ML20248D727
| ML20248D727 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/31/1997 |
| From: | SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | |
| Shared Package | |
| ML20248D701 | List: |
| References | |
| NUDOCS 9806030082 | |
| Download: ML20248D727 (90) | |
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{{#Wiki_filter:_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ - _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ ___ i 1920-98-20239 Attachment 2 l 1997 Radiological Environmental l Monitoring Report SAXTON NUCLEAR EXPERIMENTAL CORPORATION 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT FOR THE SAXTON NUCLEAR EXPERIMENTAL CORPORATION FACILITY l r January 1,1997 - December 31,1997 i l l 9906030002 990528 PDR ADOCK 05000146 ! R PM + a-_ _ -
c 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE OF CONTENTS Page Title i TABLE OF CONTENTS iii LIST OF TABLES iv LIST OF FIGURES v LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS 1
SUMMARY
AND CONCLUSIONS 4 INTRODUCTION 4 Characteristics of Radiation 5 Sources of Radiation 9 DESCRIPTION OF THE SNEC SITE 9 Location of the Plant Site 9 Description of Plant Site 10 SNEC Decommissioning Operations 10 Facility Description 10 Containment Vessel 10 Concrete Shield Wall 11 Tunnel 11 Demography - Human Activities in the Environs 12 Geology 14 RADIOLOGICAL ENVIRONMENTAL MONITORING 15 Sampling 16 Analysis 16 Data Review 17 Quality Assurance Program 21 DIRECT RADIATION MONITORING 22 Sample Collection and Analysis 22 Results 24 1997 SNEC TLD Summary 24 Highest Site Boundary Exposure Comparison 25 ATMOSPHERIC MONITORING 26 Sample Collection and Analysis 26 Air Results 31 GROUNDWATER MONITORING 32 Groundwater Results 35 BROAD LEAF VEGETATION MONITORING 36 SURFACE WATER MONITORING Page i w
1997 RADIOLOGICAL ENVIRONMENTAL MONlwRING REPORT Pr.ge Title I 37 AQU ATIC SEDIMENT MONITORING ( 39 REFERENCES APPENDIX A: 1997 REMP Sampling Locations and Descriptions, Synopsis of REMP, and Sampling and Analysis Exceptions APPENDIX B: 1997 Lower Limit of Detection (LLD) Exceptions APPENDIX C: 1997 REMP Changes APPENDIX D: 1997 Action Levels APPENDIX E: 1997 Quality Control Results APPENDIX F: 1997 Cross-Check Program Results APPENDIX G: 1997 Data Reporting and Analysis APPENDIX H: 1997 REMP Sample Collection and Quarterly Data APPENDIX I: 1997 Analysis Methods TLD I Pageii I
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REFORT LIST OF TABLES Page Title 6 Table 1 Sources and Doses of Radiation 24 Table 2 SNEC TLD Summary for 1997 24 Table 3 Highest Site Boundary Exposure Comparison 28 Table 4 1997 Average Gross Beta Concentrations in Air Particulate 28 Table 5 1997 Average Gross Alpha Concentrations in Air Particulate 34 Table 6 Tritium Concentrations in GEO-5 38 Table 7 1997 Concentrations in Aquatic Sediment 1 Page iii
1997 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT LIST OF FIGURES 1 i Page Title 13 Figure 1 SNEC Facility Site Layout , 19 Figure 2 Locations of REMP TLD and Aquatic Sediment Stations i 20 Figure 3 Locations of REMP Groundwater Wells 29 Figure 4 1997 Gross Beta Concentrations in Air Particulate 30 Figure 5 1997 Gross Alpha Concentrations in Air , Particulate I Page iv
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT LIST OF ABBREVIATIONS, SYMBOLS AND ACRONYMS ABBREVIATIONS south. southwest . . . . . . . . . . . . . . . . . . . . . . . . . . . . SSW cubic feet per second . . . . . . . . . . . . . . . . . . . . . . . . . cfs standard deviation . . . . . . . . . . . . . . . . . . . . . . . . . . . . std dev cubic meter (s) . . . . . . . . . . . . . . . ................m' standard month . . . . . . . . . . . . . . . . . . . . . . std month curie (s). . . . . . . . . . . . . . . . .......... ...........Ci west . . . . . . . . . . ... .. .... .................. .... .W curie (s) per year . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ci/yr west-northwest . . . . . . . . . . . . . . . . . . . . . . . . . . . . .WNW cast........ . ..........................E west. southwest . ... .. . . ... ....... W S W cast-northeast .. .. . ... ........ . . . . . . . . . . . . . . EN E year (s) . . . . .... .. .. . ......... . . . . . . . . . . yr east-southeast . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ES E ELEMENT SYMBOLS g ram (s ) . . . . . . . . . . . . . . . . . . . . . . . . . . . ..............g actinium . . . . . . . . . . . . . ... .................Ac bour(s) . ................................h anti mo ny . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Sb liter (s) . . . . . . . . . . . . . . . . . . . .......... ..............L arg o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ar m eter(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . m bari u m . . . . . . . . . . . . . . . . . . . . . . . ...............Ba microroentgen per hour . .... ... ..... . .. . uR/h berylliu m .. . . .. . . . ......... ..............Be mile per hour . . . . . . . . . . . . . . . . . . . . . . . . . . mph carbon. .... . ... .. ... .... ... ...............C millirem . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . mre m cesium . .. . ......... ..... . ... . . .. .Cs millirem per hour . . . . . . . . . . . . . . . . . . . . . . . . . mrem /h chro miu m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Cr millirem per standard cobalt . .... . ...... . .. ...................Co month . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . mrem /std mo nth cu ri u m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Cm millirem per year . . . . . . . . . . . . . . . . . . . . . . . . mrem /yr hydrogen (tritium) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-3 milliroentgen ....... . . .... .... .. ........... m R i odi n e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I milliroentgen per hour . . . . . . . . . . . . . . . . . . . . . . . . . mR/h iron................................... . . . . . . Fe milliroentgen per standard krypton . ..... ... ......... ... ............ . . . . . . Kr month . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . mR/std month lanthan~n . . . . . . . . . . . . . . . . . ...................La north.................................................N manganese . . . . . . . . . . . . . . . . . . . . . . . . . ..Mn no rth east . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N E niobi u m . . . . . . . . . . . . . . . . . . . . . . . . ...............Nb no rth west . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NW nitrogen . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N north-northeast. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . NNE o xyg e n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . O no rth-north west . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .NNW pl uto ni um . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Pu percent . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . % potass i u m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . K picoeurie(s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . pCi radiu m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ra picoeurie(s) per cubic meter .......... .. .. pCi/m 8 radon . . . . . ... ... .. ...... ..................Rn picoeurie(s) per gram . . . . . . . . . . . . . . . . . . . . . . . . pCi/g ruthenium .... .. . .... . .... ... .. . . . . . Ru picoeurie(s) per liter ..... ... . . . . .... . .. . ...... pCi/L s il ver . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A g reference (s) . . . . . . . . . . . . . . . . . . . . . . . . . . . . Ref. (Refs.) strontium .... .... ...............................Sr rem per year . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . rem /yr th o ri u m . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .Th Roent g e n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . R tritiated water vapor . . . . . . . . . . . . . . . . . . . . . . . . . . . . HTO Roentgen equivalent man . . . . . . . . . . . . . . . . . . . . . . . rem uraniu m . . . . . . . . . . . . . . . . .........................O south..................................................S xenon................................................Xe south east . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S E zinc..................................................Zn south west . . . . . . . . . . . ..... .... .................. S W zirconiu m . . . . . . . . . . . . . . . . . . . . . . . . ... .... . . . . . . . Zr Page v
1997 RADIOLOGICAL ENVIRON.% ENTAL MON 110 RING REPORT I ACRONYMS American National Standards institute . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ANS I National Voluntary Laboratory Accreditation Program.. ......... ...NVLAP as low as reasonably achievable. .. . . . . .. . .. . .. ALARA Offsite Dose Calculation Manual .. .....ODCM biological effects of atomic Pennsylvania State Bureau radiation.... ...... . ..... ... .. ...... . . B E A R of Radiation Protection ............ .... ... PaBRP biological effects of ionizing pressurized water reactor... . .. ...... . P W R radiation. . . . . . . . . . . . . . . . . . . . . . . . . .. . . .. B EIR quality assurance... .. . ...........QA Depanment of Energy.. ... . ....... .. ... DOE quality control. . . . .. . .... ........ . . . . . QC Department of Energy.. .... . ...... .... DOE radiological environment.! Derived Air Concentration... .. .... . . ..DAC monitoring program . . . . . . . . . . . . . . . . . . . . . . . . . REM P Federal Radiation Council... . . . . .. .FRC Saxton Nuclear Experimental Corporation...... . . . . . . . . . . . . . . . . .....SNEC Final Safety Analysis Report .... ..... . ..FSAR I th ermol u minescent d os imete r . . . . . . . . . . . . . . . . . TLD l t General Public Utilities j l Nuclear Corporation...... . ......GPU Nuclear Title 10 of the Code of I l Federal Regulations, Part 20..... ..10 CFR 20
- high efficiency particulate air....... ...... HEPA Title 10 of the Code of l
International Committee on Federal Regulations, Part 50, i ! Radiation Protection .... ...... ... .. . .lCRP Appendix 1. .. . . . . . . . . . . . 10 CFR 50 App. I lower limit of detection ...... ...... .. ... . LLD Title 40 of the Code of l Federal Regulations, mean sea level . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . msl Part 190. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 40 CFR 190 miniraum detectable concentration.. . . . ..MDC United Nations Scientific Committee en the Effects of l National Academy of Sciences ..... ...... . NAS Atomic Radiation ... ....... . . ...... UNSCEAR National Council on Radiation United States Environmental Protection and Measurements. . .. ...... NCRP Protection Agency ...... ....... . .. ...... USEPA National Institute of United States Nuclear Regulatory Standards and Technology .. ...... .......NIST Commission . . . . .. . .. ... . . . . . ... . . . . . . . . . .U S NRC Page vi l l
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l
SUMMARY
AND CONCLUSIONS l This report reviews the radiological environmental ; monitoring performed in 1997 by GPU Nuclear for the Saxton Nuclear Experimental Corporation (SNEC) Facility. The environmental sample results indicated that SNEC operations in 1997 had no adverse effect on either the environment or the health and safety of the public. Many of the radioactive materials discussed in this report are normally present in the environment, either from natural processes or as a result of non-SNEC activities such as prior atmospheric nuclear weapon tests and medical industry activities. To determine the impact of SNEC operations on the environment and the public, results from samples collected close to SNEC (indicator stations) were compared to results from samples obtained at distant sites (control or background stations). Page 1
I I 1997 RAD!0 LOGICAL ENVIRONMENTAL MONlwRING REPORT i The results of environmental measurements were used to assess the impact of SNEC decommissioning operations and to demonstrate compliance with the SNEC Offsite Dose Calculation Manual (Ref.1) and applicable Federal and State regulations. During 1997, samples of air, surface water, sediment, vegetation, and groundwater were collected. Direct radiation exposures were also measured in the vicinity of SNEC. Samples were analyzed for gross alpha and gross beta radioactivity, tritium (H-3), stmntium-90 (Sr-90), and/or gamma emitting radionuclides. The results am discussed in the various sections of this report and are sumiaanzed in the following highlights: 5 More than 250 samples were collected in 1997 fmm the aquatic, atmospheric and terrestrial l environments amund SNEC. There were nearly 500 analyses performed on these samples. l Approximately 112 direct radiation exposure measurements were taken using thermoluminescent dosimeters (TLDs). The monitoring performed in 1997 met or exceeded the sample collection and analysis requirements of the SNEC Offsite Dose Calculation Manual (ODCM). 5 The raw surface water collected downstream of the SNEC liquid discharge outfall resulted in less then detectable activities for radionuclides attributed to SNEC, including tritium (H-3). B River sediments collected just downstream of the SNEC liquid discharge outfall and at the control station upstream of the site detected low concentrations of Cs-137. These concentrations were attributed to fallout from prior nuclear weapon tests. Low concentrations of SNEC-related cobalt-60 (Co-60) and cesium-137 (Cs-137) were detected in aquatic sediments collected from storm drains that are located on site. Co-60 and Cs-137 are readily adsorbed by suspended particles in the water column and bottom sediments. E Only one groundwater sarr.ple collected fmm the onsite monitoring and supply wells contained H-3 above ambient concentrations. The activity of this sample was 180 picocuries per liter (pCi/L). Although humans do not consume this water, it was well below the United State Enviromnental Protection Agency's (USEPA) Primary Dnnking Water Standard (Ref. 2) of 20,000 pCi/L. E Gamma radiation exposure rates recorded at the offsite indicator TLD stations averaged 62 milliroentgen per year (mR/yr). These exposure rates were consistent with those presented by the National Council on Radiation Protection and Measurements (Ref. 3). No increase in ambient gamma radiation levels was detected. Page 2
l l l 1997 RADIOLOGICAL ENVIRONMENTAL MONlwRING REPORT In conclusion, radioactive materials related to SNEC operations were detected in certain on-site environmental samples, but the measured concentrations were low. No effluent releases occurred fmm SNEC during 1997, therefore, no dose to the public should be attributed to SNEC activities. Additionally, the envimnmental sample results indicated that there was no permanent buildup of radioactive materials in the environment and no increase in background radiation levels. Therefore, based on the results of the radiological envimnmental monitoring program (REMP) SNEC operations in 1997 did not have any adverse effects on the health and safety of the public or on the envimnment. 1 Page 3 I t
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT l INTRODUCTION Characteristics of Radiation Instability within the nucleus of radioactive atoms results in the release of energy in the form of radiation. Radiation is classified according to its nature -- particulate and electromagnetic. Particulate radiation consists of energetic subatomic particles such as electrons (beta particles), protons, neutrons, and alpha particles. Because of its limited ability to penetrate the ' human body, particulate radiation in the environment contributes primarily to internal radiation exposure resulting from inhalation and ingestion of radioactivity. Electromagnetic radiation in the form of x-rays and gamma rays has characteristics similar to visible light but is more energetic and, hence, more penetrating. Although x-rays and gamma rays are penetrating and can pass through varying thicknesses of materials, once they are absorbed they produce energetic electrons which release their energy in a manner that is identical to beta particles. The principal concern for gamma radiation from radionuclides in the environment is their contribution to external radiation exposure. Page 4
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The rate with which atoms undergo disintegration (radioactive decay) varies among radioactive elements, but is uniquely constant for each specific radionuclides. The term
" half-life" defines the time it takes for half of any amount of an element to decay and can vary fmm a fraction of a second for some radionuclides to millions of years for others. In fact, the natural backgmund radiation to which all mankind has been exposed is largely due to the radionuclides of umnium (U), thorium (Th), and potassium (K).
These radioactive elements were formed with the creation of the universe and, owing to their long half-lives, will continue to be present for millions of years to come. For example, potassium-40 (K-40) has a half-life of 1.3 billion years and exists naturally within our bodies. As a result, approximately 4000 atoms of potassium emit radiati .. within each of us every second of our lives. In assessing the impact of radioactivity on the environment, it is important to know the quantity of radioactivity released and the resultant radiation doses. The common unit of radioactivity is the curie (Ci). The curie represents the radioactivity in one gram (g) of natural radium (Ra), which is equivalent to a decay rate of 37 billion radiation emissions every second. Because of the extremely small amounts of radioactive material in the environment, it is more convenient to use fractions of a curie. Subunits like picoeurie, pCi, (one trillionth of a curie) are frequently used to express the radioactivity pmsent in environmental and biological samples. The biological effects of a whole body equivalent dose of radiation are the same whether the radiation source is external or intemal to the body. The important factor is how much radiation energy or dose was deposited. The unit of radiation dose is the Roentgen equivalent man (rem), which also incorporates the variable effectiveness of different forms of radiation to pmduce biological change. For environmental radiation exposures, it is convenient to use the smaller unit of millirem (mrem) to express dose (1000 mrem equals 1 rem). When mdiation exposure occurs over periods of time, it is appmpriate to refer to the dose rate. Dose rates, therefore, define the total dose for a fixed interval of time, and environmental exposures are usually expressed with reference to one year (mrem /yr). Sources of Radiation Life on earth has evolved amid the constant exposure to natural radiation. In fact, the single major source of radiation to which the general population is exposed comes from natural sources. Although everyone on the planet is exposed to natural radiation, some people receive more than others. Radiation exposure from natural backgmurxl has three components (i.e., cosmic, terrestrial, and internal) and varies with altitude and i geographic location, as well as with living habits. For example, cosmic radiation I originating fmm deep interstellar space and the sun increases with altitude, since there is Page5 l
1997 RADIOLOGICAL ENVIRONMENTAL MONImRING REPORT less air which acts as a shield. Similarly, terrestrial radiation resulting from the presence of naturally-occurring radionuclides in the soil and rocks varies and may be significantly ! higher in some areas of the country than in others. Even the use of particular building materials for houses, cooking with natural gas, and home insulation affect exposure to natural radiation. The presence of radioactivity in the human body results from the inhalation and ingestion of air, food, and water containing naturally-occurring l radionuclides. For example, drinking water contains trace amounts of uranium and radium while milk contains radioactive potassium. Table I summarizes the common sourres of radiation and their average annual doses. The average person in the United States receives about 300 miem/yr (0.3 rem /yr) from natural background radiation sources (Ref. 4). This estimate was revised from about 100 to 300 mrem because of the inclusion of radon gas which has always been present but was not previously included in the calculations. In some regions of the country, the amount of natural radiation is significantly higher. Residents of Colorado, for example, receive an additional 60 mrem /yr due to the increase in cosmic and terrestrial radiation levels. In fact, for every 100 feet above sea level, a person will receive an additional I mrem /yr from cosmic radiation. In several regions of the world, naturally high concentrations of uranium and radium deposits result in doses of several thousand mrem /yr to their residents (Ref.5). 1 TABLE 1 Sources and Doses of Radiation
- Natural (82%) Manmade (18%) l Radiation Dose Radiation Dose Source (mran/vr) Source (mrem /tr)
Radon 200 (55 %) Medical X-rays 39 (11 %) Cosmic rays 27 (8%) Nuclear Medicine 14 (4%) Terrestrial 28 (8%) Consumer products 10 (3%) Internal 40 (11 %) Other < 1 (< 1 %) (Releases from nat. gas, phosphate mining, buming of coal, weapons fallout, & nuclear fuel cycle) APPROXIMATE APPROXIMATE TOTAL 300 TOTAL 60 l
- Percentage contribution of the total dose is shown in parentheses. Source: Ref.4 l
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1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Recently, public attention has focused on radon (Rn), a naturally-occurring radioactive gas produced fmm uranium and radium decay. These elements are widely distributed in trace amounts in the canh's cmst. Unusually high concentrations have been found in cenain pans of eastem Pennsylvania and nonhem New Jersey. Radon levels in some homes in these : steas are hundreds of times greater than levels found elsewhere in the United States. l Additional surveys, however, are needed to determine the full extent of the problem j nationwide. Radon is the largest component of natural background radiation and may be responsible for a substantial number of lung cancer deaths annually. The National Council on Radiation Protection and Measurements (NCRP) estimates that the average individual in the United States receives an annual dose of about 2,400 mrem to the lung from natural radon gas (Ref. 4). This lung dose is considered to be equivalent to a whole body dose of 200 mrem. The , I NCRP has recommended actions to control indoor radon sources and reduce exposures. When radioactive substances are inhaled or swallowed, they am not uniformly distributed within the body. For example, radioactive iodine selectively concentrates in the thyroid gland, radioactive cesium is distributed throughout the body water and muscles, and radioactive strontium concentrates in the bones. The total dose to organs by a given radionuclides is influenced by the quantity and the duration of time that the radionuclides remains in the body, including its physical, biological and chemical characteristics. Depending on their rate of radioactive decay and biological elimination fmm the body, some radionuclides stay in the body for very shon times while others remain for years. In addition to natural radiation, we are exposed to radiation from a number of manmade sources. The single largest of these sources comes from diagnostic medical x-rays and nuclear medicine procedures. Some 180 million Americans receive medical x-rays and nuclear medicine treatment each year. The annual dose to an individual from such radiation averages about 53 mrem. Much smaller doses come fmm nuclear weapon fallout and consumer products such as televisions, smoke detectors, and fertilizers. Production of commercial nuclear power and its associated fuel cycle contributes less than 1 mrem to the annual dose of about 360 mrem for the average individual living in the United States. Fallout commonly refers to the radioactive debris that settles to the surface of the canh following the detonation of a nuclear weapon. It is dispersed throughout the environment either by dry deposition or washed down to the earth's surface by precipitation. There are j approximately 200 radionuclides produced in the nuclear weapon detonation process; a ; number of these are detected in fallout. The radionuclides found in fallout which produce most of the fallout radiation exposures to humans are I-131, Cs-137, Sr-89, and Sr-90. There has been no atmospheric nuclear weapon testing since 1980 and many of the Page 7 ,
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT radionuclides, still present in our environment, have decayed significantly. Consequently, doses to the public from fallout have been decreasing. As a result of the nuclear accident at Chernobyl, Ukraine, on April 26,1986, radioactive materials were dispersed thmughout the environment and detected in various media such as air, milk, and soil. Cesium-134, Cs-137, I-131 and other radionuclides were detected in the weeks following the Chernobyl accident. 1 Page 8
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1997 RADIOLOGICAL ENVIRONMENT L MONITORING REEDRT 1 DESCRIPTION OF THE ! SNEC SITE Location of the Plant Site The site is located about 100 miles east of Pittsburgh and 90 miles west of Harrisburg, Pennsylvania in the Allegheny Mountains, three-fourths of a mile north l of the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania. The site is on the ) north side of Pennsylvania Route 913,17 miles south l of U.S. Route 22, and about 15 miles north of the Breezewood Interchange of the Pennsylvania Turnpike. Description of Plant Site
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Saxton was built adjacent to the Saxton Steam l Electric Generating Station of Pennsylvania Electric Company (Penelec), a subsidiary of GPU. This coal fired station operated from 1923 to 1974 and was demolished between 1975 and 1977. The Saxton site consists of 1.148 fenced acres of the approximate 150 acres owned by Penelec. An additional 9.6 acre fenced area contains an electrical switchyard and buildings under Penelec control. A general property j layout is shown in Figure 1. The Saxton site, as well as, a portion of the Penelec area and the surrounding ) I I I Page 9
____ ______------ - - ' ~ 1997 RADIOLOGICAL ENVIRONMENTAL MONINRING REPORT uncontrolled lands, is in the 100-year floodplain of the Raystown Branch of the Juniata River which borders the north and west portion of the propeny. A small stream known as Shoup's Run crosses the central portion of the propeny and joins the Juniata River. Normal elevation of the River near Saxton is approximately 794 feet above mean sea level (msl). The site and adjacent propeny lie about 17 feet above river level. Much of the propeny consists of gently sloping open grassland, a result of the restoration activities following the demolition of the Saxton Steam Electric Generating Station. SNEC Decommissioning Operations The Saxton Nuclear Experimental Facility was a pioneer in the development of the nuclear energy program for the United States. It operated for ten years, from 1962 to 197z, and provided valuable information on operations and training. The fuel was removed from the . Containment Vessel (CV) in 1972 and shipped to the Atomic Energy Commission (AEC) I facility at Savannah River, South Carolina. Following fuel removal, equipment, tanks, and piping located outside the CV were removed. Final decontamination and dismantlement of reactor suppon stmetures and buildings were completed in 1992. Additional information can be obtained from the Reactor Support Demolition Report (Ref. 6). Facility Description The only remaining Saxton stmetures include the Containment Vessel (CV), the concrete shield wall located around the northwest and northeast quadrants of the CV, tunnel sections that are immediately adjacent to the outer circumference of the CV and portions of the septic syst:vn, weirs and associated underground discharge piping. Concrete barrier walls have been installed to isolate the open ends of the tunnel that were connected to the Control & Auxiliary Buildings, the Radioactive Waste Disposal Facility and the Steam Plant. Ponions of the Steam Plant Tunnel still exist beyond the point where the tunnel was blocked-off. Containment Vessel The Saxton Containment Vessel is a circular steel structure approximately 100 ft. tall by 50 ft. in diameter with approximately 50 percent of the structure below grade. The CV is subdivided into a reactor companment/ storage well, primary companment, auxiliary companment and an operating floor. Concrete walls, floors and ceilings separate these areas from each other. The below grade ponion of the CV is lined with concrete, as well. Concrete Shield Wd The concrete shield wall is a small exterior wall built along the nonhwest and nonheast quadrant of the containment vessel and is not contaminated. Page 10 l
r i 1997 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT l
- Tunnel The tunnel section immediately adjacent to the CV originally carried system piping between the CV and other facility buildings. This piping was removed as part of Saxton decommissioning activities that occurred following the plant's shutdown in 1972.
Demorraohv - Human Activities in the Environs The area surrounding the Saxton site is generally rural fomsted and mountainous terrain. The population density of the area is low with small concentrations in the valleys and along main highways. The site lies about three-fourths of a mile north of the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania. The population and population trends for the Borough of Saxton, Bedford County and the adjacent counties of Blair and Huntingdon have decreased by approximately 3 % between 1980 and 1990 (Ref. 7). At the time the SNEC facility was constructed the estimated population of the Bomugh of Saxton was 975 as recorded during the 1960 census. Thirty years later, the population as recorded during the 1990 census was 838, a decline of 16.3%. The nearest population center (as defined by 10 CFR 100) of 25,000 or more is the city of Altoona which lies approximately 20 miles north-northwest of the Saxton site. The 1990 I population of Altoona was 51,881. The closest incorporated towns other than the Borough of l Saxton are Coalmont Borough about 2.5 miles to the east, Dudley Borough about 3.4 miles to l the east and Bmad Top about 5.3 miles also to the east. Current uses of adjoining properties 'nclude undeveloped wooded and residential at us. A cemetery lies along the eastern property boundary while undeveloped wooded and r:sidential areas border the northern, southern and western property boundaries. The Raystown Branch of the Juniata River in the vicinity of the site is primarily used for recreational boating and fishing by local residences. The vast majority of recreational activities along the river, however, are located downstream of the site on Raystown Lake. Approximately 34 miles downstream of the site, the Raystown Branch of the Juniata River is dammed, impounding the river to form Raystown Lake. The dam built by the US Army Core of Engineers (COE) for flood control, recreation and water quality purposes was constructed from 1968 to 1973. At normal pool level, the lake is 27 miles long and has an area of 8,300 acres. Raystown Iake provides one of the better recreational areas in this part of Pennsylvania. The Federal Government developed the lake extensively for recreational activities including boating, fishing, camping, hunting, and picnicking. Page11
i 1 l 1997 RADIOLOGICAL L ENVIRONMENTAL MONITORING REPORT l Geology The Saxton site lies in the Appalachian highlands in the Ridge and Valley physiographic pmvince. This province comprises alternate successions of narrow ridges and broad or narrow valleys trending generally northeast. This region contains alternating hard and soft sedimentary rocks that have been severely folded by lateral compression into a series of anticlines and synclines. The ridge consists of Tuscarora quartzite and a small amount of Pleistocene gravel. Most of the area is underlain by strata of Upper Devonian age. Although coal was mined in the general area of the site, no coal has been reported to lie beneath the site, nor has the site been undermined. The ridges immediately to the northwest of the site rise to 1300 feet and to the southeast rise to 1500 feet with site elevation being approximately 811 feet above msl. Page 12
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I 1997 RADIOLOGICAL ENVIRONMENTAL MONI1DRING REPORT RADIOLOGICAL ENVIRONMENTAL MONITORING GPU Nuclear conducts a comprehensive radiological environmental monitoring program (REMP) at SNEC to measure levels of radiation I and radioactive materials in the environment. I The information obtained from the REMP is then \ l used to determine the effect of SNEC operations, l if any, on the environment and the public. i l The USNRC has established regulatory guides that contain ecceptable monitoring practices. The SNEC REMP was designed on the basis of these regulatory guides along with the guidance provided by the USNRC Radiological Assessment Branch Technical Position for an l acceptable radiological environmental monitoring program (Ref. 8). The SNEC REMP meets or exceeds the monitoring requirements set forth by the USNRC. l l Page 14
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT The important objectives of the REMP are: E To assess dose impacts to the public from the SNEC Facility. E To verify decommissioning contmls for the containment of radioactive aaterials. 5 To determine buildup of long-lived radionuclides in the environment and changes in background radiation levels. E To provide reassurance to the public that the program is capable of adequately assessing impacts and identifying noteworthy changes in the radiological status of the environment. 5 To fulfill the requirements of the SNEC Technical Specifications. Sampline The program consists of taking radiation measurements and collecting samples fmm the environment, analyzing them for radioactivity content, and then interpreting the results. These samples include, but are not limited to, air, water, sediment, vegetation and groundwater. Thermoluminescent dosimeters (TLDs) are placed in the environment to measum gamma radiation levels. The Offsite Dose Calculation Manual (ODCM), (Ref.1) defines the sample types to be collected and the analyses to be performed. As appropriate, chances to the REMP are initiated by recommendations from the scientific staff at the GPU Nuclear bivironmental Radioactivity Laboratory. However, the minimum sampling and analysis requirements specified in the ODCM are maintained. Sampling locations were established by considering topography, meteorology, population distribution, hydrology, and areas of public interest. The sampling locations are divided into two classes, indicator and contml. Indicator locations are those which are expected to show effects fmm SNEC activities, if any exist. These locations were selected primarily on the basis of where the highest predicted environmental concentrations would occur. The indicator locations are typically within the site boundary, along the perimeter fence or a few miles from the SNEC facility. Control stations are located generally at distances greater than 10 miles from SNEC. The samples collected at these sites are expected to be unaffected by SNEC operations. Data from control locations provide a basis for evaluating indicator data relative to natum! background radioactivity and fallout from prior nuclear weapon tests. Figures 2 and 3 show the current sampling locations around the facility. Table A-1 in Appendix A describes the sampling locations by distance along with the type (s) of samples collected at each sampling location. Page 15
i l 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Analysis l In addition to specifying the media to be collected and the number of sampfiag locations, the ODCM also specifies the frequency of sample collection and the types and frequency of analyses to be performed. Also specified are analytical sensitivities (detection limits) and reporting levels. Table A-2 in Appendix A provides a synopsis of the sample types, number l of sampling locations, collection frequencies, number of samples collected, types and { frequencies of analyses, and number of samples analyzed. Table A-3 in Appendix A lists samples which wem not collected or analyzed per the requirements of the ODCM. Changes in l sample collection and analysis are described in Appendix C. All samples analyzed meet the l l required analytical sensitivities. Measurement of low radionuclides concentrations in environmental media mquires special i analysis technique.t Analytical laboratories use state-of-the-art laboratory equipment designed to detect all three types of radiation emitted (alpha, beta, and gamma). This equipment must meet the analytical sensitivities required by the ODCM. Examples of the specialized laboratory equipment u:ed rat germanium detectors with multichannel analyzers for l determining specific gamma-emitting radionuclides, liquid scintillation counters for detecting H-3, low level proportional counters for detecting gross alpha and beta mdioactivity and alpha j spectroscopy for determining specific transuranic isotopes. Calibrations of the counting equipment are performed by using standards taceable to the ! National Institute of 'ndards and Technology (NIST). Computer hardware and software ! l used in conjunction 5 the counting equipment perform calculations and provide data l' martgement. Anv 'i: methods are described in Appendix H. Data Review l The analytical results are routinely reviewed by GPU Nuclear scientists to assure that sensitivities have been achieved and that the proper analyses have been performed. Investigations are conducted when wtion levels or USNRC reporting levels are reached or ; when anomalous valuer are discovered. This review process is discussed in more detail in l Appendix D. { I i l Tables 4 and 5 depict gross beta and gross alpha results, respectively. Table 6 lists the tritium concentrations from station GEO-5. Table 7 provides a summary of radionuclides concentrations detected in the aquatic sediment samples for 1997. Statistical methods used to derive these tabbs along with other statistical conclusions are detailed in Appendix G. Quality i control (QC) sample results were used mainly to verify the primary sample result or the first result in the csse of a duplicate analysis. Therefore, the QC results were excluded from these tables and the main text of this report to avoid biasing the results. Page 16
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Ouality Assurance Progrant A quality assurance (QA) program is conducted in accordance with guidelines provided in Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Pmgrams" (Ref.12) and as required by the Technical Specifications. The pmgram is documented by GPU Nuclear written policies, pmcedures, and records. These documents encompass all aspects of the REMP including sample collection, equipment calibation, laboratory analysis and data review. The QA pmgram is designed to identify possible deficiencies so that immediate corrective action can be taken. The program also provides a measure of confidence in the results of the monitoring program in order to assure the regulatory agencies and the public that the results are valid. The QA program for the measurement of radioactivity in envimnmental samples is implemented by: E Auditing all REMP-related activities including analytical laboratories. E Requiring analytical laboratories to participate in a cross-check program (s). E Requiring analytical laboratories to split samples for separate analysis (recounts are performed when samples cannot be split). E Splitting samples, having the samples analyzed by independent laboratories, and then comparing the results for agreement. E Reviewing QC results of the analytical laboratories including spike and blank sample results and duplicate analysis results. The QA pmgram and the results of the cross-check pmgrams are outlined in Appendix E and F, respectively. The TLD readers are calibrated monthly against standard TLDs to within five percent of the standard TLD values. Also, each group of TLDs processed by a reader contains contml TLDs that are used to correct for minor variations in the reader. The accuracy and variability of the { results for the control TLDs are examined for each gmup of TLDs to assure the reader is functioning pmperly. In addition, each element (TLD) has an individual correction factor ) based on its response to a known exposure. l Other cmss-checks, calibrations, and certifications used to assure the accuracy of the TLD program include: E Semiannually, randomly selected TLDs are sent to an independent laboratory where they are irradiated to set doses unknown to GPU Nuclear. TLDs which meet the criteria Page 17 l
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT speciGed by the National Voluntary Laboratory Accreditation Program (NVLAP) are used for this test. The GPU Nuclear dosimetry laboratory processes the TLDs and the results are compared against established limits. 5 Every two years, each TLD is checked to ensure an appropriate correction factor is assigned to each element of the TLD. 5 Every two years, GPU Nuclear's dosimetry pmgram is examined and NVLAP decertified by the NIST. The envimnmental dosimeters wem tested and qualined to the American National Standard Institutes (ANSI) publication N545-1975 and the USNRC Regulatory Guide 4.13 (Refs.10 and 11). l l . Page 18
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l 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT l DIRECT RADIATION . MONITORING Radiation is a normal component of the i environment resulting primarily from natural sources, such as cosmic radiation and naturally-occurring radionuclides, and to a lesser extent from manmade sources, such as fallout from prior nuclear weapon tests. The cessation of atmospheric nuclear weapon tests and the decay of fallout products have resulted in a gradual decrease in environmental radiation levels. Direct radiation monitoring measures ionizing radiation primarily from cosmic and terrestrial sources. Gamma radiation exposure rates near SNEC were measured using thermoluminescent dosimeters (TLDs). There are 28 TLDs that surround the SNEC facility. Sixteen Indicator Stations, one per compass sector, are located on the SNEC outer perimeter fence. One station is located in the Penelec Line Department garage. There are nine Offsite Indicator Stations in various sectors within two miles of the site. There are also two Control Stations, each about 10 miles from the site. The indicator stations are used to detect any potential effect of SNEC Facility activities on environmental radiation levels. Page 21
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT No relationship betweer. the SNEC facility activities and offsite exposure rates were detected at any station. The 1997 quarterly exposure rates for the individual TLD stations are contained in Appendix I. Sample Collection and Analysis A thermoluminescent dosimeter (TLD) is composed of a crystal (phosphor) which absorbs and stores energy in traps when exposed to ionizing radiation. These traps are so stable , that they do not decay appreciably over time. When heated, the crystal emits light ! pmportional to the amount of mdiation received, and the light is measured to determine the integrated exposure. This process is referred to as thermoluminescence. The reading process 'rezeros' (anneals) the TLD and prepares it for reuse. The TLDs in use for environmental monitoring at the SNEC facility are capable of accumtely measuring exposures from a minimum of 1 mR (well below normal environmental exposures for the quarterly monitoring periods) to a maximum of 200,000 mR. Each TLD station consists of 2 TLD badges, each of which has 4 phosphors or elements. Since each TLD responds to radiation independently, this provides 8 independent detectors at each station. Of the 4 elements in GPU Nuclear's TLDs, 3 are composed of calcium sulfate and 1 is composed of lithium borate. The calcium sulfate elements are shielded with a thin layer of lead making the response to different energies of gamma radiation more linear. The lead also shields the elements from beta radiation, making them sensitive to gamma radiation only. The lithium borate element is shielded differently to permit the detection of beta radiation as well as gamma. The combination of different phosphor materials, shielding, and multiple phosphors per badge permit quantification of both gamma and beta radiation. Only the calcium sulfate phosphors are used for environmental monitoring; however, the lithium borate elements can be used to evaluate beta exposures or as a backup to the calcium sulfate elements should more data be required. Data from the TLDs were evaluated by obtaining the average of the usable element results at each station. All TLD exposure rate data presented in this report were normalimi to a standard month (std month) to adjust for variable field exposure periods. A std month is 30.4 days. Several badges were used to quantify transit exposure duling storage and handling of TLDs. Transit exposures were subtracted from gross field exposures to produce net field exposures. Results In 1997, the avenge annual exposure rate for offsite indicator stations was 5.1i 2.0 mR/std month. Quarterly exposure rates ranged from 4.0 to 7.7 mR/std month. Offsite indicator station E2-1, located 0.25 mile from the CV, displayed the highest elevated Page 22 l 1 1 l
l l i 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT exposums. An investigation revealed that the elevated results wem due to residual waste from the coal-fired station formerly located adjacent to SNEC. The soil at station E2-1 consists of a mixture of coal slag and cinders, which emit a slightly elevated gamma from naturally occurring Th-232 and Ra-226, and thus adding to the TLD results. The average annual exposure rate for the two control stations, those stations fanher than 10 miles from SNEC, was 4.9 i 1.1 mR/std month. Quarterly exposure rates at the control stations ranged from 4.3 to 5.4 mR/std month. Table 2 depicts the average offsite indicator results with the average control results. l l No elevated exposure rates attributed to the SNEC facility activities wcre observed at any offsite station. TLDs am sensitive and accurate mechanisms for measuring the low exposure mtes characteristic of envimnmental levels. Effects of normal SNEC facility activities, however, are too small to be discernible outside the normal range of background radiation levels. Table 3 compams the highest site boundary exposure result to the allowable maximum exposure rate based on 10 CFR 20 Section 20.105(a) (Ref.16). The annual average gamma radiation exposure rate recorded from all offsite indicator l TLD stations was Lil mR/std month. This equates to an annual exposure rate of M ! mR/yr. Exposure of this magnitude is consistent with the annual average dose a person receives from cosmic and terrestrial sources (Table 1, " Sources and Doses of Radiation"). I Page 23
l 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l TABLE 2 1 1997 SNEC TLD Summary Field Cycle: January 8,1997 to January 8,1998 l mR/std month MEAN MINIMUN MAXIMUM i Average Offsite Indicator Stations 5.13 4.03 @ Kl-5 7.68 @ E2-1 Average Control Stations 4.92 4.30 @ H10-1 5.42 @ G10-1 TABLE 3 Highest Site Boundary Exposure Comparison Compared to an allowable maximum exposure ,, mR/std rate of 430 mR/std month based on 10 CFR 20 8'70 month . Section 20.105(a) (Ref.12). At Station D14 Compared to an allowable maximum exposure rate of 0.37 mR/hr. This equivalent to the 25 mR 0.0119 mR/Hr annual limit specified by 40 CFR 190 adjusted by the 67-hour recreational factor specified in Reg. ' Guide 1.109 (shoreline exposure for maximum exposed teenager) (Ref.13). l l Page 24 i L______._______________________
1997 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT ATMOSPHERIC MONITORING A potential exposure pathway to humans is the inhalation of airborne radioactive materials. To monitor this exposure pathway, ambient air was sampled by a network of continuously operating samplers and then analyzed for radioactivity content. Based on the analytical results, no contribution to the general levels of airborne l radioactivity was attributed to the SNEC facility during 1997. l The indicator air sampling stations are located in i the three predominant wind sectors around the Containment Vessel (CV), the north sector (Al-2), the east sector (D1-1), and the south sector (J1-3). The control air sampling station (G10-1), which is 10 miles from the site, provided background airborne radioactivity data for comparison. Page 25
_____ -.__. - - - - ~ I 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT l Samle Collection and Analysis Mechanical air samplers were used to continuously draw air through glass fiber filters. To maintain a constant flow rate throughout the collection period, each sampler was equipped with a mass flow probe. This electronic device maintains a constant airflow across the filter paper. All air samplers wem calibrated semiannually and maintained by instrumentation technicians. The glass fiber filters were used to collect airborne particulate matter. The filters were collected weekly (biweekly during the 1" quaner) and analyzed for gross alpha and gmss beta radioactivity. The filters were then combined quarterly by individual station locations and analyzed for gamma-emitting radionuclides. In order to generate additional background data prior to the demolition of the CV, the individual composites fmm the first and second quaner were combined by station and analyzed for Sr-90 and gross actinides, i.e., Am-241, Cm-242, Cm-243/244, Pu-239, Pu-239/240, U-234, U-235, and U-238. Air Results During 1997,133 air paniculate samples (filters) were collected and analyzed for gross alpha and gross beta radioactivity. The particulate matter (dust panicles) collected either weekly or biweekly on all indicator and control filters contained gross beta mdioactivity above the minimum detectable concentration (MDC). The gross beta concentrations measured on the filters collected from indicator sites ranged fmm 0.0088 i 0.0009 pCi/m' to 0.046 0.005 pCi/m' and averaged 0.01972 i 0.014 pCi/m'. The air paniculate samples collected from the control location had gross beta concentrations, which ranged from 0.0075 0.0029 pCi/m' to 0.039 0.004 pCi/m' and averaged 0.01828 i 0.012 pCi/m'. The average results are listed in Table 4. As depicted in Figure 4, average weekly gross beta concentrations at indicator and control air monitoring locations were analogous and trended similarly throughout the monitoring period. The weekly gross be'.a concentrations and trends at individual air sampling sites also were similar. The 1997 data indicated that gross beta radioactivity levels did not change as a result of SNEC operations. Additionally, the gross beta radioactivity associated with airborne particulate was due to naturally-occurring radionuclides. Air particulate gross alpha concentrations (detected above the MDC) at indicator stations ranged from 0.00061 0.00006 pCi/m' to 0.0045 i 0.0013 pCi/m' and averaged 0.001847 0.0017 pCi/m'. Control samples averaged 0.001685 0.0013 pCi/m' and ranged from 0.00087 i 0.00009 pCi/m' to 0.0042 0.0004 pCi/m'. Page 26 i 4
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Average weekly gross alpha concentrations are depicted in Figure 5. Due to a naturally-occurring alpha ingrowth that occurs in air particulate samples, variations in concentrations were observed. As the time between sample collection and sample analysis increased, so to did the ingrowth of alpha resulting in higher sample activity. Inconsistent or late sample deliveries to the analytical laboratory promoted these variations of concentrations. Actual concentrations (whether positive, negative or zero) were used to calculate weekly averages because approximately 30% (40 of 136) of the weekly results were below the MDC. Using actual concentrations eliminates biases in the data and missing data points on graphs. As depicted in Figure 5, average weekly gross alpha concentrations at indicator and control stations n:mained relatively constant tlnuughout the monitoring period. Generally, the trends of average gross alpha concentrations at indicator and control sites were similar. The average results are listed in Table 5. I The data obtained in 1997 indicated that gross alpha radioactivity levels did not change as a result of the SNEC facility. In addition, the gross alpha raficactivity measured on I the paniculate filters was caused by naturally-occurring radionuclides. l l Gamma-emitting radionuclides related to the SNEC facility were not detected on any of ) the quarterly composites that were analyzed in 1997. As expected, all of the quarterly composite samples contained naturally-occurring beryllium-7 (Be-7). Concentrations j detected on indicator samples were similar to those detected on control filters. Also, naturally-occurring K-40 was detected on some of the indicator and control samples. The semiannual composites from the first half of 1997 analyzed for Sr-90 and elemental actinides yielded no activities above the MDC. Page 27
1997 RADIOLOGICAL ENVIRONMENTAL MONIK) RING REPORT TABLE 4 1997 Average Gross Beta Concentrations in Airborne Particulate I (pCi/m') Station Description Averare + 2 std dev* Al-1 (I) Nonh Sector 0.0173 0.0088 D 1 4 (I) East Sector 0.0196 0.0086 Ji-1 (I) South Sector 0.0188 0.0066 G10-1 (C) New Granada 0.0186 0.0056
- Averages and standard deviations are based on concentrations > MDC (I) = Indicator Station (C) = Control Station TABLE 5 1997 Average Gross Alpha Concentrations in Airborne Particulate (pCi/m')
Station Description Averare + 2 std dev* Al-1 (I) Nonh Sector 0.0012 0.0011 Dl-4 (I) East Sector 0.0014 0.0012 J1-1 (I) South Sector 0.0012 0.0009 G10-1 (C) New Granada 0.0011 i 0.0010
- Averages and standard deviations are based on concentrations > MDC (I) = Indicator Station (C) = Control Station Page 28
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1997 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT GROUNDWATER MONITORING An investigation was performed to determine the depth to the bedrock surface and the orientation of the bedrock groundwater flow pathways (Ref.14). The site is immediately underlain by a fill-layer composed of flyash, cinders and/or silt and sand-size sediment. This fill-layer is underlain by a layer of boulders in a silty clay matrix. The surface of the bedrock lies beneath this boulder layer at a depth between approximately 7.5 to 18 feet. l The results of this investigation indicate the overburden groundwater occurs at a depth ranging from approximately 4 to 16 feet. Groundwater elevation contour maps of this data indicate that the groundwater within the overburden soil flows west toward the Raystown Branch of the Juniata River. Groundwater movement within the bedrock beneath the site is predominately controlled by fractures in the bedrock. There are two major fracture patterns; one trended northeast-southwest, the second fracture pattern trended ! northwest-southwest (Ref.15). Groundwater also moves within the spaces (bedding planes) between the individual layers of the siltstone bedrock at Saxton. 1 Page 31
1997 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT in 1994, eight overburden groundwater wells were restored. Four are hydraulically downgradient of the containment vessel (GEO-3, GEO-6, GEO-7, GEO-8). Additionally, four wells (GEO-1, GEO-2, GEO-4, GEO-5) serve as background monitoring points, since these wells are located hydraulically upgradient of the containment vessel. In addition two bedrock wells (MW-1 and MW-2) were also monitored. As part of the analysis performed by the contracted hydrogeologic consultants (GEO Engineering), it was determined that bedrock monitoring wells should be installed at an angle in order to maximize the interception of fractures and bedding planes. The boreholes were drilled into bedrock at an angle of approximately 25 degrees from vertical to accomplish this. Filling the annular space with a sand filter pack, a bentonite pellet seal and cement grout allows these wells to monitor only the significant fractures and bedding planes of the bedrock ground water. In addition, two oft-site (potable water) well samples were collected. One was from the Pennelec Line Department garage located adjacent to the site and the other was from a resident in the borough of Saxton. Likewise, these samples did not detect any radioactive contaminates. Groundwater Results Locations of the onsite groundwater stations sampled in 1997 are shown in Figure 3. The results from the analyses performed on these r i . ~ 4 no radioactive contamination from plant-related radionuri; < .ncluu. c Strontw ' 90. Of the 48 groundwater samples collected, only one ar i iEO-b mntai 1 H-3 above ambient concentrations (the acdvity was 180 pCil ). 'r ' analysis muires a minimum sensitivity of 200 pCi/L and Sr-90 requi :s .' e JL Required sensitivities for Co-60, Cs-134 and Cs-137 (gamma emitting rat o 1 e 15 pCi/L. , l The first sample obtained from GEO-5 was u 'nd analyzed July of 1994. A "Less Than" result for tritium was reported. Gamma a dyr i performed on this sample yielded "Less Than" activities. Since that time, all the ord ; ring wells continued to yield "Less Than" activities for tritium except for GEO-5. he October 1994 sample reported 560 pCi/L tritium. A special collection was performed two weeks later to confirm the positive tritium and a result of 310 pCi/L was obtained. Gamma analysis continued to show no reportable activity. The following quarterly and special collections yielded some positive and some "Less Than" Stium activities. Table 6 is a list of all tritium results that have been performed since the start of GEO-5 monitoring. 1 Page 32
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Upon review of these results, it appears that the activity can be attributed to pockets of ) tritiated water trapped in fractures leading to the overburden groundwater. GEO-5 is located in the vicinity of the former Radwaste Facility Building, which has been demolished. In order to assess the possibility of other contaminates, GPU Nuclear has contracted Haley & Aldrich, Inc. (formally GEO Engineering) to add supplemental monitoring wells in this location. Two wells will be drilled into the bedrock and one will provide an additional overburden groundwater monitoring point. All three wells will be drilled in May of this year and monitoring to begin shortly thereafter. 1 Page 33
a 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT 1DABLE 6 l SX-GW-G EO-5 TRITIUM RESULTS (pCi/L) DATE RESULTS 7/13/94 L.T. 170 10/06/94 560 i 130 10/27/94 310 i 120 1/12/95 L.T. 190 4/05/95 L.T. 180 ! 5/30/95 270 i 120 6/13/95 370 i 130 7/13/95 370 1 110 8/17/95 390 1 130 9/15/95 410 1 130 10/18/95 760 1 140 11/17/95 L.T. 200 1/25/96 L.T. 190 4/03/96 L.T. 150 7/10/96 L.T. 140 10/03/96 L.T. 140 1/08/97 L.T. 140 4/16/97 L.T. 150 7/09/97 L.T. 150 10/01/97 180 1 100 1/08/98 L.T. 150 I%ge 34
- _ ~
1997 RADIOLOGICAL ENVIRONMENTAL MONlwRING REEDRT BROAD LEAF VEGETATION i MONITORING l Radionuclides released into the atmosphere may deposit on l l vegetation. To assess the deposition, broad leaf vegetation were collected and analyzed for gamma-emitting isotopes. Collection occurred during the growing season from two different sectors on site where the prevailing wind direction l has been determined. Naturally-occurring Be-7 and K-40 l were measured in all samples. No radionuclides l attributable to SNEC operations were detected above the l MDC l l l Page 35
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT SURFACE WATER ' MONITORING The Juniata River surface water was monitored for radionuclides of potential SNEC origin. Two grab samples, one control and one indicator, were collected on a quarterly basis and analyzed for , gamma emitting radionuclides and tritium. The indicator sample was collected at the discharge bulkhead leading into the river, while the control
~
sample was collected upstream of the discharge. No tritium or radionuclides attributed to SNEC operations were detected above the MDC. Page 36
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT AQUATIC SEDIMENT MONITORING Sediment samples from storm drains that are located on site are collected on a quarterly basis (Stations Al-1 and C1-6). In addition, a sediment sample taken directly from the Juniata River at the discharge bulkhead (Al-4), as well as, a control sediment sample (Q1-2) taken up river from the discharge were also collected. The sediment is dried and then analyzed for gamma emitting
- radioisotopes.
Low concentrations of cesium-137 (Cs-137) were detected in both river sediments. These concentrations were attributed to fallout from prior nuclear weapon tests. l SNEC-related cobalt-60 (Co-60) was detected in one sample from on site station Al-1 at a level of l 0.04 0.02 pCi/g dried. Cesium-137 (Cs-137) ! was detected in all the sediments collected on site. l The average activity was 1.5 pCi/g dried. Co-60 ) and Cs-137 are readily adsorbed by suspended particles and are concentrated in the storm drains. l Sediment results are listed in Table 7. I l l Page 37 4
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE 7 Quarterly Results of Sediment Analysis Activity i 2 a pCi/g dried Mrst Qtr Second Qtr Tided Qtr Fourth Qtr 01/08/97 04/16/97 07/09/97 10/01/97 Cs-137 Al-10) 1.6 i 0.2 1.8 i 0.2 1.5 i 0.2 1.5 i 0.1 Cl-6(I) 1.6 i 0.02 1.6 i 0.2 0.92 i 0.09 1.4 i 0.1 Al-4(I) 0.13 0.03 0.068 i 0.022 < 0.02 0.092 i 0.029 Q1-2(C) < 0.0^ 0.038 i 0.012 0.044 i 0.014 0.056 0.029 Cs-134 Al 10) < 0.04 < 0.02 < 0.02 < 0.03 Cl-6(I) < 0.02 < 0.02 < 0.04 < 0.03 Al-4(I) < 0.019 < 0.015 < 0.017 < 0.03 Ql-2(C) < 0.03 < 0.011 < 0.011 < 0.03 Co-60 Al-1(I) < 0.05 < 0.03 < 0.03 0.041 i 0.023 Cl4(1) < 0.03 < 0.03 < 0.05 < 0.03 A1-4(I) < 0.02 < 0.02 < 0.02 < 0.03 Q1-2(C) < 0.03 < 0.013 < 0.014 < 0.04 (I) = Indicator Station (C) = Control Station Page 38
1997 RAI)lOLOGICAL ENVIRONMENTAL MONITORING REPORT REFERENCES (1) Saxton Nuclear Experimental Corporation, Offsite Dose Calculation 4 Manual. # (2) United States Environmental Protection Agency, Primary Drinking Water Standard. (3) National Council on Radiation Protection and Measurements. Report No.
- 22. " Maximum Permissible Body Burdens and Maximum Permissible Concentrations of Radionuclides in Air and Water for Occupational Exposure." (Published as National Bureau of Standards Handbook 69, Issued June 1959, superseding Handbook 52).
(4) National Council on Radiation Protection and Measurements. Report No.
- 93. " Ionizing Radiation Exposure of the Population of the United States."
1987. 1 (5) CRC Handbook. "Radioecology: Nuclear Energy and the Environment." F. Ward Whicker and Vincent Schultz, Volume I,1982. 1 (6) Saxton Nuclear Experimental Corporation, " Reactor Support Demolition Report." May 1993. (7) 1990 Census Information provided by The Pennsylvania State Data Center. (8) United States Nuclear Regulatory Commission Branch Technical Position.
"An Acceptable Radiological Environmental Monitoring Program."
Revision 1, November 1979. (9) United States Nuclear Regulatory Commission. Regulatory Guide 4.15.
" Quality Assurance for Radiological Monitoring Programs (Normal Operations)- Efiluent Streams and the Envienment." Revision 1, February 1979.
Page 39
1 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT i (10) American National Standards Institute, Inc. " Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry." ANSI N54'-1975. (11) United States Nuclear Regulatory Commission. Regulatory Guide 4.13.
" Performance, Testing and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications." Revision 1, July 1977.
1 (12) United States Nuclear Regulatory Commission 10 CFR 20 Section 20.105(a).
]
(13) United States Nuclear Regulatory Commission 40 CFR 190 Regulatory Guide 1.109. (14) GEO Engineering " Phase I Report of Findings - Groundwater Investigation." November 18, 1992. (15) GEO Engineering " Summary of Field Work." June 7,1994. 1 Page 40 I _
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING RELY)RT APPENDIX A 1997 REMP Sampling Locations and Descriptions, Synopsis of REMP, l and Exceptions in Sampling and Analysis ) l Page Al
1997 RAI)l0 LOGICAL ENVIRONMENTAL MONITORING REFY)RT TABLE A-I Saxten Nuclear Experimental Corporation Facility Radiological Envimnmental Monitoring Pmgram Description Station Sample Code Medium Description Hole Al-1 Sediment Drain outfall outside Water rarely present perimeter fence Al-2 Air Particulate Westinghouse Yard Area Al-2 Water Containment Vessel Sump (Radiological) Al-4 Surface Water Juniata River at the Sediment Westinghouse Weir bulkhead Al-5 TLD N sector, perimeter fence B1-4 Surface Water Drop weir in the Westinghouse Sediment Yard Area B1-6 TLD NNE sector, perimeter fence Cl-6 Sediment Drain outfall, NE corner of Water rarely present perimeter fence Cl-9 TLD NE sector, perimeter fence C2-1 TLD Weaver Ridge,0.8 mile from CV Dl-1 Air Paniculate Open Field ENE sector D1-4 TLD ENE sector, perimeter fence D2-1 TLD Weaver Bridge 1.3 miles from CV Page A2
a 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1(Cont'd) SNEC Radiological Envimnmental Monitoring Pmgram Description Stction Sample Code Medium Description Epic El-1 Potable Penelec Line Shack Water El-7 TLD E sector, perimeter fence El-17 TLD Penelec Lirie Shack E2-1 TLD E sector,0.25 mile from CV E3-1 TLD 3 miles East of CV in State Gameland #67 F1-2 TLD ESE sector, perimeter fence G1-1 TLD SE sector, private residence Potable in Saxton Water GI-2 TLD SE sector, perimeter fence GI-6 Water Containment Vessel Pipe Tunnel (Radiological) G2-1 TLD SE sector, closest private residence G10-1 Air Particulate Reichley Micmwave Tower Offsite Contml Station G10-2 TLD New Granada Offsite Contml Stz ivn H1-5 TLD SSE sector, perimeter fence H2-1 TLD 'Ibssey Mt. High School l l Page A3 l
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE A-1 (Cont'd) SNEC Radiological Environmental Monitoring Program Description Station Sample Cgic Medium Description N_olg H10-1 TLD Wells Tannery Offsite Contml Station J1-1 TLD Penelec Fence 100 feet fmm SE comer of West garage Ji-3 Air Particulate Penelec An:a S sector Kl-5 TLD Saxton Bomugh Hall Ki-8 TLD SSW sector, perimeter fence L1-1 TLD SW sector, perimeter fence L2-1 TLD SW sector, Stonerstown, I mile Fmm CV M1-6 TLD WSW sector, perimeter fence N1-4 TLD W sector, perimeter fence P1-1 TLD WNW sector, perimeter fence Ql-2 Smface Water Old Station Discharge Upstmam, contml Sediment Ql-3 TLD NW sector, perimeter fence Rl-1 TLD NNW sector, perimeter fence I l Page A4 l 1
l 1997 RADIOLOGICAL ENVIRONMEl!TAL MONITORING REl%)RT l l l TABLE A-1 (Cont'd) SNEC Radiological Envi unmental Monitoring Program Description Station Sample Code Medium Description Nolg l Geo1 Gmundwater Monitoring well South of CV fenced area Geo 2 Groundwater Monitoring well West of CV fenced area Geo 3 Groundwater Monitoring well West of CV fenced area l Geo 4 Gmundwater Monitoring well East of CV l fenced area ' Geo 5 Groundwater Monitoring well East of CV fenced area Geo 6 Groundwater Mcnitoring well North of CV fenced area Geo 7 Gmundwater Monitoring well East of CV l fenced area Geo 8 Groundwater Monitoring well North of CV fenced area Geo 9 Gmundwater Piezometerinside of CV Fenced Area MW1 Groundwater Northeast to Northwest diagonal well MW2 Grouix! water Northwest to Southwest diagonal well l Page A5
l 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIDRT TABLE A-2 Synopsis of the Radiological Environmental Monitoring Program Conducted by GPUN Environmental Re. bioactivity Laboratory for Saxton Nuclear Experimental Corporation Facilhy Number of Nanber of Number of l Sample Sampling Collection (s) Samples Type of Analysb Samples har_ taations Frwsency Conected Analy:n Frwmey Analyzed
- Air Particulate 4 WeeUy 156 Gr-Beta Weeuy/ Biweekly 156 Biweekly Or- Alpha Weekly / Biweekly 156 Gamma Quanerly 16 Aquatic Sediment 4 Quarterly 16 Gamma Quartc.rly 16 l
, Broad I m f 2 Annually 2 Gamma Annually 2 I Vegetation Groundwater 10 Quarterly 40 H-3 Quarterly 40 Osmma Quarterly 49 Sr-90 Quanerly 8 Potable Water 2 Quarterly 8 H-3 Quartedy 8 Gamma Quarterly 8 Or-Beta Quarterly 8 Dosimeters 28 Quarterly 112 Inunersion Quarterly 112* (TLD)
- Dose Surface Water 2 Quarterly 8 Gamma Quarterly 8 H-3 Quarterly 8 l
l NOTES: (1) nin table represents results from the primary (base) program. It does not include quality control (QC) resuhs. (2) The total number of analyses does not include duplicate analyses, recounts, or reanalyses. (3) For the purposes of this table a dosimeter is consid'ied to be a phosphor (elensnt). (4) he to'al number of samples or elements (TLDs) used for data analysis. (5) Biweekly means once every two weeks. i l Page A6 i 1
1997 R,1D10 LOGICAL ENVIRONMENTAL MONITORING BEFORT l TABLE A-3 Sampling and Analysis Exceptions 1997* Period of Deviation Description of Deviation and Corrutive Action January 8,1997 No sample obtained fmm SX-GW-GEO-4. The feed air supply tube leading into the geomon split due to the fmezmg weather. July 9,1997 I.ow well water volume in station SX-GW-GEO-2 (50 ml) due to dry weather conditions. Only a tritium analysis was performed. July 9,1997 Low well water volume in station SX-GW-GEO-7 (50 ml) due to dry weather conditions. Only a tritium analysis was performed. October 9,1997 to Air Sample Station SX-AP-Al-2 had a mechanical malfunction in tie November 6,1997 pump. Technicians worked on the unit but could not immediately remedy the pmblem. The unit remained off while new parts were acquired. Interruptions in sampling occurmd over four consecutive sampling periods because of this pmblem. December 24,1997 to Air Sample Station SX-AP-DI-1 had a mechanical malfunction in the December 31,1997 pump. No sample was obtained The exceptions described in this table are those that are considered deviations from radiological environmental monitoring as required by the ODCM. Other sampling and analysis deviations occurred during the year. They were not included in this table because the minimum number of samples were collected and analyzed. Reports describing all sampling and analysis exceptions are on file at GPUN Envimnmental Radioactivity I2boratory. Fare A7
I997 RAI)l0 LOGICAL ENt1RONMENTAL MONITORING REIY)RT i APPENDIX B 1997 Lower Limit of Detection (LLD) Exceptions Page Bl
_ t s n e m d m e ) o r 4 D i C u q e e g r e a T ht P ( R
)
l t 1 E e - R 7 9 e) D G N t 9 e1 e mD e I R Mgn oL l b O i t L a T oru d ( T I N t dD e n n o l O e i M iD l s D f ai t i aL ed L c d L A F L l pl eL t a e n T B h t u N iec d mieah ht e o E E L h r i S aft s D f M N B Wu q f h e c e t l t f u o i s O R A T hR s e oiM
.h s s NoWo t t I
V u ei i sP t r m m N E rem E l aL i i l L l aR D c n A c it r o C I i t C L y e i G yE L l w t c l a O L aN n d e n o e A Se aL t O i r e I D h u o d A t a e n e R 7 R e ht 9 r 9 l e f o s w t i s y e r i l s l a e A n h A T i a d e M l e p m a S_ 11
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT i APPENDIX C 1997 REMP Changes I l l l Page Cl M
l 1997 RADIOLOGICAL ENVIRONMENTAL MONI[0 RING REPORT TABLE C 1997 REMP Changes January,1997 Several changes were made to the environmental TLD program. In the past, 27 TLD stations were arranged in roughly concentric rings around the site. A few of these stations were in close proximity to the Containment Vessel (CV) building. With the decommissioning project work being performed, it was decided that these TLD stations should be monitored on a more frequent basis. Presently, 27 stations located near the CV and in the workers trailers, are being collected and analyzed by radiological controls on a monthly schedule. Environmental assessment occurs along the outer perimeter fenceline and beyond by collecting and analyzing 28 stations on a quarterly basis. One Indicator TLD Station is positioned along the perimeter fence in each of the 16 compass sectors. One station remains in the Penelec Line Department garage and nine Offsite Indicator Stations are in various sectors within 2 miles of the site. Two Control Stations, each about 10 miles from the site, are also included. These enhancements improve environmental exposure assessment during the Decommissioning project. July,1997 Vegetation, a new sample medium to the program, is being collected during the growing season at the site boundary. The samples are collected annually in the two highest prevailing wind sectors and analyzed for gamma. This sampling is done in lieu of performing a land use census. Page C2
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT APPENDIX D 1997 Action Levels l Page D1 1
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REIT)RT l Analytical results of environmental samples were routinely reviewed and evaluated by the l GPU Nuclear Envimamental Radioactivity Laboratory staff. The results were checked for LLD violations, anomalous values, USNRC reporting levels, main sample and quality control (QC) sample agreemeat (Appendix E), and action levels. ! 1 Established by GPU Nuclear, the action level is defined as that level of reactor-related radioactivity which when detected in environmental samples initiates an investigation and subsequent actions, as necessary. An action level is reached if either of the following two ! criteria is met: j i E The radioactivity concentration at an indicator station reaches or exceeds those j concentrations listed in Table D-1. ) E The radioactivity concentration at the indicator station reaches or exceeds 10 ' times the mean concentration for the control locations. (This criteria applies only to those media and analyses which are not listed in Table D-1.) Action levels for gamma exposure rates measured by TLDs have also been established. For TLDs, an action level is reached if any of the following three criteria is met: E The exposure rate at an indicator station not on the owner controlled area fence exceeds three times the mean of the control stations. m The exposure rate at an indicator station on the owner controlled area fence exceeds 135 mR/std month (50% of the 40 CFR 190 limit of 25 mR/yr adjusted by a 67 hour recreational factor). 5 The exposure rate at an indicator station not on the owner controlled area fence exceeds either two times the previous quarterly result or two times the historical average for the station. If an action level is reached, an investigation is initiated which consists of some or all of the following actions: E Examine the collection sheets for an indication of any equipment malfunctions, collection or delivery errors " E Examine the running tables (prior data) for trends. E Review control station data. l l 1 Page D2
I997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT E Review QC or duplicate sample data (if available). W Recount and/or reanalyze the sample. E Collect and analyze an additional sample. The results of the investigation are then documented. As appropriate, site personnel are apprised of plant-related radioactivity which exceeds the GPU Nuclear action level. If it is concluded that the detected activity is related to SNEC operations and also exceeds the USNRC reporting limits as defined in the ODCM, a detailed report will be issued to the USNRC. During 1997, there were no sample results that equaled or exceeded action level violations. l l l l Page D3
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE D-1 SNEC REMP Analytical Required Sensitivities (LLD) and Reporting Levels i Exposure /Pattways and/or Sample (J Dji.t3 Analysis Reauired LLD Reportine level Air Particulate pCi/m3 Gr Alpha 1.5E-3 1.0E-1 (AP) Gr Beta 1.0E-2 1.0E0 Cs-134 5.0E-2 1.0El Cs-137 6.0E-2 2.0El Sr-90 1.0E-2 1.0E-1 Sediment / Soil pCi/G (dry) Cs-134 1.5E-1 1.0E0 (SD/S) Cs-137 1.8E-1 5.0E0 Sr-90 5.0E-2 5.0E-1 Water pCi/L Gr Alpha 5.0E0 1.0E2 (SW/GW) Gr Beta 4.0E0 5.0El Tritium 2.0E3 2.0E4 Co-6G 1.5El 3.0E2 Cs-134 1.5El 3.0El Cs-137 1.8El 5.0El Sr-90 2.0E0 8.0E0 Vegetation pCi/g (wet) Cs-134 2.0E-2 1.0E0 (BR) Cs-137 7.0E-2 2.0E0 Sr-90 1.0E-1 1.0E-1 Page D4 l
1997 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT l l APPENDIX E : l l l 1997 Quality Control Program l l l l t Page El
I 1997 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT A quality assurance (QA) program is an essential part of any radiological environmental monitoring program (REMP). It provides reasonable assurance that the results of radiation measurements are valid. To be effective, elements of quality assurance must be evident in all phases of the monitoring program. These include, but are not limited to, I sample collection, preservation and shipment, receipt of samples by the analysis laboratory, preparation and analysis of samples and data review and reporting. An I effective QA program will allow for the identification of deficiencies in all monitoring processes so that appmpriate investigative and corrective actions can be implemented. The USNRC published Regulatory Guide 4.15, " Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams and the Environment", which defmes an acceptable QA program (Ref. 9). The guidance contained in Regulatory Guide 4.15 has been adopted by GPU Nuclear. To meet the objectives of this position document, procedures and plans have been written and implemented. In the laboratory, samples are typically analyzed one time. Therefore, laboratory personnel must be reasonably confident with the analytical results which are genemted. One means of achieving confidence in the results is through the analysis of quality control (QC) samples. Three types of QC samples are routinely analyzed by the labomtories as part of the GPU Nucle r Three Mile Island Environmental Affairs REMP QA Program. They include intralaboratory split samples, cross-check program samples, and interlaboratory split samples. A discussion of each QC sample type is pmvided below. Intralaboratory Solit Samples Each laboratory is required to split at a minimum every twentieth sample and perform an analysis (or analyses) on each portion. The samples which can not be split (e.g., air particulate filters) are counted twice. The results of the two analyses are then checked by staff scientists for agreement using the criteria defined in procedure 6510-SUR-4523.03. Agreement is considered acceptable if the coefficient of variation for the two values is eighty-five percent or less. Not agreement of the sample concentrations may result in recounting or reanalyzing the sample (s) in question. During 1996, all of the pairrd intralabomtory split sample results were found to agree. Cross-check Program Samoles Each laboratory analyzing environmental samples for GPU Nuclear participates in at least two separate cross-check programs. USDOE, USEPA, and Analytics supply either Page E2 l 1
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT water, air paniculates, vegetation and soil samples. All samples are sent to the laboratories as unknowns. Panicipation in these programs provides an independent check on the ability of each laboratory to perform analyses on various kinds of samples containing detectable concentrations of radioactivity. The results submitted by the laboratories are compared to:
- 1) limits established by the USEPA, or 2) agreement criteria used by the NRC in their Configuratory Measurement Inspection Program. If the results are outside the established limits or agreement criteria, the laboratories are requested to perform an investigation and take corrective action as necessary.
The 1997 cross-check progam results from each laboratory are listed in Appendix F. Explanations are provided for those results which were not submitted and/or which were not within the established limits. Ir.1erlaboratory Solit Samoles The third type of QC sample is the interlaboratory split sample. These samples are the ones which are collected routinely for the REMP. After or during the collection process, the sample is thoroughly mixed (as necessary) to ensure that, as much as possible, the distribution of radioactivity in the sample is homogeneous. The sample is then split into two portions. One portion is sent to the primary (main) lab and the other portion is sent to the QC laboratory. Analysis results from the QC laboratory are then compared to those from the primary laboratory. The agreement criteria is the same as that used for the intralaboratory split samples. Corrective action for disagreements may include recounting or reanalyzing the sample (s). There were no interlaboratory nonagreement during the entire year. 1 Page E3
1997 RADIOLOGICAL ENVIRONMENTAL MONIMRING REPORT APPENDIX F 1997 Cross-Check Program Results Page FI
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE F-1 1997 USEPA Cross Check Program Results EPA Control GPUN-ERL TBE Collection Limits Results Results Date Media Nuclide (A) (B) (B) 01/17/97 Water Sr49 12.0
- 8.7 19.67
- 2.52 10.00
- 1.00 Sr-90 25.0
- 8.7 22.33 2.52 25.00
- 1.00 01/31/97 Water Alpha 5.2
- 8.7 5.57
- 1.56 8.10
- 0.89 Beta 14.7
- 8.7 18.33
- 3.21 15.00
- 1.00 02/07/97 Water 1131 86.0
- 15.6 92.33
- 5.51 106.00
- 4.36 (C) (E) 86.0
- 15.6 91.67
- 2.08 (D) 03/07/97 Water H-3 7900.0
- 1370.6 7933.33
- 57.74 7366.67
- 378.59 04/15/97 Water Alpha 48.0
- 20.8 30.00
- 1.00 54.67
- 1.53 Beta 102.1
- 26.5 83.00
- 1.73 103.33 5.77 Co-60 21.0 8.7 24.00
- 1.00 22.67 i 0.58 Sr49 24.0
- 8.7 26.00
- 1.00 23.00 1.00 Sr-90 13.0
- 8.7 10.00
- 0.00 12.67
- 1.15 Cs-134 31.0
- 8.7 31.00 1.00 28.67 0.58 Cs 137 22.0 8.7 24.67
- 0.58 24.67 1.53 06/06/97 Water Co-60 18.0
- 8.7 18.67 0.58 19.00
- 0.00 Zn-65 100.0
- 17.3 106.67
- 5.77 99.33
- 1.15 Ba-133 25.0
- 8.7 25.00
- 0.00 22.33
- 2.52 Cs-134 22.0
- 8.7 20.33
- 1.53 18.67
- 1.15 Cs-137 49.0
- 8.7 52.33
- 2.08 48.67
- 0.58 07/11/97 Water Sr49 44.0
- 8.7 39.67
- 0.58 38.33
- 1.53 Sr 90 16.0
- 8.7 16.67
- 1.53 25.00
- 0.00 (F) 07/18/97 Water Alpha 3.1
- 8.7 4.47
- 1.27 2.93 i 0.25 Beta 15.1
- 8.7 15.00
- 2.00 14.00
- 1.00 08/08/97 Water H-3 11010
- 1910.2 11333.33
- 577.35 12000.00
- 0.00 09/19/97 Water I-131 10.0
- 10.4 9.00
- 1.00 11.00
- 0.00 (C) 10.0
- 10.4 10.87
- 2.20 l (D) 10/21/97 Water Alpha 49.9
- 21.7 49.33
- 0.58 45.67
- 1.15 Beta 143.4
- 37.3 140.00
- 0.00 136.67
- 5.77 Co-60 10.0
- 8.7 12.00
- 2.65 10.67
- 0.58 Sr49 36.0
- 8.7 42.33
- 2.52 36.00
- 1.00 Sr-90 22.0
- 8.7 24.33
- 2.31 21.67
- 2.08 Cs-134 41.0
- 8.7 40.67
- 0.58 41.33 + 0.58 Cs-137 34.0
- 8.7 36.33
- 0.58 36.00
- 1.00 PageF2 ,
I l
r 1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT TABLE F-1 1997 USEPA Cross Check Program Results EPA Control GPUN-ERL TBE Collection Limits Results Results Date Media Nuclide (A) (B) (B) 10/31/97 Water Alpha 14.7
- 8.7 14.33
- 3.21 19.67
- 1.53 Beta 48.9 x 8.7 47.67
- 7.23 50.67
- 3.51 i
l1/7/97 Water Co-60 27.0
- 8.7 30.00 i 1.00 25.00
- 1.00 I Zn45 75.0 13.9 80.33
- 6.66 71.00
- 3.61 Ba-133 99.0
- 17.3 99.67
- 0.58 78.67 0.58 )
(G) Cs-134 10.0
- 8.7 10.67
- 1.53 10.67 0.58 Cs-137 74.0
- 8.7 78.33
- 3.21 76.00
- 1.00 A. The EPA Control Limit is the known concentration i 3 sigma for three determinations. The units are pCi/L.
B. The GPUN-ERL and TBE results are the average of three determinations
- one standard deviation. The units are pCi/L.
C. The analysis was performed by first concentrating 1-131 on a resin. He resin was then counted by gamma spectroscopy. l D. The analysis was performed by gamma spectroscopy. The I 131 in the sample was not concentrated prior to i counting. l l E. An erroneously high reading of the stable iodine content by ion specific electrode occurred. This caused an erroneously low chemical yield. If the electrode reading is ignered, the average I-131 result becomes 90 pCi/L, which is in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. The laboratory will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample witt.out the addition ofiodide carrier. The I-131 content of active samples also may be verified by performing a gamma spectral analysis. F. An error was apparently caused by insufficient training. A summer employee petformed the strontium separation chemisty on 7/22/97. Initial results for the three samples did not agree well, so all were re-milked by a senior analyst. This was insufficient to correct the problem. In-house QC samples showed c. satisfactory results at this time. There will be additional quahfication of analysts according to performance ofin-louse blanks and spikes. G. An investigation is being conducted. The results will be available shortly. Critcria are listed in EPA 600/4-81-004. l l i l i Page F3
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1997 RADIOLOGICAL ENVIRON %fENTAL .110NITORING REPORT TABLE F-4 1997 ANALYTICS Environmental Cross Check Program Results ANAIXTICS TBE Collection Value Result Rauo Date Media Nuclide tA> (B) (C) 3/20/97 Milk 1-131 20 2 1 18 m 1 0.90 Cc-141 232 = 12 LT.1. (D) Cr 51 387 2 19 381 2 38 0.98 Cs 134 143 2 7 132 m 13 0.92 Cs-137 114 2 6 128 x 13 1.12 Co-58 79 x 4 89 z 9 1.13 Mn-54 176 = 9 195 = 20 1.11 Fe-59 144 z 161 = 16 1.12 Zn 65 165 S 171 = 17 1.04 Co-60 176 2 9 179 z 18 1.02 3/20r95 Milk St-89 25 z 1 13 2 3 0.52 (E) St-90 19 m 1 16 2 1 0.84 6/19/97 Filter Cc-141 132 * 143 m 8 1.08 Cr-51 198 2 10 229 m 17 1.16 Cs-134 81 = 4 74 2 4 0.91 Cs-137 115 6 143 m 8 1.24 Co-58 77 2 4 89 m 5 1.16 Mn-54 84 2 4 102 2 6 1.21 Fe-59 75 2 4 98 2 6 1.31 Zn 65 139
- I88 = 11 1.35 (F)
Co-60 104
- 5 113 x 7 1.09 6/19/97 Cartndge I-131 88 2 4 106 x 6 1.20 6/19/97 Filter Sr-90 96 m 5 88 2 5 0.92 6/19/97 Filter Alpha 93 z 5 103 m 6 1.11 Beta 193
- 10 210 2 6 1.09 9/18/97 Milk I-131 87 2 4 97 10 1.11 Cc 141 77 4 83 m 8 1.08 Cr 51 304 z 15 323 m 40 1.06 Cs-134 102
- 5 98 x 10 0.96 Cs 117 107 5 117 12 1.09 Co-58 60 z 3 6i 2 6 1.07 Mn-54 88 2 4 99
- 10 1.13 Fe-59 119
- 6 132 2 13 1.11 Zn 65 1% 2 10 218
- 22 1.11 Co-60 197 m 10 209 z 21 1.06 1
9/18/97 Milk Sr-89 15 1 14 2 1 0.93 Sr-90 14 2 1 18 1 1.29 Page F10
N97 RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Notes: A. De Anantics Value is the known concentranon and its associated three sigma uncenatory. The unns are pCUI for milk. pCieg (dry) for soil and tota pCi for filters and canndges. B. The TBE Result is the sample concentration of one determmahon and its two sigma counting uncertamtv. If the two sigma counting uncenamtv is less than 10% of the samale concentrabon, then a 10% counung uncertainty is reportM. ne uruts are pCi/L for nulk. pCPg (dry) for soil snd total pCi for fdiers and cartridges. C. The ratio is the TBE result divided by the Anahtics value. D. ne Ce 141 result was reported mcorrectly. The correct result (232123 oCs L) agreed well with the Analvtics value. E. ne non-agreement was caused bv mcorrect nasing of the stronnum extracuoc column. Addtuonal trauung was conducted. Subsequent tests on two nutk sampics spiked wrth Sr-87 produced acceptable results. F. No correcuve action was requested because the In45 result was just outside the acceptable range and pnar and subsequent In45 results were acceptable. To determme aareement:
- 1. Divide each Analyucs vthe by its associated one sigma uncenamty to obtain the resolubon.
- 2. Divide each TBE value by the corresponding Analytics value to obtain the rauo
- 3. De TBE toensurement is in agreement if the value of the raue falls within the lumts sh(wn in the following table for the corresponding resolution Agreement Agreement Resoluuan " A" Cntena "B" Cntens (3 no companson no companson 2 3 and < 4 0.3-30 no companson 2 4 and < 8 0.4 - 2.5 0.3-30 2 8 and < 16 0.5 - 2.0 04 ".5 216 and < 51 060 1.67 0.5 - 2.0 2 51 and < 200 0.75 -1.33 0.60-1 67 2 200- 0.80 -1.25 075 1.33 "A" cnteria are apphed to the followmg analyses:
- 1. Gamma Spectror,etry where the pnncipal gamma energy used for identificauon is greater than 250 kev,
- 2. Tnuum %3) and
- 3. low-level l 13I "B" cntens are applied to the followmg analyses:
- 1. Garnma Spectrometry where the pnncipal gamma energy used for identificauan is leu than 250 kev,
- 2. St " and Sr-90 and
- 3. Gross Alpha and Beta Cntena are simdar to those bsted in USNRC Inspection Procedure 84750. Minor adjusunents were made because some analyses (e4 Sr-90 and Gross Alpha) typically yield acuvuv concentraboos wnh large uncertainties.
Page F11
1997 RADIOLOdlCAL ENVIRONMENTAL MONITORING REPORT l APPENDIX G Data Reporting and Analysis Page GI
1997 RADIOLOGICAL ENVIRONMENTAL MONITORING REFORT Environmental samples frequently contain very little, if any, radioactivity. Even when very sensitive, state-of-the-art counting equipment is used, many of the sample count mtes can not be differentiated from the background count rate or the count rate of the blank sample. When this occurs, the sample is said to have a mdioactivity level or concentration at or below the sensitivity of the analysis method. In this case, the analysis result is reponed as less than a numerical value, which corresponds to the sensitivity of the analysis method. Sensitivities are influenced by parameters such as sample volume, background or blank sample count rate and efficiency of the counting device. The terms used to describe the sensitivity are the lower limit of detection (LLD) and minimum detectable concentration (MDC). For this report, these two terms are considered to be synonymous. They are defined as: LLD (MDC) = 4.66 Sb E
- V
- 2.22
- Y
- exp (- I -t) where:
Sb = the standard deviation of the background counting rate or the counting rate of a blank sample, as counts per minute, E = the counting efficiency of the equipment, es counts per disintegration, V = the volume or mass of the sample, such as L, g or m', 2.22 = the number of disintegrations per minute per picocurie, Y = the chemical yield, if applicable, I = the radioactive decay constant for the panicular radionuclides and
-t = the elapsed time between sample collection (or end of sample collection period) and counting.
The applicable LLD or MDC for each radionuclides and analysis is listed in Table D-1. A large percentage of the 1997 sample results were reponed as less than the LLD or MDC. Results which were reponed as less than the LLD or MDC were not included in the calculations of averages, standard deviations and anges (by station or group) in the text and tables of this report. The data frorn samples which contained concentrations above the LLD or MDC wem used in the calculations (averages, standard deviations and ranges) contained in this report. The individual results were generally reported to two significant figures. Each result also included a two-sigma counting uncenainty (95 % confidence interval) to the same decimal place. At a minimum, a counting uncertainty equal to 10 percent of the measured concentration was reponed. The counting uncenaitties were not used in any statistical calculations in this repon. ! Page G2
1997 RAI)l0 LOGICAL ENVIRONMENTAL MONITORING REPORT The data used in a few tables and all annual graphs were actual sample concentrations. For historical graphs, actual sample concentrations were used for 1997 data points only. The actual concentration is calculated by subtracting the background count rate or the count rate of a blank sample from the count rate of the sample. The net count rate is the converted to a net sample concentration which is either positive, negative or zero. There are several advantages of using actual sample concentrations. Biases in the data (averages, ranges, etc.), such as those caused by avenging only sample concentrations above the MDC, are eliminated. Missing data points us graphs also are eliminated. It should be noted that negative sample concentrations are important to the overall averages and trends in the data, but they have no physical significance. A negative sample concentration simply means that the background or blank sample count rate is greater than the sample. Quality control results (interlaboratory and intralabomtory) were not statistically analyzed with other data. Including quality mntrol data would introduce a bias at selected setions while providing little additional interpretive information. Page G3
1997 RAI)l0 LOGICAL ENL1RONMENTAL MONITORING REIY)RT APPENDIX H 1997 REMP Sample Collection and l Analysis Methods ; Pape H1
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1997 RADIOLOGICAL ENVIRONMENTAL MONimRING REPORT APPENDIX I 1997 TLD Quarterly Data PageI1
1997 RAI)l0 LOGICAL ENVIRONMENTAL MONITORING REPORT TABLEI 1997 TLD Quarterly Data mR Per Std Month 2a li Station 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter A1-5 5.6i 0.8 5.1* 0.7 5.4+ 0.6 5.It 0.5 B1-6 6.2 0.6 5.3* 0.7 5.9* 0.8 5.4* 0.3 C1-9 6.6* 0.4 5.1* 0.3 5.3* 0.6 5.0* 0.2 C2-1 5.1* 0.4 5.2* 0.6 5.5* 0.6 5.2 0.3 D l-4 8.7* 1. I 6.1* 0.8 6.5* 0.7 5.9* 0.6 D2-1 5.4* 0.6 5.5* 0.5 0.0* 0.0 5.6+ 0.3 El-7 5.9 0.9 5.0* 0.2 5.4* 0.8 5.3* 0.4 El-17 4.5i 0.5 4.1
- 0. 2 0.0* 0.0 4.1* 0.4 E2-1 7.2* 0.5 7. 2* 0. 5 7.7* 0.6 7. 3* 0. 9 E3-1 4.6* 0.7 4.6* 0.4 0.0* 0.0 0.0* 0.0 F1-2 6.9* 0.6 5.at 0.7 6.3 0.6 5.8* 1.0 Gl-1 4.5* 0.4 4.5i 0.4 4.9* 0.3 4.9* 0. 3 GI-2 5.8* 0.5 5.3* 0. 3 5.9* 0.8 5.9 0.5 G2-1 4.2* 0.5 4.1 0.6 4.6 0.4 4.7* 0.4 G10 . 5.3* 0.4 5.1* 0.7 5.4* 0.7 5.4* 0.3 H1-5 5.4* 0.5 5.3* 0.3 5.5* 0.7 5.4* 0.6 H2-1 5.4* 0.6 5.4i 0.6 5.9* 0.7 5.7* 0.5 H10-1 4.4* 0.5 4.3* 0.4 4.8* 0.4 4. 7* 0. 3 Il-1 4.8* 0.2 4.6* 0.4 5.2* 0.4 4.8* 0.4 K1-5 4.1* 0.4 4.0* 0.2 4.3* 0.3 4.2 0.5 K1-8 4.7* 0.6 4.8* 0.7 5.2* 0.6 5. 2* 0. 4 LI-1 4.9i 0.4 4.9t 0.4 5.3* 0.4 5.3* 0.4 L2-1 4.90.6 4.9* 0.5 5.0* 0.6 5.0 0.4 M l-6 5.0* 0.4 5.0* 0.5 5.4* 0.6 5.3* 0.5 N1-4 5.1* 0.3 5.0* 0.3 5. 2* 0. 9 5.3i 0.3 Pl-1 5.1* 0.6 5.1* 0.5 5.4* 0.7 5.6 0.7 Q1-3 4.5* 0.4 4.1* 0.3 4.5* 0.4 4. 5* 0. 7 Rl-1 5.4* 0.3 5.0* 0.4 5.5* 0.6 5.2* 0.2 NOTES: 1) A Value of Zero Indicates No Data Page 12 l _ _ _ - _ _ _}}