gww uww aww Swa tw= tww ww www wu w
a u e M e - w me w
- F G a - e a we N w e h%
w W e s J mm e a -N
= w&
...
-I
.
TABLE 6
.
!.
VERMONT YANKEE l!
QUARTERLY AVERACE X/Q, D/Q AND CAMMA I/Q
'
'
VALUES FOR SELECTED RECEPTORS
.
.
POINT OF INTEREST t THIRD QUARTER FOURTH QUARTER
.
Maximum offsite ground Location: ;
1evel air concentration WNW 1.5 mi Location: i location X/Q (undepleted)*: 4.904x10-}es NW 2.5 mi1
- X/Q (depleted)*: X/Q (undepleted): 4.811x109s 4.882 x 10-7 X/Q (depleted):
>
D/Q**: 9.418 x 10-10 4.588 x 10-7
- i Camma X/Q:* D/Q: 1.290 x 10-10 .
2.211 x 10-7 ,
,
Camma X/Q: 2.347 x 10-7
- For whole body and skin ,
doses from noble gases
- 1) Maximum site boundary t
Location: S 0.24 mi location
,
X/Q (undepleted): 2.10x10-ges Location: N 0.25 mi
!
X/Q (depleted): 2.10 x 10-9 X/Q (undepleted): 3.04x10-gs i D/Q: X/Q (depleted): 3.04 x 10-II t
1.03 x 10-II D/Q: ,
Camma X/Q: 7.38 x 10-7 2.90 x 10-13 ,
Camma X/Q: 5.38 x 10-7 ',
- 2) Maximum nearest Location:
residence S 0.33 mi Location:
X/Q (undepleted): 3.65x10ges S 0.33 miles '
X/Q (depleted): X/Q (undepleted): 5.58 x 10-10 3.65 x 10-9 X/Q (depleted):
,
D/Q: 2.00 x 10-II 5.58 x 10-10 D/Q: 4.17 x 10-12 Camma X/Q: 5.41 x 10-7 For organ doses from Camma X/Q: 3.21 x 10-7
,
iodine and particulates in gaseous effluents -
,
- 1) Maximum farm location Location: 1
,!
SSE 3.5 m Location:
X/Q (undepleted): 2.84x10-}1es SSE 3.5 mi -
e X/Q (depleted): X/Q (undepleted): 2.42x10-}1es 2.80 x 10-7 X/Q (depleted):
D/Q: 9.71 x 10-II 2.37 x 10-7 D/Q 1.02 x 10-9 Camma X/Q: 1.82 x 10-7 Camma X/Q: 1.58 x 10-7
"
.
G
'
,i
. v - . ... g
. . *
!
-
. t i
. .
-
TABLE 6 (continued) \
,
POINT OF INTEREST i s
TillRD QUARTER . \
FOURTil QUARTER a !
'
- 2) Maximum nearest residence Location: SSE 1.3 a .
- X/Q (undepleted): 8.27x10gles Location: SSE 1.3 m X/Q (depleted): X/Q (undepleted): 8.35x10gles .,
8.25 x 10-8 X/Q (depleted): ,' :
D/Q: 4.63 x 10-10 8.33 x 10-8 , i D/Q: 5.74 x 10-10 i
,
Camma X/Q: 2.82 x 10-7 ,
Camma X/Q: 2.44 x 10-7 l I
- 3) Maximum site boundary Location:
location SSE 0.53 Location:
'
i X/Q (undepleted): 4.33x10-giles SSE 0.53
- X/Q (depleted): X/Q (undepleted): 6.67x10-giles
- 4.32 x 10-8 X/Q (depleted):
D/Q: 2.82 x 10-10 6.66 x 10-9 -
l Camma X/Q: 5.47 x 10-7 D/Q 6.90 x 10-II i Camma X/Q: 4.49 x 10-7 l Depleted and undepletedX/Qs and Gamma X/Q are in units of sec./m 3 Delta (D/Q) in units of 1/m2
,
.
.
..
.
~
TABLE 7
'
SUMMARY
OF RADIOLOGICAL IMPACT ON MAN
-
' Vermont Yankee Nuclear Power Station :
- Third and Fourth Quarters, 1979
.
t EST1 HATED THIRD ESTIMATED FOURTH 1
TENTIAL PATHWAY OR TYPE OF EXPOSURE '
QUARTER DOSE !
QUARTER DOSE . '
COMMITNENT COMMITMENT l {
Maximum individual whole body and Whole Body
-
.
critical organ doses from receiving- 3.2 x 10-6 ! I water exposure pathways from 2.6 x 10-6 (adult)
' '
liquid releases (arem). teen) No liquid releases ,
'
2.2 x 10-6 ((child)
Castro-Intestinal- l i
'
Lower-Largg 4.2 x 10- (Intestine '
!
3.0 x 10-6 teen)
(adult) ,
1.8 x 10-6 (child)
.
A. Whole body and skin doses to individuals exposed at point '
of maximum offsite ground I 1evel air concentration of radioactive noble gaseous l effluents i (at WNW, 2400m) (at NW, 4000m)
- 1. Skin dose (arem)
- 11. 6.9 x 10- 4.9 x 10-2 Whole body dose (ares) 3.0 x 10-2 2.2 x 10-2 B. Whole body and skin doses at maximum site boundary location from radioactive noble gaseous ef,fluents (at S, 0.24 miles) (at N, 0.25 miles)
- 1. Skin dose (area)
- 11. Whole body dose (area) 9.9 x 10-2 5.0 x 10-2 9.9 x 10-2 5.0 x 10-2 C. Whole body and skin doses at maximum nearest residence ,-
from radioactive noble gaseous ,
effluents.
(at S, 0.33 miles) (at S, 0.33 miles)
- 1. Skin dose (mrem)
- 11. Whole body dose (arem) 7.3 x 10-2 3.0 x 10-2 7.2 x 10-2 1.0 , in-2
.
. , . . .
'
, . . . . . .
.
.
.- i'
- \
8 TABLE 7 (continued) ii
.
50TENTIAL PATifWAY OR TYPE OF EXPOSURE ESTIMATED TIIIRD F .TIMATED FOURTil '
QUARTER DOSE QUARTER DOSE '
COMMITMENT COMMITMENT
- 11. Organ doses to individuals from .
radioactive lodine and particulates .
in gaseous effluents (including tritium). ,
,
'
A. Maximum farm location e
' i
'
Maximum individual whole body !
and organ doses from all pathways (at SSE, 3.5 miles) (at SSE, 3.5 miles) i i.
Bone (mrem) {
, 11. Thyroid (arem) 1.1 x 10-3 .
4.9 x 10-2infant)
((child) 8.2 x 10~3 child) !
111. CI(LLI) (arem) 8.1 x 10-3 ((child) iv. Whole body (arem) 8.6 x 10~4 (child) 7.4 x 10~3 teen) !
1.0 x 10-3 (child) 7.3 x 10-3 ((child) !
B. Critical organ doses to maximum nearest resident from the inhalation, lngestion and ground plane exposure of iodine and particulates (at SSE, 1.3 miles) (at SSE, 1.3 miles)
- 1. Bone dose (mrem)
- 11. Thyroid dose (mrem) 3.7 x 10~4 (child) 111. CI(LLI) (arem) 1.7 x 10-3 4.4 x 10-3 child) iv.
Whole body as critical organ 2.8 x 10-4 (child) 4.3 x 10~3 ((child)
(mrem) 3.2 x 10-4child)
((child) 4.0 x 10~3 teen) 3.9 x 10-3 ((child)
.
.
- - , . . . . . .
,
.
.
.
'
.
.
'
.
'
TABLE 7 (continued) '
'
- l POTENTIAL PATifWAY OR TYPE OF EXPOSURE ESTIMATED TIIIRD !
ESTIMATED FOUR1H QUARTER DOSE !
QUARTER DOSE '
COMMITHENT COMMITMENT '
,I C.
Organ doses to individuals at point of maximum ground level air l-
'
concentration of gaseous effluents ,
- from inhalation and ground exposure .
of iodine and particulates e .
(at VNW, 2400m) -
,'
i.
(at NW, 4000m)
Bone dose (arem) ,'
- 11. Thyroid dose (arem) 3.4 x 10-4 (teen) 1.6 x 10'3 8.2 x 10-4 111. GI(LLI) (arem) 2.5 x 10-3 (child) iv.
Whole body as critical organ (mrem) 4.8 x 10 (child) teen) 8.8 x 10~4 (child)
I S 4.8 x 10-4 ((teen) 8.5 x 10-4 adult
((adult) -
j
' D. Organ doses to individuals at or teen) j point cf maximum site boundary air concentration of gaseous !
'
effluents from Inhalation and ground exposure of iodine ' }
and particulates .
(at SSE, 0.35 miles)
- 1. (at SSE, 0.53 miles) ,
Bone dose (arem)
- 11. Thyroid dose (mrem) 9.9 x 10-5 (all) .
4.2 x 10~4 111. GI(LLI) (arem) 2.1 x 10 (child) 4.4 x 10-4 (all) iv. Whole body as 1.1 x 10'4 (all) 4.2 x 10~4 (child) critical organ 1.1 x 10-4 (all) 4.2 x 10-4 all)
((all) t
.
.
. . . , ..
..
-;.
- -i
.
.
'
,
-
1
' !
1
, .
TABLE 7 (continued) l
, I i i i
ESTIMATED TIIIRD ESTIMATED FOURTH
'OTENTIAL PATilVAY OR TYPE OF EXPOSURE k QUARTER DOSE QUARTER DOSE COMMITMENT !
.
COMMITHENT l
V. !
Whole body doses to individuals and I populations in unrestricted areas i i
from direct radiation from the :
g facility.
i e A. Maximum site boundary (mrem)
'
'
.
.
(west of turbine -
.
building) 2.8 2.3 ! >
B. Population dose (person-rem) 1.5 x 10-2 1.3 x 10-2
.
Whole body dose to the population from all receiving-water related pathways from liquid releases.
(person-rem). ,
3.5 x 10-3 No liquid releases t
.
.
- . . ~ . - . . . . . . ,
,
. . . .
. ;1
.-
>
.
9 . hh
(
-
il
,,,
,
, i, TABLE 7 (continued) l l
f'
QUARTER DOSE COMMITMENT [
!
COMMITNENT e .l VI.
- I!
A. ~ ! ,!
Whole body doses to the population
and average individual out to 50 l'
'I alles from noble gaseous ! i I,'
effluents i
'
,
t *
- 1. Whole body dose to population 1 l (person-rem) l
- 11. 1.3 !
Average individual whole body , 5.1 x 10-I '
dose (mrem) ,
111. Skin dose to population 1.11 x 10-3 4.5 x 10-4 i (person-rem) iv. Average individual skin dose 2.1 9.5 x 10-I (arem) ,
1.8 x 10-3 8.2 x 10-4 B. Organ doses to 50 mile popula- ;
, .
tion, and average individual, '
'
from inhalation, inge,' tion of milk, meat, and vegetables, and ground exposure to iodine and parti-culates in gaseous effluents *
- 1. Thyroid population dose (person-rem)
- 11. Ayerage individual thyroid 6.3 x 10-2 1.1 x 10-I dose (mrem) iii. Whole body population dose 5.5 x 10-5 9.2 x 10-5 (person-rem) .
iv.
Average individual whole body 1.1 x 10-2 9.4 x 10-2 dose (mrem) 9.5 x 10-6 .
8.2 x 10-5
.
. . _ . ,. . . . . _ _ . . . . . . _ . . . ' . _ _ _ _ _ . . . . . . . . . _ _ _ _ . . -
- ' .
._..
.
. . . . _ ... . ._ . . . . . . . . . . . _ _ _ . . . . .
. .
.
APPENDIX A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT
-
Supplemental Information July - December 1979
Facility: Vermont Yankee Nuclear Power Station
, . _
_.
Licensee: Vermont Yankee Nuclear Power Corporation
_ 1. Regulatory Limits
.
.
- a. Fission and activation gases: 0.08/E7 Ci/sec.
.
- b. Iodines: 0.48 pC/sec.
- c. Particulates, half-lives >8 days:
1.6E+3 MPCa Ci/sec.
- d. Liquid effluents:
1.03-7 uC/ml (HTO: 3.0E-3 pC/ml, dissolved Noble gases:
,
,
4.0E-5 uC/ml). isotopic limits are found in 10CFR20 App. B, Table II, Column 2.
.
- 2. Mar.imum Permissible Concentrations
.
. Provided below are the MPC's used in determining allowable release rates or concentrations.
- .-
.
.
- a. Fission and activation gases: No MPC limits
,
.
t i
N
._ _-
' _ . . _ . _ _ _ . . .
, 2.'-...,........-.................-..
.
c.
Particulates, half-lives >8 days: See 100FR20, App. B, Table II, Column
- d. Liquid effluents: See 10CFR20, App. B, Table II, Colucm 2.
. 3. Average Energy Provided below are the average energy (I) of the radionuclide mixture in releases of fission and activation gasses, if applicable.
- a. Average gamma energy: 3rd Quarter 0.987 MeV/ Dis.
- - - - .
. _ _ .
4th Quarter 0.685 MeV/ Dis.
- b. Average beta energy: Not Applicable 4.
Measurements and Approximations of Total Radioactivity ,
.
Provided below are the methods used to measur, or approximate the total radioactivity in effluents and the methods used to determine radionuclide composition.
a.
Fission and Activation Cases
.
Daily samples are drawn at the discharge of the Air Ejector.
Isotopic breakdown of the releases are determined from these samples. A logarithmic chart 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 Cas system the error of release rates may be approximately 2'
+ 100%. -
.
@
.
. . . . . . . . ..
- . . - . . - . . . . . . . . . .
- - . . .
- - - . - . . - - .
, .... .. . . .
. . . . . . . . . . . . - - . . . . .
...
.
- b. Iodines Continuous isokinetic samples are drawn from the plant stack
,
through a particulate filter and charcoal cartridge. The filters 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 radioicdine 131, 132, 133, 134, and 135.
5
-
The iodines found on the filter are added to those
,
- - .- - : .- -- - .
_
on the charcoal cartridge. The error involved in these steps
-
may be approximately 150%.
- c. Particulates
- .
_
The particulate filters described in b. above are also counted -
for particulate radioactivity. The error involved in this sample is also approximately 150%.
- d. Liquid Effluenta
.
Radioactive liquid effluents released from the facility are continuously rionitored.
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 (pCi/ml) of gross
- radioactivity, volume (liters), and approximate total quantity
,.
. . of water (liters) used to dilute the liquid effluent prior to release to the Connecticut River. r
.
M
.
.
. -p - _ . - - - . . . . . - . . . .
- -- - - . - - - - - ~ . . . ~ . .. . . . . .
Each batch of radioactive liquid effluent released is analyzed for gross gamma and gan=a isotopic radioactivity. .A monthly proportional composite sample, comprising an aliquot of each batch I
released during a month, is also analyzed for tritium, SR-89, SR-90, gross beta and gross alpha radioactivity, in addition to gamma spectroscopy.
,
There were no liquid releases during the reporting period.
t ~
. . . . . ~ 5..' Batch Releases~
- a. Liquid
- 1. Number of batch releases: 16 ".
.
- 2. Total time period for batch releases: 14,490 min.
- 3. Maximum time period for a batch release: 1,539 min.
- 4. Average time period for batch releases: 905 min.
- 5. Minimum time period for a batch release: 331 min.
- 6. Average stream flow during periods of release 4,063 cfs
.
i of effluent into a flowing stream:
- b. Caseous
.
-
'
There were no routine gaseous batch releases during the repo,rting
' t
.
.
, period.
. *
{
. :.
-
)
.
@
A4
. . . _ _ . . . _ .
~
,
,. . _ _ _ . _ _ _ . . _ . _ .
.. . - _ . . . _ . -
. . . . _ _ _ _ ..._
.
- 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 period.
.
e 6
9
.
.
&
O 9
RE