ML20206M632
| ML20206M632 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 08/13/1986 |
| From: | Stello V NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Frank B HOUSE OF REP. |
| Shared Package | |
| ML20206M636 | List: |
| References | |
| NUDOCS 8608210281 | |
| Download: ML20206M632 (36) | |
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AUG is W The Honorable Barney Frank United States House of Representatives Washington, DC 20515 1
Dear Congressman Frank:
We are pleased to respond to your letter dated July 1,1986, which requested detailed information regarding the records of radioactive effluent releases at the Pilgrim Nuclear Power Plant in Plymouth, Massachusetts.
i i
In response to your request to provide various listings, enclosure 1 to this L
letter: describes some of the radionuclides released during routine operation i
and the radiological impact on humans; provides a summary of actual release data and calculated resultant doses; and identifies those releases which exceed-ed the limits for normal operation. The limits for normal operation are defined in the facility license as Technical Specification limits. These are normally a fraction of the values for routine releases allowed by NRC regulations,10 CFR, Part 20. Enclosure 2 contains the licensee's Semiannual Radioactive Effluent Release Reports.
Small amounts of radioactive effluents are expected from commercial operating I
reactors. Gaseous and liquid radioactive material is produced which consists of fission products and activation products resulting from irradiation of the reactor water and impurities therein (principally metallic corrosion products).
Small amounts of these radioactive wastes are released to the environment through the gaseous and liquid. radioactive waste treatment systems. These systems are designed to collect, filter and holdup for decay the radioactive i
i waste so that it may be discharged from the site at levels which do not exceed i
regulatory requirements and which are as low as reasonably achievable.
Instru-mentation is provided on the radioactive waste systems to monitor and control the releases of radioactive materials to the environment.
t Radioactive effluents from commercial power stations are limited by regulations; further refinements to these regulations resulted in the establishment of a con-cept designed to restrict releases to "as icw as is reasonably achievable" (ALARA).
Title 10 of the Code of Federal Regulations, Part 20 (10 CFR 20) establishes limits on the concentrations of radioactive material that may be released to un-r restricted areas in the environment. These concentrations have been derived such that any individual exposed to them for the duration of one year will not I
exceed 500 millirem.
Numerical guides and design objectives for further limit-ing releases were codified in Appendix I to 10 CFR Part 50. Several design ob-jectives are included in Appendix I, but to simplify comparison the threshold for annual gaseous releases is 5 millirems to the total body of an individual.
The Technical Specification limits are derived from Appendix I.
Consequently, maintaining releases within the established limits should result in negligible radiological impact on members of the public from routine operation of the facility.
8608210281 860813 PDR COMMS NRCC CORRESPONDENCE PDR
-L,--..--...-
The Honorable Barney Frank 2
A review of the enclosed effluent data for Pilgrim indicates that liquid efflu-ents in 1981 slightly exceeded Appendix I guidelines for maintaining exposures as low as reasonably achievable, however, the doses calculated were small per-centages of the limits specified in 10 CFR 20 and posed no threat to members of the public. No other instances of doses above Appendix I guidelines were noted.
I trust this information is responsive to your request.
Sincerely, (somed) T. A. *
- 1 Victor Stello, Jr.
Executive Director for Operations
Enclosures:
1.
Effluent Data for Pilgrim 2.
Radioactive Effluent Release Reports July 1976 - December 1985
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The. Honorable-Barney Frank 3
Distribution:
H. R. Denton, NRR J. M. Taylor, IE
- T. E. Murley, RI R. W.'Starostecki, RI T. T. Martin, RI H. B. Kister, RI J. R. Strosnider, RI R. R. Bellarny, RI W. J. Pasciak, RI EDO 001916 SECY 86-680-Public Document Room (PDR) local Public Document Room (LPDR)
Docket No. 50-293 OCA V. Stello J. Roe T. Rehm J. Sniezek RI:DRP RI:DRSS RI:DRP RI:DRP RI:RA Strosnider/ms Bellamy Kister Starostecki Murley 7/ /86 7/ /86 7/ /86 7/ /86 8/1/86 Ste
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86
s ATTACMENT I Pilgrim Nuclear Power Station Liquid and Gaseous Effluents Radioactive Effluent Releases Limited quantities of radioactive effluents are released to the atmosphere and to the hydrosphere from Pilgrim Nuclear Power Station (PNPS) during normal operations. These radioactive effluents are then diluted by the air and water into which they are released before they reach areas accessible to the general public.
Radioactive effluents can be divided into several groups. Among the airborne effluents, the radioisotopes of the fission product noble gases, krypton and xenon, as well as of argon, do not deposit on the ground nor are they absorbed and accumulated within living organisms; therefore, the noble gas effluents act primarily as a source of direct external radiation emanating from the effluent plume. Dose calculations are performed for the site boundary where the highest external-radiation doses to a member of the general public as a result of gaseous effluents have been estimated to occur; these include the total body and skin doses as well as the annual beta and gamma air doses from the plume at that boundary location.
Another group of airborne radioactive effluents--the fission product radio-iodines, as well as carbon-14 and tritium--are also gaseous, but these tend to be deposited on the ground and/or inhaled into the body during breathing.
For this class of effluents, estimates of direct external-radiation doses from deposits on the ground, and of internal radiation doses to total' body, thyroid, bone, and other organs from inhalation and from vegetable, milk, and meat consumption are made. Concentrations of iodine in the thyroid and of carbon-14 in bone are of particular significance here.
A third group of airborne effluents, consisting of particulates that remain after filtration of airborne effluents in the plant prior to release, includes i
fission products such as cesium and barium and activated corrosion products I
such as cobalt and chromium. The calculational model determines the direct external radiation dose and the internal radiation doses for these contami-nants through the same pathways as described above for the radiofodines, carbon-14, and tritium. Doses from the particulates are combined with those of the radioiodines, carbon-14, and tritium for comparison to one of the j
design objectives of Appendix I to 10 CFR 50.
The waterborne-radioactive-effluent constituents could include fission products such as nuclides of strontium and iodine; activation products, such l -
2
+
as nuclides of sodium and manganese; and tritium as tritiated water. Calcu-lations estimate the internal doses (if any) from fish consumption as well as -
any direct external radiation from recreational use of the water near the point of discharge.
1 The release values for each group of effluents, along with site-specific meteorological and hydrological data, serve as input to radiation-dose models that. estimate the maximum radiation dose that would be received outside the facility via these pathways for individual members of the public, and for the general public as a whole. These models and the radiation-dose calculations
~
are discussed in the October 1977 Revision 1 of RG 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluatinr Compliance with 10 CFR Part 50, Appendix I."
Doses from all airborne effluents except the noble gases are calculated for individuals at the location (for example, the site boundary, garden, resi-dence, milk cow, and meat animal) where the highest radiation dose to a member of the public has been established from all applicable pathways (such as ground deposition, inhalation, vegetable consumption, cow milk consumption, or l
meatconsumption). Only those pathways associated with airborne effluents that are known to exist at a single location are combined to calculate the i
total maximum exposure to an exposed individual.
Pathway doses associated with liquid effluents are combined without regard to any single location, but they are assumed to be associated with maximum exposure of an individual through other than gaseous-effluent pathways, i
Radiological Impact on Humans Operation of the PNPS facility is governed by operating license Technical Specifications that are based on the dose-design objectives of Appendix I to 10 CFR 50. Because these design-objective values were chosen to permit flexibility of operation while still ensuring that plant operations result in offsite doses that are as low as is reasonably achievable (ALARA), the actual radiological impact of plant operation may result in doses close to or occa-siona11y greater than the dose-design objectives. Even if this situation exists, the individual doses for the member of the public subject to maximum i
i exposure will still be very small when compared to natural background doses i
(~100 mrems/ year) or the dose limits (500 mrems/ year - total body) specified l
in 10 CFR 20 as consistent with considerations of the health and safety of the public. As a result, the radiological impact on members of the public 4
j from routine operation of the facility is negligible.
Operating standards of 40 CFR 190, the Environmental Protection Agency's Environmental Radiation Protection Standards for Nuclear Power Operations, specify that the annual dose equivalent must not exceed 25 mrems to the whole i
body, 75 mrems to the thyroid, and 25 mrems to any other organ of any member materials (radon and its daughters excepted) planned discharges of radioa of the public as the result of exposures to to the general environment from all uranium-fuel-cycle operations and radiation from these operations that can be expected to affect a given individual. The PNPS facility has operated l
within these standards.
3.
1 Regulatory Requirements Appendix I to 10 CFR 50 provides guidance on the doses to members of the general public resulting from effluent releases that may be considered to be as low as is reasonably achievable.
2 Experience with the design, construction and operation of nuclear power reactors-indicates that compliance with the technical specifications will keep average annual releases of radioactive materials in liquid and gaseous efflu-ents at small percentages of the limits specified in 10 CFR 20.106 and in the operating license. At the same time, the licensee.is permitted the flex-
- ibility of operation, compatible with considerations of health and safety, to assure that the public is provided a dependable source of power even under i
unusual operating conditions which may temporarily result in releases higher than such small percentages, but still within the limits specified in 10 CFR 20.106 and the operating license.
It is expected that in using this opera-tional flexibility under unusual operating conditions, the licensee will exert his best efforts to keep levels of radioactive material in effluents as low as is reasonably achievable. The guides set out in Appendix I provide numerical guidance on limiting conditions for operation for light-water-cooled nuclear power reactors to meet the requirement that radioactive materials in effluents l
released to unrestricted areas be kept as low as is reasonably achievable.
l Appendix I Evaluation of PNPS 1
i In 1977, the NRC completed an evaluation of the Pilgrim Nuclear Power Station (PNPS) with respect to the requirements of 10 CFR 50 Appendix I.
The evalu-ation consisted of several parts, including a review of the licensee's radwaste treatment and effluent control systems, calculation of expected releases of radioactive materials in liquid and gaseous effluents (source terms), and calculation of potential doses to members of the public in un-restricted areas as a result of these expected releases.
were described in the NRC's Safety Evaluation Report (ystems installed at PNPS The original radwaste treatment and effluent control s SER) dated May 20, 1968,
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and in the Final Environmental Statement (FES) dated May 1972. The source terms and potential doses given in the FES are based on the original systems.
After the FES and SER were issued, the licensee modified the gaseous and liquid i
radwaste systems. The NRC staff considered these modifications with respect j
to evaluating the licensee's ability to meet the Appendix I guidelines.
Based on the source terms calculated for the Appendix I evaluation, doses to a maximally-exposed individual were determined to be well within the Appendix I guidelines. Actual measurements of effluent releases made since this evalua-i tion have been close to or below the projected values contained in the evalua-tion, except for tritium in liquid and gaseous effluents. Tritium releases i
have been within the projected values since 1982. The higher than projected values between 1978 and 1982 have contributed a negligible amount to the dose l
projection due to the very small dose conversion factors for this radionuclide.
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Data concerning actual releases of radioactive materials in liquid and gaseous effluents from PNPS are contained in the licensee's Semiannual Radioactive l
Efficent Release Reports. These data are summarized in Table 1 (Appendix A).
The semiannual reports also contain summaries of calculated radiation doses to hypothetical maximally-exposed individuals based upon measured effluent releases. These data, which are provided/sumarized in Tables 2 and 3, indi-cate that Appendix I guidelines were exceeded in 1981 for exposure to bone and total body via the liquid effluent pathway. No other instances of doses above Appendix I guidelines were noted, i
l These calculated doses for 1981 were still small percentages of the dose limits specified in 10 CFR 20 for members of the public. Data concerning doses to members of the public prior to 1976 could not be located. Appendix I guidelines were not applicable during the early years of operation of PNPS
?
(1972-1976). However, doses were most certainly maintained at small fractions of the 10 CFR 20 limits for the following reasons:
i During the early years of operation of PNPS, from December 1972 through 1977, releases from the facility were generally larger than in recent years, par-ticularly the noble gases. The FES (May 1972) projected annual releases of noble gases up to 2,000,000 curies, which was considered acceptable at the time, and would have resulted in a dose to a maximally exposed individual at the site boundary of up to 46 mrem /yr due to direct exposure from airborne radionuclides. The projected release of 2,000,000 curies of noble gas was never reached in any one year of operation; the maximum was 550,000 curies in 1974, or abut one-fourth the projected maximum. Because noble gases contri-i bute nearly all the dose due to direct exposure from the atmosphere, the actual dose received by the maximally-exposed individual would be closer to i
about 13 mrem in 1974, and less than this in subsequent years. The dose to a real individual would be even lower, since there is little likelihood of any individual spending all his time at or near the site boundary where the maximum doses are calculated. Releases of iodines and particulates in gaseous effluents l
were consistently below projected values. Even at the higher projected levels, doses to the child thyroid would have been below Appendix I guidelines. Re-i leases of fission and activation products in liquid effluents were also consis-i l
tently below projected values. The projected releases in liquid effluents would have resulted in doses below the Appendix I guidelines. Therefore, the actual i
releases would have resulted in doses that were within Appendix I.
Releases of tritium in both liquid and gaseous effluents were larger than projected until 1981, but the contribution of tritium to the total dose is very low. As stated previously, the licensee's dose reports since 1976, based on actual releases rather than projected values such as those in the FES and the Appendix I evalu-l ation, indicated that doses to members of the public did not generally exceed l
Appendix I guidelines, and were always small fractions of the 10 CFR 20 limits.
s 5
APPENDIX A Data Tables
L 5
6 Table 1 - Effluent Release Data (Curies)
GASEOUS RELEASES 1985 1984 1983 Fission and 3,259 18.4 20,090 Activation Products Iodine - 131 4.81 E-02 7.83 E-05 3.24 E-02 Total Iodine 0.345 5.37 E-03 0.435 Particulates 8.78 E-03 5.09 E-03 1.45 E-02 Tritium 6.50 1.77 59.9 LIQUID RELEASES Fission and 1.06 4.75 0.935 Activation Products Tritium 7.81 14.8 15.6 Dissolved and 6.44 E-02 1.72 E-03 3.40 E-03 Entrained Gases Gross Alpha 4.70 E-04 1.04 E-03 1.57 E-03 1982 1981 1980 1979 1978 19,400 5300 26,200 13,900 32,700 2.36 E-02 5.24 E-02 9.19 E-02 0.104 0.124 0.222 0.535 0.442 1.64 1.72 2.08 E-02 1.63 E-02 1.97 E-02 5.26 E-02 5.63 E-02 19.1 76.9 43.8 156.
95.5 0.904 1.94 2.73 0.512 1.77 5.91 34.1 40.
13.4 2.98 5.39 E-03 4.89 E-04 6.56 E-03 1.87 E-03 1.20 E-03 1.84 E-04 4.28 E-04 3.61 E-04 6.81 E-05 5.69 E-05
7 1977 1976 1975 1974 413,000 180,000 110,000 550,000 0.486 0.34 2.2 1.4 0.564(1) 1.43(1)
N/A(2)
N/A(2) 0.207 0.33 0.66 0.019 61.1 37 75 8.0 3.39 2.3 2.1 4.2 32.7 47 18 10 1.93E-03(1) 2.86E-04(1)
N/A(2)
N/A(2) 1.69E-04(1) 6.55E-05(1)
N/A(2)
N/A(2)
(1) Data for Jul-Dec only (2)DataNotAvailable i
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i Tabla 2 - Doses Due ta Lfquid Effluents (mres/ years Total Bone Liver Thyroid Kidney Lung GI-LLI Skin Body 1985 (Jan-Jun) (1)
Adult 0.02 0.02 0.01 0.01 0.01 0.12 0.01 0.03 Teen 0.04 0.05 0.03 0.04 0.04 0.10 0.04 0.03 Child 0.02 0.02 0.01 0.01 0.01 0.03 0.01 0.03 1984 Adult 2.0 2.2 0.18 0.65 0.72 3.5 1.5 1.2 Teen 2.6 2.7 0.96 1.3 1.5 3.0 1.1 1.7 Child 2.6 2.1 0.17 0.52 0.83 1.1 0.28 1.1 1983 Adult 0.22 0.15 0.002 0.005 0.082 0.11 0.002 0.041 as Teen 0.21 0.15 0.005 0.008 0.092 0.080 0.005 0.042 Child (2) 0.29 0.16 0.001 0.003 0.085 0.034 0.001 0.053 1982 Adult 1.8 1.9 0.10 0.50 0.65 2.9 0.12 0.89 Teen 2.1 2.2 0.54 0.90 1.2 2.3 0.64 1.2 Child 2.4 1.8 0.11 0.42 0.71 0.83 0.13 0.93
'981 Idult 12.
9.5 0.31 0.65 4.5 9.7 0.02 2.9 Teen 12.
10.
0.30 0.64 5.6 7.3 0.04 3.1 Child 17.
9.9 0.30 0.50 4.9 2.8 0.02 3.6 J1? Doses based on second half of 1985 effluents have not yet been submitted to NRC dose for Adu t and Teen was from 2nd half, so these numbers, most of th No data aval; able for Child for 1st half of 1983. However J2J are very close to total.
+.
2 Bone Liver Thyroid Kidney Lung GI-LLI~
Skin 1980 Adult 4.9 5.0 0.12 0.82 1.6 6.6 0.6 2.4 Teen 5.1 5.2 0.11 0.82
-2.0 4.7 0.01-2.0 Child 6.7 4.9 0.12 0.69 1.7 1.8 0.01 1.9 1979 Adult 0.09 0.06 0.01 0.01 0.04 0.05 0.01 0.03 Teen 0.09 0.06 0.01 0.01 0.04 0.04 0.01 0.03 Child 0.11 0.06 0.01 0.01 0.04 0.02 0.01 0.03 1978 Adult 0.22 0.22 0.07 0.09 0.12 0.28 0.07 0.12 Teen 0.23
'O.23 0.08 0.11 0.15 0.22 0.09 0.19 e
Child 0.25 0.19 0.04 0.06 0.10 0.10 0.04 0.11 1977 (Jul-Dec)
Adult 0.95 4.2 0.01 0.06 4.7 1.9 0.01 1.1 Teen 0.71 2.9 0.05 0.08 3.3 1.3 0.06 0.83 Child 0.34 1.4 0.01 0.03 1.6 0.63 0.01 0.40 1976 Adult 0.34 1.25 0.02 0.15 1.13 1.26 0.01 0.42 Teen 0.30 0.93 0.07 0.16 0.84 0.89 0.07 0.34 Chi 1d 0.15 0.45 0.02 0.06 0.39 0.37 0.02 0.16
10 APPENDIX B Gaseous Effluent Releases in Excess of 4
Technical Specification Limits 9/26/74 - 9/28/74 Average release rate of gross gaseous activity from the main stack was 0.058
)
Ci/sec during the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period from 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br /> on 9/26/74 and ending at 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on 9/28/74. Technical Specifications 3.8.8 required notification of NRC when release rate exceeds 0.05 C1/sec for a period of greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
The ' average release rate of 0.058 Ci/sec was only about 16% of the instanta-1 i
neous limit allowed by Technical Specifications.
12/20/74 i
On December 19, 1974 it was determined that the A0G System Post Treatment i
Sample System return valve had been installed backward. On December 20, 1974 i
an attempt was made to turn this valve around. When the valve was removed from the system, high activity was released into the retention building. This gas was then released through the reactor building exhaust vent and con-tributed to the release of radioactive airborne effluents on December 20 j
1974.
I The charcoal and particulate filters were removed from the Reactor Building i
Vent Process Radiation Monitor System at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br /> on December 20, 1974..The
}
analysis showed that the technical specification limit for iodine and parti-i culates, with half lives greater than eight days, being released from the f
reactor building exhaust vent had been exceeded by a factor of 1.4.
At this time it was decided to hold the reactor power reduction and remove the char-l coal and particulate filter again.
}
The charcoal and particulate filters were again removed at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> on December 20, 1974 and the analysis of these filters showed that the technical l
specification limit had been exceeded again by a factor of 1.14.
1 i
i 1/7/75 - 1/14/75 An analysis of the charcoal and particulate filters from the Reactor Building Vent Process Radiation Monitoring System on January 12 and 13,1975 revealed that a release of radioactive airborne effluents from the reactor building
)
exhaust vent had exceeded those specified in PNPS Technical Specification section 3.8.B.2.
This release followed a shutdown and cooldown of the reactor on January 11, 1975 and exceeded the specification value by 55%.
An analysis of charcoal and particulate filters from the Reactor Building Vent j
and the Main Stack for the one week period beginning 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on January 7, 1975 and ending 0819 hours0.00948 days <br />0.228 hours <br />0.00135 weeks <br />3.116295e-4 months <br /> on January 14, 1975 revealed the release rates of halogens and particulates with half lives greater than eight days, released to l
the environs as part of airborne effluents, exceeded the limit set forth in i
PNPS Technical Specification section 3.8.B.2 by approximately 13 percent. This period included the release of January 12 and 13,1975, which was reported as i
an Abnormal Occurrence in Licensee Event Report 75-4.
i l
1
11 1/21/75 - 1/28/75 An analysis of charcoal and particulate filters from the Reactor Building Vent and the Main Stack for the one week period beginning 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on January 21, 1975 and ending 0803 hours0.00929 days <br />0.223 hours <br />0.00133 weeks <br />3.055415e-4 months <br /> on January 28, 1975 revealed the release rates of halogens and particulates with half lives greater than eight days, released to the environs as part of airborne effluents, exceeded the limit set forth in PNPS Technical Specification section 3.8.8.2 by approximately 24 percent.
5/13/75 - 5/20/75 An analysis of charcoal and particulate filters from the Reactor Building Vent and the Main Stack for the one week period of May 13, through May 20, 1975 revealed the release rates of halogens and particulates with half lives greater than eight days, released to the environs as part of airborne effluents, exceeded the limit set forth in PNPS Technical Specification section 3.8.B.2 by approximately 23 percent.
y 12 i
i j
Licensee's Evaluation of Probable Consequences of Preceding i
Gaseous Releases in Excess of Technical Specifications I
It is worthwhile to discuss the safety significance of exceeding this Techni-cal Specification. As mentioned above, the high Reactor Building Vent release rate was the primary cause of exceeding the limit. An examination of the i
equation in Tech. Spec. 3.8.B.2 indicates the limit will be exceeded any time the Reactor Building Vent release rate exceeds.061 mci /sec. Based on the i
normal air flow from the Reactor Building Vent, this corresponds to an air-the vent exhaust duct at the point it discharges from borne activity level i j
thestationof7x10~f0 mC1/cc. This can be compared with the limit for breathable air (i.e., no respiratory protection equipment required) for radi-ationoccupationalworkerssuchasPilgrimStationemployees,which(or iodine-131, by far the major radionuclide being released, is 9 x 10~ mC1/cc.
In other words, the air exiting the vent is over 10 times lower in activity than what a station employee (worker) is permitted to breathe without respi-ratory protection. Of course, once the air leaves the station it is then dispersed into the atmosphere so that the concentration at the site boundary, where the public could potentially be located, is much less than at the vent.
The concentration calculated at the site boundary for the equivalent of the Tech.Sgc.releaseratelimitfromtheReactorBuildingVentisabout i
2 x 10~
mC1/cc. This is a factor of 45000 less than what a worker is allowedtobreatheandafactorof500lessthanallogbleannualaverage j
concentration for the general public which is 1 x 10~
mC1/cc for iodine-131.
l Therefore, it is concluded that exceeding the Reactor Building Vent release i
rate does not pose a threat to the health or safety of the public.
1 i
No other gaseous effluent releases in excess of Technical Specification limits t
were noted.
i No liquid effluent releases in excess of Technical Specification limits were noted.
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s 13 Table 3 - Doses Due to Gaseous Effluents t
(Reproduced from licensee's semiannual effluent release reports, 1976-1985) 4 i
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I Table 4.2-6 i
1976 Caseous Release Maximum Individual Doses (0.8 miles SSW) 1 j
Bone Liver Thyroid Kidney Lung CI-LLI Skin Total Body Ate Group (MEM)
(MEM)_
(ISEM)
DetEM)
(MtEM)
(letEM)
(l#EM)
(MREM)
Adult 0.3 0.3 0.4 0.3 0.3 0.3 6.6 3.9 Teenager 0.3 0.3 0.4 0.3 0.3 0.3 6.6 3.9 Child 0.3 0.3 0.4 0.3 0.3 0.3 6.6 3.9 I
Infant 0.3 0.3 0.4 0.3 0.3 0.3 6.6 3.9
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.j No'td -- (1) Organ Doses are based on radiciodine and particulates only (Tables 4.2-2 through 4.2-5 included noble gas doses) i l
(2) Skin and total body doses are from all pathways j
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Table 4.2-6 July-December 1977 Gaseous Release Heximum Iadividual Doses (0.8 Miles WSW)
Bone Liver Thyroid Kidney Lung CI-LLI Skin Total Body Age Croup (MEM)
(MEM)
(MEM)
(MEM)
(MEM)
(MEM)
(MEM)
(MREM)
Adult 0.45 0.46 1.3 0.45 4.44 0.48 1.6 1.1 Teenager 0.48 0.46 1.6 0.45 0.45 0.49 1.6 1.1 Child O.52 0.46 2.7 0.45 0.44 0.48 1.6 1.1 Infant 0.49 0.48 5.2 0.44 0.44 0.44 1.6 1.1 I
Note - (1) Organ Doses are based on radiciodine and particulates only (Tables 4.2-2 through 4.2-5 included noble gas doses)
(2) Skin and total body doses are from all isotopes
i Table 4.2-6 Jannery-June 1978 Caseous Release Maximum Individual Doses (0.8 niles WSW) i f
Bone Liver Thyroid Kidney Lung cI-LLI Skin Total Body j
Aae croup Dean)
Oman)
Omsu)
Oman)
(namn)
(namn)
(naan)
(m j
Adult 0.47 0.44 1.1 0.44 0.43 0.52 1.7 1.1 l
Teenager 0.50 0.45 1.4 0.45 0.47 0.54 1.7 1.1 i
1 Child 0.58 0.47 2.2 0.46 0.43 0.52 1.7 1.1' 1
1 1.7 11 l
Infant 0.50 0.49 4.0 0.47 0.43 0.43 Note - (1) Organ Doses are based on radioiodine and particulates only (Tables 4.2-2 through 4.2-5 4
i included noble gas doses)
(2) Skin and total body doses are irom all isotopes i
l i
I 1
I l
3 I
i I
Table 4.2-6 July-December 1978 Caseous Release Maximum
)
Individus1 Doses (0.8 Miles USW) f Bone Liver Thyroid Kidney Lung CI-LLI Skin Total Body l
Aae Croup (IEEM)
(IEM)
(IEEM)
(MEM)
(MEM)
(MEM)
(petEM)
(MM)
^
Adult 0.054 0.055 0.589 0.055 0.052 0.063 0.229 0.15 Teenager 0.058 0.057
~0.82 0.058 0.055 0.063 0.229 0.16 i
j Child 0.069 0.062 0.88 0.062 0.054 0.062 0.229 0.16 Infant 0.064 0.066 1.65 0.065 0.051 0.052 0.229 0.16 i
i i
Nome - (1) Organ Doses are based on radioindine and particulates only (Tables 4.2-2 through 4.2-5
)
included noble gas doses)
I i
(2) Skin and total body doses are from all isotopes i
i 1
Tablo 4.2-6 January-June 1979 Caseous Release Maximum l
Individual Dosee 2.2 Miles W I
1 I
Bone Liver Thyrold Kidney Lung CI-LLI Skin Total Ebdy e
,MatM),
(MRW)
(MREM)
(MREM)
(MRM)
(MR W)
(DEt EM)
(DELM)
(
Age Group
}
AJult 0.02 0.02 0.15 0.02 0.02 0.02 0.07 0.051 l
j
]
Teenager 0.02 0.02 0.20 0.02 0.02 0.02 0.07 0.05,
)
Child 0.03 0.02 0.36 0.02 0.02 0.02 0.07 0.05g, s
j j
Infant 0.02 0.02 0.75 0.02 0.02 0.02 0.07 0.05 1
l
)
i i
Note - (1) Organ Doses are based on radiciodine and particulates only (Tables 4.2-2 through 4.2-5 included noble gas doses) j (2).%In and total body doses are from all isotopee 1
i l
f i
e
Table 4.2-5 July-Decemoer 1979 Caseone Release Maximum i
Individual Doses 0.6 Miles 7.SE r*
I i
=
l e
Bone Liver Thyroid Kidney Lung CI-111 Skin Total Body Age Croup (NEDt)
(MRDt)
(MRDI)
(MRDt)
(MRDt)
(MitBG)
(petSt)
(WBG) 1 I
l Adult 0.22 0.21 0.28 0.21 0.21 0.23 0.24 0.21 1
Teenager 0.23 0.21 0.27 0.21 0.22 0.24 0.24 0.21 1
j
, Child 0.26 0.21 0.30 0.21 0.21 0.23 0.24 0.21 Infant 0.21 0.21 0.21 0.21 0.21 0.21 0.24 0.21 1
l l
l Note - (1) Organ Dooes are beoed on radiolodine and particulates only (Tables 4.2-2 through 4.2-5 f
included noble gas doses) j (2) Skin and total body doses are from all footopes I
i 4
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.,__._._ _ _. -..._. _ _ _ __ _ _ ~ - -.
Table 4.2-6 January-June 1982 Gaseous Release Maximum
- o Individual Doses 0.5 Miles SE l
l Bone Liver Thyroid Kidney Lun9 GI-LLI Skin Total Body Age Group _
(MREM)
(MREM)
(MEM)
(MREM)
(MREM)
(MREM)
(MtEM)
(MREM)
Adult 0.079 0.062 0.115 0.062 0.061 0.080 0.118 0.062 Teena9er 0.089 0.062 0.145 0.062 0.068 0.084 0.118 0.063 Child 0.127 0.063 0.186 0.062 0.062 0.080 0.118 0.065 Infant 0.036 0.035 0.102 0.035 0.035 0.035 0.068 0.035
Table 4.2.6 January - June 1983 Gaseous Release Maximum Individual Doses 0.5 Miles SE (MREM)
~"M Total
'l
' d,'p i. '.'i.
y'. "'.Q.
SI-LLI Skin Body Oone Liver A.
Age Group M
M 1
#e l'
M OctDI)
(MREM) n Adult 1.01 1.02 1.05 1.02 +
1.02 1.02 1.77 1.02 i
Teenager 1.01 1.02 1.05 1.02 1.02 1.02 1.77 1.02 i
j Child 1.01 1.02 1.07 1.02 1.02 1.02 1.77 1.02 5
l Infant 1.00 1.01 1.03 1.01 1.01 1.01 1.77 1.01 o
,e I
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=
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i
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4
>=
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T Table 4.2.6 I
January - June 1984 Gaseous Release Maximum Individual Doses 0.5 Miles SE (mREW) l Age Group Sone Liver Thyroid Kidney Lung GI-LLI Skin Total Body 1
Adult
<. 01
<. 01
<.01
<.01
<. 01
<.01
<.01
<. 01 1
leenager
<. 01
<. 01
<. 01 C.01
<. 01
<.01
<.01
<.01 1
l Child
<. 01
<. 01
<. 01
<.01
<.01
<.01
<. 01
<. 01 4
i Infant
(.01
<.01
<. 01
<. 01
<. 01
<. 01 C.01
. 01,
1
- {
e I
1
)
Table 4.2.6 January - June 1984 Gaseous Release Maximum Individual Doses 0.7 Miles N (MREM)
Amt Grets m
lJ3nt Myreld
- 5. lear kvan GI-tLI E la total two, i
Adult 4.01 4.01 4.01 d.01 4.01 4.01 4.01 4.01 Teenager 4.01 4.01 4.01 4.01 4.01 4.01 4.01 4 01 i
t Chlid 4.01 4.01 4.01 4.01 4.01 4.01 4 01
< il
'l l
Infcat 4.01 4.01 4.01
<.01 4.01 4.01 4.0i l
I i
Table 4.2.6 January - June 1985 Gaseous Release Maximum Individual Doses 0.6 Miles ESE (MREM)
Age _GrgM!g tone Ltver hwold gl$ney L,ung Gt.LLI Skin io,t a I. Booy a a-Adult 0.04 0.04 0.10 0.04 0.04 0.04 0.07 0.0a
..........e7 l
l I;cnager 0.04 0.04 0.10 0.04 0.04 0.04 0.07 0.04 I
'.04 0.04 0.07 0.04 Child 0.04 0.04 0.13 0.04 0
i infant 0.04 0.04 0.07 0.04 0.04, 0.04 0 ~. 7 0 A4
(
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r:
'o UNITED STATES
^,,
8 NUCLEAR REGULATORY COMMISSION
-o
. 2 E
WASHINGTON. D. C. 20555 a[
EDO PRINCIPAL CORRESPONDENCE CONTROL
~
FROM:
DUE: 07/22/86 EDO CONTROL: 001916 DOC DT: 07/01/86 REP. BARNEY FRANK FINAL REPLY:
TO:
CHAIRMAN 7ECH FOR SIGNATURE OF:
- PRIORITY **
SECY NO: 86-680 EXECUTIVE DIRECTOR DESC:
ROUTING:
REQUEST INFO ON RADIOACTIVE EMISSIONS AT PILGRIM DENTON PLANT TAYLOR DATE: 07/07/86 ASSIGNED TO: RI CONTACT: MURLEY SPECIAL INSTRUCTIONS OR REMARKS:
w m u 4
w-r p
-- r,p--
w---
r&-
v m--==
+e
-m
r-t
,o OFFICE OF THE SECRETARY CORRESPONDENCE CONTROL TICKET PAPER NUMBER:
CRC-86-0680 LOGGING DATE: Jul 3 86 ACTION OFFICE:
EDO AUTHOR:
B.
Frank AFFILIATION:
U.S. HOUSE OF REPRESENTATIVES LETTER DATE:
Jul 1 86 FILE CODE: I&P-2
SUBJECT:
Req info re radioactive emissions at the Pilgrim plant ACTION:
Direct Reply DISTRIBUTION:
OCA to Ack SPECIAL HANDLING: None NOTES:
DATE DUE:
Jul 1 86 SIGNATURE:
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AFFILIATION:
iterd Off. EDO 3 7 Go Date_
Tsme I >43kf 001916
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