ML112980304
| ML112980304 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 10/19/2011 |
| From: | Eugene Dipaolo Division Reactor Projects I |
| To: | Stamos M - No Known Affiliation |
| dipaolo, em | |
| References | |
| Download: ML112980304 (54) | |
Text
{{#Wiki_filter:UNITED STATES NUCLEAR REGU LATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA. PENNSYLVANIA 19406-1415 0ctober 19, 2OII Ms. Mary Stamos
Dear Ms. Stamos:
power plant I am responding to questions you raised about the Three Mile lsland (TMl) nuclear in a collection of letters mailed to the NRC on August 30, 201 1. You had questions about the health effects of the Three Mile lsland accident. In particular, you were concerned about a about metallic taste you experienced at the time of the accident. You also expressed concern the quantity of radioictive materials released by the operating unit, Three Mile lsland Unit 1. As stated in a letter sent to you in July 2004, the NRC has no definitive technical explanation of the regarding the metallic taste you expeiienced during the accident. Extensive studies dose to a person raliotogilal consequences of the TMI-2 accident calculated that the maximum located at the site boundary would have been less than 100 millirem. Such a dose is Attached for considerably less than the'5 rer (5000 millirem) you say causes a metallic taste.
"dackgrounder: ihree Mile lsland Accident" summarizing the your review is a document tiiled This document also lists additional Three Mile lsland Accident and its potential health etfects.
sources of information which may prove useful to you and directions for obtaining them' a small The radioactive effluents released from TMI-1 during 2010 resulted in doses that were Effluent fraction of NRC regulatory limits. This is discussed in the 2010 Annual Radioactive can be Release Report for TMl. Excerpts from the report are attached as well. The full report found on the NRC website at httP:/ info.html. questions, Thank you for your continued interest in nuclear safety. lf you have any further please contact me at (610) 337-5046. Sincerely, 4^--nL /U//u Eugene M. DiPaolo, Acting Chief Division of Reactor Projects Branch 6
Enclosures:
- 1) US NRC Backgrounder on the Three Mile lsland Accident
- 2) Excerpts from three Mile lsland Combined 2010 Radioactive Effluent Release Report
Ms. Mary Stamos
Dear Ms. Stamos:
I am responding to questions you raised about the Three Mile lsland (TMl) nuclear power plant in a collection of letters mailed to the NRC on August 30, 201 1. You had questions about the health effects of the Three Mile lsland accident. In particular, you were concerned about a metallic taste you experienced at the time of the accident. You also expressed concern about the quantity of radioactive materials released by the operating unit, Three Mile lsland Unit 1. As stated in a letter sent to you in July 2004, the NRC has no definitive technical explanation regarding the metallic taste you experienced during the accident. Extensive studies of the radiological consequences of the TMI-2 accident calculated that the maximum dose to a person located at the site boundary would have been less than 100 millirem. Such a dose is considerably less than the 5 rem (5000 millirem) you say causes a metallic taste. Attached for your review is a document titled "Backgrounder: Three Mile lsland Accident" summarizing the Three Mile lsland Accident and its potential health effects. This document also lists additional sources of information which may prove useful to you and directions for obtaining them. The radioactive effluents released from TMI-1 during 2010 resulted in doses that were a small fraction of NRC regulatory limits. This is discussed in the 2010 Annual Radioactive Effluent Release Report for TMl. Excerpts from the report are attached as well. The full report can be found on the NRC website at http:i/www.nrc.qov/reactors/operatinq/ops-experience/tritium/plant-info.html. Thank you for your continued interest in nuclear safety. lf you have any further questions, please contact me at (610) 337-5046. Sincerely, A//U.fu/1,-'= Eugene M. DiPaolo, Acting Chief Division of Reactor Projects Branch 6
./
suNst Review complete: ( Ftn"uiewer's Initiats) DOCUMENT NAME: G:\DRP\BRANCH6\+++Three Mile lsland\Letter to Mary Stamos TMl.docx Afier declaring this document "An Official Agency Record" it will be released to the Public. To receive a copy of this document, indicate in the box: 'C" = Copy without attachmenVenclosure 'E" = Copy with attachmenUenclosure "N" = No copy
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BACKGROUNDER rux;t't. Pblsrrang l)otth' flnrl tht Ewircnwatl Office of Public Atfairs Phone: 301 -41 5-8200 Email: Three Mile Island Accident plant near Middletown, Pa', on March The accident at the Three Mile Island unit 2 (TMI-2) nuclear power Zg, lgTg,was the most serious in U.S, commercial nuciear power plant operating history, evcn though it deaths or injuries to plant workers or members of the nearby cotnmunity. But it brought about led to
'o sweeping changes involving emergency response planning, reactor operator training, human factors raiiation protection, and many other areas.of nuclear power plant operations' It also caused "ngin".iing, its regulatory oversight' Resultant the u.S. Nuclear Reguiatory commission io tighten and heighten changes in the nucl# po*Lr industry and at the NRC had the effect of enhancing safety' problems and worker errors
- The sequence of certain events - equipment malfunctions, design-related led to ;partial meltdown of the rMr-z reactor core but only very small off-site releases of radioactivity, Summary of Events a failure in the The accident began about 4:00 a.m. on March 28,l97g,when the plant experienced pumps s-topped running, causgd by-either secondary, non-nuclear section of the plant, The main feedwater generators from removing heat' First the a mechanical or electrical failure, which prevented the steam pressure in the primary systcm (thc turbine, then the reactor automatically shut down. Immediately, the pressure from becoming excessive, nucleaiportion of the plant) began to increase. In order to prevent that pressurizer) opened"-The valve should have the piloioperated relief valve (i valve located at the top of the closed when the pressure decreased by a certain amount, but it did not. Signals available to the operator valve failed to show that the valve was still open. As a result, cooling water poured out of the stuck-open and caused the core ofthe reactor to overheat.
to reactor operators As coolant flowed from the core through the pressurizer, the instruments available insffument that showed the level of coolant in the core. fiovided confusing information. There *ur nb in the pressuri zet, and since it was Instead, the operators judged the level of water in the core by the level high, ttrey assumed that ttie core was properly covered with coolant, In addition, there was no clear signal and warning lights flashed,.the that the pilot-operated relief valve *ui open.'As a result, as alarms rang accident' They took a series of operators did not rca]izethat the plant was experiencing a loss-of-coolant actions that made conditions *orr. by simply reducing the flow of coolant through the core' to the point at which the Because adequate cooling was not available, the nuclear fuel_overheated fuel pellets) ruptured and the fuel pellets zirconium cladding (the i"ong metal tubes which hold the nuclear melted during the early stages of the began to melt. It was later fJund that about one-half of tho corc the most dangerous kind of nuclear accident. Although the TMI-2 plant suffered a severe core meltdown, that reactor experts had long feared' In a fo*.,. accident, i] did not produce the worst-case consequences breach of the walls of the containment worst*case accident, the melting of nuclear fuel would lead to a to the environment. But this did not occur as a result of building and release massive qiantities of radiation the three Mile Island accident.
The accident caught fecleral and state authorities off-guard. They were concetned about the small releases concerned of radioactiv. gur., that were measured off-site by the late morning of March 28 and-even more that the about the potentiat threat that thc rcactor posed to the surrounding population. They did not know to try to gain control of the reactor and ensure adequate core had melted, but they imrnediately took steps cooling to the core. Tlie NRC's regional office in King of Prussia, Pa,, was notified at7:45 a.m. on March Center in ZS. ny t:OO, NRC Headquarters in Washington, D.C., was alerted and the NRC Operations Bethesda, Md., was activated. The regionaioffice promptly dispatched the first team of inspectors to the site and other agcncies, such as the Department of Energy and the Environmental Protection Agency, also mobilized their response teams. I{elicopters hired by TMI's owner, General Public Utilities Nuclear, and the Department of bnergy were sampling radioactivity in the atmosphere above the plant by midday. A team from the Brookhaien National Laboratory was also sent to assist in radiation monitoring. At 9:i5 ordered off the a.m., thc White House was notified and at 1 1:00 a.m., all non-essential personnel were plant's premises. to be By the evening of March 28, the core appeat'ed to be adequately cooled and the reactor appeared of radiation from stable. But new concerns arose by the morning of Friday, March 30. A significant release the plant's auxiliary building, peiformed to reiievc prcssure on the primary system and avoid curtailing the flow of coolalt to the core, caused a greatdeal of c-onfusion and consternation. In an atmosphere of growing uncertainty about the condition of the plant, the govefiior of Pa', Richard L. Thornburgh, consulted with the NRC about evacuating the population n.ut the plant. Eventually, he and NRC Chairman Joseph to Hendrie agreed that it would Ue prua"nt for those members of society most vulnerable to radiation evacuate the area. Thornburgh announced that he was advising pregnant women and pre-school-age children within a 5-mile radius of the plant to leave the area' the Within a short time, the presence of a large hydrogen bubble in the dome of the pressure vcssel, hydrogen bubble might container that holds the ieactor core, stined new worries. The concel'n was that the burn or even explode and rupture the pressure vessel. In that event, the core would fall into the containment scrutiny building and peihaps .uur. i breach of containment. The hydrogen bubble was a source of intense and the population, throughouJ the day on Saturday, and gre-at anxiety, both among government authorities not burn or March 31 . The crisis ended wiJn experts determined on Sunday, April 1, that the bubble could explode because of the absence of oiygen in the pressure vessel. Further, by that time, the utility had succeeded in greatly reducing the size of the bubble' Health Effects the NRC, the Detailed studies of the radiological consequences of the accident have been conducted by Education and Welfare (now Health and Environmental Protection Agelncy, the Department of Health, studies have also Human Services), the Deparlment of Energy, and the State of Pa.. Several independent was only about 1 been conducted. Estimates are that the uu*ug" dose to about 2 million people in the area to the natural millirem. To put this into context, exposure f,otn u chest x-ray is about 6 millirem. Compared dose to the radioactive background dose of about I 00- 125 millirem per year for the area, the collective dose to person at the site boundary would community from-the accident was very small. The maximum a have been less than 100 millirem. adverse effects from In the months following the accident, although questions were raised about possible to the radiation on human, animal, and plant life in the TMI area, none could be directly conelated water, milk, vegetation, soil, and foodstuffs were accident. Thousands of environmental samples of air, could be attributed to collected by various groups monitoring the area. Very low levels of radionuclides
releases from the accident. However, comprehensive investigations and asssssments by several reactor, most of the well-respected organizations have concluded that in spite of serious damage to the physical health of radiation was contained and that the actual release had negligible effects on the individuals or the environment. Impact of the Accident and component failures', The accident was caused by a combination of personnel error, design deficiencies, changed both the nuclear industry and There is no doubt that the accident at Three Mlle Island permanently the NRC. public fear and distrust increased, NRC's regulations and oversight became broader and more problems identified from careful robust, and management of the plants was scrutinized more carefully, The changes in how NRC analysis of the evlnts during those days have led to permanent and sweeping public health and safety. reguiates its licensees wh[h, in turn, has reduced the risk to Here are some of the major changes which have occurred since the accident:
, includes fire UpFading and strengthening of plant design and equipment requirements._This piJectioti, piptng ,yit*rnr, a:uxiliary feedwater systgm;, containment building isolation, reliability of individual coriponents (pressurarelief valves and electrical circuit breakers),
and the ability of plants to shut dowr automaticallY; and identiffing human perfotmance as a critical part of plant s.afety, revamping operator training instrumentation and controls for operating the plant, staffing reluirements, followed by improved and establishment of fitness-for-duty progtatos for plant workers to guard against alcohol or drug abuse; the accident; a Improved instruction to avoid thc confusing signals that plagued operations during a Enhancement of emergency preparedness to include immediate NRC notification requirements for and response plans plant events and an Ni.C op"rations center that is staffed 24 hours a day' Drills local agencics participate in drills
*. no* tested by licensees several times a year, and slate and with the Federal Emergency Management Agency and NRC; conclusions about licensee Establishment of a prolru- to intelrate NRC observations, findings, and performance and management effectiveness into a periodic, public report; plants needing hegular analysis of plait performance by senior NRC managers who identiff those additional regulatory attention ;
- whereby at least two Expansion gFNRC'r resident inspector program - first authorized in 1977 inspectors live nearby and work exclusively at each plant in the U.S. to provide daily surveillance of licensee adherence to NRC regulations; and the use of risk Expansion of performance-or[nted as well as safety-oriented inspections, assessment toidentify vulnerabilities of any plant to sevele accidents; the NRC; o Strengthening and reorganization of enforcement as a separate office within industry's o\rm The eitablish-ment of tlie Institute of Nuclear Power Operations (INPO),
a the
,,policing,, group, and formation of what is now the Nuclear Energy Institute to provide a unified lnoustry-approurh to generic nuclear regulatory issues, and interaction with NRC and other govemment agencies; conditions, and monitor The installing oruooitlonal equipment by licensees to mitigate accident radtation levels and Plant status; safety-related Employment of major initiatives by licensees in early identification of important data so lessons of experience can be shared and protl.*r, and in collecting and assessing relevant quickly acted upon; and
. Expansion of NRC's international activities to share enhanced knowledge of nuclear safety with other countries in a number of important technical areas.
Current Status Today, the TMI-2 reactor is permanently shut down and defueled, with the reactor coolant system drained, the radioactive water decontaminated and evaporated, radioactive waste shipped off-site to an appropriate disposal site, reactor fuel and core debris shipped off-sitc to a Department of F.nergy facility, and the remainder of the site being monitored. In 2001, FirstEnergy acquired TMI-2 from GPU. FirstEnergy has contracted the monitoring of TMI-2 to Exelon, the curent owner and operator of TMI-1. The companies plal to keep the TMI-2 facility in long-term, monitored storage until the operating license for the TMI-1 plant expires, at which tirne both plants will be decommissioned. Below is a chronology of highlights of the TMI-2 cleanup from 1980 through 1993. Date Event July 1980 Approximately 43,000 curies of krypton were vented from the reactor building. July 1980 The first manned entry into the reactor building took place. Nov. 1980 An Advisory Panel for the Decontamination of TMI-2, composed of citizens, scientists, and State and local officials, held its first meeting in Harrisburg, PA. July 1984 The reactor vessel head (top) was removed. Oct, 1985 Defueling began. July 1986 The off-site shipment of reactor core debris began, Aug. 1988 GpU submitted a request for a proposal to amend the TMI-2 license to a "possession-only" license and to allow the facility to enter long-term monitoring storage. Jan. 1990 Defueling was completed. July 1990 GpU submitted its funding plan for placing $229 million in escrow for radiological decommissioning of the plant. Jan,199l The evaporation of accident-generated water began. April 1991 NRC published a notice of opportunity for a hearing on GPU's request for a liccnse amcndment Feb.1992 NRC issued a safety evaluation report and granted the licensc amendment. Aug. 1993 The processing of 2.23 million gallons accident-generated water was completed. Sept. 1993 NRC issued a possession-only license.
Sept. 1993 The Advisory Panel for Decontamination of TMI-2 held its last meeting. Dec. 1993 Post-Defueling Monitoring Storage began' Additional Information listed below. The documents can Further information on the TMI-2 accident can be obtained from sources be ordered for a fee from the NRC's Public Document Room at30l-415'4737 or 1-800-397-4209; e-matl p!i,,6gu-{q,g{)-y, The pDR is located at 11555 Rockville Pike, Rockville, Maryland; however the mailing D.C. 20555' A ,ddrr*-
- U.S, Nuclear Regulatory Commission, Public Document Room, Washington, glossary is also Provided below.
Additional sources for Information on Three Mile Island NRC Annual Report - l979,NUREG-0690
,,population Dose and tteaittr Impact of the Accident at the Three Mile Island Nuclear Station,"
NUREG-0558 .,Environmental Assessment of Radiological Effluents from Data Gathering and Maintenance operation on Three Mile Island lJnit2," NUREG-0681
.,Report of The president's Commission on The Aocident at Three Mile Island," October, 1979 ,.Investigation into the March 28,lgTg Three Mile Island Accident by the Office of Inspection and Enforcement," NUREG-0600 ,Three Mile Island; A Report to the Commissioners and to the Public," by Mitchell Rogovin and George T. Frampton, NUREG/CR-1250, Vols' I-II, 1980 ,,Lessons learned From the Three Mile Island - Unit 2 Advisory Paneln" NUREG/CR-6252 ,,The Status of Recommendations of the President's Commission on the Accident at Three Mile Island,"
(A ten-Year review), NUREG-1355
,,NRC Views and Analysis of the Recommendations of the President's Commission on the AL:cident at Three Mile Island," NUREG-0632 .,Environmental Impact Statement related to decontamination and disposal of radioactive wastes resulting from March Zg, IgTg accident Three Mile Island Nuclear Station, IJnit2,"
NUREG-0683
,,Answers to Radiation Doses at Three Mile Island, euestions About updated Estimates of occupational Unit 2." NUREG-1060 ,,Answers to Frequently Asked Questions About Cleanup Activities at Three Mile Island, Unit 2,"
NUREG-0732
,,Status of Safety Issues at Licensed Power Plants" (TMI Action Plan Reqmts'), NUREG-1435
Walker, J. Samuel, Three Mile Island: A Nuclear Crisis in Historical Perspective, Berkeley: University of California Press, 2004. Glossary Auxiliary feedwater - (see emergency feedwater) Background radiation - The radiation in the natural environment, including cosmic rays and radiation from ihe naturally radioactive elements, both outside and inside the bodies of humans and animals. The usually quoted average individual exposurc from background radiation is 300 millirem per year. Cladding - The thin-ialled rnetal tube that forms the outer jacket of a nuclear fuel rod. It prevents the corrosion of the fuet by the coolant and the release of fission products in the coolants. Aluminum, stainless steel and zirconium atloys are common cladding materials. Emergency feedwater system - Backup feedwiter supply used during nuclear plant startup and shutdown; also known as auxiliary feedwater. Fuel rod - A long, slender tube that holds fuel (fissionable material) for nuclear reactor use. Fuel rods are assembled into bundles called fuel elements or fuel assemblies, which are loaded individually into the feactor core. Containment - The gas-tight shell or other enclosure around a reactor to confine fission products that otherwise might be released to the aknosphere in the event of an accident. Coolant - A substance circulated through a nuclear reactor to remove or transfer heat. The most commonly used coolant in the U.S. is water. Other coolants include air, carbon dioxide, and helium. Core - The central portion of a nuclear reactor containing the fuel elentents, and control rods, has been shut Decay heat - The lreat produced by the dccay of radioactive fission products after the reactor down. Decontamination - The reduction or removal of contaminating radioactivc material from a structure, area, (1) the surface to rernove or decrease object, or person, Decontamination may be accomplished by treating decay; and the contamination; (2) letting the mateiial stand so that the radioactivity is decrcased by natural (3) covering the contamination to shield the radiation emitted' Feedwater - Watcr supplied to the steam generator that removes heat from the fuel rods by boiling and becoming steam. The steam then becomes the driving force for the turbine generator' Nuclear Reactor - A device in which nuclear fission may be sustained and controlled in a self-supporting nuclear reaction. There are several varieties, but all incorporate certain features, such as fissionable neuffons, material or fuel, a moderating material (to control the reaction), a reflector to conserve escaping provisions for removal of heat, measuring and controlling instrumcnts, and protective devices' b..rrur. Vessel - A strong-walled container housing the core of most types of power reactors. pressurizer - A tank or vessel that controls the pressure in a certain type of nucl eat teactor ' primary System - The cooling system used to ..mou. energy from the reactor core and transfer that energy eithlr directly or indirectly to the steam turbine. Radiation - par-ticles (alpha, betan neutrons) or photons (gamma) emitted from the nucleus of an unstable atom as a result ofradioactive decay. Reactor Coolant System - (see primary system) pumps, a1d Secondary System - The steam generatoriubes, steam turbine, condenser and associatcd pipes, energy for electrical heaters uscd to convert the heat Jn"rgy ofthe reactor cootant system into mechanical generation. the primary Steam Generator - The heat exchanger used in some reactor designs to transfer heat from (reactor coolant) system to the secondary (steam) system. This design permits heat exchange with little or no contamination of the secondary system equipment'
tumed by water Turbine - A rotary engine made with a series of curved vanes on a rotating shaft' Usually to turn large electrical generators, or steam. Turbines are*considcred to be the most economical means
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2010 Annual Radioactive Eftluent Release ReportlorTMl Attachment I- Page 2 ol 15 TABLE 1A EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2O1O GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES TMFl ffiting ol TMIODCM Lower Lirnil of Detection {LLD).
'ODCM Limits - Usted on Dose summary Table. *C-14 production was estimated using EPRI Technical Report 1021100 Methodology.
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2010 Annual Radioactive Effluent Release Report for TMI - Page 5 of 15 TABLE 2A EFFLUENT ANDWASTE DISPOSAL ANNUAL BEPORT 2O1O LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES TMhl ESTTOTAL UNIT QUARTERI I OUARTER2 QUARTER3 QUARTER 4 ERROR o/" A. FISSION AND ACTIVATIS}I PRODUGTS 1- Total Release (Not incl. Tritium. qases, alpha) ci 1.18E-05 4.34E-Os 1.99E-05 8.41 E-05 25"/"
- 2. Avo diluted concentration clurino Derlod uCi/rnl 1.71E-'t2 7.08E-12 2.77E-'12 1.28E-11
- 3. Percent of applicable limit
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'_.'i i:i.. i.:+,r.'. _.:.:: j:i..;::il: .r:. ir. ..:'1- : - +; 1..:.it;,.:s+:,*.; iti:':iti,a:i,:;jj-fi.rj::ti"tlii.X.{-l-e.iii;ilra 5 F :l:iii. t r+,:.'i; j :i'. :#?..i'il-.:::-.fi ir B. TRITIUM 1- Total Release Ci 1.42E+O'l 6E+Ol 4.40E+OI 5.39E+O1 25"/"
2- Avq diluted concentration clurinq periocl uoi/ml o/o 2.07E{6 2.71E{'6 6.13E-06 8.23E-05
- 3. Percent of applieable limit l l -' _
ll:i-iifi.Si*5"rdtrIsf,ssfl*"{ir.Jli.trffi#ii$ffi*ffi i}i{i"i&ffi:g a{-d];{.*il: C. DISSOLVED AND ENTRAINED GASES iiF-i;:ii,:?-1i';;5:..,.:i'-T i5t:$.F{i,=?: 1- Total Belease ci <LLD <LLD 1.07E44 1.20E-04 ,o
- 2. Avq diluted concentration durino periocl uCi/ml o/ol'l N/A N/A 1.49E-1 1 1.83E-11 3 Pcrcent af annlinahlc limit D. GROSS ALPHA RADIOACTIVITY 1- Toial Release ci <LLD lier:-t;ci:j+ir'.+'.ir:r31i{'iill-F-.':r',ir:'.i{r.::.j:t";'i.}i}jif;..ii:':;
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{.i'irii lii}i'tif{liild.n':::r,ir*lf ;-:i: iG_S::jj:if.; E. VOLUME OFWASTE RELEASE (PRTORTO LITERS 1.14E{OB 1.12E+08 1.16E+OB 1.20E+08 fiV" DILUTIONT F. VOLUME OF DILUTION WATER USED LITERS 6.88E+Og 5.13E+09 7.17E+09 6.55E+09 10% Note: Table 3 contains a listing of TMI ODCM Lower Limit of Detection (LLD).
"ODCM Limits - Listed on Dose summary Table
2010 Annual Radioactive Effluent Release Report for TMI AftachmentT-Page1 ol4 Assessment of Radiation Doses Due to Radioactive Liquid and Gaseous Effluents Released from TMI During 2010 TMr-1 general The attached table presents the maximum hypothetical doses to an individual and the popri.iion resulting irom 2010 TMl.1 reteases of gaseous and liquid etfluents. Provided below is a brief explanation of the table. A. Liqr.{id(lnSividual) in Calculations were performed on the four age groups and seven organs recommended Aegufatory Guide i.rOg. The pathways considered for TMI-1 were the consumption of dririking water and fish and standing on tlre shoreline influenced by TMI'1 effluents, The tuttrr tfro pathways are considered io be the primary recreational activities associated with tne Susqu'enanna River in the vicinity of TMl. The "critical receptor" or Receptor 1 was that individualwho 1) consumed Susquehanna River water from the nearest downstream drinking
*itur rrpplier (Wrightsville Water Supply), 2) consumed fish residing !n the vicinity ofliquid the TMI-1 liquid dischalge and 3) occupied an area of shoreline influenced by the TMI-1 discharge.
For 2010 the calculated maximum whole body (or total body) dose from TMI'1 liquid effluents the was 1.43E-2 mrem to an adult (line 1), The maximum organ dose was 1.50E-2 mrem to liver of an adult (line 2). B. @ryqdryueu There were six major pathways considered in the dose calculations for TMI-1 gaseous
'(1) effluents. These were: pluine exposure (2) inhalation, consumption of; (3) cow milk' (4) vegeianfes and fruits, (bi heat, and (6) standing on contaminated ground. Realtime miteorotogy was used in all dose calculations for gaseous effluents' The Lines O and 4 present the maximum plume exposure at or beyond the site.boundary.
these doses are not to an individual, but is notation of 'hir.dose" is interpreted to mean that considerecl to be the maximum doses that would have occurred at or beyond lhe site oounOary. The table presents the distance in meters to the location in the affected sector t.orpuri point) wherd the theoretical maximum plume exposures occuned' The calculated
'plurne maximum exposures were 1 .17E-4 mrad and 3.72E-4 mrad for gamma and beta, resPectivelY.
The maximum organ dose due to the release of iodines, particulates and.tritium from TMI-1 in lhe in 2010 was 1,OgE-1 mrem to the bone of a child residing 2150 meters from the site NNE sector (line S). This dose again reflects the maximum exposed organ for the appropriate age group, that For 2010, TMI-1 liquid and gaseous effluents resulted in maximum hypothetical doses were a smallfraction of the quarterly and yearly oDcM dose limits'
2010 Annual Radioactive Effluent Release Report for TMI AttachmentT-Page2of4 TMFl
SUMMARY
OF MA)OMUM INDIVIDUAL DOSES FOR TMF1 FROM Januarv 1. 2010 through December 31' 2010 ODCM Dose Location % of ODCM Dose Limit Limit (mrem) Applicable Estimaled Effluent Organ Dose (mrem) Age Group Dist Dir (m) (to) Quarter Annual Quafter Annual (1) Liq uid Totat Body 1.43E-2 Adult Receptor 1 9.53E-1 4.77E-2 1.5 3 Liver 1-50E-2 Aduft Beceptor 1 3.00E-1 1.50E-1 3 10 {2) Liquid Air Dose 1.17E-4 610 SSE s.85E-2 1.17E-3 5 10 (3) Noble Gas (gamma-mrad) (4) Noble Gas Air Dose 3.72E-4 3000 SSE 3.72E-3 1.86E-3 10 20 (beta-mrad) (5) lodine, Tritium Bone 1.53E-1 chird 2150 NNE 2.MEO 1.02E0 7.5 15
& Particulates
2010 Annual Fladioactive Effluent Release Fleportfor TMI AttachmentT*Page3of4 lMr-2 The attached table presents the maximum hypothetical doses to an individual and the general population resulting from 2010 TMI-2 releases of gaseous and liquid effluents, Provided below is a briel explanation of the table. A. Liquid (lndividual) Calculations were performed on the four age groups and seven organs recommended in Regulatory Guide 1.109. The pathways considered for TMI-2 were the consumption of drinking water and fish and standing on the shoreline influenced by TMI-2 etfluents. The latter two pathways are considored to be the primary recreational activitjes associated with the Susquehanna River in the vicinity of TMl. The "critical receptor" or Receptor 1 was that individuiil who 1) consumed Susquehanna River water from the nearest downstream drinking water supplier (Wrightsville Water Supply), 2) consumed fish residing in the vicinity of the TMI-2 liquid discharge and 3) occupied an area of shoreline influenced by the TMI-2 liquid discharge. For 2010 the calculated maximum whole body (or total body) dose from TMI-2 liquid effluents was 3.04E-4 mrem to an adult (line 1). The maximum organ dose wae 4.758-4 mrem to the liver of a teen (line 2). B. Gaseous(lndividuql) There were six major pathways considered in the dose calculations for TMI-2 gaseous elfluents, These were: (1) plume exposure (2) inhalation, consumption ol; (3) cow milk, (4) vegetables and fruits, (5) meat, and (6) standing on conlaminated $round, Real-time meteorology was used in all dose calculations for gaseous etfluents. Since there were no noble gases released from TMI-2 during 2010, the gamma and beta air doses (lines 3 and 4, respectively)were zelo. The maximum organ dose due to the release of particulates and tritium from TMI-2 in 2010 was 3.87E-5 mrem to the liver, total body, thyroid, kidney, lung, and Gl tract of a child residing 2000 meters from the site in the SE sector (line 5)' For 2010, TMI-2 liquid and gaseous effluents resulted in maximum hypothetical doses that were a smallfraction of the quarterly and yearly ODCM dose limits.
2010 Annual Radioactive Effluent Release Reportlor TMI AtlachmentT-Page4ol4 TI\'ll-2
SUMMARY
OF MA)fiMUM TNDIVIDUAL DOSES FOR TMI-2 FROM Januarv 1.2010 through Decmber 31.2010 uuuM uose Location "/" of ODCM Dose Limit Limit(mrem) Applicable Estimated Eff luent Dose {mrem) Age Group Dist Dir Organ (m) (to) Quarter Annual Quarter Annual (1) Liquid Total Body 3.04E-4 Ardult Receptor 1 2.O3E-2 1.01E-2 1.5 3 (2) Liquid Liver 4.75E-4 Teen Receptor 1 9.50E-3 4.75E-3 5 10 (3) Noble Gas Air Dose u 0 0 5 10 {gamma-mrad) (4) Noble Gas Air Dose 0 0 0 10 2A (beta-mrad) (5) Tritium & Liver, Total 3.87E-5 chitd 2000 5E 5.16E-4 2.58E-4 7.5 15 Particulate Body, Thyroid, Kidney, Lung & GlTract}}